U.S. Nuclear Regulatory Commission Operations Center Event Reports For 04/10/98 - 04/13/98 ** EVENT NUMBERS ** 33891 33903 34050 34051 34052 34053 34054 34055 34056 34057 34058 34059 34060 34061 34062 34063 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 33891 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 03/13/98 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 08:11 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 03/12/98 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 12:30[EST]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 04/11/98 | | CITY: PIKETON REGION: 3 +-----------------------------+ | COUNTY: PIKE STATE: OH |PERSON ORGANIZATION| |LICENSE#: GDP-2 AGREEMENT: N |GARY SHEAR RDO | | DOCKET: 0707002 |JOSEPHINE PICCONE EO | +------------------------------------------------+ | |NRC NOTIFIED BY: KEITH VANDERPOOL | | |HQ OPS OFFICER: LEIGH TROCINE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |OCBC 76.120(c)(2)(iii) REDUNDANT EQUIP INOP | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | FAILURE TO HAVE THE REQUIRED URANIUM HEXAFLUORIDE SMOKE DETECTORS OUTSIDE | | OF TWO COMPRESSORS IN THE X-330 PROCESS BUILDING (24-HOUR REPORT) | | | | AT 1230 ON 03/12/98, ENGINEERING PERSONNEL DISCOVERED THAT OPERATIONS AT | | THE TAILS WITHDRAWAL COMPRESSOR AREA DID NOT HAVE THE REQUIRED URANIUM | | HEXAFLUORIDE SMOKE DETECTORS OUTSIDE OF TWO COMPRESSORS. THESE COMPRESSORS | | NORMALLY OPERATE BELOW ATMOSPHERE. THE TAILS WITHDRAWAL STATION IS | | CURRENTLY INOPERABLE FOR UPGRADE WORK. THE TWO COMPRESSORS IN QUESTION | | WILL REMAIN OUT OF SERVICE UNTIL APPROPRIATE INSTALLATIONS ARE COMPLETED. | | ALL OTHER PLANT WITHDRAWAL COMPRESSORS WERE INSPECTED AND CONFIRMED TO BE | | IN COMPLIANCE. THERE WAS NO LOSS OF HAZARDOUS OR RADIOACTIVE MATERIAL, AND | | THERE WERE NO RADIOACTIVE OR RADIOLOGICAL CONTAMINATION EXPOSURES AS A | | RESULT OF THIS EVENT. | | | | PORTSMOUTH NOTIFIED THE NRC RESIDENT INSPECTOR AND THE DEPARTMENT OF ENERGY | | SITE REPRESENTATIVE. | | | | * * * UPDATE AT 1704 ON 4/11/98 BY KEITH VANDERPOOL TAKEN BY JOLLIFFE * * * | | | | AFTER SAFETY ANALYSIS & ENGINEERING REVIEW, PORTSMOUTH PERSONNEL DETERMINED | | THAT THE UF6 SMOKE DETECTORS WERE NOT REQUIRED TO BE INSTALLED OUTSIDE THE | | TAILS FIRST STAGE COMPRESSOR HOUSINGS DUE TO OPERATING AT SUBATMOSPHERIC | | PRESSURE. THUS, COMPLIANCE WITH THE TECHNICAL SAFETY REQUIREMENT WAS | | MAINTAINED. THEREFORE, PORTSMOUTH PERSONNEL DESIRE TO RETRACT THIS EVENT. | | | | PORTSMOUTH PERSONNEL NOTIFIED THE NRC RESIDENT INSPECTOR AND THE DOE SITE | | REPRESENTATIVE. THE NRC OPERATIONS OFFICER NOTIFIED THE R3DO MARK RING. | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33903 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: NORTH ANNA REGION: 2 |NOTIFICATION DATE: 03/15/98 | |UNIT: [ ] [2] [ ] STATE: VA |NOTIFICATION TIME: 18:46 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 03/15/98 | +------------------------------------------------+EVENT TIME: 18:05[EST]| |NRC NOTIFIED BY: JEFF MOSHER |LAST UPDATE DATE: 04/10/98 | |HQ OPS OFFICER: FANGIE JONES +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MARK LESSER 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 92 POWER OPERATION | 92 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LIMIT FOR EXTERNAL LEAKAGE FROM ECCS COMPONENT DURING POST LOCA | | RECIRCULATION EXCEEDED. | | | | LEAKAGE FROM CHARGING PUMP 2-CH-P-1B, AS MEASURED FROM THE PUMP DRAIN | | VALVES, WITH THE PUMP SUCTION AND DISCHARGE VALVES SHUT, MEASURED 1827 | | CC/HR WHICH EXCEEDS THE LIMIT OF 900 CC/HR. THE MEASUREMENT WAS MADE WHILE | | THE PUMP WAS BEING PREPARED FOR SEAL MAINTENANCE FOR A LEAKING INBOARD PUMP | | SEAL. CALCULATIONS SHOW CONTROL ROOM DOSES COULD BE EXCEEDED DURING THE | | RECIRCULATION MODE AFTER A DESIGN BASIS LOCA. HOWEVER, OFFSITE DOSES WOULD | | REMAIN WELL WITHIN 10CFR100 LIMITS. BLANK FLANGES ARE CURRENTLY BEING | | INSTALLED TO STOP LEAKAGE & MAINTENANCE WILL CONTINUE ON THE SEAL PACKAGE. | | | | THE PLANT HAS 3 CHARGING PUMPS AND REQUIRES ONLY 2 FOR FULL OPERABILITY OF | | THE ECCS AND BORON INJECTION SYSTEMS. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE AT 1539 ON 04/10/98 BY DAVE ROBERTS ENTERED BY JOLLIFFE * * * | | | | UPON FURTHER REVIEW OF THIS EVENT, THE LICENSEE DETERMINED THAT THE | | OBSERVED LEAK RATE WOULD NOT HAVE CAUSED ANY RADIOLOGICAL EXPOSURES TO | | EXCEED NRC LIMITS SET FORTH IN 10CFR100 OR GENERAL DESIGN CRITERIA #19. | | THEREFORE, THIS EVENT IS DETERMINED TO BE NOT REPORTABLE TO THE NRC AND | | THUS, THE LICENSEE DESIRES TO RETRACT THIS REPORT. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. THE NRC OPERATIONS | | OFFICER NOTIFIED THE R2DO PIERCE SKINNER. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 34050 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 04/10/98 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 12:35 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 04/09/98 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 13:00[EDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 04/10/98 | | CITY: PIKETON REGION: 3 +-----------------------------+ | COUNTY: PIKE STATE: OH |PERSON ORGANIZATION| |LICENSE#: GDP-2 AGREEMENT: N |MARK RING RDO | | DOCKET: 0707002 |DON COOL, NMSS EO | +------------------------------------------------+ | |NRC NOTIFIED BY: KEITH VANDERPOOL | | |HQ OPS OFFICER: DICK JOLLIFFE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |OCBA 76.120(c)(2)(i) ACCID MT EQUIP FAILS | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - AUTOCLAVE CONTAINMENT VALVES FAILED A TEST DUE TO LEAKS IN AIR SYSTEM - | | | | AT 1300 ON 04/09/98, PLANT OPERATIONS PERSONNEL WERE PERFORMING A | | FUNCTIONAL TEST OF THE CONTAINMENT VALVES ON AUTOCLAVES #1 AND #2 IN THE | | X-342 FEED FACILITY. BOTH AUTOCLAVES WERE INOPERABLE DURING THIS TEST. | | A STEP IN THE TEST PROCEDURE REQUIRES OPERATORS TO VALVE OFF THE PLANT | | AIR SUPPLY TO THE VALVES TO CONFIRM THAT THE CONTAINMENT VALVES FAIL IN | | THE CLOSED POSITION, AS DESIGNED. | | | | DURING THIS TEST, ALL THREE CONTAINMENT VALVES PER AUTOCLAVE (SIX TOTAL) | | DID NOT FAIL IN THE CLOSED POSITION, AS DESIGNED. THIS FAILURE IS | | ATTRIBUTED TO AIR LEAKS WITHIN THE CONTAINMENT VALVE AIR RESERVOIRS. | | | | PLANT OPERATIONS PERSONNEL DECLARED ALL AUTOCLAVES IN THE PLANT SITE | | (SEVEN IN THE X-343 FEED FACILITY AND FOUR IN THE X-344 FEED FACILITY) | | INOPERABLE IN ORDER TO DETERMINE IF A SIMILAR CONDITION EXISTS IN THESE | | FACILITIES. | | | | PLANT OPERATIONS PERSONNEL PLAN TO TEST THE AIR SYSTEMS TO ALL THIRTEEN | | AUTOCLAVES IN ALL THREE FEED FACILITIES, REPAIR ALL AIR LEAKS, AND RETEST | | THE SYSTEMS, AS NECESSARY, PRIOR TO DECLARING THE AUTOCLAVES OPERABLE. | | | | THERE WAS NO LOSS OF HAZARDOUS OR RADIOACTIVE MATERIAL NOR RADIOACTIVE OR | | RADIOLOGICAL CONTAMINATION EXPOSURE AS A RESULT OF THIS EVENT. | | | | PLANT PERSONNEL NOTIFIED THE NRC RESIDENT INSPECTOR AND THE DOE SITE | | REPRESENTATIVE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34051 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: WOLF CREEK REGION: 4 |NOTIFICATION DATE: 04/10/98 | |UNIT: [1] [ ] [ ] STATE: KS |NOTIFICATION TIME: 14:54 [ET]| |RX TYPE: [1] W-4-LP |EVENT DATE: 04/09/98 | +------------------------------------------------+EVENT TIME: 16:00[CDT]| |NRC NOTIFIED BY: JOE LaRUE |LAST UPDATE DATE: 04/10/98 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CHARLES CAIN RDO | |NLTR LICENSEE 24 HR REPORT | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | -RCP LUBE OIL LEAK PATH NOT EVALUATED DURING A PREVIOUS THREE YEAR PERIOD- | | | | AT 1600 CDT ON 04/09/98, AN NRC SAFETY SYSTEM ENGINEERING INSPECTION TEAM | | INSPECTOR IDENTIFIED THE FOLLOWING CONDITION THAT OCCURRED DURING THE 1994 | | THROUGH 1996 PERIOD: WHEN A REACTOR COOLANT PUMP (RCP) LUBE OIL LEAK WAS | | INDICATED, THE LICENSEE EVALUATED THE SITUATION FROM THE STANDPOINT OF | | COMBUSTIBILITY BUT DID NOT EVALUATE THE SITUATION FROM THE STANDPOINT OF A | | NEW POSSIBLE LEAK PATH SITE AND THE NEED FOR ADDITIONAL COLLECTION SYSTEMS | | TO BE PUT IN PLACE. THIS LATER EVALUATION WAS REQUIRED BY FACILITY | | OPERATING LICENSE CONDITION 2.C.(5)(a) AND UFSAR TABLES 9.5A-1 AND 9.5E-1. | | | | IN 1997, THE RCP LUBE OIL LEAK CONDITION WAS PROPERLY EVALUATED FOR ALL | | COMPLIANCE ISSUES AND A PLANT MODIFICATION WAS INSTALLED TO RESOLVE THE | | LEAK PATH ASPECT OF THIS CONDITION. | | | | THIS 24 HOUR INITIAL NOTIFICATION OF THE 1994 - 1996 SITUATION IS BEING | | MADE IN ACCORDANCE WITH FACILITY OPERATING LICENSE CONDITION 2.F. THE | | LICENSEE PLANS TO SUBMIT A WRITTEN LICENSEE EVENT REPORT OF THIS SITUATION | | TO THE NRC WITHIN 30 DAYS. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34052 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VERMONT YANKEE REGION: 1 |NOTIFICATION DATE: 04/10/98 | |UNIT: [1] [ ] [ ] STATE: VT |NOTIFICATION TIME: 15:50 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 04/10/98 | +------------------------------------------------+EVENT TIME: 15:10[EDT]| |NRC NOTIFIED BY: MIKE EMPEY |LAST UPDATE DATE: 04/10/98 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GLENN MEYER RDO | |AMED 50.72(b)(2)(v) OFFSITE MEDICAL | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - NON-CONTAMINATED CONTRACTOR TRANSPORTED TO OFFSITE HOSPITAL - | | | | AT 1510 ON 04/10/98, A NON-CONTAMINATED CONTRACTOR WAS TRANSPORTED TO | | OFFSITE BRATTLEBORO MEMORIAL HOSPITAL FOR TREATMENT FOR A POSSIBLE HEART | | ATTACK. HIS MEDICAL CONDITION IS UNKNOWN AT THE PRESENT TIME. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34053 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: LASALLE REGION: 3 |NOTIFICATION DATE: 04/10/98 | |UNIT: [1] [2] [ ] STATE: IL |NOTIFICATION TIME: 16:42 [ET]| |RX TYPE: [1] GE-5,[2] GE-5 |EVENT DATE: 04/10/98 | +------------------------------------------------+EVENT TIME: 14:45[CDT]| |NRC NOTIFIED BY: JEFF WILLIAMS |LAST UPDATE DATE: 04/10/98 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MARK RING RDO | |DDDD 73.71 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - PLANT SECURITY EVENT - | | | | ENTRY OF AN UNAUTHORIZED CONTRACTOR INTO THE PLANT PROTECTED AREA. | | IMMEDIATE COMPENSATORY MEASURES WERE TAKEN UPON DISCOVERY. THE LICENSEE | | INFORMED THE NRC RESIDENT INSPECTOR. REFER TO THE HOO LOG FOR ADDITIONAL | | DETAILS. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34054 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CALVERT CLIFFS REGION: 1 |NOTIFICATION DATE: 04/10/98 | |UNIT: [1] [2] [ ] STATE: MD |NOTIFICATION TIME: 17:25 [ET]| |RX TYPE: [1] CE,[2] CE |EVENT DATE: 04/10/98 | +------------------------------------------------+EVENT TIME: 16:25[EDT]| |NRC NOTIFIED BY: MARK GECKLE |LAST UPDATE DATE: 04/10/98 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GLENN MEYER RDO | |DDDD 73.71 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - PLANT SECURITY EVENT - | | | | GRANTING OF PLANT ACCESS AUTHORIZATION TO TWO UNAUTHORIZED CONTRACTORS. | | IMMEDIATE COMPENSATORY MEASURES WERE TAKEN UPON DISCOVERY. THE LICENSEE | | INFORMED THE NRC RESIDENT INSPECTOR. REFER TO THE HOO LOG FOR ADDITIONAL | | DETAILS. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34055 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OYSTER CREEK REGION: 1 |NOTIFICATION DATE: 04/10/98 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 17:26 [ET]| |RX TYPE: [1] GE-2 |EVENT DATE: 04/10/98 | +------------------------------------------------+EVENT TIME: 16:45[EDT]| |NRC NOTIFIED BY: DAVE PIETRUSKI |LAST UPDATE DATE: 04/10/98 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GLENN MEYER 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 +------------------------------------------------------------------------------+ | - TECH SPEC BASES & UFSAR DISAGREE ON MAX PLANT HEATUP & COOLDOWN CYCLES - | | | | WHILE REVIEWING THE LICENSEE ADMINISTRATIVE CONTROLS FOR TRACKING | | THE NUMBER OF PLANT HEATUPS AND COOLDOWNS, THE LICENSEE DISCOVERED A | | DISCREPANCY BETWEEN THE TECHNICAL SPECIFICATION BASES (SECTION 3.3) | | AND THE UFSAR SECTION 5.2. THE TECHNICAL SPECIFICATION BASES STATE | | THAT THE NUMBER OF PLANT HEATUPS AND COOLDOWNS IS LIMITED TO 120 CYCLES. | | HOWEVER, THE UFSAR HAS BEEN UPDATED TO REFLECT MORE RECENT TECHNOLOGIES | | AND PLACED THE LIMIT AT 300 CYCLES. FURTHER LICENSEE EVALUATION REVEALED | | THAT STARTING ON THE DAY THAT THE PLANT PERFORMED ITS 121st HEATUP, THE | | PLANT WAS BEING OPERATED OUTSIDE OF ITS DESIGN BASES. | | | | THE LICENSEE PERFORMED AN OPERABILITY DETERMINATION AND ALTHOUGH AGREEMENT | | ON THE CORRECT NUMBER OF ALLOWABLE CYCLES IS CURRENTLY BEING DETERMINED, | | IT WILL BE NO LESS THAN 240 CYCLES. THEREFORE, THE REACTOR VESSEL IS WELL | | WITHIN ITS ACTUAL ALLOWABLE NUMBER OF CYCLES. | | | | THE LICENSEE IS ALSO DETERMINING THE NECESSITY OF A REQUEST FOR A CHANGE TO | | THE TECHNICAL SPECIFICATIONS AND PLANS TO SUBMIT A LICENSEE EVENT REPORT ON | | THIS EVENT TO THE NRC WITHIN 30 DAYS. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34056 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DAVIS BESSE REGION: 3 |NOTIFICATION DATE: 04/10/98 | |UNIT: [1] [ ] [ ] STATE: OH |NOTIFICATION TIME: 23:27 [ET]| |RX TYPE: [1] B&W-R-LP |EVENT DATE: 04/10/98 | +------------------------------------------------+EVENT TIME: 22:31[EDT]| |NRC NOTIFIED BY: TIM CHAMBERS |LAST UPDATE DATE: 04/10/98 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MARK RING RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION |WILLIAM BECKNER, NRR EO | | |JOSEPH GIITTER IRD | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | M/R Y 27 POWER OPERATION | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - Rx TRIP FROM 27% POWER DUE TO HI PZR LEVEL; LETDOWN RELIEF VALVE LIFTED - | | | | WHILE SHUTTING THE PLANT DOWN FOR A PLANNED REFUELING OUTAGE, THE #1 AND #2 | | MAKEUP FILTER DIFFERENTIAL PRESSURE INCREASED FOR UNKNOWN REASONS CAUSING | | THE LETDOWN RELIEF VALVE TO LIFT FOR 10 TO 20 SECONDS DUMPING TO THE | | REACTOR COOLANT DRAIN TANK. CONTROL ROOM OPERATORS ISOLATED LETDOWN. | | WITH LETDOWN ISOLATED, PRESSURIZER LEVEL BEGAN TO INCREASE. CONTROL ROOM | | OPERATORS BEGAN A RAPID PLANT SHUTDOWN FROM 48% POWER DUE TO INCREASING | | PRESSURIZER LEVEL AND THEN MANUALLY TRIPPED THE PLANT FROM 27% POWER DUE | | TO HIGH PRESSURIZER LEVEL. PRESSURIZER LEVEL REACHED A MAXIMUM HEIGHT | | 290 INCHES (TECH SPEC MAX LEVEL IS 305 INCHES). ALL CONTROL RODS INSERTED | | COMPLETELY. SECONDARY RELIEF VALVES LIFTED FOR A FEW SECONDS AND THEN | | RESEATED. STEAM IS BEING DUMPED TO THE MAIN CONDENSER. THE PLANT IS | | STABLE IN MODE 3 (HOT STANDBY). | | | | THE LICENSEE IS INVESTIGATING THE ROOT CAUSE OF THIS EVENT. | | | | THE LICENSEE NOTIFIED OTTAWA COUNTY OFFICIALS AND THE NRC RESIDENT | | INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 34057 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 04/10/98 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 23:53 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 04/10/98 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 20:33[EDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 04/10/98 | | CITY: PIKETON REGION: 3 +-----------------------------+ | COUNTY: PIKE STATE: OH |PERSON ORGANIZATION| |LICENSE#: GDP-2 AGREEMENT: N |MARK RING RDO | | DOCKET: 0707002 |MICHAEL WEBER EO | +------------------------------------------------+JOSEPH GIITTER IRD | |NRC NOTIFIED BY: STEVE MAY | | |HQ OPS OFFICER: STEVE SANDIN | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NBNL RESPONSE-BULLETIN | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | NRC BULLETIN 91-01, 4 HOUR REPORT | | | | "ON APRIL 10, 1998 AT 2033 HOURS, OPERATIONS PERSONNEL DISCOVERED THAT | | A NUCLEAR CRITICALITY SAFETY APPROVAL (NCSA) REQUIREMENT WAS NOT BEING | | MAINTAINED WITHIN THE X-330 PROCESS BUILDING. A TSR SHIFTLY SURVEILLANCE | | FOR CELL 29-5-2 INDICATED THAT THE CELL WHICH WAS AT A UF6 NEGATIVE AND | | SHOULD HAVE BEEN PRESSURIZED TO GREATER THAN 14 PSIA WITH DRY AIR OR | | NITROGEN, WAS AT 13.85 PSIA. THE CELL HAD BEEN PREVIOUSLY CLASSIFIED AS | | PROCESS EXPEDITIOUS HANDLING (PEH) INDICATING MORE THAN A SAFE MASS OF | | FISSIONABLE MATERIAL WAS INVOLVED. NCSA-0330_004.A02 REQUIREMENT #8 | | STATES, IN PART, 'ANY CASCADE EQUIPMENT SHUTDOWN (MOTOR TURNED OFF) AND | | AT A UF6 NEGATIVE SHALL HAVE A PLANT DRY AIR OR N2 BUFFER AT 14 PSIA | | OR GREATER.' THE NCSA FURTHER STATES THAT WHEN A 'PEH' DEPOSIT EXISTS | | CONTINGENCIES FOR THIS OPERATION DO NOT MEET THE DOUBLE CONTINGENCY | | CRITERIA. OPERATIONS PERSONNEL PRESSURIZED THE CELL TO GREATER THAN | | 14 PSIA AT 2045 HOURS. | | | | "THERE WAS NO LOSS OF HAZARDOUS/RADIOACTIVE MATERIAL OR | | RADIOACTIVE/RADIOLOGICAL CONTAMINATION EXPOSURE AS A RESULT OF THIS EVENT." | | | | CORRECTIVE ACTIONS INCLUDE INCREASING THE SHIFTLY, i.e., EVERY 12 HOURS, | | MONITORING OF THE CELLS TO TWO HOUR CHECKS. ALSO, THE BLOCK VALVES WERE | | RETORQUED AND PRESSURE IS MAINTAINED AT APPROXIMATELY 14.7 PSIA. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR AND THE DOE SITE | | REPRESENTATIVE. | | | | HOO NOTE: SEE EVENT #34037. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34058 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 04/11/98 | |UNIT: [ ] [ ] [3] STATE: CT |NOTIFICATION TIME: 03:38 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 04/11/98 | +------------------------------------------------+EVENT TIME: 03:30[EDT]| |NRC NOTIFIED BY: WILLIAM HOFFNER |LAST UPDATE DATE: 04/11/98 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GLENN MEYER 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 HOT STANDBY | 0 HOT STANDBY | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNIT 3 EXPERIENCED AN AUTOSTART OF BOTH MOTOR DRIVEN AUXILIARY FEEDWATER | | PUMPS DUE TO LOW LEVEL IN THE "C" STEAM GENERATOR. | | | | THE LICENSEE WAS PLACING THE MOTOR DRIVEN MAIN FEEDWATER PUMP IN SERVICE | | WHEN EITHER THE SEAL OR BEARING MECHANICALLY FAILED. SINCE THE INSERVICE | | CONDENSATE PUMP WAS UNABLE TO PROVIDE ADEQUATE FLOW DURING PLANT HEATUP, | | LEVEL IN THE "C" STEAM GENERATOR DECREASED TO THE AFW AUTOSTART SETPOINT. | | ALL SYSTEMS FUNCTIONED AS REQUIRED. THE LICENSEE IS CURRENTLY SECURING | | BOTH MD AFPs AND INTENDS TO ENTER MODE 4 FOR UNRELATED TESTING. | | | | THE LICENSEE INFORMED STATE/LOCAL AGENCIES AND THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34059 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DUANE ARNOLD REGION: 3 |NOTIFICATION DATE: 04/11/98 | |UNIT: [1] [ ] [ ] STATE: IA |NOTIFICATION TIME: 04:11 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 04/10/98 | +------------------------------------------------+EVENT TIME: 23:33[CDT]| |NRC NOTIFIED BY: KEVIN STEIMER |LAST UPDATE DATE: 04/11/98 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MARK RING 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 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE UNIT EXPERIENCED VARIOUS ESF ACTIONS DUE TO THE MOMENTARY LOSS OF THE | | DIVISION 1 INSTRUMENT AC SYSTEM FOR REASONS UNKNOWN. | | | | "THE DAEC INSTRUMENT AC CONTROL POWER SYSTEM IS COMPRISED OF 2 INDEPENDENT | | DIVISIONS OF 120 VOLT, SINGLE PHASE, 60 HZ INSTRUMENT POWER. EACH DIVISION | | IS SUPPLIED FROM AN INDEPENDENT 125 VDC INVERTER. EACH INVERTER HAS A | | BACKUP 480 VAC TO 120 VAC REGULATING TRANSFORMER. OPERATIONS WAS | | ATTEMPTING TO SECURE THE DIVISION 1 REGULATING TRANSFORMER (1Y1A), WHICH | | WAS NOT SUPPLYING INVERTER, WHEN A MOMENTARY LOSS OF THE DIVISION 1 | | OCCURRED WHEN THE BREAKER FROM THE REGULATING TRANSFORMER TO THE INVERTER | | (1Y1503) WAS OPENED. | | | | "THE MOMENTARY LOSS OF THE DIVISION 1 INSTRUMENT AC SYSTEM (1Y11) CAUSED | | THE FOLLOWING AUTOMATIC ACTIONS TO OCCUR: | | | | -PCIS DIVISION 1 GROUP 3 CONTAINMENT ATMOSPHERE CONTROL ISOLATION, | | SECONDARY CONTAINMENT ISOLATION AND 'A' STANDBY GAS TREATMENT INITIATION | | DUE TO LOSS OF POWER TO THE REACTOR BUILDING VENT SHAFT RADIATION MONITOR | | AND FUEL POOL EXHAUST RADIATION MONITOR. | | | | -'A' CONTROL BUILDING VENTILATION ISOLATION AND STANDBY FILTER UNIT | | INITIATION DUE TO LOSS OF POWER TO THE CONTROL BUILDING AIR INTAKE | | RADIATION MONITOR. | | | | -TRAVERSE IN-CORE PROBE (TIP) ISOLATION SIGNAL DUE TO LOSS OF POWER TO THE | | ISOLATION LOGIC BUT THE TIP SYSTEM WAS ALREADY REMOVED FROM SERVICE. | | | | "ALL ISOLATIONS AND SYSTEM INITIATION PERFORMED AS EXPECTED. | | | | "THE AREA RADIATION MONITOR (ARM) SYSTEM IS POWERED FROM DIVISION 1 | | INSTRUMENT AC. THE MOMENTARY LOSS OF POWER CAUSED ALL OF THE ARMs TO GO | | INTO ALARM. NO FUEL MOVEMENTS WERE IN PROGRESS WHEN THIS EVENT OCCURRED | | BUT 2 PORTABLE RADIATION MONITORS (FOR CRITICALITY MONITORING) REMAINED | | IN-SERVICE ON THE REFUEL FLOOR. | | | | "CONCURRENT WITH THIS EVENT THE DIVISION 2 INVERTER APPEARS TO HAVE | | EXPERIENCED AN UNDERVOLTAGE CONDITION AND IT AUTOMATICALLY REVERSE | | TRANSFERRED AND THEN FORWARD TRANSFERRED WITH NO LOSS OF POWER TO THE | | SYSTEM. | | | | "DAEC WILL BE INVESTIGATING BOTH INSTRUMENT AC INVERTERS TO DETERMINE THE | | CAUSE OF THE EVENTS. THIS EVENT IS BEING CONSIDERED A 4-HOUR NON-EMERGENCY | | REPORT PER 10CFR50.72(b)(2)(ii)." | | | | ALL ISOLATIONS AND SYSTEMS HAVE BEEN RESET. THE LICENSEE WILL INFORM THE | | NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34060 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FARLEY REGION: 2 |NOTIFICATION DATE: 04/11/98 | |UNIT: [ ] [2] [ ] STATE: AL |NOTIFICATION TIME: 08:59 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 04/11/98 | +------------------------------------------------+EVENT TIME: 06:00[CDT]| |NRC NOTIFIED BY: BILL OLDFIELD |LAST UPDATE DATE: 04/11/98 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PIERCE SKINNER RDO | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | STEAM GENERATOR (SG) "2C" CLASSIFIED AS CATEGORY C-3 DURING ONGOING SG TUBE | | INSPECTION. | | | | UNIT 2 IS CURRENTLY DEFUELED. A 100% SG TUBE INSERVICE INSPECTION IS IN | | PROGRESS WITH APPROXIMATELY 63%, 30% AND 60% OF THE "2A", "2B" AND "2C" SG | | TUBES INSPECTED. SG "2C" WAS CLASSIFIED CATEGORY C-3, i.e., >1% SG TUBES | | DEFECTIVE (CURRENTLY 1.1% DEFECTIVE TUBES). THE LICENSEE BELIEVES THAT | | BOTH THE "2A" AND "2B" SGs MAY ALSO BE CATEGORY C-3. A WRITTEN REPORT WILL | | BE SUBMITTED. THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34061 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BEAVER VALLEY REGION: 1 |NOTIFICATION DATE: 04/11/98 | |UNIT: [ ] [2] [ ] STATE: PA |NOTIFICATION TIME: 13:57 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 04/11/98 | +------------------------------------------------+EVENT TIME: 11:27[EDT]| |NRC NOTIFIED BY: DAVE HELD |LAST UPDATE DATE: 04/11/98 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GLENN MEYER 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 N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - AUTOMATIC ACTUATION OF REACTOR PROTECTION SYSTEM DUE TO PERSONNEL ERROR - | | | | WITH UNIT 2 IN MODE 5 (COLD SHUTDOWN) IN A MAINTENANCE OUTAGE WITH | | ALL CONTROL RODS FULLY INSERTED INTO THE CORE, PLANT TECHNICIANS WERE | | PERFORMING TIME RESPONSE TESTING OF THE SOLID STATE PROTECTION (SSP) | | SYSTEM. WHILE PERFORMING THE INITIAL CONDITIONS PORTION OF THE MAINTENANCE | | SURVEILLANCE TEST PROCEDURE, TECHNICIANS PLACED THE 'A' TRAIN OF THE SSP | | SYSTEM IN THE "TEST" POSITION WITH ALL THE REACTOR TRIP BREAKERS OPEN. | | THE TECHNICIAN THEN CLOSED THE 'B' REACTOR TRIP BYPASS BREAKER. CLOSING | | THIS BREAKER CREATED A 2 OF 2 GENERAL WARNING SIGNAL FROM THE SSP SYSTEM | | WHICH CAUSED A REACTOR TRIP SIGNAL WHICH IMMEDIATELY TRIPPED OPEN THE | | 'B' REACTOR TRIP BYPASS BREAKER. ALL OTHER REACTOR TRIP BREAKERS WERE | | ALREADY OPEN. ALL CONTROL RODS REMAINED FULLY INSERTED INTO THE CORE. | | | | CLOSING THE 'B' REACTOR TRIP BYPASS BREAKER CONSTITUTED A MISAPPLICATION | | OF THE INITIAL CONDITION PORTION OF THE TEST PROCEDURE. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34062 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PALO VERDE REGION: 4 |NOTIFICATION DATE: 04/12/98 | |UNIT: [1] [ ] [ ] STATE: AZ |NOTIFICATION TIME: 11:06 [ET]| |RX TYPE: [1] CE,[2] CE,[3] CE |EVENT DATE: 04/12/98 | +------------------------------------------------+EVENT TIME: 04:25[MST]| |NRC NOTIFIED BY: DAN MARKS |LAST UPDATE DATE: 04/12/98 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CHARLES CAIN RDO | |AINA 50.72(b)(2)(iii)(A) POT UNABLE TO SAFE SD | | |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 N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE DISCOVERED DURING TESTING THAT THE UNIT 1 "A" EMERGENCY DIESEL | | GENERATOR WOULD NOT RESTART ON A VALID SIGNAL IF MANUALLY OVERRIDDEN DUE TO | | AN INCORRECTLY INSTALLED ELECTRICAL JUMPER. | | | | "ON APRIL 12, 1998 AT APPROXIMATELY 0425 MST, PALO VERDE NUCLEAR GENERATING | | STATION (PVNGS) UNIT 1 OPERATIONS PERSONNEL DETERMINED, WHILE SHUTDOWN FOR | | ITS SEVENTH REFUELING OUTAGE, THAT EMERGENCY DIESEL GENERATOR 'A' COULD NOT | | RESPOND TO ALL EVENTS AS DESCRIBED IN THE UPDATED FINAL SAFETY ANALYSIS | | REPORT (UFSAR). THE SPECIFIC SCENARIO, DESCRIBED IN THE UFSAR, IS A DIESEL | | GENERATOR START DUE TO AN INADVERTENT ACTUATION OF A SAFETY INJECTION | | ACTUATION SIGNAL (SIAS) OR CONTAINMENT SPRAY ACTUATION SIGNAL (CSAS) | | FOLLOWED BY A MANUAL OVERRIDE AND SHUTDOWN OF THE EMERGENCY DIESEL | | GENERATOR. IF A SUBSEQUENT LOSS OF POWER TO THE 'A' ENGINEERED SAFEGUARDS | | FEATURES (ESF) BUS OCCURS, THE MANUAL OVERRIDE SHOULD BE REMOVED AND THE | | EMERGENCY DIESEL GENERATOR WILL RESTART. THIS FEATURE REMOVING THE MANUAL | | OVERRIDE WAS DISCOVERED TO NOT BE FUNCTIONAL. THE 'A' EMERGENCY DIESEL | | GENERATOR WAS NOT REQUIRED TO BE OPERABLE PRIOR TO DISCOVERY, THEREFORE, | | THE SAFETY SIGNIFICANCE WAS NEGLIGIBLE. | | | | "THE DISCOVERY THAT THE REMOVAL OF THE MANUAL OVERRIDE WAS NOT FUNCTIONAL | | WAS THE FIRST PERFORMANCE ON UNIT 1 EMERGENCY DIESEL GENERATOR 'A' OF NEW | | SURVEILLANCE PROCEDURE STEPS IMPLEMENTED SINCE THE ISSUANCE OF GENERIC | | LETTER (GL) 96-01, 'TESTING OF SAFETY-RELATED LOGIC CIRCUITS.' THE | | APPARENT CAUSE WAS A PERMANENT JUMPER THAT WAS INSTALLED ACROSS THE | | INCORRECT TERMINAL CONTACTS. THE DURATION THAT THIS CONDITION HAS EXISTED | | IS NOT YET KNOWN, BUT THE ASSUMPTION THAT IT HAS EXISTED FOR SIGNIFICANTLY | | LONGER THAN THE ALLOWED OUTAGE TIME PERMITTED BY TECHNICAL SPECIFICATION | | 3.8.1.1 AND 3.8.1.2 RESULTED IN A DETERMINATION THAT THE EMERGENCY DIESEL | | GENERATOR WAS INCAPABLE OF FULFILLING ITS SAFETY FUNCTION FOR AN | | INADVERTENT ACTUATION FOLLOWED BY A MANUAL OVERRIDE THEN A SUBSEQUENT LOSS | | OF POWER. | | | | "THE TESTING OF THIS FEATURE HAD ALREADY BEEN SUCCESSFULLY COMPLETED ON THE | | 'B' EMERGENCY DIESEL GENERATOR. IT ALSO HAD BEEN SUCCESSFULLY COMPLETED ON | | BOTH EMERGENCY DIESEL GENERATORS IN UNIT 2. THE WIRING OF THE JUMPER HAS | | BEEN CHECKED AND VERIFIED CORRECT IN UNIT 3. NO AUTOMATIC OR MANUAL | | RPS/ESF ACTUATIONS OCCURRED AND NONE WERE REQUIRED. | | | | "THE DISCOVERY THAT THE MANUAL OVERRIDE WAS NOT CAPABLE OF BEING REMOVED | | DID NOT RESULT IN ANY CHALLENGES TO THE FISSION PRODUCT BARRIER OR RESULT | | IN ANY RELEASES OF RADIOACTIVE MATERIALS. THERE WERE NO ADVERSE EFFECTS TO | | THE SAFE OPERATION OF THE PLANT OR HEALTH AND SAFETY OF THE PUBLIC. | | | | "UNIT 1 IS IN ITS 29TH DAY OF ITS SEVENTH REFUELING OUTAGE. THE CORE HAS | | BEEN REFUELED WITH ALL RODS IN. REACTOR COOLANT SYSTEM PRESSURE IS | | ATMOSPHERIC AND TEMPERATURE IS 115 DEGREES FAHRENHEIT." | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34063 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DUANE ARNOLD REGION: 3 |NOTIFICATION DATE: 04/13/98 | |UNIT: [1] [ ] [ ] STATE: IA |NOTIFICATION TIME: 06:37 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 04/13/98 | +------------------------------------------------+EVENT TIME: 03:21[CDT]| |NRC NOTIFIED BY: KEVIN STEIMER |LAST UPDATE DATE: 04/13/98 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MARK RING 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 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNIT EXPERIENCED A PCIS GROUP 3A ISOLATION DURING MAINTENANCE ACTIVITIES. | | | | "THE DAEIC PCIS GROUP 3 CONTAINMENT ATMOSPHERE CONTROL ISOLATION LOGIC IS | | COMPRISED OF 5 INPUTS WHICH ARE DRYWELL PRESSURE HIGH, REACTOR VESSEL LEVEL | | LOW WATER LEVEL, OFFGAS STACK HIGH RADIATION, FUEL POOL EXHAUST RADIATION | | HIGH, AND REACTOR BUILDING VENT SHAFT RADIATION HIGH. THE LAST SIGNAL IS | | PROVIDED FROM REACTOR BUILDING VENT SHAFT RADIATION MONITOR AUXILIARY RELAY | | (95-K134A) WHICH RESIDES IN 'A' STANDBY GAS TREATMENT SYSTEM LOGIC. THIS | | NORMALLY ENERGIZED RELAY DE-ENERGIZES ON HIGH RADIATION, DOWNSCALE, OR | | INOPERABLE CONDITION. | | | | "DAEC WAS MAKING PREPARATIONS TO PERFORM MAINTENANCE INSPECTIONS ON THE 125 | | VDC DIVISION 1 ELECTRICAL DISTRIBUTION SYSTEM BY DE-ENERGIZING THE | | INDIVIDUAL LOADS ONE AT A TIME. WHEN THE SUPPLY BREAKER (1D1119) TO THE | | 'A' STANDBY GAS TREATMENT SYSTEM WAS TURNED OFF, IT DE-ENERGIZED 95-K134A | | WHICH CAUSED A PCIS GROUP 3A ISOLATION. THIS SIGNAL CAUSED THE FOLLOWING | | VALVES TO CLOSE: | | | | CV-4300 INBOARD TORUS VENT ISOLATION | | CV-4302 INBOARD DRYWELL VENT ISOLATION | | CV-4307 INBOARD DRYWELL PURGE ISOLATION | | CV-4308 INBOARD TORUS PURGE INLET ISOLATION | | CV-4309 INBOARD TORUS VENT BYPASS ISOLATION | | CV-4310 INBOARD DRYWELL VENT BYPASS ISOLATION | | | | "THIS EVENT IS BEING CONSIDERED A 4-HOUR NON-EMERGENCY REPORT PER | | 10CFR50.72(b)(2)(ii)." | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+