U.S. Nuclear Regulatory Commission Operations Center Event Reports For 11/18/94 - 11/21/94 ** EVENT NUMBERS ** 27832 27977 28045 28046 28047 28048 28049 28050 28051 28052 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27832 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DRESDEN REGION: 3 |NOTIFICATION DATE: 09/28/94 | |UNIT: [ ] [2] [ ] STATE: IL |NOTIFICATION TIME: 17:33 [ET]| |RX TYPE: [1] GE-1,[2] GE-3,[3] GE-3 |EVENT DATE: 09/28/94 | +------------------------------------------------+EVENT TIME: 15:00[CDT]| |NRC NOTIFIED BY: JERRY LIZALEK |LAST UPDATE DATE: 11/19/94 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |WAYNE SHAFER 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LICENSEE RESPONSE TO GENERIC LETTER 89-10 (SAFETY-RELATED MOTOR-OPERATED | | VALVE TESTING AND SURVEILLANCE). | | | | "AS A RESULT OF GENERIC LETTER 89-10, POTENTIAL DISCREPANCIES WERE | | IDENTIFIED ON 6/4/92 BETWEEN THE COMPONENT CONFIGURATION USED IN THE | | MARK 1 PIPING ANALYSIS AND THE AS-BUILT CONDITION. THIRTY NINE LINES | | WERE IDENTIFIED WITH POTENTIAL DISCREPANCIES. ON SEPTEMBER 28, 1994, | | TWO LINES WERE DETERMINED TO EXCEED UFSAR ALLOWABLE STRESSES. THESE | | TWO LINES CONTAIN THE "2-1501-19A & B" VALVES. THESE VALVES ARE REQUIRED | | TO FULFILL THE LOW PRESSURE COOLANT INJECTION (LPCI) TORUS SPRAY FUNCTION. | | AN OPERABILITY DETERMINATION "ENC-QE-40.1" CHRON #186845 WAS PERFORMED | | PREVIOUSLY ON 6/4/92 AND IT WAS CONCLUDED THAT THE "2-1501-19A & B" LINE | | STRESSES REMAIN WITHIN OPERABILITY STRESS LIMITS. OF THE THIRTY NINE LINES | | IDENTIFIED WITH POTENTIAL DISCREPANCIES, THIRTY FIVE LINES HAVE BEEN SHOWN | | TO BE WITHIN UFSAR ALLOWABLE STRESSES. TWO LINES REMAIN TO BE ANALYZED. | | THESE LINES ARE THE UNIT 3 LOW PRESSURE COOLANT INJECTION TORUS SPRAY LINES | | CONTAINING THE "3-1501-19A & B" VALVES." | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | * * UPDATE AT 0457 ON 09/29/94 BY McDONALD REQUESTED BY HOO JOLLIFFE * * | | | | THE FOLLOWING IS A CLARIFICATION OF THE ABOVE REPORT: | | | | THE ANALYSIS OF THE ADEQUACY OF THE TWO LINES CONTAINING THE UNIT 2 LPCI | | TORUS SPRAY VALVES (#2-1501-19A & B) PERFORMED IN 1992 WAS BASED ON | | ENGINEERING DESIGN DOCUMENTS. THE REANALYSIS OF THE ADEQUACY OF THESE | | SAME TWO LINES AND VALVES PERFORMED IN 1994 WAS BASED ON FIELD WALKDOWNS | | OF THE INSTALLED EQUIPMENT AS WELL AS ENGINEERING DESIGN DOCUMENTS. | | | | THIS REANALYSIS SHOWED THAT 35 OF 39 LINES AND VALVES IN QUESTION ARE | | ADEQUATE. THE UNIT 2 LPCI TORUS SPRAY LINES AND VALVES WERE DETERMINED | | TO EXCEED UFSAR ALLOWABLE STRESS LIMITS. LICENSEE IS ANALYZING THE UNIT 3 | | LPCI TORUS SPRAY LINES AND VALVES. | | | | LICENSEE HAS BEEN IN CONTACT WITH REGION 3 ON THIS ISSUE. | | | | HOO NOTIFIED R3DO SHAFER. | | | | * * * UPDATE AT 1408 ON 11/19/94 BY MATTSON ENTERED BY HOO JOLLIFFE * * * | | | | LICENSEE REQUESTS THAT THE FOLLOWING REPORT REPLACES THE ABOVE REPORT: | | | | LICENSEE HAS PERFORMED AN OPERABILITY DETERMINATION FOR THE UNIT 2 | | LOW PRESSURE COOLANT INJECTION (LPCI) TORUS SPRAY VALVES (#2-1501-19A & B) | | AND HAS DETERMINED THAT THESE VALVES ARE OPERABLE AND THEREFORE DID NOT | | MEET THE NOTIFICATION CRITERIA OF 10CFR50.72(b)(2)(i) ON 09/28/94. | | | | HOWEVER, LICENSEE HAS ALSO DETERMINED THAT THESE UNIT 2 VALVES EXPERIENCE | | STRESSES BEYOND THE UFSAR DESIGN CODE DESIGN BASIS. | | | | LICENSEE HAS STARTED UNIT 2 UP WITH THESE VALVES OUTSIDE THE UFSAR DESIGN | | BASIS (PRESENTLY AT 2% POWER) AND THEREFORE MEET THE NOTIFICATION CRITERIA | | OF 10CFR50.72(b)(1)(ii)(B). | | | | LICENSEE PLANS TO RESTORE THESE UNIT 2 VALVES TO WITHIN UFSAR DESIGN CODE | | ALLOWABLE STRESSES DURING THE UPCOMING UNIT 2 REFUELING OUTAGE SCHEDULED | | FOR MID-1995. | | | | THIS SITUATION WAS DISCUSSED WITH THE NRC RESIDENT INSPECTOR AND REGION 3 | | REPRESENTATIVES ON 10/13/94. | | | | A PLANT MODIFICATION WAS PERFORMED ON THE UNIT 3 LPCI TORUS SPRAY VALVES | | (#3-1501-19A & B) DURING THE RECENT UNIT 3 OUTAGE TO BRING THESE UNIT 3 | | VALVES TO WITHIN UFSAR DESIGN CODE ALLOWABLE STRESS LIMITS. UNIT 3 IS | | PRESENTLY AT 69% POWER. | | | | LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | HOO NOTIFIED R3DO JACK GROBE. | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27977 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 11/02/94 | |UNIT: [ ] [2] [ ] STATE: CT |NOTIFICATION TIME: 16:44 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 11/02/94 | +------------------------------------------------+EVENT TIME: 16:30[EST]| |NRC NOTIFIED BY: ALBERT OLECHNOWICZ |LAST UPDATE DATE: 11/18/94 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CLIFF ANDERSON RDO | |AINC 50.72(b)(2)(iii)(C) POT UNCNTRL RAD REL | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | "B" ENCLOSURE FILTRATION FAN FOUND TO BE BELOW DESIGN FLOW RATE DURING ITS | | 18 MONTH SURVEILLANCE TEST. | | | | DESIGN FLOW RATE OF THE "B" ENCLOSURE BUILDING FILTRATION FAN (F25B) IS | | 9000cfm. DURING ITS 18 MONTH SURVEILLANCE TEST "B" ENCLOSURE BUILDING | | FILTRATION (F25B) FLOW RATE WAS MEASURED AT 7892cfm & 7974cfm. TRAIN "A" & | | "B" ENCLOSURE BUILDING FILTRATION FANS ARE REQUIRED TO BE FULLY OPERABLE | | WHEN IN MODES 1,2,3, & 4 (DESIGN FLOW RATE OF AT LEAST 9000cfm PER FAN). | | LICENSE WILL PERFORM A SYSTEM FLOW CHECK TO FIND FLOW RESTRICTION. LICENSEE | | THINKS THAT ONE OR MORE OF THE SYSTEM DAMPERS IS NOT PROPERLY POSITIONED. | | TRAIN "A" ENCLOSURE BUILDING FILTRATION FAN IS FULLY OPERABLE. | | LAST REFUELING OUTAGE BOTH TRAIN "A" & "B" ENCLOSURE BUILDING FILTRATION | | FANS PASSED THEIR SURVEILLANCE TEST. LICENSEE NOTIFIED NEW LONDON COUNTY | | AND THE STATE OF CONNECTICUT OF THIS EVENT. | | | | RESIDENT INSPECTOR WILL BE INFORMED BY THE LICENSEE. | | | | ***UPDATE AT 09:52 11/18/94 BY RESETAR TO GOULD*** THE LICENSEE IS | | RETRACTING THIS EVENT SINCE IT WAS DETERMINED THAT THE AUX EXHAUST SYSTEM | | DOES NOT HAVE TO BE CAPABLE OF 9000cfm, ITS ONLY REQUIREMENT IS TO MAINTAIN | | A NEGATIVE PRESSURE, WHICH IT DOES, ON THEIR SPENT FUEL POOL AREA. | | THEREFORE THE SYSTEM HAS BEEN OPERABLE ALL ALONG AND SHOULD NOT HAVE BEEN | | REPORTED. THE 9000cfm IS FOR THEIR ENCLOSURE BUILDING FILTRATION SYSTEM, | | WHICH IS PART OF THE AUX EXHAUST SYSTEM. THE RI WAS INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28045 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SALEM REGION: 1 |NOTIFICATION DATE: 11/18/94 | |UNIT: [1] [2] [ ] STATE: NJ |NOTIFICATION TIME: 04:11 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 11/18/94 | +------------------------------------------------+EVENT TIME: 01:03[EST]| |NRC NOTIFIED BY: HAMILTON |LAST UPDATE DATE: 11/18/94 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN WHITE 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 | 98 POWER OPERATION | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE HAD AN AUTO START OF THE UNIT 2 EMERGENCY DIESELS DUE TO THE | | OPENING OF THE #4 STATION POWER TRANSFORMER(SPT) LOAD BREAK DISCONNECT. | | | | THE CAUSE FOR THIS SPT LOAD BREAK DISCONNECT OPENING IS UNKNOWN AND BEING | | INVESTIGATED AT THIS TIME. THIS CONDITION CAUSED THE #14 & #23 SPT TO | | BECOME DEENERGIZED. AFFECTS ON UNIT 1 WERE THE "1C" 4KV VITAL BUS BEING | | TRANSFERRED TO #13 SPT AND #14 CIRC WATER 4KV BUS BECOMING DEENERGIZED, | | RESULTING IN THE LOSS OF 2 CIRCULATORS. THE THIRD CIRCULATOR ON THIS BUS | | WAS ALREADY OUT OF SERVICE FOR MAINTENANCE. UNIT 1 POWER WAS INITIALLY | | REDUCED FROM 100% TO 98% DUE TO THE REDUCED CONDENSER COOLING. AFFECTS ON | | UNIT 2 ARE THE "2B" & "2C" 4KV VITAL BUSES BEING DEENERGIZED AS A RESULT OF | | THE LOSS OF #23 SPT. THESE BUSES WERE REENERGIZED BY THEIR RESPECTIVE | | DIESEL GENERATORS("2B" & "2C"). NOTE, ONLY ONE SOURCE OF OFFSITE POWER WAS | | AVAILABLE BECAUSE OF THE ONGOING REFUELING OUTAGE. BY DESIGN, THE BLACKOUT | | SEQUENCER SECURED THE INSERVICE SPENT FUEL PIT PUMP. THIS PUMP WAS | | RESTARTED WITHIN 18 MINS WITH NO NOTICEABLE TEMPERATURE INCREASES IN THE | | SPENT FUEL PIT. THE DIESELS ARE STILL RUNNING UNTIL THEY DETERMINE THE | | CAUSE OF THE PROBLEM AND MAKE CORRECTIVE ACTIONS. THE RI WAS INFORMED ALONG | | WITH LOCAL AGENCIES. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28046 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PRAIRIE ISLAND REGION: 3 |NOTIFICATION DATE: 11/18/94 | |UNIT: [1] [2] [ ] STATE: MN |NOTIFICATION TIME: 12:54 [ET]| |RX TYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 11/18/94 | +------------------------------------------------+EVENT TIME: 11:10[CST]| |NRC NOTIFIED BY: MARK JOHNSON |LAST UPDATE DATE: 11/18/94 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN GROBE 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 | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - 2 OF 5 COOLING WATER PUMPS INOPERABLE WITH BOTH UNITS AT FULL POWER - | | | | WHILE ALIGNING THE COOLING WATER SYSTEM FOR SAFEGUARDS (SAFETY-RELATED) | | OPERATION, LICENSEE DETERMINED THAT THE #121 COOLING WATER PUMP WAS | | INOPERABLE FOR SAFEGUARDS OPERATION AFTER DISCOVERING THAT A PORTION | | OF THE AUTOSTART CIRCUITRY FOR THE PUMP VENTILATION SYSTEM WAS POWERED | | BY A NON-SAFEGUARDS SOURCE. | | | | WITH THIS PUMP AND ANOTHER SAFEGUARDS COOLING WATER PUMP BEING INOPERABLE | | (2 OF 5 SAFEGUARDS COOLING WATER PUMPS), TECH SPEC LCO A/S 3.3.D.2.a | | REQUIRES LICENSEE TO RESTORE AT LEAST 1 OF THE 2 INOPERABLE PUMPS TO | | OPERABLE STATUS WITHIN 7 DAYS OR TO PLACE BOTH UNITS IN AT LEAST HOT | | SHUTDOWN MODE WITHIN THE NEXT 6 HOURS. | | | | LICENSEE PLANS TO RESTORE ONE OF THE TWO INOPERABLE PUMPS TO OPERABLE | | STATUS LATER TODAY. | | | | LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28047 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOK REGION: 3 |NOTIFICATION DATE: 11/18/94 | |UNIT: [1] [2] [ ] STATE: MI |NOTIFICATION TIME: 15:31 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 11/18/94 | +------------------------------------------------+EVENT TIME: 14:45[EST]| |NRC NOTIFIED BY: SCOTT GANE |LAST UPDATE DATE: 11/18/94 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN GROBE RDO | |DDDD 73.71 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | CONTRACTOR GRANTED PLANT ACCESS BASED ON FALSE BACKGROUND INFORMATION. | | IMMEDIATE COMPENSATORY MEASURES TAKEN UPON DISCOVERY. SEE HOO LOG FOR | | DETAILS. LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |HOSPITAL | |EVENT NUMBER: 28048 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: COLLETON REGIONAL HOSPITAL |NOTIFICATION DATE: 11/18/94 | | CITY: WALTERBOROUGH REGION: 2 |NOTIFICATION TIME: 18:49 [ET]| | COUNTY: COLLETON STATE: SC |EVENT DATE: 11/18/94 | |LICENSE#: 226 AGREEMENT: Y |EVENT TIME: 16:15[EST]| | DOCKET: |LAST UPDATE DATE: 11/18/94 | | +-----------------------------+ | |PERSON ORGANIZATION| | |EDWARD MCALPINE RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: MANLEY | | |HQ OPS OFFICER: TIM McGINTY | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |LADM 35.33(a) MED MISADMINISTRATION | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | COLLETON REGIONAL HOSPITAL, LOCATED IN WALTERBOROUGH, SC, REPORTED A | | MEDICAL MISADMINISTRATION. | | | | A LUNG SCAN WAS BEING PERFORMED ON A PATIENT, AND INSTEAD OF INJECTING 4 | | MILLI-CURIES OF TC-99M MAA, 4 MILLI-CURIES OF TC-99M DPTA (A KIDNEY SEEKER) | | WAS INJECTED. THE VIAL THAT CONTAINED THE RADIO-PHARMACEUTICAL WAS | | MIS-LABELED, DUE TO AN ADMINISTRATIVE ERROR. THE PATIENT WAS NOTIFIED OF | | THE MIS-ADMINISTRATION, AND THERE ARE NO ADVERSE CONSEQUENCES EXPECTED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |HOSPITAL | |EVENT NUMBER: 28049 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: US NAVAL HOSPITAL, PORTSMOUTH, VA |NOTIFICATION DATE: 11/18/94 | | CITY: PORTSMOUTH REGION: 2 |NOTIFICATION TIME: 19:12 [ET]| | COUNTY: STATE: VA |EVENT DATE: 11/18/94 | |LICENSE#: 45-23645-01NA AGREEMENT: N |EVENT TIME: 16:30[EST]| | DOCKET: |LAST UPDATE DATE: 11/18/94 | | +-----------------------------+ | |PERSON ORGANIZATION| | |EDWARD MCALPINE RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: J. MALINOSKI | | |HQ OPS OFFICER: DICK JOLLIFFE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |LADM 35.33(a) MED MISADMINISTRATION | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - 27.5% UNDER RADIATION DOSE ADMINISTERED TO FEMALE PATIENT - | | | | PERSONNEL AT US NAVAL HOSPITAL, PORTSMOUTH, VIRGINIA, ADMINISTERED AN | | UNDER RADIATION DOSE TO AN INTERVAGINAL TUMOR USING A WANG APPLICATOR. | | THE PRESCRIBED DOSE WAS 5000 RADS; THE ADMINISTERED DOSE WAS 3624 RADS; | | (AN UNDER DOSE OF 27.5%). THERE WERE NO ADVERSE CONSEQUENCES TO THE | | PATIENT. | | | | LICENSEE NOTIFIED THE PATIENT AND HER PHYSICAN OF THE UNDER DOSE. | | | | LICENSEE WILL SUBMIT A WRITTEN REPORT OF THIS INCIDENT TO THE NRC. | | | | SEE HOO LOG FOR TELEPHONE NUMBERS. | | | | LICENSEE HAS DISCUSSED THIS INCIDENT WITH R2 JERRY ENNIS. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28050 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HATCH REGION: 2 |NOTIFICATION DATE: 11/19/94 | |UNIT: [1] [ ] [ ] STATE: GA |NOTIFICATION TIME: 00:52 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 11/19/94 | +------------------------------------------------+EVENT TIME: 00:05[CST]| |NRC NOTIFIED BY: R MUSGROVE |LAST UPDATE DATE: 11/19/94 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |ED McALPINE 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 59 POWER OPERATION | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | MOISTURE SEPARATOR REHEATER (MSR) DRAIN TANK HIGH LEVEL TRIP CAUSED MAIN | | TURBINE TRIP/ REACTOR SCRAM. NO COMPLICATIONS EXPERIENCED DURING THE | | REACTOR SCRAM. | | | | REACTOR SCRAM DUE TO MAIN TURBINE TRIP. MAIN TURBINE TRIP WAS CAUSED BY A | | MSR DRAIN TANK HIGH LEVEL TRIP (DID NOT KNOW WHICH DRAIN TANK THEY RECEIVED | | THE HIGH LEVEL TRIP FROM, THEY HAVE FOUR DRAIN TANKS). ALL RODS FULLY | | INSERTED INTO THE CORE. LOWEST REACTOR VESSEL WATER LEVEL WAS -7" (NORMAL | | LEVEL IS +37") AT WHICH LEVEL THEY RECEIVED A GROUP 2 ISOLATION SIGNAL | | (PRIMARY CONTAINMENT VENTILATION ISOLATION). LICENSEE IS RESTORING THE | | PRIMARY CONTAINMENT VENTILATION SYSTEM TO ITS NORMAL LINEUP. NO EMERGENCY | | CORE COOLING SYSTEMS ACTUATED (LEVEL TWO ACTUATION IS AT -45"). NO SRVs | | OPENED AND THEIR TURBINE BYPASS CONTROL SYSTEM IS OPERATING PROPERLY. | | REACTOR VESSEL WATER LEVEL IS BEING MAINTAINED BY MANUAL OPERATION OF THEIR | | REACTOR FEEDWATER SYSTEM. LICENSEE IS INVESTIGATING WHY THEY RECEIVED A MSR | | DRAIN TANK HIGH LEVEL TRIP SIGNAL. | | LICENSEE WAS INITIALLY AT 59% POWER BECAUSE THEY EARLIER IN THE EVENING HAD | | LOST BOTH STRINGS OF THEIR HIGH PRESSURE FEEDWATER HEATERS. LICENSEE HAD | | RESTORED BOTH STRING OF THEIR FEEDWATER HEATER STRINGS TO SERVICE AND THEY | | WERE PREPARING TO INCREASE REACTOR POWER WHEN THEY RECEIVED A MSR DRAIN | | TANK HIGH LEVEL TRIP/MAIN TURBINE TRIP/REACTOR SCRAM. | | | | RESIDENT INSPECTOR WILL BE INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28051 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OYSTER CREEK REGION: 1 |NOTIFICATION DATE: 11/19/94 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 20:10 [ET]| |RX TYPE: [1] GE-2 |EVENT DATE: 11/19/94 | +------------------------------------------------+EVENT TIME: 19:23[EST]| |NRC NOTIFIED BY: VAN BLARCOM |LAST UPDATE DATE: 11/19/94 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN WHITE 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 | A N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - Rx SCRAM SIGNAL RECEIVED FOR UNKNOWN REASONS WITH PLANT IN CONDITION 4 - | | | | WITH THE PLANT IN CONDITION 4 (COLD SHUTDOWN) IN A REFUELING OUTAGE, THE | | PLANT RECEIVED AN ACTUAL FLOW UNIT UPSCALE SCRAM SIGNAL (114% OF RATED) | | WHILE I & C TECHNICIANS WERE WORKING ON THE RECIRCULATION SYSTEM DIGITAL | | CONTROL SYSTEM. | | | | ALL CONTROL ROD WERE ALREADY COMPLETELY INSERTED INTO THE REACTOR CORE. | | | | LICENSEE IS INVESTIGATING THE CAUSE OF THE SCRAM SIGNAL. | | | | LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28052 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OCONEE REGION: 2 |NOTIFICATION DATE: 11/21/94 | |UNIT: [ ] [2] [ ] STATE: SC |NOTIFICATION TIME: 04:44 [ET]| |RX TYPE: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-LP |EVENT DATE: 11/21/94 | +------------------------------------------------+EVENT TIME: 01:40[EST]| |NRC NOTIFIED BY: TOM STEVENS |LAST UPDATE DATE: 11/21/94 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |ED McALPINE RDO | |AINA 50.72(b)(2)(iii)(A) POT UNABLE TO SAFE SD | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 72 POWER OPERATION | 72 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | NUCLEAR INSTRUMENT (NI) # 8 DELTA FLUX (TOP TO BOTTOM OF CORE) WAS FOUND TO | | BE RESPONDING OPPOSITE OF OTHER NUCLEAR INSTRUMENT CHANNELS (# 5, 6, & 7). | | | | DURING POWER ESCALATION FOR PHYSICS TESTING IT WAS NOTED THAT NI # 8 DELTA | | FLUX WAS RESPONDING OPPOSITE OF NI's 5, 6, & 7 WHEN REACTOR POWER | | DISTRIBUTION WAS BEING CHANGED. AT 0140ET RPS CHANNEL "D" (NI # 8) WAS | | DECLARED INOPERABLE AND PLACED IN MANUAL BYPASS AT 0201ET. INVESTIGATION BY | | I&E TECHNICIANS SHOWED THAT WHEN THE OUTPUT LEADS FOR NI # 8 DELTA FLUX | | WERE REVERSED IN THE RPS CHANNEL "D" PROPER NI RESPONSE WAS ACHIEVED. | | PREVIOUS TO THIS THERE WAS NI CALIBRATIONS PERFORMED ON NI's 5, 6, & 7 | | WITHOUT NI # 8 (RPS CHANNEL "D") BEING IN THE TRIPPED POSITION. THIS | | RESULTED IN THE RPS BEING IN A 2 OUT OF 2 LOGIC INSTEAD OF BEING IN 2 OUT | | OF 3 WHICH IS THE NORMAL CASE WHEN CALIBRATIONS ARE BEING PERFORMED. | | LICENSEE WILL REMAIN AT 72% POWER UNTIL INVESTIGATION IS COMPLETED AND THE | | LEADS ARE PROPERLY CONNECTED BEFORE INCREASING REACTOR POWER. LICENSEE | | THINKS THAT THE LEADS FOR NI # 8 (RPS CHANNEL "D") WERE IMPROPERLY HOOKED | | UP DURING THEIR REFUELING OUTAGE. DELTA FLUX IS USED IN THE RPS FOR THE | | FLUX TO FLOW IMBALANCE TRIP. | | IF EITHER NI's 5, 6, OR 7 HAVE TO BE CALIBRATED BEFORE NI # 8 IS CORRECTED | | LICENSEE WILL PLACE RPS CHANNEL "D" (NI # 8) IN ITS TRIPPED POSITION BEFORE | | CALIBRATING THE OTHER CHANNEL. | | | | RESIDENT INSPECTOR WILL BE INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+