U.S. Nuclear Regulatory Commission Operations Center Event Reports For 01/22/98 - 01/23/98 ** EVENT NUMBERS ** 33557 33566 33569 33574 33575 33576 33577 33578 33579 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33557 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OCONEE REGION: 2 |NOTIFICATION DATE: 01/17/98 | |UNIT: [1] [2] [3] STATE: SC |NOTIFICATION TIME: 01:22 [ET]| |RX TYPE: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-LP |EVENT DATE: 01/16/98 | +------------------------------------------------+EVENT TIME: 15:30[EST]| |NRC NOTIFIED BY: DAN GREENE |LAST UPDATE DATE: 01/22/98 | |HQ OPS OFFICER: FANGIE JONES +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CAUDLE JULIAN RDO | |NMAT MATL IN UNCNTRL AREA | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 | | 3 | N Y 100 POWER OPERATION | 100 POWER OPERATION | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | CONTAMINATED PACKAGES ON TRUCK LOAD OF NON-RADIOACTIVE MATERIAL | | | | THE LICENSEE RECEIVED A TRUCK CONTAINING NON-RADIOACTIVE MATERIAL FROM | | THE CATAWBA NUCLEAR SITE ON 01/02/98. SOME MATERIALS WERE OFF LOADED TO | | ASSIST IN THE CURRENT UNIT 1 STEAM GENERATOR TUBE LEAK OUTAGE. AT 1530 | | ON 01/16/98, THE TRUCK WAS BEING SURVEYED FOR RELEASE WHEN TWO PACKAGES | | (THAT HAD NOT BEEN OFF LOADED AT OCONEE NUCLEAR SITE) WERE FOUND TO BE | | CONTAMINATED WITH FIXED CONTAMINATION. ONE PACKAGE HAD A HOT PARTICLE AT | | 4,000 COUNTS PER MINUTE CONTAINING ISOTOPES CHROMIUM-51, COBALT-58 & 60, | | AND IRON-59. THE SECOND PACKAGE REGISTERED 250 COUNTS PER MINUTE. THE | | PACKAGES WERE DECONTAMINATED AND RELEASED. THERE WAS NO OTHER | | CONTAMINATION FOUND. THIS REPORT IS MADE UNDER 10CFR20.1906(d)(1 & 2). | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE AT 1531 ON 01/22/98 FROM RANDY TODD RECEIVED BY TROCINE * * * | | | | THE LICENSEE IS RETRACTING THIS EVENT NOTIFICATION. | | | | LIMITED INFORMATION AVAILABLE ON THE NIGHT OF FRIDAY, 01/16-17/98, | | INDICATED THAT THE TWO PACKAGES (WHICH WERE FOUND TO HAVE EXTERNAL FIXED | | CONTAMINATION) HAD BEEN RECEIVED IN A SHIPMENT THAT WAS NOT LABELLED AS | | RADIOACTIVE MATERIAL AND THAT THE PACKAGES HAD NOT BEEN UNLOADED AT OCONEE. | | IMMEDIATE NOTIFICATION WAS CONSERVATIVELY MADE BASED ON THIS LIMITED | | INFORMATION. HOWEVER, FURTHER INVESTIGATION HAS REVEALED THAT THE | | CONTAINERS IN QUESTION WERE ACTUALLY RECEIVED AS PART OF A PROPERLY | | PACKAGED AND LABELED RADIOACTIVE MATERIAL SHIPMENT FROM CATAWBA NUCLEAR | | STATION AND THAT THE CONTAINERS HAD BEEN OFF-LOADED AT OCONEE PRIOR TO | | BEING RELOADED FOR TRANSPORT OFF SITE. AS STATED IN THE INITIAL | | NOTIFICATION, THE CONTAMINATION WAS IDENTIFIED DURING A SURVEY FOR RELEASE. | | THE PACKAGES WERE SUBSEQUENTLY DECONTAMINATED AND RELEASED. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | | | | THE NRC OPERATIONS OFFICER NOTIFIED THE R2DO (ANN BOLAND). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33566 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: NINE MILE POINT REGION: 1 |NOTIFICATION DATE: 01/21/98 | |UNIT: [1] [ ] [ ] STATE: NY |NOTIFICATION TIME: 09:23 [ET]| |RX TYPE: [1] GE-2,[2] GE-5 |EVENT DATE: 01/21/98 | +------------------------------------------------+EVENT TIME: 07:50[EST]| |NRC NOTIFIED BY: DOUG LeCUYER |LAST UPDATE DATE: 01/22/98 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN CARUSO RDO | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | | |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 | 90 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - UNIT 1 SHUTTING DOWN DUE INOPERABLE PLANT LIQUID POISON SYSTEM - | | | | THE LICENSEE QUESTIONED THE OPERABILITY OF THE PLANT LIQUID POISON SYSTEM | | (aka STANDBY LIQUID CONTROL SYSTEM) SINCE THE TWO-FOOT SECTION OF SYSTEM | | PIPING FROM THE TANK TO THE PUMP DOES NOT GET FLOW TESTED ON A REGULAR | | BASIS. THUS, IT CANNOT BE ASSURED THAT THIS LINE IS CLEAR. | | | | AT 0750, THE LICENSEE DECLARED THE LIQUID POISON SYSTEM INOPERABLE PER | | TECHNICAL SPECIFICATION LIMITING CONDITION FOR OPERATION (LCO) ACTION | | STATEMENT 3.1.2. AT 0835, THE LICENSEE COMMENCED SHUTTING UNIT 1 DOWN. | | | | THE LICENSEE PLANS TO PERFORM A SPECIAL TEST TO VERIFY THAT THIS TWO-FOOT | | SECTION OF PIPE IS FREE OF SODIUM PENTABORATE. ONCE THIS IS VERIFIED, THE | | LICENSEE PLANS TO RETURN THE UNIT TO FULL POWER OPERATION. | | | | THE LICENSEE IS ALSO DETERMINING IF THIS CONDITION EXISTS ON UNIT 2. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE AT 0634 ON 01/22/98 FROM JOHN WEBBER ENTERED BY JOLLIFFE * * * | | | | AT 1430 ON 01/21/98, THE LICENSEE SATISFACTORILY TESTED THE LIQUID POISON | | SYSTEM (LINE NOT PLUGGED), DECLARED THE SYSTEM OPERABLE, AND EXITED THE | | TECHNICAL SPECIFICATION LCO ACTION STATEMENT. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. THE NRC OPERATIONS | | OFFICER NOTIFIED THE R1DO (JOHN CARUSO). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33569 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PRAIRIE ISLAND REGION: 3 |NOTIFICATION DATE: 01/21/98 | |UNIT: [ ] [2] [ ] STATE: MN |NOTIFICATION TIME: 16:03 [ET]| |RX TYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 01/21/98 | +------------------------------------------------+EVENT TIME: 13:22[CST]| |NRC NOTIFIED BY: SILVERBERG |LAST UPDATE DATE: 01/22/98 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |ROGER LANKSBURY RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION |JOHN ZWOLINSKI, NRR EO | |NLCO TECH SPEC LCO A/S |JOSEPH GIITTER, AEOD IRD | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | 7-DAY LIMITING CONDITION FOR OPERATION DUE TO THE LOSS OF ONE OF TWO | | OFFSITE POWER SOURCES | | | | AT 1322, THE 10-BANK TRANSFORMER LOCKED OUT FOR UNKNOWN REASONS. THE | | LOSS OF THE 10-BANK TRANSFORMER CAUSED A LOSS OF VOLTAGE ON THE CT-12 | | AUXILIARY TRANSFORMER WHICH CAUSED AN UNDERVOLTAGE ON SAFEGUARDS BUS 26. | | AUTOMATIC VOLTAGE RESTORATION RESTORED POWER TO BUS 26 FROM THE 2R4 | | TRANSFORMER. THE 22 COMPONENT COOLING PUMP WHICH WAS RUNNING ON BUS 26 | | TRIPPED, AND THE 21 COMPONENT COOLING PUMP AUTOMATICALLY STARTED ON LOW | | PRESSURE. THE 23 CHARGING PUMP TRIPPED ON THE LOSS OF BUS 26 WHICH CAUSED | | THE AUTOMATIC ISOLATION OF THE LETDOWN. THE 22 CHARGING PUMP WAS | | SUBSEQUENTLY STARTED, AND LETDOWN WAS RESTORED. THE LICENSEE CURRENTLY HAS | | ONLY ONE OFFSITE POWER SOURCE AND ALL FOUR EMERGENCY DIESEL GENERATORS | | AVAILABLE. | | | | THE LICENSEE IS INVESTIGATING THE CAUSE OF THIS EVENT. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE AT 0424 ON 01/22/98 FROM STEVE SCHMIDT TAKEN BY JOLLIFFE * * * | | | | AT 2219 CST ON 01/21/98, THE LICENSEE RESTORED BOTH SOURCES OF OFFSITE | | POWER TO UNIT 2. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. THE NRC OPERATIONS | | OFFICER NOTIFIED THE R3DO (ROGER LANKSBURY). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33574 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DIABLO CANYON REGION: 4 |NOTIFICATION DATE: 01/22/98 | |UNIT: [1] [2] [ ] STATE: CA |NOTIFICATION TIME: 12:25 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 01/22/98 | +------------------------------------------------+EVENT TIME: 09:12[PST]| |NRC NOTIFIED BY: DAVID PATTY |LAST UPDATE DATE: 01/22/98 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN PELLET 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 | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DISCOVERY THAT WATER MAY PASS THROUGH THE PRESSURIZER SAFETY VALVES (PSVs) | | AT LOWER TEMPERATURES THAN REQUIRED TO ENSURE VALVE OPERABILITY. | | | | THE LICENSEE WAS INFORMED THAT A TRANSIENT ANALYSIS PERFORMED BY | | WESTINGHOUSE USED AN INCORRECT ASSUMPTION WHICH AFFECTED THE ANALYSIS | | FOR INADVERTENT EMERGENCY CORE COOLING SYSTEM (ECCS) ACTUATION. THE | | REVISED ANALYSIS INDICATED THAT WATER MAY PASS THROUGH THE PSVs AT | | LOWER TEMPERATURES THAN REQUIRED TO ENSURE VALVE OPERABILITY. | | | | AS PART OF THE DIABLO CANYON DESIGN BASIS, TEMPORARY WATER RELIEF THROUGH | | THE PSVs MAY OCCUR FOR THE INADVERTENT ECCS ACTUATION EVENT USING | | WCAP-11677 METHODOLOGY. IT WAS CONCLUDED THAT PSV OPERABILITY WOULD BE | | MAINTAINED FOR WATER RELIEF TEMPERATURE ABOVE 600øF. HOWEVER, IN THE | | REVISED ANALYSIS, IT HAS NOW BEEN DETERMINED THAT THE WATER TEMPERATURE | | MUST REMAIN ABOVE 613øF IN ORDER TO JUSTIFY STABLE PSV OPERATION. | | INADVERTENT ECCS ACTUATION ANALYSIS FOR DIABLO CANYON ACHIEVED A FINAL | | WATER RELIEF TEMPERATURE OF 603øF BEFORE SAFETY INJECTION (SI) TERMINATION. | | AS A RESULT, THE REVISED ANALYSIS INDICATES THAT DAMAGE TO THE PSVs | | MAY OCCUR, AND THIS WOULD CAUSE THE VALVES TO FAIL TO RESEAT PROPERLY. | | FAILURE OF THE PSVs TO RESEAT WOULD BREACH THE RCS PRESSURE BOUNDARY. | | | | A LICENSEE PROMPT OPERABILITY ASSESSMENT HAS BEEN PERFORMED FOR THIS | | CONDITION, AND IT HAS BEEN DETERMINED THAT THE SI WILL BE TERMINATED PRIOR | | TO LIFTING THE PSVs WHEN USING THE REVISED EMERGENCY OPERATING PROCEDURES. | | COMPENSATORY MEASURES HAVE BEEN TAKEN TO CONTROL POSITIVE DISPLACEMENT PUMP | | OPERATION TO SUPPORT THIS ASSESSMENT. THIS PROVIDES ADEQUATE ASSURANCE | | THAT PSV OPERABILITY WILL BE MAINTAINED IN THE EVENT OF AN INADVERTENT ECCS | | ACTUATION. THE LICENSEE PLANS TO NOTIFY THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33575 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SEABROOK REGION: 1 |NOTIFICATION DATE: 01/22/98 | |UNIT: [1] [ ] [ ] STATE: NH |NOTIFICATION TIME: 12:51 [ET]| |RX TYPE: [1] W-4-LP |EVENT DATE: 01/22/98 | +------------------------------------------------+EVENT TIME: 12:15[EST]| |NRC NOTIFIED BY: MIKE DAVID |LAST UPDATE DATE: 01/22/98 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN CARUSO 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 +------------------------------------------------------------------------------+ | DISCOVERY OF THE POTENTIAL INABILITY TO SATISFY MAXIMUM FLOW REQUIREMENTS | | WHEN THE TEST ISOLATION VALVE FOR THE SAFETY INJECTION COLD LEG CHECK | | VALVES IS OPEN. | | | | DURING THE EARLIER PART OF THIS OPERATING CYCLE (OL05), THE TEST ISOLATION | | VALVE FOR THE SAFETY INJECTION COLD LEG CHECK VALVES (#SI-V131) REMAINED | | OPEN FOR EXTENDED PERIODS OF TIME TO SUPPORT A CHECK VALVE BACK-LEAKAGE | | SURVEILLANCE PROCEDURE. THIS VALVE PROVIDES AN ALTERNATE PARALLEL FLOW | | PATH FOR EMERGENCY CORE COOLING SYSTEM (ECCS) COLD LEG INJECTION. THE | | PERIOD OF OPERATION WHEN THE VALVE WAS OPEN COULD HAVE RESULTED IN THE | | INABILITY TO SATISFY THE TECHNICAL SPECIFICATION [4.5.2.h.2(b)] MAXIMUM | | FLOW REQUIREMENT OF 669 GPM, ASSUMING STANDARD FAILURE CRITERIA. THE | | POTENTIAL ACCIDENT SCENARIO WOULD INVOLVE VALVE #SI-V131 BEING OPEN | | CONCURRENT WITH A B-TRAIN SOLID STATE PROTECTION SYSTEM (SSPS) FAILURE. THE | | B-TRAIN SSPS FAILURE WOULD PREVENT OPERATION OF THE B-TRAIN ECCS PUMPS AND | | WOULD ALSO PREVENT THE AUTOMATIC CLOSURE OF VALVE #SI-V131. POST-ECCS | | OPERATION WOULD RESULT IN THE A-TRAIN SAFETY INJECTION PUMP EXCEEDING THE | | VALUE STATED IN TECHNICAL SPECIFICATIONS FOR PUMP RUNOUT CONDITIONS. | | | | THE LICENSEE BELIEVES THAT THIS CONDITION IS REPORTABLE, AS A 4-HOUR | | NON-EMERGENCY REPORT, PURSUANT TO 10CFR50.72(b)(2)(iii)(D) AS A CONDITION | | THAT ALONE COULD HAVE PREVENTED THE FULFILLMENT OF THE SAFETY FUNCTION OF | | STRUCTURES OR SYSTEMS THAT ARE NEEDED TO MITIGATE THE CONSEQUENCES OF AN | | ACCIDENT. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33576 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: POINT BEACH REGION: 3 |NOTIFICATION DATE: 01/22/98 | |UNIT: [1] [2] [ ] STATE: WI |NOTIFICATION TIME: 14:17 [ET]| |RX TYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 01/22/98 | +------------------------------------------------+EVENT TIME: 11:48[CST]| |NRC NOTIFIED BY: HENNIG |LAST UPDATE DATE: 01/22/98 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |ROGER LANKSBURY 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 91 POWER OPERATION | 91 POWER OPERATION | | 2 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNANTICIPATED PARTIAL SERVICE WATER ISOLATION DURING THE PERFORMANCE OF A | | NEW SPECIAL TEST PROCEDURE (INADEQUATE PROCEDURE). | | | | DURING PERFORMANCE OF POINT BEACH TEST PROCEDURE PBTP-77, TRANSIENT | | RESPONSE OF G02 REPLACEMENT GOVERNOR, IN ORDER TO REQUALIFY THE G02 | | EMERGENCY DIESEL GENERATOR (EDG) AS A STANDBY EMERGENCY POWER SOURCE, | | AN UNANTICIPATED ENGINEERED SAFETY FEATURE (SAFEGUARDS) ACTUATION OCCURRED | | WHICH CAUSED A PARTIAL SERVICE WATER ISOLATION. A PORTION OF THE TEST | | REQUIRES A EDG FULL-LOAD REJECTION. DURING THIS REJECTION, THE UNIT 2 | | A-TRAIN SAFETY INJECTION (SI) SIGNAL WAS PRESENT WITH THE G02 EDG SUPPLYING | | AC POWER TO SAFEGUARDS BUSSES 2A05 AND 2B03. (BUS 2A05 IS A 4,160-VOLT BUS | | AND BUS 2B03 IS A 480-VOLT BUS WHICH IS CONNECTED TO BUS 2A05.) | | ADDITIONALLY, FOUR SERVICE WATER PUMPS WERE RUNNING, AND ONE (PUMP P32F) | | WAS POWERED FROM BUS 2B03. WHEN THE EDG OUTPUT BREAKER WAS OPENED FOR | | THE LOAD REJECTION, THE P32F SERVICE WATER PUMP STRIPPED AS EXPECTED ON | | UNDERVOLTAGE AND THUS LEFT ONLY THREE SERVICE WATER PUMPS RUNNING. WITH | | LESS THAN FOUR SERVICE WATER PUMPS RUNNING AND WITH AN SI SIGNAL PRESENT, | | THE UNIT 2 A-TRAIN SERVICE WATER ISOLATION OCCURRED AS DESIGNED. SERVICE | | WATER WAS ISOLATED TO NON-SAFETY-RELATED LOADS VIA VALVES SW-61 (RADWASTE | | SERVICE WATER ISOLATION) AND SW-2816 (AUXILIARY BUILDING AIR CONDITIONING | | CONDENSER SERVICE WATER ISOLATION.) | | | | THE LICENSEE STATED THAT THE TEST PROCEDURE DID NOT RECOGNIZE THAT THIS | | SAFEGUARDS ACTUATION WOULD OCCUR. (THIS WAS THE FIRST TIME THAT THIS | | SPECIAL TEST PROCEDURE HAD BEEN PERFORMED.) | | | | AFTER THE G02 EDG RESTORED POWER TO THE BUSSES 2A04 AND 2B03, THE P32F | | SERVICE WATER PUMP AUTOMATICALLY STARTED, THUS RESTORING SERVICE WATER TO | | FOUR PUMPS RUNNING AND CLEARING THE PARTIAL SERVICE WATER ISOLATION SIGNAL. | | THE VALVES WERE THEN RE-OPENED TO RESTORE NORMAL SERVICE WATER COOLING | | FLOW. THE TESTING PORTION OF PROCEDURE PBTP-77 WAS COMPLETED WITHOUT | | FURTHER INCIDENT, AND RESTORATION FROM THE TEST IS NOW IN PROGRESS. A | | CONDITION REPORT WAS GENERATED TO DOCUMENT THE EVENT. | | | | HOO NOTE: POINT BEACH IS A FOUR EDG STATION, AND THE EDGs ARE NOT | | DEDICATED TO ONE BUS. THEY CAN BE ALIGNED SO THAT ONE EDG CAN | | CARRY BOTH THE UNIT 1 AND UNIT 2 A-TRAINS OR THE UNIT 1 AND | | UNIT 2 B-TRAINS. THE G02 EDG IS AN A-TRAIN EDG WHICH IS | | TYPICALLY ALIGNED TO UNIT 2 BUT CAN ALSO SUPPLY POWER TO UNIT 1. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33577 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PRAIRIE ISLAND REGION: 3 |NOTIFICATION DATE: 01/22/98 | |UNIT: [1] [2] [ ] STATE: MN |NOTIFICATION TIME: 16:22 [ET]| |RX TYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 01/22/98 | +------------------------------------------------+EVENT TIME: 14:45[CST]| |NRC NOTIFIED BY: PETER VALTAKIS |LAST UPDATE DATE: 01/22/98 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |ROGER LANKSBURY 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 | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DISCOVERY OF AN OUTSIDE-DESIGN-BASIS CONDITION AND USE OF AN INADEQUATE | | 10CFR50.59 REVIEW TO SUPPORT AN UPDATED SAFETY ANALYSIS REPORT CHANGE | | INVOLVING CABLING FOR THE CONTAINMENT FAN COIL UNITS' DISCHARGE DAMPERS. | | | | A CONDITION WAS DISCOVERED WHICH THE LICENSEE CONSIDERED TO BE OUTSIDE THE | | DESIGN BASIS OF THE PLANT AS DESCRIBED IN THE FINAL SAFETY ANALYSIS REPORT | | AND THE UPDATED SAFETY ANALYSIS REPORT (USAR) THROUGH REVISION 11. THE | | CABLING FOR THE DISCHARGE DAMPERS FOR THE CONTAINMENT FAN COIL UNITS IS | | ROUTED AS NORMAL CABLES IN NON-SAFETY-RELATED CABLE TRAYS. THIS HAS BEEN | | THE CONFIGURATION SINCE ORIGINAL CONSTRUCTION. PRIOR TO REVISION 12, THE | | USAR STATED THAT THESE CABLES WOULD BE ROUTED IN SAFETY RELATED CABLE | | TRAYS. THE USAR WAS REVISED IN EARLY 1994 TO CHANGE THIS ROUTING | | REQUIREMENT. UPON RE-EVALUATION, THE LICENSEE CONCLUDED THAT THE 10CFR50.59 | | REVIEW USED TO SUPPORT THIS USAR CHANGE WAS NOT ADEQUATE. A SUBSEQUENT | | EVALUATION HAS DETERMINED THAT THE PLANT IS OPERABLE WITH THE CURRENT | | CONFIGURATION. | | | | THE LICENSEE PLANS TO NOTIFY THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33578 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SOUTH TEXAS REGION: 4 |NOTIFICATION DATE: 01/22/98 | |UNIT: [1] [2] [ ] STATE: TX |NOTIFICATION TIME: 22:25 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 01/22/98 | +------------------------------------------------+EVENT TIME: 16:50[CST]| |NRC NOTIFIED BY: ROYCE BROWN |LAST UPDATE DATE: 01/22/98 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN PELLET RDO | |NLTR LICENSEE 24 HR REPORT | | |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 +------------------------------------------------------------------------------+ | DISCOVERY THAT TWO TENDON SURVEILLANCES WERE NOT ADEQUATELY COMPLETED. | | | | ON 01/22/98, IT WAS DETERMINED THAT A REPORTABLE CONDITION EXISTED IN | | ACCORDANCE WITH 10CFR50.73(a)(2)(i)(b) IN THAT TWO CONTAINMENT TENDON | | SURVEILLANCES PERFORMED IN ACCORDANCE WITH SURVEILLANCE REQUIREMENT | | 4.6.1.6.a.2 WERE NOT ADEQUATELY COMPLETED. SPECIFICALLY, THE SURVEILLANCES | | PERFORMED IN APRIL 1992 FOR UNIT 1 AND SEPTEMBER 1989 FOR UNIT 2 FAILED TO | | IDENTIFY THAT ONE TENDON ON EACH UNIT FELL BELOW THE PRESCRIBED LOWER | | LIMIT. AS A RESULT, THE ADDITIONAL ACTION OF TESTING TWO ADDITIONAL | | TENDONS, ONE ON EITHER SIDE OF THE DEFICIENT TENDON, WAS NOT PERFORMED. | | | | THE LICENSEE CONCLUDED THAT THIS CONSTITUTES FAILURE TO PERFORM A | | SURVEILLANCE, AND THE LICENSEE HAS ENTERED AN ACTION STATEMENT. AT THIS | | TIME, THE LICENSEE PLANS TO VERIFY CONTAINMENT INTEGRITY WITHIN 15 DAYS AS | | PRESCRIBED BY ACTION 'b' OF TECHNICAL SPECIFICATION 3.6.1.6. | | | | THIS NOTIFICATION WAS MADE AS A 24-HOUR REPORT IN ACCORDANCE WITH LICENSE | | CONDITION 2.g. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33579 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PERRY REGION: 3 |NOTIFICATION DATE: 01/23/98 | |UNIT: [1] [ ] [ ] STATE: OH |NOTIFICATION TIME: 03:36 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 01/23/98 | +------------------------------------------------+EVENT TIME: 03:10[EST]| |NRC NOTIFIED BY: TOM GOODMAN/BOB KIDDER |LAST UPDATE DATE: 01/23/98 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: UNUSUAL EVENT +-----------------------------+ |10 CFR SECTION: |ROGER LANKSBURY RDO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |PHILLIP MCKEE, NRR EO | | |JOHN SURMEIER, NMSS EO | | |JOSEPH GIITTER AEOD | | |CHUCK BAGWELL FEMA | | |JOE CONNOLLY-EPA/DOE NRCT | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | - UE DECLARED DUE TO TRICHLOROETHYLENE SPILL/TOXIC GAS RELEASE FROM PLANT - | | | | AT 0310, THE LICENSEE DECLARED AN UNUSUAL EVENT EMERGENCY DUE TO UP TO 250 | | GALLONS OF LIQUID TRICHLOROETHYLENE SPILLING FROM THE NON-SAFETY RELATED | | OFF-GAS BRINE COOLING SYSTEM (PART OF THE PLANT OFF-GAS COOLING SYSTEM) | | INTO THE OFF-GAS ROOM IN THE OFF-GAS BUILDING. THE 275 GALLON BRINE SYSTEM | | TANK IS EMPTY AND THE CONTROL ROOM OPERATORS HAVE STOPPED THE SYSTEM PUMP. | | PLANT PERSONNEL WEARING SELF CONTAINED BREATHING APPARATI ENTERED THE ROOM | | TO CLOSE THE SYSTEM ISOLATION VALVE BUT WERE UNSUCCESSFUL. | | | | NO PLANT PERSONNEL WERE IN THE BUILDING AT THE TIME OF THE SPILL AND PLANT | | PERSONNEL ACCESS TO THE BUILDING HAS BEEN RESTRICTED. NO PLANT PERSONNEL | | WERE INJURED OR AFFECTED BY THE SPILL. A PORTION OF THE LIQUID SPILL HAS | | VAPORIZED AND THE RESULTANT TOXIC GAS IS BEING RELEASED BY THE OFF-GAS | | VENTILATION SYSTEM OFFSITE THROUGH THE PLANT STACK TOWARDS LAKE ERIE. THE | | WIND IS BLOWING FROM THE SOUTHEAST AWAY FROM THE PLANT TOWARDS LAKE ERIE AT | | APPROXIMATELY 20 MPH. THE OUTSIDE TEMPERATURE IS 35øF. THE MATERIAL IS | | CLASSIFIED AS NATIONAL FIRE PROTECTION AGENT 2 (MODERATE FLAMMABILITY) AND | | IS CONSIDERED TO BE MODERATELY TOXIC. | | | | NO RADIOLOGICAL RELEASE FROM THE PLANT WAS DETECTED. | | | | THE CONTROL ROOM VENTILATION SYSTEM WAS (AND STILL IS) IN RECIRC MODE PRIOR | | TO THE BEGINNING OF THIS EVENT. | | | | THE LICENSEE NOTIFIED THE EPA/DOT NATIONAL RESPONSE CENTER, AND STATE & | | LOCAL OFFICIALS AND WILL NOTIFY THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+