U.S. Nuclear Regulatory Commission Operations Center Event Reports For 06/15/95 - 06/23/95 ** EVENT NUMBERS ** 28868 28875 28946 28947 28948 28949 28950 28951 28952 28953 28954 28955 28956 28957 28958 28959 28960 28961 28962 28963 28964 28965 28966 28967 28968 28969 28970 28971 28972 28973 28974 28975 28976 28977 28978 28979 28980 28981 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28868 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BIG ROCK POINT REGION: 3 |NOTIFICATION DATE: 05/30/95 | |UNIT: [1] [ ] [ ] STATE: MI |NOTIFICATION TIME: 16:12 [ET]| |RX TYPE: [1] GE-1 |EVENT DATE: 05/30/95 | +------------------------------------------------+EVENT TIME: 13:35[EDT]| |NRC NOTIFIED BY: MIKE BOURASSA |LAST UPDATE DATE: 06/22/95 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |ROY CANIANO RDO | |AINA 50.72(b)(2)(iii)(A) POT UNABLE TO SAFE SD | | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 99 POWER OPERATION | 99 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - 125-VOLT DC STATION BATTERY SYSTEM VOLTAGE DEGRADED FOR 20 MINUTES - | | | | WHILE TESTING AN EMERGENCY LIGHTING TRANSFORMER CIRCUIT BREAKER, LICENSEE | | TECHNICIANS RACKED OUT THE BREAKER. THIS UNEXPECTEDLY CAUSED THE 125-VOLT | | DC STATION BATTERY SYSTEM VOLTAGE TO DEGRADE TO 122 VOLTS DC. TECH SPEC | | REQUIRED MINIMUM SYSTEM VOLTAGE IS 125 VOLTS DC. | | | | AT 1335, THE CONTROL ROOM RECEIVED A 125-VOLT DC SYSTEM TROUBLE ALARM. | | | | AT 1355, THE TECHNICIANS RACKED THE BREAKER BACK IN, AND THE SYSTEM TROUBLE | | ALARM CLEARED WITH THE SYSTEM VOLTAGE INDICATED AT 126 VOLTS DC. | | | | THE SYSTEM IS PRESENTLY OPERATING AT AN INDICATED VOLTAGE OF 132 VOLTS DC. | | | | LICENSEE IS INVESTIGATING THE CAUSE OF THE SYSTEM VOLTAGE DROP WHEN THE | | BREAKER IS RACKED OUT. | | | | LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE 06/22/95 1515EDT FROM:BOURASSA BY:TROCINE * * * | | | | THE LICENSEE IS RETRACTING THIS EVENT ON THE BASIS THAT THE LICENSEE DID | | NOT ENTER ANY LIMITING CONDITION FOR OPERATION, AND THE CONDITION ABOVE | | COULD NOT HAVE PREVENTED THE FULFILLMENT OF THE SAFETY FUNCTION OF | | STRUCTURES OR SYSTEMS NEEDED TO SHUTDOWN THE PLANT OR MITIGATE THE | | CONSEQUENCES OF AN ACCIDENT. THE COMPONENTS AFFECTED BY THE LOSS OF | | STATION BATTERIES INCLUDE MOTOR-OPERATED VALVES IN THE CORE SPRAY SYSTEM. | | THESE VALVES ARE DESIGNED TO OPERATE WITH DC VOLTAGES AS LOW AS 105 VDC. | | THEREFORE, THE CORE SPRAY SAFETY FUNCTION WOULD HAVE BEEN COMPLETED. THE | | LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. R3DO (JACOBSON) NOTIFIED. | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28875 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PILGRIM REGION: 1 |NOTIFICATION DATE: 06/01/95 | |UNIT: [1] [ ] [ ] STATE: MA |NOTIFICATION TIME: 15:47 [ET]| |RX TYPE: [1] GE-3 |EVENT DATE: 06/01/95 | +------------------------------------------------+EVENT TIME: 14:00[EDT]| |NRC NOTIFIED BY: GORDON FIDLER |LAST UPDATE DATE: 06/22/95 | |HQ OPS OFFICER: JOSEPH SEBROSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MOHAMED SHANBAKY RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | GROUP III ISOLATION OCCURRED DURING REFERENCE LEG BACKFILL. | | | | DURING PERFORMANCE OF PROCEDURE 3M2-12.4 (REFERENCE LEG BACKFILL) THE | | LICENSEE RECEIVED A GROUP III ISOLATION ON REACTOR PRESSURE GREATER THAN 70 | | PSIG. THE CAUSE OF THE PROBLEM WAS TOO HIGH OF A PRESSURE ON THE WATER | | SOURCE FOR THE REFERENCE LEG BACKFILL. THE RHR SYSTEM WAS SECURED AT THE | | TIME, HOWEVER, THE SHUTDOWN COOLING VALVES IN THE SYSTEM WERE IN THE OPEN | | POSITION. UPON RECEIPT OF THE GROUP III ISOLATION SIGNAL THESE VALVES | | CLOSED (MO1001-47, MO1001-50, AND MO1001-29B). THE ISOLATION SIGNAL HAS | | BEEN RESET AND THESE VALVES HAVE BEEN REOPENED. | | | | THE PRESSURE TRANSMITTER THAT CAUSED THE ISOLATION IS IN THE SAME LINE AS | | THE REFERENCE LEG THAT WAS BEING BACKFILLED AT THE TIME. PRIOR TO THE | | EVOLUTION THERE HAD BEEN SOME DISCUSSION ABOUT A POSSIBLE SPIKE IN PRESSURE | | AND THE LICENSEE HAD CLOSED THE MSIVS, AND THE MAIN STEAM DRAIN LINE VALVES | | TO PREVENT THEM FROM REPOSITIONING IN CASE THERE WAS A PRESSURE SPIKE. THE | | SHUTDOWN COOLING VALVES, HOWEVER, WERE NOT REPOSITIONED PRIOR TO THE | | EVOLUTION. | | | | THE LICENSEE WILL INFORM THE RESIDENT INSPECTOR. | | | | *** JUNE 22, 1995, RETRACTION RECEIVED FROM DICROCE AT 12:36 BY TROCINE *** | | | | THE LICENSEE DETERMINED THAT THIS EVENT WAS NOT REQUIRED TO BE REPORTED AND | | RETRACTED THE EVENT. THE LICENSEE WILL NOTIFY THE RESIDENT INSPECTOR. THE | | R1DO (DOERFLEIN) WAS NOTIFIED BY THE OPERATIONS CENTER. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28946 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SALEM REGION: 1 |NOTIFICATION DATE: 06/15/95 | |UNIT: [1] [2] [ ] STATE: NJ |NOTIFICATION TIME: 08:44 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 06/14/95 | +------------------------------------------------+EVENT TIME: 15:15[EDT]| |NRC NOTIFIED BY: HEALY |LAST UPDATE DATE: 06/15/95 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JENNY JOHANSEN RDO | |ADAS 50.72(b)(2)(i) DEG/UNANALYZED COND | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | 2 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE PLANT ENTERED TS LCO 3.4.1.4 @ 1515 ON 06/14/95 WHEN THEY DECLARED BOTH | | TRAINS OF BOTH UNITS OF RHR INOPERABLE DUE TO POSSIBLE IMPROPER | | INSTALLATION OF PUMP RECIRC VALVE CONTROL FLOW ORIFICE. | | | | THE CONDITION WAS IDENTIFIED DURING AN ENGINEERING REVIEW OF THE RHR | | DISCHARGE PIPING. IT WAS DETERMINED THAT THE DESIGN AND INSTALLATION IS NOT | | IN ACCORDANCE WITH ASME AND INDUSTRY STANDARDS. THIS COULD RESULT IN | | INADEQUATE FLOW MEASUREMENT ACROSS THE ORIFICE AND SUBSEQUENT INADEQUATE | | RECIRC VALVE OPERATION. THE RECIRC VALVES(RH29'S) ARE REQUIRED TO OPEN IN | | LOW FLOW CONDITION FOR PUMP PROTECTION AND CLOSE ON INCREASING FLOW FOR | | ADEQUATE INJECTION. BOTH UNITS ARE CURRENTLY IN MODE 5 WITH RHR IN SERVICE | | AND WILL REMAIN IN THIS CONDITION WHILE EVALUATION AND/OR TESTING IS | | COMPLETE TO VALIDATE THE ORIFICE FLOW INDICATION AND CONTROL FUNCTION. THE | | LCO THAT THEY ENTERED REQUIRES THAT THE RHR BE IMMEDIATELY RESTORED. RHR IS | | FUNCTIONAL, BUT TECHNICALLY INOPERABLE SINCE THE VALVE DESIGN IS | | QUESTIONABLE. THE LICENSEE DETERMINED THAT THIS EVENT IS REPORTABLE at 0745 | | ON 06/15/95. THE RI WILL BE INFORMED. LOCAL AGENCIES HAVE BEEN INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |HOSPITAL | |EVENT NUMBER: 28947 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: ST JOSEPH HOSPITAL |NOTIFICATION DATE: 06/15/95 | | CITY: MARSHFIELD REGION: 3 |NOTIFICATION TIME: 11:42 [ET]| | COUNTY: STATE: WI |EVENT DATE: 06/08/95 | |LICENSE#: AGREEMENT: N |EVENT TIME: 09:15[CDT]| | DOCKET: |LAST UPDATE DATE: 06/15/95 | | +-----------------------------+ | |PERSON ORGANIZATION| | |LEWIS MILLER RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: LOSHEK | | |HQ OPS OFFICER: CHAUNCEY GOULD | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |LADM 35.33(a) MED MISADMINISTRATION | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE ST JOSEPH HOSPITAL/MARSHFIELD CLINIC IN MARSHFIELD WI REPORTED A | | MEDICAL MISADMINISTRATION. | | | | AN IMPLANT OF CS-137 FOR CERVIX CANCER WAS LEFT INSIDE THE PATIENT 15 HRS | | TOO LONG DUE TO THE WRONG EXTRACTION DATE(JUN 8 INSTEAD OF JUN 7) BEING PUT | | IN THE LOG. THE PATIENT HAS BEEN NOTIFIED AND THEY DO NOT ANTICIPATE ANY | | ADVERSE AFFECTS. THE LICENSEE HAS NOTIFIED THE REGION(B. GATONE). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 28948 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: SYNCOR |NOTIFICATION DATE: 06/15/95 | | CITY: SHARON HILL REGION: 1 |NOTIFICATION TIME: 12:06 [ET]| | COUNTY: STATE: PA |EVENT DATE: 06/14/95 | |LICENSE#: 37-1846101-MD AGREEMENT: N |EVENT TIME: 14:00[EDT]| | DOCKET: |LAST UPDATE DATE: 06/15/95 | | +-----------------------------+ | |PERSON ORGANIZATION| | |JENNY JOHANSEN RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: TARA DOMITER | | |HQ OPS OFFICER: DOUG WEAVER | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |IBBE 30.50(b)(2)(i) ACCID MIT EQUIP FAILS | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | SYNCOR - FUME HOOD FAILURE - | | | | SYNCOR LOCATED AT 650 ELMWOOD AVE., SHARON HILL, PA REPORTED THE FOLLOWING | | EVENT. CONTACT PHONE NUMBER LOCATED IN THE HOO LOG. | | | | A FUME HOOD FAILED AT 1400 ON 6/14/95. THE HOOD CONTAINED 20 mCi OF I-131 | | AND 150 mCi OF Xe-133 AT THE TIME OF THE FAILURE. THERE WERE NO RELEASES | | ABOVE ALLOWABLE LIMITS. THE HOOD IS BEING REPAIRED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28949 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BROWNS FERRY REGION: 2 |NOTIFICATION DATE: 06/15/95 | |UNIT: [ ] [ ] [3] STATE: AL |NOTIFICATION TIME: 15:12 [ET]| |RX TYPE: [1] GE-4,[2] GE-4,[3] GE-4 |EVENT DATE: 06/15/95 | +------------------------------------------------+EVENT TIME: 11:29[CDT]| |NRC NOTIFIED BY: DON SMITH |LAST UPDATE DATE: 06/15/95 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DAVID VERRELLI RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | | | | | 3 | N N 0 REFUELING | 0 REFUELING | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ESF ACTUATION - DIESEL AND STANDBY GAS TREATMENT AUTO STARTS - | | | | AT 1129 (CDT) ON 6/15/95 AN AUTO START OF THE 3A AND 3B DIESEL GENERATORS | | OCCURRED AS A RESULT OF THE LOSS OF THE ATHENS 161 KV LINE WHICH WAS | | PROVIDING POWER TO THE 1A & 2A START BUSES. | | | | UNIT 3 4KV SHUTDOWN BOARDS 3EA & 3EB WERE BEING FED FROM THE ATHENS 161 KV | | LINE AT THE TIME OF THE EVENT. THE RESULTING UNDERVOLTAGE LED TO THE | | EXPECTED AUTO START OF THE 3A & 3B DGs AND SUPPORTING EECW PUMP STARTS. | | ADDITIONALLY, 3A RPS WAS LOST RESULTING IN THE EXPECTED AUTO START OF THE | | STANDBY GAS TREATMENT AND CONTROL ROOM EMERGENCY VENTILATION SYSTEMS. UNIT | | 2 WAS UNAFFECTED BY THE EVENT. | | | | THE CAUSE OF THE EVENT WAS LATER DETERMINED TO BE A RESULT OF A CROP DUSTER | | PLANE CUTTING THE C PHASE LINE AND BREAKING A CROSS ARM OF THE 161 ATHENS | | LINE OFF SITE SOUTH OF QUINN ROAD. (SEVERAL MILES AWAY FROM THE SITE) THE | | TRINITY 161 LINE IS NOW SUPPLYING POWER TO THE AFFECTED BUSES AND THE | | DIESELS HAVE BEEN RETURNED TO STANDBY. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 28950 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: COGEMA MINING, INC. |NOTIFICATION DATE: 06/15/95 | | CITY: LYNCH REGION: 4 |NOTIFICATION TIME: 16:05 [ET]| | COUNTY: STATE: WY |EVENT DATE: 06/13/95 | |LICENSE#: SUA1341 AGREEMENT: N |EVENT TIME: 12:00[MDT]| | DOCKET: |LAST UPDATE DATE: 06/15/95 | | +-----------------------------+ | |PERSON ORGANIZATION| | |CHRIS VANDENBURGH RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: JOHN VASELIN | | |HQ OPS OFFICER: DOUG WEAVER | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | COGEMA MINING, INC. - CHEMISTRY OUTSIDE OF ALLOWABLE BANDS AT SEVERAL WELLS | | | | THE LICENSEE MADE THIS REPORT IN ACCORDANCE WITH LICENSE CONDITION 28 OF | | THEIR LICENSE. THE MINE IN QUESTION IS THE IRIGARY URANIUM MINE LOCATED | | NEAR LYNCH, WYOMING. THE MINE IS NO LONGER BEING MINED AND IS IN THE FIRST | | STAGES OF RESTORATION. | | | | WELLS SSM3, SSM18 AND M2 WERE SAMPLED FOR CHLORIDES, CONDUCTIVITY AND | | ALKALINITY. EACH MINE EXCEEDED LIMITS IN TWO OF THE THREE CATEGORIES. NO | | URANIUM IS EXPECTED TO BE IN THESE SAMPLES, BUT THE RESULTS OF THE TEST FOR | | URANIUM WERE NOT YET AVAILABLE. THESE SAMPLES WERE ORIGINALLY TAKEN ON THE | | 11TH AND 12TH OF JUNE. CONFIRMATORY SAMPLES WERE TAKEN ON THE 13TH AND | | 14TH OF JUNE. THE LICENSEE INDICATED THERE WAS NO PUBLIC HAZARD ASSOCIATED | | WITH THESE SAMPLE RESULTS. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 28951 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: COOPER CAMERON CORPORATION |NOTIFICATION DATE: 06/15/95 | | CITY: GROVE CITY REGION: 1 |NOTIFICATION TIME: 16:44 [ET]| | COUNTY: STATE: PA |EVENT DATE: 06/15/95 | |LICENSE#: AGREEMENT: N |EVENT TIME: 00:00[EDT]| | DOCKET: |LAST UPDATE DATE: 06/15/95 | | +-----------------------------+ | |PERSON ORGANIZATION| | | | | | | +------------------------------------------------+VERN HODGE NRR | |NRC NOTIFIED BY: SCHNEIDER | | |HQ OPS OFFICER: DOUG WEAVER | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |CDEF 21.21(b)(2) DEFECTS/NONCOMPLIANCE | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | PART 21 NOTIFICATION | | | | THERE EXISTS A POTENTIAL PROBLEM WITH A BELLOFRAM AIR CYLINDER, COOPER PART | | NUMBER AJ-009-000 WHICH IS USED TO CONTROL A BUTTERFLY VALVE IN THE DIESEL | | ENGINE INTAKE AIR SYSTEM. THESE AIR CYLINDERS ARE INSTALLED ON ALL NUCLEAR | | ENTERPRISE EDGs CURRENTLY IN SERVICE. | | | | THE FOLLOWING DOMESTIC PLANTS ARE AFFECTED - SHOREHAM, GRAND GULF, RIVER | | BEND, SHEARON HARRIS, CATAWBA, PERRY, BELLEFONTE, HARTSVILLE, COMANCHE | | PEAK, VOGTLE. THESE DIESELS ARE ALSO USED AT KORI AND YONGGWANG IN KOREA | | AS WELL AS KUOSHENG AND MAANSHAN IN TAIWAN. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 28952 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: DIAMOND H. TESTING |NOTIFICATION DATE: 06/15/95 | | CITY: HONOLULU, HI REGION: 4 |NOTIFICATION TIME: 17:43 [ET]| | COUNTY: STATE: HI |EVENT DATE: 06/15/95 | |LICENSE#: AGREEMENT: N |EVENT TIME: 21:40[AH ]| | DOCKET: |LAST UPDATE DATE: 06/15/95 | | +-----------------------------+ | |PERSON ORGANIZATION| | |CHRIS VANDENBURGH RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: HANGES | | |HQ OPS OFFICER: DOUG WEAVER | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |BAD1 20.2202(a)(1) PERS OVEREXPOSURE | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - PERSONNEL OVEREXPOSURE DURING RADIOGRAPHY - | | | | A RADIOGRAPHER RECEIVED 650 mR AS DETERMINED BY HIS SELF READING DOSIMETER. | | HIS FILM BADGE HAS BEEN SENT IN TO BE READ. THE SOURCE INVOLVED IS 40 Ci | | OF Ir-192. THE RADIOGRAPHER RECEIVED THE DOSE WHEN HE FORGOT THAT THE | | SOURCE HAD NOT BEEN STOWED. WHEN HE APPROACHED THE SOURCE THE SOURCE WAS | | PARTIALLY SHIELDED BY THE PIPE (1.5" WALL THICKNESS) AND READINGS APPEARED | | NORMAL. THIS CONTRIBUTED TO HIS EXPOSURE DURING THE EVENT. | | | | THE LICENSEE HAD INFORMED THE REGION PRIOR TO THIS CALL TO THE OPERATIONS | | CENTER. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28953 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BIG ROCK POINT REGION: 3 |NOTIFICATION DATE: 06/15/95 | |UNIT: [1] [ ] [ ] STATE: MI |NOTIFICATION TIME: 17:50 [ET]| |RX TYPE: [1] GE-1 |EVENT DATE: 06/15/95 | +------------------------------------------------+EVENT TIME: 17:07[EDT]| |NRC NOTIFIED BY: WITHROW |LAST UPDATE DATE: 06/15/95 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LEWIS MILLER RDO | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 95 POWER OPERATION | 95 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - DC LOADS OUTSIDE OF DESIGN BASIS - | | | | DURING TESTING OF THE 125 VDC BATTERY CHARGER THE LICENSEE DISCOVERED THAT | | THE STACK LIGHTS ARE DRAWING 22 AMPS INSTEAD OF 10 AMPS. BASED ON THE MOST | | RECENT LOAD TESTING OF THE BATTERY AND DESIGN CALCULATIONS, THE LICENSEE | | CONCLUDED THAT THE BATTERY WOULD MEET ALL DESIGN REQUIREMENTS. | | | | THE LICENSEE ALSO DISCOVERED THAT THE STACK LIGHTS ARE NOT POWERED FROM THE | | BREAKER WHICH THEY BELIEVED WAS THE SUPPLY BREAKER. THE STACK LIGHTS ARE | | NORMALLY SUPPLIED BY AC POWER, BUT SWITCH TO DC WHEN AC POWER IS NOT | | AVAILABLE. THE LICENSEE IS INVESTIGATING BOTH THE ADDITIONAL LOAD AND THE | | ACTUAL POWER SUPPLY PATH TO THE LIGHTS. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28954 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OYSTER CREEK REGION: 1 |NOTIFICATION DATE: 06/15/95 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 18:29 [ET]| |RX TYPE: [1] GE-2 |EVENT DATE: 06/15/95 | +------------------------------------------------+EVENT TIME: 14:17[EDT]| |NRC NOTIFIED BY: VAN BLARCOM |LAST UPDATE DATE: 06/15/95 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JENNY JOHANSEN RDO | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | STRUCTURAL FAILURE OF A FUEL BUNDLE | | | | A 7 X 7 FUEL ASSEMBLY SUFFERED STRUCTURAL FAILURE WHEN THE BOTTOM PLATE | | SEPARATED FROM THE TIE RODS WHILE LOWERING THE FUEL ASSEMBLY INTO THE SPENT | | FUEL POOL. THE BOTTOM TIE PLATE AND 41 FUEL RODS DROPPED ABOUT 7 FEET INTO | | THE FUEL RACK. THE UPPER TIE PLATE AND THE EIGHT TIE RODS ARE STILL | | SUSPENDED IN THE FUEL POOL. | | | | THE LICENSEE IS STILL ASSESSING THE SITUATION. AIR SAMPLES DID NOT | | INDICATE ANY ACTIVITY ABOVE NORMAL. APPROPRIATE STATE AND LOCAL OFFICIALS | | HAVE BEEN NOTIFIED. | | | | THE LICENSEE IS CONDUCTING A PRESS BRIEFING TONIGHT IN A LOCAL TOWN HALL. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | * * * COMMISSIONER'S ASSISTANT BRIEFING AT 2000; AEOD (BROCKMAN), | | STATE PROGRAMS (SCHNEIDER), NMSS EO (WEBER), COMM JACKSON (BOYLE), | | COMM De PLANQUE (MCKENNA), NRR EO (MARSH), RI (PINDALE), PAO (DRICKS), | | R1 (LANNING), NRR (ZWOLINSKI), NRR PM (DROMERICK). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28955 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: GINNA REGION: 1 |NOTIFICATION DATE: 06/16/95 | |UNIT: [1] [ ] [ ] STATE: NY |NOTIFICATION TIME: 10:25 [ET]| |RX TYPE: [1] W-2-LP |EVENT DATE: 06/16/95 | +------------------------------------------------+EVENT TIME: 00:00[EDT]| |NRC NOTIFIED BY: WIDAY |LAST UPDATE DATE: 06/16/95 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: | | |CCCC 21.21 UNSPECIFIED PARAGRAPH | | | |HODGE NRR | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 97 POWER OPERATION | 97 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE REPORTED THAT THE BUTTERFLY VALVE MANUFACTURED BY FISHER | | CONTROLS WAS SUPPLIED AS AN AIR-TO-OPEN VALVE INSTEAD OF AN AIR-TO-CLOSE | | VALVE. THIS VALVE IS A BASIC COMPONENT IN THE SERVICE WATER OUTLET FOR | | CONTAINMENT RECIRCULATION FAN COOLERS, A SAFETY HAZARD COULD BE CREATED BY | | SUCH A DEFECT, WHICH WOULD CAUSE THE LOSS OF SERVICE WATER TO THE FAN | | COOLERS. CORRECTIVE ACTION WAS COMPLETED WHEN THEY ALTERED THE ACTUATOR | | LEVER WHICH RESULTED IN THE VALVE FUNCTIONING CORRECTLY. THIS VALVE WAS | | PURCHASED AS A REPLACEMENT FOR A SPECIFIC SERIAL NUMBERED ITEM. THE | | ORIGINAL ENGINEERING REQUIREMENTS FOR THIS VALVE STIPULATED AIR-TO-CLOSE | | OPERATION. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28956 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: WATERFORD REGION: 4 |NOTIFICATION DATE: 06/16/95 | |UNIT: [3] [ ] [ ] STATE: LA |NOTIFICATION TIME: 13:54 [ET]| |RX TYPE: [3] CE |EVENT DATE: 06/16/95 | +------------------------------------------------+EVENT TIME: 12:00[CDT]| |NRC NOTIFIED BY: PENDERGRASS |LAST UPDATE DATE: 06/16/95 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CHRIS VANDENBURGH RDO | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 3 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | OUTSIDE DESIGN BASIS - SHUTDOWN COOLING VALVE FOUND TO BE INOPERABLE | | | | ON 6/11/95 AT 1311, WHILE MAKING PREPARATIONS TO PLACE SHUTDOWN COOLING IN | | SERVICE, THE TRAIN "B" SUCTION VALVE (SI-405B) WOULD NOT FULLY OPEN. THE | | VALVE WAS DECLARED INOPERABLE. FURTHER INVESTIGATION REVEALED THAT THE | | HYDRAULIC OIL RESERVOIR LEVEL WAS LOW. THE LICENSEE DISCOVERED A SMALL OIL | | LEAK WHICH EXPLAINED THE LOW LEVEL. REPAIRS WERE MADE AND THE VALVE WAS | | RETURNED TO OPERABILITY. | | | | THE EXACT TIME AT WHICH THE VALVE BECAME INOPERABLE IS UNKNOWN. THEREFORE, | | THE LICENSEE CONCLUDED THAT THEY MAY HAVE OPERATED FOR SOME PROLONGED | | PERIOD OF TIME WITH THE VALVE (AND ONE TRAIN OF SHUTDOWN COOLING) | | INOPERABLE. THE LAST TIME OPERABILITY WAS VERIFIED WAS APRIL 1994. THIS | | PLACED THE PLANT IN A CONDITION OUTSIDE OF DESIGN BASIS. THE ENGINEERING | | REVIEW WHICH LED TO THIS CONCLUSION WAS COMPLETED AT 1200 CDT TODAY. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 28957 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: SYNCOR |NOTIFICATION DATE: 06/16/95 | | CITY: OKLAHOMA CITY REGION: 4 |NOTIFICATION TIME: 15:15 [ET]| | COUNTY: STATE: OK |EVENT DATE: 06/13/95 | |LICENSE#: 35-23359-01MD AGREEMENT: N |EVENT TIME: 12:00[CDT]| | DOCKET: |LAST UPDATE DATE: 06/16/95 | | +-----------------------------+ | |PERSON ORGANIZATION| | |CHRIS VANDENBURGH RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: PELLIGRINO | | |HQ OPS OFFICER: DOUG WEAVER | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |IBBE 30.50(b)(2)(i) ACCID MIT EQUIP FAILS | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | SYNCOR - FUME HOOD FAILURE | | | | THE EVENT OCCURRED AT 7801 N. ROBINSON, SUITE D-2, OKLAHOMA CITY, OK 73116 | | | | A FUME HOOD WAS FOUND TURNED OFF AT 1200 ON 6/13/95. THE LAST TIME THE | | HOOD WAS NOTICED TO BE RUNNING WAS AT 0330 ON 6/13/95. THE HOOD CONTAINED | | SEALED VIALS OF IODINE AND XENON. THE HOOD HAS BEEN TURNED ON. | | | | THE LICENSEE PREVIOUSLY NOTIFIED THE REGIONAL OFFICE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28958 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CALVERT CLIFFS REGION: 1 |NOTIFICATION DATE: 06/16/95 | |UNIT: [1] [ ] [ ] STATE: MD |NOTIFICATION TIME: 20:05 [ET]| |RX TYPE: [1] CE,[2] CE |EVENT DATE: 06/16/95 | +------------------------------------------------+EVENT TIME: 19:17[EDT]| |NRC NOTIFIED BY: DENTON |LAST UPDATE DATE: 06/16/95 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JENNY JOHANSEN RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | M/R Y 100 POWER OPERATION | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LOSS OF MAIN FEED - MANUAL REACTOR TRIP | | | | THE #12 MAIN FEED PUMP TRIPPED AT 1917 AND COULD NOT BE RESTORED. OPERATORS | | MANUALLY TRIPPED THE REACTOR. THE #11 MAIN FEED PUMP THEN TRIPPED. | | AUXILIARY FEED PUMPS STARTED AND RESTORED STEAM GENERATOR LEVEL. THE UNIT | | IS CURRENTLY STABLE IN HOT STANDBY. | | | | ALL RODS FULLY INSERTED. ALL SAFETY RELATED EQUIPMENT IS OPERABLE. STEAM | | IS BEING DUMPED TO THE MAIN CONDENSER AS NECESSARY TO REMOVE DECAY HEAT. | | | | THE CAUSE OF THE LOSS OF THE FEED PUMPS IS NOT KNOWN AND IS BEING | | INVESTIGATED. CALVERT COUNTY OFFICIALS WERE NOTIFIED. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28959 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HATCH REGION: 2 |NOTIFICATION DATE: 06/18/95 | |UNIT: [1] [ ] [ ] STATE: GA |NOTIFICATION TIME: 11:37 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 06/18/95 | +------------------------------------------------+EVENT TIME: 10:50[CDT]| |NRC NOTIFIED BY: ANDERSON |LAST UPDATE DATE: 06/18/95 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DAVID VERRELLI RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - THE "B" RPS MG SET TRIPPED CAUSING AN ESF ACTUATION - | | | | THE "B" RPS MG SET TRIPPED CAUSING PARTIAL GROUP 5 (REACTOR WATER CLEAN UP) | | AND GROUP 2 (SMALL BORE PIPING) ISOLATIONS. THE TRIP ALSO CAUSED A HALF | | SCRAM AND A HALF GROUP 1 (MSIV) ISOLATION. THE CAUSE OF THE MG TRIP IS | | UNKNOWN, BUT IT IS UNDER INVESTIGATION. | | | | THE "B" RPS BUS HAS BEEN POWERED FROM ITS ALTERNATE POWER SOURCE AND ALL | | SIGNALS HAVE BEEN RESET. PLANT RESTORATION IS IN PROGRESS. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28960 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SEABROOK REGION: 1 |NOTIFICATION DATE: 06/18/95 | |UNIT: [1] [ ] [ ] STATE: NH |NOTIFICATION TIME: 19:01 [ET]| |RX TYPE: [1] W-4-LP |EVENT DATE: 06/18/95 | +------------------------------------------------+EVENT TIME: 18:27[EDT]| |NRC NOTIFIED BY: DENNIS BEMAN |LAST UPDATE DATE: 06/19/95 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JENNY JOHANSEN RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | M/R Y 100 POWER OPERATION | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | MANUAL REACTOR TRIP | | | | THE LOSS OF A SECONDARY POWER SUPPLY (UNIT SUB 14) CAUSED A LOSS OF BOTH | | EHC PUMPS ASSOCIATED WITH THE MAIN TURBINE. OPERATORS MANUALLY TRIPPED THE | | REACTOR BEFORE EHC PRESSURE LOWERED TO ITS TRIP SETPOINT. ALL RODS FULLY | | INSERTED. | | | | EMERGENCY FEEDWATER (EFW) STARTED ON LOW STEAM GENERATOR LEVELS. S/G LEVEL | | HAS BEEN RECOVERED. DECAY HEAT IS BEING REMOVED VIA THE S/G ATMOSPHERIC | | DUMPS. THE PLANT IS STABLE IN HOT STANDBY. | | | | DURING THE EVENT THE "D" REHEATER DRAIN TANK HIGH LEVEL DUMP STUCK CLOSED | | AND THE "A" HEATER DRAIN PUMP DID NOT TRIP. THE PUMP WAS MANUALLY TRIPPED. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. A PRESS RELEASE IS | | PLANNED. | | | | ***UPDATE 06/19/95 @ 0430 EDT BY BEMIS TAKEN BY MACKINNON*** | | | | LOSS OF THE POWER SUPPLY MENTIONED ABOVE CAUSED A LOSS OF THE SEAL STEAM | | SUPPLY TO THE MAIN TURBINE SEALS WHICH CAUSED A PARTIAL LOSS OF MAIN | | CONDENSER VACUUM. THE AUXILIARY BOILER WAS SUPPLYING STEAM TO THE MAIN | | TURBINE SEALS. WHEN POWER WAS LOST IT CAUSED THE AUXILIARY BOILER | | DEMINERALIZER WATER PUMP (SUPPLYING WATER TO THE AUXILIARY BOILER) TO | | DEENERGIZE. THIS IS WHY LICENSEE USED THEIR S/G ATMOSPHERIC DUMPS. STEAM | | DUMP BYPASS CONTROL SYSTEM WAS FULLY OPERABLE WITHIN ONE HOUR AFTER THE | | REACTOR TRIP. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28961 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SAINT LUCIE REGION: 2 |NOTIFICATION DATE: 06/19/95 | |UNIT: [1] [2] [ ] STATE: FL |NOTIFICATION TIME: 10:24 [ET]| |RX TYPE: [1] CE,[2] CE |EVENT DATE: 06/19/95 | +------------------------------------------------+EVENT TIME: 09:50[EDT]| |NRC NOTIFIED BY: K KORTH |LAST UPDATE DATE: 06/19/95 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DAVID VERRELLI RDO | |AARC 50.72(b)(1)(v) OTHER ASMT/COMM INOP | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LOSS OF NORMAL AND EMERGENCY POWER TO THE EMERGENCY OPERATIONS FACILITY | | (EOF). | | | | AT APPROXIMATELY 0700 EDT THE BUILDING ATTENDANT ARRIVED AT THE FACILITY TO | | FIND THE EMERGENCY DIESEL GENERATOR RUNNING AND SUPPLYING POWER TO THE | | BUILDING. POWER WAS AVAILABLE TO THE ADJACENT SUBSTATION. AT APPROXIMATELY | | 0930 EDT THE DIESEL FAILED RESULTING IN A TOTAL LOSS OF POWER TO THE | | FACILITY. AT 0950 EDT THE NUCLEAR PLANT SUPERVISOR WAS INFORMED OF THE | | EVENT. REPAIRS AND ROOT CAUSE ANALYSIS ARE CURRENTLY UNDER WAY. | | | | RESIDENT INSPECTOR WILL BE INFORMED BY THE LICENSEE. | | | | * * * UPDATE AT 1201 EDT FROM KELLY KORTH TAKEN BY R. KARSCH * * * | | NORMAL OFF-SITE POWER WAS RESTORED AT 1025 EDT. THE CAUSE OF THE EDG START | | WAS AN AUTOMATIC TRANSFER SWITCH MALFUNCTION. THE EDG RAN FOR 62 HOURS | | UNTIL IT RAN OUT OF FUEL. R2DO (VERRELLI) NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28962 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: TURKEY POINT REGION: 2 |NOTIFICATION DATE: 06/19/95 | |UNIT: [3] [4] [ ] STATE: FL |NOTIFICATION TIME: 12:14 [ET]| |RX TYPE: [3] W-3-LP,[4] W-3-LP |EVENT DATE: 06/19/95 | +------------------------------------------------+EVENT TIME: 09:30[EDT]| |NRC NOTIFIED BY: TERRY JONES |LAST UPDATE DATE: 06/19/95 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DAVID VERRELLI RDO | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 3 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | 4 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE FOLLOWING IS THE TEXT OF A FAX SUBMITTED BY THE LICENSEE: | | | | "IN NOVEMBER OF 1994, FPL DISCOVERED A DEFECT IN THE EMERGENCY BUS LOAD | | SEQUENCER SOFTWARE. THE DEFECT WAS REPORTED IN LER 250/94-005. AS PART OF | | THE CORRECTIVE ACTION FOR THAT DEFECT, FPL PERFORMED A DETAILED REVIEW OF | | ALL OF THE SEQUENCER SOFTWARE TO DETERMINE IF OTHER DEFECTS EXISTED." | | | | "AS A RESULT OF THAT REVIEW, A CONDITION HAS BEEN IDENTIFIED THAT, ABSENT | | MANUAL ACTION, COULD HAVE PREVENTED THE FULFILLMENT OF THE SAFETY FUNCTION | | OF THE 480 VOLT LOAD CENTERS. IF A SAFETY INJECTION (SI) SIGNAL OCCURS | | 15.5 TO 16 SECONDS AFTER A LOSS OF OFFSITE POWER (LOOP) SIGNAL, THE 4.16 KV | | BREAKERS WHICH FEED THE 480 VOLT LOAD CENTER WILL RECEIVE SIMULTANEOUS | | CLOSE AND STRIP PULSES. WITH CONFLICTING SIGNALS, THE BREAKERS WILL NOT | | CLOSE." | | | | "THE UFSAR SAFETY ANALYSIS FOR SMALL BREAK LOCAs ASSUMES A LOOP COINCIDENT | | WITH THE REACTOR TRIP SIGNAL. FOR THE CASES ANALYZED IN THE UFSAR, THE SI | | SIGNAL IS ASSUMED TO OCCUR APPROXIMATELY 10 TO 40 SECONDS AFTER THE TRIP, | | DEPENDING ON THE SIZE OF THE BREAK. THE LOAD CENTERS MAY NOT PERFORM AS | | DESIGNED FOR A 0.5 SECOND PERIOD, DURING A SPECIFICALLY ANALYZED LOCA WITH | | NON-CONCURRENT LOOP." | | | | "TECHNICAL SPECIFICATION SAFETY LIMITS ARE NOT CHALLENGED AS A RESULT OF | | LOSS OF THE AUTOMATIC CLOSURE OF THE 480 VOLT LOAD CENTER SUPPLY BREAKERS. | | SUFFICIENT TIME IS AVAILABLE FOR CREDIBLE MANUAL OPERATOR ACTION TO | | MANUALLY CLOSE THE BREAKERS. THEREFORE THE LOAD CENTERS REMAIN OPERABLE." | | | | "THE PROBABILITY OF A SB LOCA OF THE EXACT SIZE TO RESULT IN THE SI SIGNAL | | 15.5 TO 16 SECONDS AFTER THE LOOP/REACTOR TRIP IS EXTREMELY LOW. | | PROBABILISTIC SAFETY ANALYSIS OF THE ANOMALY INDICATES AN INCREASE IN CORE | | DAMAGE FREQUENCY ON THE ORDER OF 1E-8 PER YEAR (BELOW THE EPRI PSA | | APPLICATION GUIDELINES), ASSUMING NO CREDIT FOR OPERATOR RECOVERY. | | THEREFORE THE ANOMALY IS NOT SAFETY SIGNIFICANT." | | | | "THE CONDITION WILL BE CORRECTED DURING THE NEXT REFUELING OUTAGE ON EACH | | UNIT. BOTH UNITS REMAIN IN MODE 1." | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28963 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BROWNS FERRY REGION: 2 |NOTIFICATION DATE: 06/19/95 | |UNIT: [ ] [2] [ ] STATE: AL |NOTIFICATION TIME: 16:02 [ET]| |RX TYPE: [1] GE-4,[2] GE-4,[3] GE-4 |EVENT DATE: 06/19/95 | +------------------------------------------------+EVENT TIME: 14:05[CDT]| |NRC NOTIFIED BY: DON SMITH |LAST UPDATE DATE: 06/19/95 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DAVID VERRELLI RDO | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE DETERMINED THAT THE FLOW CONTROL VALVE SETPOINT WHICH ISOLATES | | NON-SAFETY LOADS FROM THE EMERGENCY EQUIPMENT COOLING WATER (EECW) SYSTEM | | IS OUTSIDE ITS DESIGN BASIS. | | | | "2 FCV-67-50" (EECW ISOLATION VALVE) WAS FOUND BY POST MODIFICATION TESTING | | TO BE OUTSIDE THE DESIGN BASIS OF THE PLANT. IT WAS DETERMINED THAT THE | | AUTOMATIC CLOSURE SETPOINT FOR THE VALVE, WHICH CROSS CONNECTS EECW TO THE | | UNIT 2 REACTOR BUILDING CLOSED COOLING WATER (RBCCW), WAS SET IN A | | NON-CONSERVATIVE DIRECTION. A PRESSURE OF 67.5 PSI WAS DETERMINED TO BE | | REQUIRED TO ASSURE ADEQUATE COOLING OF THE EMERGENCY DIESEL, BUT THE | | CURRENT PRESSURE SETPOINT IS 64 PSI. THAT PRESSURE SETPOINT WAS ESTABLISHED | | DURING THE UNIT 2 RESTART TEST PROGRAM USING A TEST BASIS OF ONE EECW PUMP | | PER HEADER AND THE NEW TEST BASIS PROVIDES TWO EECW PUMPS PER HEADER. | | | | THE LICENSEE'S IMMEDIATE CORRECTIVE ACTION HAS BEEN TO CLOSE "2 FCV-67-50" | | TO PREVENT EECW FROM FEEDING RBCCW FOR NONESSENTIAL LOADS. THE LICENSEE | | INFORMED THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE AT 2114 EDT FROM MORROW TAKEN BY KARSCH * * * | | THE LICENSEE IS RETRACTING THIS EVENT. THE ACTUAL SETPOINT FOR THE VALVE | | WAS DETERMINED TO BE 69.8 +/- 1.0 PSIG. THE MINIMUM VALUE AT WHICH | | ISOLATION WOULD OCCUR IS 68.8 PSIG, WHICH IS SUFFICIENTLY ABOVE THE MINIMUM | | VALUE TO ASSURE ADEQUATE COOLING OF EMERGENCY EQUIPMENT LOADS. BASED ON THE | | ACTUAL VALVE SETPOINT, NO DESIGN-BASIS PROBLEM EXISTS. THEREFORE, THE | | LICENSEE IS RETRACTING THIS EVENT. THE LICENSEE INFORMED THE NRC RESIDENT | | INSPECTOR. R2DO (VERRELLI) NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28964 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MAINE YANKEE REGION: 1 |NOTIFICATION DATE: 06/19/95 | |UNIT: [1] [ ] [ ] STATE: ME |NOTIFICATION TIME: 18:59 [ET]| |RX TYPE: [1] CE |EVENT DATE: 06/19/95 | +------------------------------------------------+EVENT TIME: 18:05[EDT]| |NRC NOTIFIED BY: PETE EBERT |LAST UPDATE DATE: 06/19/95 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CURTIS COWGILL RDO | |AENS 50.72(b)(1)(v) ENS INOPERABLE | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ALL NORMAL AND EMERGENCY PHONE COMMUNICATIONS IN AND OUT OF THE SITE ARE | | INOPERABLE. THE CAUSE IS UNKNOWN. ALL FUEL HAS BEEN REMOVED FROM THE CORE. | | COMMUNICATION TO THE SITE VIA VERMONT YANKEE IS POSSIBLE. THE LICENSEE | | WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28965 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CRYSTAL RIVER REGION: 2 |NOTIFICATION DATE: 06/20/95 | |UNIT: [3] [ ] [ ] STATE: FL |NOTIFICATION TIME: 11:11 [ET]| |RX TYPE: [3] B&W-L-LP |EVENT DATE: 06/20/95 | +------------------------------------------------+EVENT TIME: 01:50[EDT]| |NRC NOTIFIED BY: SWEENEY |LAST UPDATE DATE: 06/20/95 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DOUG COLLINS RDO | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 3 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | WHEN "A" HIGH PRESSURE INJECTION (HPI) PUMP IS ALIGNED TO ITS ALTERNATE | | COOLING WATER SOURCE ITS COOLING WATER FLOW RATE IS LESS THAN ITS DESIGN | | BASIS VALUE. | | | | WHEN "A" HPI PUMP IS ALIGNED TO ITS ALTERNATE COOLING WATER SOURCE THE | | COOLING WATER FLOW RATE IS 32 gpm WHICH IS LESS THAN ITS DESIGN BASIS VALUE | | WHICH IS SUPPOSED TO BE 50 gpm. THIS PUMP IS INOPERABLE FOR EMERGENCY | | SAFEGUARDS FUNCTION WHEN ALIGNED TO ITS ALTERNATE COOLING SOURCE. NORMALLY | | "A" HPI IS NOT AN EMERGENCY SAFEGUARDS SELECTED PUMP OR ALIGNED TO ITS | | ALTERNATE COOLING WATER SOURCE. HPI PUMPS "B" & "C" ARE THE NORMALLY | | SELECTED PUMPS. LICENSEE SUSPECTS THAT THIS EVENT IS A DESIGN BASIS ISSUE. | | ENGINEERING IS INVESTIGATING THIS EVENT. THIS PROBLEM WAS DISCOVERED DURING | | A SCHEDULED SYSTEM OUTAGE. | | | | RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 28966 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: BETHLEHEM STEEL |NOTIFICATION DATE: 06/20/95 | | CITY: CHESTERTON REGION: 3 |NOTIFICATION TIME: 13:12 [ET]| | COUNTY: PORTER STATE: IN |EVENT DATE: 06/15/95 | |LICENSE#: 37-01861-05 AGREEMENT: N |EVENT TIME: 10:00[EDT]| | DOCKET: |LAST UPDATE DATE: 06/20/95 | | +-----------------------------+ | |PERSON ORGANIZATION| | |CURTIS COWGILL RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: TONY LAMASTRA | | |HQ OPS OFFICER: RUDY KARSCH | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |BAD1 20.2202(a)(1) PERS OVEREXPOSURE | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | BETHLEHEM STEEL; BURNS HARBOR PLANT; CHESTERTON, INDIANA. | | EXPOSURE TO NON-RADIATION WORKERS. | | | | THE LICENSEE WAS RUNNING CALIBRATION TESTS ON A THICKNESS GAGE WHEN THREE | | WELDERS WANDERED INTO THE ROOM. THE ROOM WAS IDENTIFIED AS A HIGH RADIATION | | AREA. THE SOURCE, 50 CURIES OF Cs 137, COULD CAUSE A WORST CASE EXPOSURE | | OF 120 mR FOR THE TWO MINUTES THE SOURCE WAS OUTSIDE THE SHIELD. | | | | THE LICENSEE HAS TAKEN THE FOLLOWING CORRECTIVE ACTIONS: THE WARNING LIGHT | | AT THE DOOR HAS BEEN MOVED TO A MORE VISIBLE LOCATION; THE DOOR LOCKING | | PROCEDURE HAS BEEN MADE MORE STRICT; THE WORKERS WERE COUNSELLED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28967 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: POINT BEACH REGION: 3 |NOTIFICATION DATE: 06/20/95 | |UNIT: [1] [2] [ ] STATE: WI |NOTIFICATION TIME: 18:08 [ET]| |RX TYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 06/20/95 | +------------------------------------------------+EVENT TIME: 16:45[CDT]| |NRC NOTIFIED BY: CAPT SCHWALBE |LAST UPDATE DATE: 06/20/95 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN JACOBSON RDO | |DUNE 73.71(b)(1) UNAUTHORIZED ENTRY | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ENTRY INTO THE PROTECTED AREA BY AN EMPLOYEE WHOSE ACCESS HAD BEEN | | TERMINATED. | | | | AN EMPLOYEE HAD HIS ACCESS TO THE PROTECTED AREA CANCELED ON JUNE 16, 1995. | | DUE TO A MIS-COMMUNICATION HIS BADGE WAS NOT REMOVED FROM THE RACK OF | | ACTIVE BADGES. ON JUNE 18, 1995, IN VIOLATION OF INSTRUCTIONS FROM HIS | | SUPERVISOR, HE ENTERED THE PROTECTED AREA TO CLEAN OUT HIS DESK. THE | | LICENSEE CONSIDERS THIS AN UNAUTHORIZED ENTRY. THE LICENSEE WILL INFORM | | THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28968 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: ROBINSON REGION: 2 |NOTIFICATION DATE: 06/20/95 | |UNIT: [2] [ ] [ ] STATE: SC |NOTIFICATION TIME: 18:35 [ET]| |RX TYPE: [2] W-3-LP |EVENT DATE: 06/20/95 | +------------------------------------------------+EVENT TIME: 18:03[EDT]| |NRC NOTIFIED BY: MARTIN ARNOLD |LAST UPDATE DATE: 06/21/95 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: ALERT +-----------------------------+ |10 CFR SECTION: |JOHN POTTER RDO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |STEVEN VARGA EO | |NLCO TECH SPEC LCO A/S |BELCHER FEMA | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 2 | N Y 0 STARTUP | 0 STARTUP | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ALERT DECLARED AND TERMINATED AT 1803 EDT DUE TO REACTOR COOLANT SYSTEM | | LEAKAGE IN EXCESS OF 50 GALLONS PER MINUTE DUE TO A FAILED CHARGING PUMP | | RELIEF VALVE. | | | | AT 1735 EDT A CHARGING PUMP RELIEF VALVE WENT FULLY OPEN CAUSING A REACTOR | | COOLANT LEAK OF 75 GALLONS PER MINUTE. AT 1750 EDT THE LEAK WAS STOPPED BY | | ISOLATING PUMP "A". ABOUT 1125 GALLONS OF PRIMARY COOLANT WERE RELEASED | | VIA THE 3/4 INCH RELIEF LINE TO A DRAIN TO A LIQUID RAD WASTE HOLD UP TANK. | | PRESSURIZER LEVEL FLUCTUATED SLIGHTLY (BETWEEN 10 TO 15%) BUT WAS | | CONTROLLED WITH ADDITIONAL CHARGING FROM PUMPS "B" AND "C" AND BY REDUCING | | LETDOWN. THE LEAK EXCEEDED THE TECH SPEC 3.1.5.1 LIMIT OF 1 GALLON PER | | MINUTE. | | | | THE PLANT WAS IN THE PROCESS OF RESTART FOLLOWING A REFUELING OUTAGE. | | CONSEQUENTLY ACTIVITY WAS LOW. GROSS ACTIVITY WAS MEASURED AT 1.15 EXP -3 | | MICRO-CURIES PER CUBIC CENTIMETER DUE TO MIXED NUCLIDES. NO PERSONNEL WERE | | EXPOSED. | | | | THE LICENSEE WILL REPAIR OR REPLACE THE FAILED VALVE AND CONTINUE WITH | | PLANT RESTART. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR AND THE STATE AND THREE | | LOCAL COUNTY WARNING POINTS. | | | | ** UPDATE @ 0917 EDT ON 6/21/95 ***FROM LICENSEE: DORMAN BY:McGINTY ** | | THE LICENSEE PROVIDED A FOLLOWUP NOTIFICATION TO SPECIFY THAT A PRESS | | RELEASE REGARDING THE EVENT HAD BEEN ISSUED AT ABOUT 2000 EDT ON 6/20/95. | | THE LICENSEE WILL NOTIFY THE RESIDENT INSPECTOR. HOO NOTIFIED THE R2DO. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 28969 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: SYNCOR |NOTIFICATION DATE: 06/20/95 | | CITY: SHARON HILL REGION: 1 |NOTIFICATION TIME: 19:19 [ET]| | COUNTY: DELAWARE STATE: PA |EVENT DATE: 06/20/95 | |LICENSE#: 37-18461-01MD AGREEMENT: N |EVENT TIME: 12:10[EDT]| | DOCKET: |LAST UPDATE DATE: 06/20/95 | | +-----------------------------+ | |PERSON ORGANIZATION| | |LAWRENCE DOERFLEIN RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: TARA DOMITER |ELMO COLLINS R4DO | |HQ OPS OFFICER: RUDY KARSCH | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |IBBF 30.50(b)(2)(ii) EQUIP DISABLED/FAILS | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LOCATION: SYNCOR, AT 650 ELMWOOD AVE, SHARON HILL, PA. NOTIFICATION BY | | CORPORATE OFFICE IN CHATSWORTH, CA. | | | | A FUME HOOD FAILURE WILL CAUSE WORK STOPPAGE IN EXCESS OF 24 HOURS. THE | | FUME HOOD WAS USED FOR THE STORAGE OF SEALED RADIOPHARMACEUTICALS (I 131 | | AND Xe 133). AIR SAMPLING OF THE EXHAUST STACK SHOWED NO EFFLUENT RELEASE | | AND ACTIVITY BELOW REGULATORY LIMITS. THE CAUSE OF THE FUME HOOD FAILURE | | (BLOWER MOTOR FAILED) IS NOT KNOWN. NO ONE WAS IN THE ROOM AT THE TIME THE | | FUME HOOD FAILED. NO PERSONNEL WERE EXPOSED TO RADIATION. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28970 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: ARKANSAS NUCLEAR REGION: 4 |NOTIFICATION DATE: 06/20/95 | |UNIT: [1] [ ] [ ] STATE: AR |NOTIFICATION TIME: 21:04 [ET]| |RX TYPE: [1] B&W-L-LP,[2] CE |EVENT DATE: 06/20/95 | +------------------------------------------------+EVENT TIME: 17:50[CDT]| |NRC NOTIFIED BY: REX KNIGHT |LAST UPDATE DATE: 06/20/95 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |ELMO COLLINS RDO | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 99 POWER OPERATION | 99 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ARKANSAS DEPARTMENT OF HEALTH NOTIFIED THAT AN EMPLOYEE WAS TRANSPORTED TO | | A HOSPITAL DUE TO A MEDICAL EMERGENCY. | | | | A CONTRACTOR EMPLOYEE COMPLAINED OF CHEST PAINS. AN AMBULANCE WAS CALLED, | | BUT THE EMPLOYEE ELECTED TO HAVE HER SUPERVISOR DRIVE HER TO DARDENELLE | | HOSPITAL. NO CONTAMINATION WAS INVOLVED. THE LICENSEE INFORMED THE NRC | | RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28971 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FITZPATRICK REGION: 1 |NOTIFICATION DATE: 06/20/95 | |UNIT: [1] [ ] [ ] STATE: NY |NOTIFICATION TIME: 21:09 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 06/20/95 | +------------------------------------------------+EVENT TIME: 18:15[EDT]| |NRC NOTIFIED BY: KERRY ALLEN |LAST UPDATE DATE: 06/20/95 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LAWRENCE DOERFLEIN RDO | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | HIGH PRESSURE COOLANT INJECTION (HPCI) DECLARED INOPERABLE DUE TO HIGH PUMP | | VIBRATION. | | | | DURING THE PERFORMANCE OF "HPCI FLOW RATE AND INSERVICE TEST" THE HPCI MAIN | | PUMP VERTICAL VIBRATION MEASUREMENT EXCEEDED THE TEST IST ACCEPTANCE | | CRITERIA. THE LICENSEE DECLARED THE TEST UNSATISFACTORY AND DECLARED THE | | HPCI SYSTEM INOPERABLE. THE LICENSEE IS CURRENTLY IN DAY ONE OF THE SEVEN | | DAY LCO, FOR TECH SPEC 3.5.C.1, AND IS DETERMINING THE OPERABILITY OF ADS, | | RHR, AND CORE SPRAY. RCIC IS OPERABLE. THE LICENSEE INFORMED THE NRC | | RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28972 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HADDAM NECK REGION: 1 |NOTIFICATION DATE: 06/21/95 | |UNIT: [1] [ ] [ ] STATE: CT |NOTIFICATION TIME: 09:44 [ET]| |RX TYPE: [1] W-4-LP |EVENT DATE: 06/21/95 | +------------------------------------------------+EVENT TIME: 09:31[EDT]| |NRC NOTIFIED BY: BROWN |LAST UPDATE DATE: 06/21/95 | |HQ OPS OFFICER: TIM McGINTY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LAWRENCE DOERFLEIN RDO | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | NON-PLANT WORKERS ESTABLISHED A PICKET LINE ON PLANT ACCESS ROAD. | | | | THE LICENSEE REPORTED THAT COMPENSATORY MEASURES HAVE BEEN IMPLEMENTED DUE | | TO NON-PLANT WORKERS ESTABLISHING A PICKET LINE ON THE PLANTS ACCESS ROAD. | | THE PICKET LINE, HOWEVER, IS BEING OBSERVED BY SOME OF THE UNION PLANT | | WORKERS, AND TELEVISION NEWS MEDIA HAVE ARRIVED AT THE PICKET LINE. THE | | LICENSEE HAS IMPLEMENTED THE NORMAL STRIKE CONTINGENCY PLAN, WHICH INCLUDES | | RE-ARRANGING SCHEDULES AND PERSONNEL TO COVER THE POSITIONS NORMALLY | | OCCUPIED BY THE PEOPLE WHO WILL NOT CROSS THE LINE. THE LICENSEE HAS | | INFORMED THE RESIDENT INSPECTOR, AND MAY ISSUE A PRESS RELEASE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 28973 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: INDIANA DOT |NOTIFICATION DATE: 06/21/95 | | CITY: REGION: 3 |NOTIFICATION TIME: 11:45 [ET]| | COUNTY: VIGO STATE: IN |EVENT DATE: 06/20/95 | |LICENSE#: 13-26344-01 AGREEMENT: N |EVENT TIME: 18:00[EDT]| | DOCKET: |LAST UPDATE DATE: 06/21/95 | | +-----------------------------+ | |PERSON ORGANIZATION| | |JOHN JACOBSON RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: DONALD FINE | | |HQ OPS OFFICER: DOUG WEAVER | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |BBBB 20.403 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | INDIANA DOT - STOLEN TROXLER GAUGE | | | | THE INDIANA DEPARTMENT OF TRANSPORTATION REPORTED A MODEL 3440 TROXLER | | GAUGE STOLEN. THE GAUGE CONTAINS 8 mCi OF Cs-137 AND 40 mCi OF Am 241. | | THE GAUGE WAS STOLEN SOMETIME BETWEEN 3:00 PM ON JUNE 20TH AND 7:00 AM ON | | JUNE 21ST. | | | | THE LICENSEE FILED A REPORT WITH THE INDIANA STATE POLICE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28974 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PEACH BOTTOM REGION: 1 |NOTIFICATION DATE: 06/21/95 | |UNIT: [2] [3] [ ] STATE: PA |NOTIFICATION TIME: 12:06 [ET]| |RX TYPE: [2] GE-4,[3] GE-4 |EVENT DATE: 06/21/95 | +------------------------------------------------+EVENT TIME: 01:38[EDT]| |NRC NOTIFIED BY: GLENN DISHONG |LAST UPDATE DATE: 06/21/95 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LAWRENCE DOERFLEIN RDO | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | 3 | N Y 81 POWER OPERATION | 81 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE DETERMINED AT 1130 EDT THAT A DESIGN ERROR IN A MOD COMMON TO | | TWO EMERGENCY DIESEL GENERATORS (EDG) PLACED THE PLANTS OUTSIDE OF THEIR | | DESIGN BASIS. | | | | EDG "E4" WAS OUT OF SERVICE FOR MAINTENANCE AND FOR INSTALLATION OF A | | MODIFICATION. EDG "E2" HAD THE SAME MOD INSTALLED ON 6/4/95. AT 0138 EDT | | THE LICENSEE DETERMINED THAT A DESIGN PROBLEM WITH THE MOD WOULD PREVENT | | AUTO CLOSURE OF THE EDG OUTPUT CIRCUIT BREAKERS UPON LOSS OF POWER TO THEIR | | RESPECTIVE EMERGENCY LOAD CENTERS. CONSEQUENTLY THE "E2" EDG WAS DECLARED | | INOPERABLE AT 0138 EDT. THE SIMULTANEOUS INOPERABILITY OF THE "E2" AND | | "E4" EDGs IS NOT PART OF THE DESIGN BASIS. | | | | THE DESIGN ERROR WAS CORRECTED AND THE "E2" EDG WAS DECLARED OPERABLE AT | | 0250 EDT ON 6/21/95. MAINTENANCE AND MOD WORK IS CONTINUING ON THE "E4" | | EDG. WITH ONE EDG OUT OF SERVICE THE LICENSEE IS IN A SEVEN DAY LCO PER | | TECH SPEC 3.9.B.3. THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28975 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PRAIRIE ISLAND REGION: 3 |NOTIFICATION DATE: 06/21/95 | |UNIT: [ ] [2] [ ] STATE: MN |NOTIFICATION TIME: 21:59 [ET]| |RX TYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 06/21/95 | +------------------------------------------------+EVENT TIME: 20:02[CDT]| |NRC NOTIFIED BY: JIM HUEBNER |LAST UPDATE DATE: 06/21/95 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN JACOBSON RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | A/R N 0 HOT SHUTDOWN | 0 HOT SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | REACTOR TRIP DUE TO LOW LEVEL IN ONE STEAM GENERATOR. | | | | WHILE PREPARING TO INITIATE AUXILIARY FEEDWATER FLOW FOR MAKE UP TO THE | | STEAM GENERATORS DURING UNIT HEAT UP, A REACTOR TRIP OCCURRED BECAUSE OF | | LOW WATER LEVEL IN ONE STEAM GENERATOR. ALL CONTROL RODS (SHUTDOWN BANKS) | | FULLY INSERTED. THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28976 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 06/21/95 | |UNIT: [1] [ ] [ ] STATE: CT |NOTIFICATION TIME: 23:36 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 06/21/95 | +------------------------------------------------+EVENT TIME: 23:03[EDT]| |NRC NOTIFIED BY: WILLIAM SPAHN |LAST UPDATE DATE: 06/21/95 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LAWRENCE DOERFLEIN RDO | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE REPORTED THAT DESIGN DISCREPANCIES HAVE THE POTENTIAL TO | | PREVENT THE FULFILLMENT OF THE SAFETY FUNCTION OF THE SECONDARY CONTAINMENT | | AIR TREATMENT SYSTEM. | | | | THE LICENSEE HAS DETERMINED THAT DURING SBGT (STANDBY GAS TREATMENT) | | OPERATION WITH SUBSEQUENT FAILURE OF THE OTHER SBGT TRAIN CONCURRENT WITH | | THE LOSS OF NON-QA INSTRUMENT AIR, RECIRCULATION THROUGH THE IDLE SBGT | | FILTER TRAIN VIA FAIL OPEN ON LOSS OF AIR VALVES COULD POTENTIALLY RESULT | | IN THE INABILITY TO MAINTAIN SAFETY TECH SPEC REQUIRED NEGATIVE PRESSURE IN | | SECONDARY CONTAINMENT. THE CONDITION IS APPARENTLY THE RESULT OF A POOR | | ORIGINAL DESIGN CHARACTERISTIC. | | | | FOR THIS POTENTIAL "WINDMILLING" PROBLEM, THE LICENSEE HAS DECLARED BOTH | | SBGT TRAINS INOPERABLE (@ 2200 EDT), AND HAS 24 HOURS TO RETURN ONE TRAIN | | TO OPERATION OR TO BE SHUTDOWN PER T/S SECTION 3.7.B. THE LICENSEE | | ANTICIPATES RETURNING ONE SBGT TRAIN TO SERVICE, THUS ENTERING A 7 DAY LCO, | | AND WILL INITIATE THE PROCESS OF TAGGING OUT AND ISOLATING ONE OF THE SBGT | | TRAINS. THE LICENSEE WILL BE PERFORMING A SPECIAL TEST IN THE NEW | | ALIGNMENT TO CONFIRM THAT SECONDARY CONTAINMENT REQUIREMENTS ARE MET. | | | | ADDITIONALLY, THE LICENSEE HAS ALSO EVALUATED T/S LCO 3.7.B.6, WHICH | | REQUIRES THAT "PRIMARY CONTAINMENT SHALL BE PURGED THROUGH THE SBGT SYSTEM | | AT ALL TIMES WHEN PRIMARY CONTAINMENT IS REQUIRED". THIS ALIGNMENT | | REQUIREMENT COULD POTENTIALLY CHALLENGE THE OPERABILITY (STRUCTURAL/LEAKAGE | | INTEGRITY) OF BOTH TRAINS OF THE SBGT FILTER HOUSING (FABRICATED OF SHEET | | METAL) IF LOCA TORUS/DRYWELL PRESSURE CONDITIONS OF APPROXIMATELY 45 PSIG | | WERE EXPERIENCED COINCIDENTALLY WITH PURGING/VENTING OPERATIONS. | | | | FOR THIS CONCERN, THE LICENSEE WILL RESTRICT VENTING OF PRIMARY CONTAINMENT | | TO THE SGTS AS A CORRECTIVE ACTION. THE LICENSEE WILL ALSO BE EVALUATING | | THE ABILITY TO ISOLATE A POSTULATED DEGRADED SBGT TRAIN AFTER RECEIPT OF A | | GROUP 2 ISOLATION (PRIMARY CONTAINMENT PRESSURE > 2.0 PSI) SIGNAL, AND THE | | POTENTIAL FOR DEGRADATION TO THE RESERVE SGTS FILTER HOUSING IF A LOCA WERE | | EXPERIENCED. | | | | THE LICENSEE WILL NOTIFY THE RESIDENT INSPECTOR, AND HAS NOTIFIED STATE AND | | LOCAL AUTHORITIES. LONG TERM CORRECTIVE ACTIONS FOR THE PROBLEMS ARE BEING | | EVALUATED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28977 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PALO VERDE REGION: 4 |NOTIFICATION DATE: 06/22/95 | |UNIT: [1] [2] [3] STATE: AZ |NOTIFICATION TIME: 14:33 [ET]| |RX TYPE: [1] CE,[2] CE,[3] CE |EVENT DATE: 06/22/95 | +------------------------------------------------+EVENT TIME: 10:30[MST]| |NRC NOTIFIED BY: BRAD EKLUND |LAST UPDATE DATE: 06/22/95 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DALE POWERS RDO | |AINB 50.72(b)(2)(iii)(B) POT RHR INOP | | |AINC 50.72(b)(2)(iii)(C) POT UNCNTRL RAD REL | | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | 3 | N Y 100 POWER OPERATION | 100 POWER OPERATION | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | IF A SAFE SHUTDOWN EARTHQUAKE HAD OCCURRED BETWEEN JULY 17, 1992, AND APRIL | | 28, 1994, A FAILURE OF NON-SEISMIC RADIATION MONITORS COULD HAVE PREVENTED | | THE FULFILLMENT OF THE SAFETY FUNCTION OF ESSENTIAL COOLING WATER. | | | | THE LICENSEE DISCOVERED THAT IF A SAFE SHUTDOWN EARTHQUAKE HAD OCCURRED | | BETWEEN JULY 17, 1992, AND APRIL 28, 1994, A FAILURE OF NON-SEISMIC | | RADIATION MONITORS COULD HAVE PREVENTED THE FULFILLMENT OF THE SAFETY | | FUNCTION OF THE ESSENTIAL COOLING WATER SYSTEM. THIS CONDITION WAS | | PREVIOUSLY IDENTIFIED, BUT IT WAS DETERMINED AT THAT TIME THAT IT DID NOT | | AFFECT THE OPERABILITY OF THE ESSENTIAL COOLING WATER SYSTEM. HOWEVER, THE | | RADIATION MONITORS HAVE BEEN ISOLATED SINCE APRIL 28, 1994, AS A | | CONSERVATIVE MEASURE. ON JUNE 14, 1995, DURING THE PERFORMANCE OF | | ADDITIONAL EVALUATIONS TO UPGRADE THE RADIATION MONITORS TO SEISMIC | | REQUIREMENTS, THE LICENSEE'S ENGINEERING PERSONNEL DETERMINED THAT THE | | ESSENTIAL COOLING WATER RADIATION MONITORS WERE NOT CAPABLE OF WITHSTANDING | | A SAFE SHUTDOWN EARTHQUAKE. THE LICENSEE EVALUATED THIS CONDITION FOR | | REPORTABILITY AND DETERMINED IT TO BE REPORTABLE ON JUNE 22, 1995. | | | | THE ESSENTIAL COOLING WATER RADIATION MONITORS ARE LOCATED IN LINES | | APPROXIMATELY ONE-INCH IN DIAMETER WHICH GO FROM THE SUCTION SIDE OF THE | | PUMP TO THE DISCHARGE SIDE OF THE PUMP. THE LICENSEE'S EVALUATION | | DETERMINED THAT THERE WAS NOT ENOUGH SEISMIC SUPPORT FOR THESE LINES AND | | THAT IF ONE OF THESE LINES WOULD HAVE BROKEN DURING A SAFE SHUTDOWN | | EARTHQUAKE (WHILE THE LINE WAS NOT ISOLATED AND DEPENDING ON THE SIZE OF A | | POTENTIAL LINE BREAK), SURGE TANK LEVEL COULD HAVE DECREASED LOW ENOUGH SO | | THAT IT COULD HAVE AFFECTED ESSENTIAL COOLING WATER PUMP OPERATIONS. | | | | THE RESIDENT INSPECTOR WAS NOTIFIED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28978 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SALEM REGION: 1 |NOTIFICATION DATE: 06/22/95 | |UNIT: [1] [2] [ ] STATE: NJ |NOTIFICATION TIME: 16:48 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 06/22/95 | +------------------------------------------------+EVENT TIME: 15:00[EDT]| |NRC NOTIFIED BY: MIKE HEALY |LAST UPDATE DATE: 06/22/95 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CURTIS COWGILL RDO | |ADAS 50.72(b)(2)(i) DEG/UNANALYZED COND | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | 2 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ANALYSIS OF A WESTINGHOUSE BULLETIN REGARDING THE USE OF RIVER WATER AS A | | POTENTIAL BACKUP SOURCE FOR THE STEAM GENERATORS RESULTED IN THE | | DETERMINATION THAT BOTH UNITS PREVIOUSLY OPERATED IN AN UNANALYZED | | CONDITION. | | | | WESTINGHOUSE BULLETIN 89-02 CHANGED THE DESIGN OF THE STATION SUCH THAT THE | | RECOMMENDATION FOR THE USE OF SERVICE WATER (RIVER WATER) AS A BACKUP | | SOURCE OF COOLING WATER FOR THE STEAM GENERATORS WAS DEEMED NOT | | RECOMMENDED. BOTH UNITS HAD OPERATED SINCE THE ISSUANCE OF THE BULLETIN | | WITHOUT ANY CHANGES TO THE STATION, AND IT HAS BEEN DETERMINED THAT A | | MODIFICATION CHANGE WILL BE REQUIRED PRIOR TO THE STARTUP OF EITHER UNIT. | | THE MODIFICATION (WHICH IS STILL UNDER EVALUATION) WOULD INVOLVE THE USE AN | | ALTERNATE SOURCE OF COOLING WATER AND/OR THE COMPLETION OF AN ANALYSIS THAT | | WOULD RECOMMEND THE USE OF RIVER WATER. | | | | THE BULLETIN RESCINDED A RECOMMENDATION FOR THE INITIAL DESIGN FOR ALLOWING | | USE OF THE RIVER WATER, BUT IT HAD A STIPULATION ALLOWING THE USE OF RIVER | | WATER AT A CERTAIN CHLORIDE CONCENTRATION FOR A CERTAIN LENGTH OF TIME. IF | | AN ACCIDENT (EARTHQUAKE/TORNADO) WERE TO OCCUR IN WHICH THE NORMAL STEAM | | GENERATOR COOLING WATER SUPPLY (AUXILIARY FEEDWATER TANKS) WAS LOST, THE | | BULLETIN STIPULATION WOULD ALLOW THE USE OF RIVER WATER FOR ONLY A CERTAIN | | AMOUNT OF TIME IN ORDER TO COOL DOWN. ALTHOUGH THERE IS A CAVEAT IN THE | | WESTINGHOUSE BULLETIN THAT ALLOWS THE USE OF RIVER WATER, THE UNITS ARE | | CURRENTLY NOT DESIGNED TO MEET THE WESTINGHOUSE SPECIFICATIONS TO COOL DOWN | | WITHIN THE 24-HOUR PERIOD SPECIFIED IN THE BULLETIN. | | | | THE RESIDENT INSPECTOR AND LOWER ALLOWAYS CREEK TOWNSHIP WILL BE NOTIFIED | | BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28979 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HOPE CREEK REGION: 1 |NOTIFICATION DATE: 06/22/95 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 18:01 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 06/22/95 | +------------------------------------------------+EVENT TIME: 16:30[EDT]| |NRC NOTIFIED BY: JOHN DEDOMENICO |LAST UPDATE DATE: 06/22/95 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CURTIS COWGILL RDO | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | BOTH HPCI AND RCIC WERE DETERMINED TO HAVE BEEN INOPERABLE ON 6/21/95. | | | | AT 0622 ON JUNE 21, 1995, THE OPERATING CREW WAS INFORMED OF A CRACK IN THE | | LEAK-OFF LINE OF THE HPCI MINIMUM FLOW LINE CHECK VALVE. A MAINTENANCE | | WORKER DISCOVERED WEEPING AT THE TOE OF THE WELD WHERE IT ATTACHES TO THE | | STUFFING BOX ON THE BODY OF THE VALVE. THE INITIAL OPERABILITY | | DETERMINATION PROVIDED REASONABLE ASSURANCE OF CONTINUED HPCI OPERABILITY. | | (THE UNIT HAS A SINGLE HPCI PUMP THAT PROVIDES BOTH THE HIGH PRESSURE CORE | | SPRAY AS WELL AS THE THE HIGH PRESSURE FEED THROUGH THE FEEDWATER LINE.) AT | | 1630 ON 6/22/95, FURTHER ANALYSIS OF THE ASME BOILER AND PRESSURE VESSEL | | CODE REQUIREMENTS RESULTED IN THE DETERMINATION THAT TECHNICAL | | SPECIFICATION 3.4.8 (STRUCTURAL INTEGRITY) WERE NOT MET. THE ACTION | | REQUIREMENT FOR THIS TECHNICAL SPECIFICATION IS TO ISOLATE THE AFFECTED | | COMPONENT. THIS RENDERS THE HPCI SYSTEM INOPERABLE. MAINTENANCE | | ACTIVITIES ARE IN PROGRESS TO PERFORM REPAIRS AND RESTORE THE OPERABILITY | | OF THE MINIMUM FLOW CHECK VALVE AND THE HPCI SYSTEM TONIGHT. | | | | IN ADDITION, THE RCIC PUMP HAD BEEN DECLARED OUT-OF-SERVICE AT 0348 ON JUNE | | 20, 1995, DUE TO A MOMENTARY LOW SUCTION PRESSURE RCIC TRIP ALARM AND THE | | OBSERVANCE OF LOW SUCTION PRESSURE SPIKES DURING THE PERFORMANCE OF THE | | MONTHLY HPCI SURVEILLANCE. (THE SINGLE HPCI AND RCIC PUMPS SHARE A COMMON | | SUCTION LINE FROM THE CONDENSATE STORAGE TANK.) FOLLOWING AN EVALUATION, | | THE RCIC PUMP WAS RETURNED TO SERVICE AT 1410 ON JUNE 21, 1995. THE | | LICENSEE DETERMINED THAT THE LOW SUCTION PRESSURE SPIKES WERE ASSOCIATED | | WITH THE DIFFERENCES IN THE FLOW PATHS FOR THE TEST AND OPERATING VALVE | | LINE UPS. WHEN HPCI IS OPERATED NORMALLY, THE FLOW DOES NOT INCREASE AS | | QUICKLY AS IN THE TEST LINEUP BECAUSE THE VALVES ACTUALLY STROKE OPEN DUE | | TO THE INITIATION SIGNAL; WHEREAS THE VALVES IN THE TEST FLOW PATH ARE | | ALIGNED PRIOR TO THE INITIATION OF HPCI AND THE SYSTEM HAS MINIMAL | | RESISTANCE. THE RAPID INITIATION OF HPCI FLOW THROUGH THE COMMON SUCTION | | LINE CAUSED THE RCIC SUCTION PRESSURE TO SPIKE LOW. | | | | AT THE TIME OF THE DISCOVERY OF THE FLAW IN THE HPCI MINIMUM FLOW CHECK | | VALVE, THE RCIC PUMP WAS INOPERABLE. SINCE RCIC WAS INOPERABLE AT THE TIME | | OF DISCOVERY OF THE HPCI FLAW, THE LICENSEE DID NOT MEET THE LIMITING | | CONDITION FOR OPERATION FOR HPCI OR RCIC AS PROVIDED IN THE ASSOCIATED | | ACTION REQUIREMENTS. THEREFORE, TECHNICAL SPECIFICATION 3.0.3 WAS | | APPLICABLE FROM 0622 TO 1410 ON JUNE 21, 1995, BUT WAS NOT ENTERED BECAUSE | | HPCI WAS BELIEVED TO BE OPERABLE AT THE TIME. | | | | THIS UNIT HAS FOUR LPCI PUMPS AND FOUR LPCS PUMPS. THESE PUMPS WERE | | OPERABLE THROUGHOUT THIS EVENT. | | | | THE RESIDENT INSPECTOR AND THE LOCAL TOWNSHIP WILL BE NOTIFIED BY THE | | LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28980 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SALEM REGION: 1 |NOTIFICATION DATE: 06/22/95 | |UNIT: [1] [2] [ ] STATE: NJ |NOTIFICATION TIME: 23:08 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 06/22/95 | +------------------------------------------------+EVENT TIME: 22:30[EDT]| |NRC NOTIFIED BY: JOE SERWAN |LAST UPDATE DATE: 06/22/95 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CURTIS COWGILL RDO | |ADAS 50.72(b)(2)(i) DEG/UNANALYZED COND | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | 2 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE ENGINEERING ASSUMPTIONS CONTAINED IN WCAP-11634 ARE NOT IN AGREEMENT | | WITH UFSAR SECTION 3.6.5.2 WHICH RESULTS IN BOTH UNITS POTENTIALLY | | OPERATING OUTSIDE THE DESIGN BASIS. | | | | WCAP-11634 DATED OCTOBER 20, 1987, HAS BEEN USED AS THE BASIS FOR | | ENVIRONMENTAL QUALIFICATION OF EQUIPMENT IN THE STEAM LINE PENETRATION AREA | | SINCE THE IMPLEMENTATION OF THE BORON INJECTION TANK REMOVAL LICENSE | | AMENDMENTS (NOS. 78 AND 52 FOR UNITS 1 AND 2, RESPECTIVELY) DATED APRIL 7, | | 1987. THE WCAP DOES NOT AGREE WITH THE UFSAR ASSUMPTIONS OF THE PIPE BREAK | | SIZE. ADDITIONALLY, THE WCAP USED THE ASSUMPTION THAT THE SUBJECT MAIN | | STEAM SYSTEM PIPING IS DESIGNED TO SUPERPIPE CRITERIA WITHOUT PROVIDING A | | DETAILED DEMONSTRATION OF THE CONFORMANCE TO THE NRC PIPE BREAK EXCLUSION | | CRITERIA OF BRANCH TECHNICAL POSITION MEB 3-1. THIS RESULTS IN BOTH UNITS | | POTENTIALLY OPERATING OUTSIDE THE DESIGN BASIS. RESOLUTION OF THIS ISSUE | | IS REQUIRED PRIOR TO RESTART OF EITHER UNIT, AND THE LICENSEE'S | | INVESTIGATION IS CURRENTLY ONGOING. | | | | THE LICENSEE HAS NOTIFIED THE RESIDENT INSPECTOR AND WILL NOTIFY THE LOWER | | ALLOWAYS CREEK TOWNSHIP. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28981 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SEQUOYAH REGION: 2 |NOTIFICATION DATE: 06/23/95 | |UNIT: [1] [ ] [ ] STATE: TN |NOTIFICATION TIME: 04:58 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 06/23/95 | +------------------------------------------------+EVENT TIME: 03:27[EDT]| |NRC NOTIFIED BY: EPPERSON |LAST UPDATE DATE: 06/23/95 | |HQ OPS OFFICER: TIM McGINTY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN POTTER RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | A/R Y 100 POWER OPERATION | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | REACTOR TRIP FROM 100% WHEN A NON-LICENSED PLANT EQUIPMENT OPERATOR | | INCORRECTLY OPENED A BREAKER TO PROCESS PROTECTION SET 1. | | | | THE UNIT 1 REACTOR TRIPPED FROM FULL POWER AT 0327 EDT ON 6/23/95. THE | | INITIATING SIGNAL WAS LOW-LOW LEVEL IN STEAM GENERATOR #2. THIS OCCURRED | | APPROXIMATELY 45 SECONDS AFTER THE 120 VAC VITAL POWER SUPPLY TO PROCESS | | PROTECTION SET 1 WAS INCORRECTLY OPENED BY A NON-LICENSED PLANT EQUIPMENT | | OPERATOR WHO WAS IN THE PROCESS OF PLACING AN EQUIPMENT CLEARANCE FOR | | ANOTHER DEVICE. | | | | THE PROCESS PROTECTION SETS (4) MONITOR VARIOUS PLANT PARAMETERS AND | | PROVIDE INPUT TO THE REACTOR PROTECTION SYSTEM LOGIC TRAINS AS WELL AS | | INPUT TO VARIOUS CONTROL SYSTEMS. THE OPENING OF THE POWER SUPPLY BREAKER | | APPARENTLY AFFECTED THE CONTROL OF THE MAIN FEEDWATER (STEAM GENERATOR | | WATER LEVEL CONTROL) SYSTEM, RESULTING IN THE REACTOR TRIP ON AN ACTUAL | | LOW-LOW LEVEL CONDITION IN STEAM GENERATOR #2. THE OTHER THREE PROTECTION | | SETS REMAINED ENERGIZED THROUGHOUT THE EVENT. | | | | ALL RODS FULLY INSERTED IN RESPONSE TO THE REACTOR TRIP. THERE WERE NO | | UNUSUAL PRIMARY LEVEL OR PRESSURE TRANSIENTS, AND NO PRIMARY RELIEF VALVES | | LIFTED. THE STEAM GENERATOR PORV's OPENED MOMENTARILY, AS EXPECTED, DUE TO | | THE TRANSIENT. THE PLANT IS STABLE IN HOT STANDBY, STEAMING VIA THE | | BYPASSES TO THE MAIN CONDENSER AND FEEDING THE STEAM GENERATORS WITH AUX | | FEEDWATER (AFW AUTO-STARTED, AS EXPECTED). THERE WERE NO PROBLEMS WITH BUS | | TRANSFERS. THE EDG's AND ECCS's ARE OPERATIONAL AND IN STANDBY. THE | | LICENSEE HAS INITIATED AN INVESTIGATION OF THE CAUSE, AND HAS INFORMED THE | | RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+