U.S. Nuclear Regulatory Commission Operations Center Event Reports For 03/31/97 - 04/01/97 ** EVENT NUMBERS ** 32046 32055 32056 32057 32058 32059 32060 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32046 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BROWNS FERRY REGION: 2 |NOTIFICATION DATE: 03/28/97 | |UNIT: [1] [2] [3] STATE: AL |NOTIFICATION TIME: 05:18 [ET]| |RX TYPE: [1] GE-4,[2] GE-4,[3] GE-4 |EVENT DATE: 03/28/97 | +------------------------------------------------+EVENT TIME: 03:19[CST]| |NRC NOTIFIED BY: DON SMITH |LAST UPDATE DATE: 03/31/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DAVID VERRELLI RDO | |DSAF 73.71(b)(1) SECURITY DEGRADATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | 3 | N Y 100 POWER OPERATION | 100 POWER OPERATION | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | SAFEGUARDS SYSTEM DEGRADATION RELATED TO SECURITY COMPUTER SYSTEM FAILURE. | | | | AT 0319 CST, THE LOCK AND ALARM COMPUTER FAILED, RESULTING IN THE TOTAL | | FAILURE OF THE ALARM SYSTEM AND A PARTIAL LOSS OF THE LOCKING SYSTEM. | | IMMEDIATE COMPENSATORY MEASURES WERE TAKEN IN THE REQUIRED TIME. THE | | COMPUTER HAS NOT BEEN RESTORED AS OF THE TIME OF THE REPORT. THE LICENSEE | | IS CONDUCTING AN INVESTIGATION TO DETERMINE ROOT CAUSE. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | | | | [HOO NOTE: A SIMILAR REPORT WAS RECEIVED 2/25/96 AND LATER RETRACTED. | | SEE EN 30024.] | | | | ***RETRACTION ON 03/31/97 @ 1523 EST BY TIM GOLDEN TAKEN BY MACKINNON*** | | | | THE LICENSEE IS RETRACTING THIS EVENT BECAUSE THE SECURITY DEGRADATION WAS | | DETERMINED TO BE CAUSED BY AN INADVERTENT TRANSFER OF THE PRIMARY SECURITY | | COMPUTER TO THE SECONDARY SECURITY COMPUTER WITH A FAILURE TO TRANSFER DUE | | TO A BAD LOGIC CARD IN THE SECONDARY COMPUTER. UPON REVIEW OF THE SYSTEM | | DIAGNOSTIC PRINTOUT, IT WAS VERIFIED THAT MONITORED STATUS OF ALL VITAL | | AREA LOCK AND ALARM ITEMS WAS MAINTAINED. | | | | IN ACCORDANCE WITH SITE SECURITY PROCEDURES, THE SECURITY DEGRADATION | | DOES NOT MEET CRITERIA FOR 1 HOUR REPORTABILITY BUT SHALL BE LOGGED AS A | | SECURITY DEGRADATION IN THE SECURITY QUARTERLY LOGS. THE LICENSEE INFORMED | | THE NRC RESIDENT INSPECTOR. THE HOO NOTIFIED R2DO DAVE VERRELLI. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32055 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SEQUOYAH REGION: 2 |NOTIFICATION DATE: 03/31/97 | |UNIT: [1] [2] [ ] STATE: TN |NOTIFICATION TIME: 14:01 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 03/31/97 | +------------------------------------------------+EVENT TIME: 13:07[EST]| |NRC NOTIFIED BY: SIMMONS |LAST UPDATE DATE: 03/31/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DAVE VERRELLI RDO | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | | |NLCO TECH SPEC LCO A/S | | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | BOTH TRAINS OF AUXILIARY BUILDING GAS TREATMENT SYSTEMS (ABGTS) DECLARED | | INOPERABLE. UNIT 2 ENTERED TECHNICAL SPECIFICATION (TS) 3.0.3 AND UNIT 1 | | STOPPED MOVING FUEL PER TECHNICAL SPECIFICATION 3.9.12. | | | | AUXILIARY BUILDING SECONDARY CONTAINMENT ENCLOSURE (ABSCE) BREACH OF 78.54 | | SQUARE INCHES EXCEEDS THE MAXIMUM ALLOWABLE BREACH ALLOWED PER PROCEDURE, | | WHICH IS CURRENTLY 50.5 SQUARE INCHES. UNIT 1 IS IN MODE 6 (REFUELING) AND | | 50.2 SQUARE INCHES WAS ALLOCATED FOR ABSCE BREACHES ASSOCIATED WITH OUTAGE | | ACTIVITIES. THE ADDITIONAL BREACH OF 78.54 SQUARE INCHES RAISES THE TOTAL | | ABSCE BREACH TO 128.74 SQUARE INCHES. BECAUSE OF THIS, BOTH TRAINS OF ABGTS | | WERE DECLARED INOPERABLE AT 1307 EST. | | | | UNIT 2 ENTERED TECHNICAL SPECIFICATION 3.0.3 FOR NONCOMPLIANCE WITH T.S. | | LIMITING CONDITION OF OPERATION 3.7.8 (ABGTS DURING MODES 1,2,3,& 4) AND | | UNIT 1 STOPPED FUEL MOVEMENT PER TECHNICAL SPECIFICATION 3.9.12. THE SHIFT | | SUPERVISOR FOR UNIT 2 IS CURRENTLY DISCUSSING A PLANT SHUTDOWN WITH HIS | | SHIFT CREW. UNIT 2 REACTOR POWER WILL BE DECREASED SLOWLY. AT 2007 EST UNIT | | 2 IS REQUIRED TO BE IN MODE 3 (HOT STANDBY). ALL EMERGENCY CORE COOLING | | SYSTEMS AND THE EMERGENCY DIESEL GENERATORS ARE FULLY OPERABLE. ENGINEERING | | IS CURRENTLY DETERMINING IF THE ABGTS CAN HANDLE AN ABSCE BREACH OF 128.74 | | SQUARE INCHES. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. | | | | *** UPDATE ON 03/31/97 @ 1529 EST BY SIMMONS TAKEN BY MACKINNON *** | | | | THE LICENSEE COMMENCED A UNIT SHUTDOWN PER TECHNICAL SPECIFICATION 3.0.3 AT | | 1407 EST. REACTOR POWER HAS BEEN REDUCED TO 98%. AT THIS TIME, A COMPLETE | | SHUTDOWN IS NOT EXPECTED TO BE REQUIRED BECAUSE EFFORTS ARE UNDERWAY TO | | RETURN THE ABGTS TO AN OPERABLE CONDITION. R2DO (DAVE VERRELLI) NOTIFIED. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. | | | | *** UPDATE ON 03/31/97 @ 1631 EST BY SIMMONS TAKEN BY MACKINNON *** | | | | ABGTS DECLARED OPERABLE AT 1620 EST. UNIT 2 EXITED TECHNICAL SPECIFICATION | | 3.0.3 AND TECHNICAL SPECIFICATION 3.7.8. REACTOR POWER FOR UNIT 2 HAD BEEN | | DECREASED TO 94%. REACTOR POWER WILL BE INCREASED TO 100%. UNIT 1 EXITED | | TECHNICAL SPECIFICATION 3.9.12 AT 1620 EST. R2DO (DAVE VERRELLI) NOTIFIED. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED BY THE LICENSEE OF THIS UPDATE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32056 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: QUAD CITIES REGION: 3 |NOTIFICATION DATE: 03/31/97 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 15:28 [ET]| |RX TYPE: [1] GE-3,[2] GE-3 |EVENT DATE: 03/31/97 | +------------------------------------------------+EVENT TIME: 12:31[CST]| |NRC NOTIFIED BY: KEVIN CRAVENS |LAST UPDATE DATE: 03/31/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RON GARDNER RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | EMERGENCY DIESEL GENERATOR UNEXPECTEDLY STARTED DURING SURVEILLANCE TEST | | | | WHILE PERFORMING THE UNIT ONE EMERGENCY DIESEL GENERATOR (EDG #1) MONTHLY | | SURVEILLANCE TEST, THE EDG STARTED WHEN THE CONTROL SWITCH IN THE MAIN | | CONTROL ROOM WAS TAKEN TO STOP (THE SWITCH IS ROTATED COUNTERCLOCKWISE FROM | | THE 'AUTO' POSITION TO THE 'STOP' POSITION AND THEN TO THE 'START' | | POSITION). THE EDG RAN FOR THE 11 MINUTE COOLDOWN PERIOD AND THEN STOPPED. | | EDG #1 WAS DECLARED INOPERABLE PER TECHNICAL SPECIFICATION 3.9.A.2 (7 DAYS | | TO RETURN IT TO SERVICE OR SHUT DOWN). THE SWING EDG AND THE UNIT 2 EDG ARE | | FULLY OPERABLE. ALL UNIT 2 EMERGENCY CORE COOLING SYSTEMS ARE FULLY | | OPERABLE AND THE ELECTRICAL GRID IS STABLE. | | | | THE NRC RESIDENT INSPECTOR WILL BE NOTIFIED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32057 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VERMONT YANKEE REGION: 1 |NOTIFICATION DATE: 03/31/97 | |UNIT: [1] [ ] [ ] STATE: VT |NOTIFICATION TIME: 16:07 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 03/31/97 | +------------------------------------------------+EVENT TIME: 15:45[EST]| |NRC NOTIFIED BY: A WISNIEWSKI |LAST UPDATE DATE: 03/31/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RICH BARKLEY 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 +------------------------------------------------------------------------------+ | FEEDER CABLE FOR A LIGHTING PANEL RUN IN BOTH DIVISION I & II CABLE TRAYS | | | | CONTROL ROOM PERSONNEL WERE NOTIFIED BY ENGINEERING DEPARTMENT PERSONNEL | | THAT THE FEEDER CABLE FOR LIGHTING PANEL LP-NE/1A WAS ROUTED THROUGH BOTH | | DIVISION I AND DIVISION II CABLE TRAYS. THIS IS CONTRARY TO DIVISIONAL | | SEPARATION AND PLACES THE PLANT OUTSIDE OF ITS DESIGN BASIS. | | | | THE LICENSEE HAS NOT DECLARED ANY ELECTRICAL SYSTEMS INOPERABLE. THE | | LICENSEE IS TAKING CREDIT FOR THE SAFETY CLASS BREAKERS THAT ARE ON THE | | CABLE THAT WOULD PRECLUDE A SINGLE FAULT FROM PROPAGATING FROM ONE DIVISION | | TO THE NEXT DIVISION. THE LICENSEE ALSO STATED THAT THEY HAVE ADEQUATE | | FAULT PROTECTION BY THE SAFETY CLASS BREAKERS IF ONE OF THE BREAKERS FAILS. | | THE LICENSEE IS ALSO TAKING CREDIT FOR THE FIRE PROTECTION BETWEEN THE | | DIVISION I AND DIVISION II TO PRECLUDE A FIRE FROM AFFECTING BOTH | | DIVISIONS. | | | | THIS IS AN ONGOING INVESTIGATING BY THE LICENSEE. SEE RELATED EN 32035 | | REPORTED ON 03/27/97. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED BY THE LICENSEE OF THIS EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32058 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BRUNSWICK REGION: 2 |NOTIFICATION DATE: 03/31/97 | |UNIT: [1] [ ] [ ] STATE: NC |NOTIFICATION TIME: 18:54 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 03/31/97 | +------------------------------------------------+EVENT TIME: 16:00[EST]| |NRC NOTIFIED BY: WILLIAMS |LAST UPDATE DATE: 03/31/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DAVE VERRELLI RDO | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 95 POWER OPERATION | 95 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE DISCOVERED AN ERROR IN THEIR ACCIDENT ANALYSIS. THIS IS | | SIMILAR TO A REPORT FROM HATCH (EN 32011) ON 03/25/97. | | | | AN INCONSISTENCY BETWEEN THE FUEL VENDOR (GENERAL ELECTRIC) ROD WITHDRAWAL | | ERROR (RWE) ANALYSIS ASSUMPTIONS AND TECHNICAL SPECIFICATION OPERABILITY | | REQUIREMENTS FOR THE ROD BLOCK MONITOR (RBM) SYSTEM HAS BEEN IDENTIFIED. | | THE VENDOR ASSUMED THAT THE RBM WAS OPERABLE DURING THE RWE EVENTS FOR | | BRUNSWICK OPERATING CYCLE B1C10 TO ENSURE THAT THE FUEL MECHANICAL | | OVERPOWER (MOP) CRITERIA WERE NOT EXCEEDED. THE LICENSEE IDENTIFIED AT | | LEAST ONE OCCURRENCE DURING THE B1C10 OPERATING CYCLE (1995) WHEN CONTROL | | RODS WERE WITHDRAWN WITH THE RBM SYSTEM INOPERABLE PER TECHNICAL | | SPECIFICATION GUIDANCE. WITH REACTOR POWER ABOVE 90% RATED THERMAL POWER | | AND MINIMUM CRITICAL POWER RATIO (MCPR) ABOVE 1.4, THE TECHNICAL | | SPECIFICATIONS DO NOT REQUIRE THE RBM TO BE OPERABLE. A RWE ANALYSIS | | INDICATED A SMALL VIOLATION OF THE MOP CRITERIA. THIS IS BEING REPORTED AS | | A FAILURE OF THE RBM TO MITIGATE THE CONSEQUENCE OF A RWE. THIS IS BASED | | UPON NEITHER RBM BEING AVAILABLE TO PREVENT THE RWE. | | | | THE CURRENT TECHNICAL SPECIFICATION REQUIREMENTS FOR THE RBM ARE ACCEPTABLE | | FOR BRUNSWICK OPERATING CYCLE B1C11. | | | | THE SAFETY SIGNIFICANCE OF THIS EVENT IS SMALL. THE VENDOR INDICATED THAT | | THE SMALL VIOLATION OF THE MOP CRITERIA, WITH THE CONSERVATIVE NATURE OF | | THE MOP CRITERIA WITH RESPECT TO THE 1% PLASTIC STRAIN AND BASED UPON | | GENERIC CALCULATIONS, IT IS HIGHLY UNLIKELY THAT THE 1% PLASTIC STRAIN | | CRITERIA WOULD HAVE BEEN EXCEEDED, EVEN WITH NO CREDIT FOR THE RBM ROD | | BLOCK. | | | | THERE ARE NO IMMEDIATE CORRECTIVE ACTIONS FOR THIS EVENT SINCE THE CURRENT | | TECHNICAL SPECIFICATIONS ARE ADEQUATE FOR BRUNSWICK OPERATING CYCLES B1C11 | | AND B2C12. THE INVESTIGATION OF THIS EVENT THROUGH CORRECTIVE ACTION | | PROGRAM WILL ADDRESS THE NEEDED CORRECTIVE ACTIONS TO PRECLUDE RECURRENCE. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32059 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PILGRIM REGION: 1 |NOTIFICATION DATE: 04/01/97 | |UNIT: [1] [ ] [ ] STATE: MA |NOTIFICATION TIME: 03:59 [ET]| |RX TYPE: [1] GE-3 |EVENT DATE: 04/01/97 | +------------------------------------------------+EVENT TIME: 03:49[EST]| |NRC NOTIFIED BY: M. MANTSENFEL |LAST UPDATE DATE: 04/01/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: UNUSUAL EVENT +-----------------------------+ |10 CFR SECTION: |BARKLEY RDO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |MARSH EO | | |KNUPP FEMA | | |BARRETT IRD | | |AXELSON R1 | | |MIRAGLIA NRR | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNUSUAL EVENT DECLARED DUE TO LOSS OF ALL OFFSITE POWER. | | | | AT 0257 EST, THE 345kV OFFSITE POWER SUPPLY WAS LOST DUE TO A FAULT | | OFFSITE. THE LICENSEE HAD PREVIOUSLY STARTED AND LOADED BOTH SAFETY-RELATED | | EMERGENCY DIESEL GENERATORS AFTER OBSERVING PERTURBATIONS IN THE OFFSITE | | ELECTRICAL DISTRIBUTION SYSTEM. THE 24kV ALTERNATE OFFSITE POWER WAS LOST | | AT 0349 EST, AT WHICH TIME THE LICENSEE DECLARED AN UNUSUAL EVENT, DUE TO | | THE INABILITY TO PROVIDE OFFSITE ELECTRICAL POWER TO THE 'A5' AND 'A6' | | SAFETY-RELATED ELECTRICAL BUSSES. | | | | SHUTDOWN COOLING WAS LOST FOR APPROXIMATELY 10 MINUTES WHEN THE 345kV LINE | | WAS LOST, BUT HAS BEEN RESTORED [SEE EN 32060]. CURRENT REACTOR WATER | | TEMPERATURE IS 89øF. SPENT FUEL POOL COOLING WAS ALSO LOST AT 0257 EST, AND | | HAS NOT YET BEEN RESTORED. THE LICENSEE REPORTED THAT THE CURRENT SPENT | | FUEL POOL TEMPERATURE IS 82øF, AND HAS NOT INCREASED APPRECIABLY. IT IS | | BEING MONITORED HOURLY. EFFORTS ARE UNDERWAY TO PROVIDE TEMPORARY POWER TO | | THE SPENT FUEL POOL COOLING PUMPS. THE BLACKOUT DIESEL GENERATOR IS | | RUNNING, BUT IS NOT LOADED AT THIS TIME. | | | | THE LICENSEE ESTIMATES THAT POWER WILL NOT BE RESTORED FOR ANOTHER 4-5 | | HOURS. THE NRC RESIDENT INSPECTORS HAVE BEEN INFORMED BY THE LICENSEE. | | | | * * * UPDATE 0410 4/1/97: CONFERENCE CALL REGARDING PILGRIM EVENT * * * | | PARTICIPANTS: MARSH (NRR EO), BARRETT (AEOD), BARKLEY (R1DO), AXELSON (R1), | | CONTE (R1), HALE (R1), KAUFMAN (R1), LAURA (R1), KORONA (R1), MIRAGLIA | | (NRR), MOHSENI (RCT). AGENCY WILL ENTER MONITORING PHASE OF NORMAL MODE DUE | | TO CONTINUED INCLEMENT WEATHER IN THE VICINITY OF THE SITE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32060 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PILGRIM REGION: 1 |NOTIFICATION DATE: 04/01/97 | |UNIT: [1] [ ] [ ] STATE: MA |NOTIFICATION TIME: 04:20 [ET]| |RX TYPE: [1] GE-3 |EVENT DATE: 04/01/97 | +------------------------------------------------+EVENT TIME: 02:57[EST]| |NRC NOTIFIED BY: M. MANTSENFEL |LAST UPDATE DATE: 04/01/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BARKLEY 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 +------------------------------------------------------------------------------+ | SHUTDOWN COOLING ISOLATION DUE TO LOSS OF OFFSITE POWER. | | | | THE SHUTDOWN COOLING SUCTION ISOLATION VALVE AUTOMATICALLY CLOSED WHEN | | OFFSITE POWER WAS LOST, CAUSING THE RUNNING SHUTDOWN COOLING PUMP TO TRIP. | | THE LICENSEE STATED THAT THE VALVE CLOSURE APPEARS TO BE SPURIOUS. THE | | SHUTDOWN COOLING SYSTEM WAS RESTORED WITHIN 10 MINUTES, WITH NO APPRECIABLE | | INCREASE IN REACTOR VESSEL TEMPERATURE. THE NRC RESIDENT INSPECTOR HAS BEEN | | INFORMED. | +------------------------------------------------------------------------------+