U.S. Nuclear Regulatory Commission Operations Center Event Reports For 09/23/97 - 09/24/97 ** EVENT NUMBERS ** 32979 32980 32981 32982 32983 32984 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32979 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PERRY REGION: 3 |NOTIFICATION DATE: 09/23/97 | |UNIT: [1] [ ] [ ] STATE: OH |NOTIFICATION TIME: 01:50 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 09/23/97 | +------------------------------------------------+EVENT TIME: 00:16[EDT]| |NRC NOTIFIED BY: BRIAN STETSON |LAST UPDATE DATE: 09/23/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PATRICK HILAND RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | A N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | GENERATION OF A FULL SCRAM SIGNAL (WITH NO ROD MOTION) DUE TO AN OVERSIGHT | | DURING REFUEL INTERLOCK TESTING | | | | DURING THE PERFORMANCE OF REFUEL INTERLOCK TESTING, THE REACTOR MODE SWITCH | | WAS REQUIRED TO BE TAKEN FROM THE 'REFUEL' TO THE 'STARTUP' POSITION. WHEN | | THE REACTOR MODE SWITCH WAS TAKEN TO 'STARTUP,' A FULL SCRAM SIGNAL WAS | | GENERATED. | | | | THE SCRAM DISCHARGE VOLUME INSTRUMENT VOLUMES WERE AT 100% DUE TO A SYSTEM | | TAGOUT, AND THE INSTRUMENT VOLUME LEVEL HIGH SCRAM BYPASS KEYS WERE IN THE | | 'BYPASS' POSITION. HOWEVER, PLACING THE REACTOR MODE SWITCH IN THE | | 'STARTUP' POSITION UN-BYPASSED THE BYPASS KEYS, AND THIS GENERATED THE | | SCRAM SIGNAL. THE LICENSEE STATED THAT ALL SYSTEMS FUNCTIONED AS REQUIRED | | AND THAT THERE WAS NOTHING THAT WAS UNUSUAL OR NOT UNDERSTOOD. | | | | THERE WAS NO CONTROL ROD MOTION AS A RESULT OF THE SCRAM SIGNAL. ALL | | CONTROL RODS REMAINED FULLY INSERTED. PRIOR TO THE EVENT, THE CONTROL ROD | | DRIVES WERE ISOLATED, AND THE ACCUMULATORS WERE DEPRESSURIZED. THE SCRAM | | AIR HEADER WAS ALSO DEPRESSURIZED PRIOR TO THE EVENT. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32980 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PEACH BOTTOM REGION: 1 |NOTIFICATION DATE: 09/23/97 | |UNIT: [ ] [3] [ ] STATE: PA |NOTIFICATION TIME: 11:28 [ET]| |RX TYPE: [2] GE-4,[3] GE-4 |EVENT DATE: 09/23/97 | +------------------------------------------------+EVENT TIME: 10:10[EDT]| |NRC NOTIFIED BY: BOB FRANSSEN |LAST UPDATE DATE: 09/23/97 | |HQ OPS OFFICER: FANGIE JONES +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |TOM MOSLAK 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 Y 66 POWER OPERATION | 66 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DIESEL GENERATOR AUTOMATICALLY STARTED DUE TO AN I&C TECHNICIAN INSTALLING | | A RELAY COVER INCORRECTLY. | | | | I&C TECHNICIAN ACTIVATED OVERCURRENT RELAY E343 WHILE INSTALLING RELAY | | COVER FOLLOWING CALIBRATION. RELAY E343 ACTIVATION CAUSED A BUS E43 | | LOCKOUT. THE UNDERVOLTAGE CAUSED DIESEL GENERATOR E4 TO AUTOSTART, BUT THE | | LOCKOUT DID NOT ALLOW THE BUS TO BE ENERGIZED. | | | | THE LOCKOUTS WERE RESET AND BUS E43 WAS REENERGIZED AT 1019. DIESEL | | GENERATOR E4 WAS SHUTDOWN AT 1030. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32981 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PALISADES REGION: 3 |NOTIFICATION DATE: 09/23/97 | |UNIT: [1] [ ] [ ] STATE: MI |NOTIFICATION TIME: 12:37 [ET]| |RX TYPE: [1] CE |EVENT DATE: 09/23/97 | +------------------------------------------------+EVENT TIME: 12:20[EDT]| |NRC NOTIFIED BY: BILL ROBERTS |LAST UPDATE DATE: 09/23/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PATRICK HILAND 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 +------------------------------------------------------------------------------+ | LICENSEE IDENTIFIED AN APPENDIX R OUTSIDE DESIGN BASIS ISSUE. | | | | "DURING A REVIEW OF APPENDIX R ANALYSIS SUPPORTING DOCUMENTATION, IT WAS | | DETERMINED THAT THE ALTERNATE IMPLEMENTING PROCEDURE (ONP 25.2) DID NOT | | ADEQUATELY ACCOUNT FOR LIMITED FIRE DAMAGE SCENARIOS WHICH MIGHT CAUSE A | | LOSS OF COMPONENT COOLING WATER TO PRIMARY COOLANT PUMP (PCP) SEALS AND | | CONTROL ROOM EVACUATION WITHOUT A TRIP OF PCPs OR A LOSS OF OFFSITE POWER. | | WITHOUT CONTROL ROOM INDICATIONS AVAILABLE, A SUBSEQUENT LOSS OF PCP SEALS | | COOLING WATER COULD OCCUR WITHOUT DETECTION BY OPERATORS AND LEAD TO | | EXCESSIVE PCS LEAKAGE DUE TO PUMP SEAL FAILURES. ALTHOUGH THIS COMBINATION | | OF EVENTS IS HIGHLY UNLIKELY, FAILURE TO ACCOUNT FOR THIS SCENARIO IN | | ALTERNATE SHUTDOWN PROCEDURES CONSTITUTES A VIOLATION OF SECTION 111.L OF | | 10 CFR 50, APPENDIX R, AND THEREFORE IS A CONDITION OUTSIDE THE DESIGN | | BASIS. ALL ASSOCIATED EQUIPMENT REMAINS OPERABLE. THE APPROPRIATE PROCEDURE | | REVISIONS ARE IN PROCESS AND WILL BE IMPLEMENTED AS SOON AS PRACTICAL." | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32982 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SAN ONOFRE REGION: 4 |NOTIFICATION DATE: 09/23/97 | |UNIT: [1] [2] [3] STATE: CA |NOTIFICATION TIME: 13:07 [ET]| |RX TYPE: [1] W-3-LP,[2] CE,[3] CE |EVENT DATE: 09/22/97 | +------------------------------------------------+EVENT TIME: 13:58[PDT]| |NRC NOTIFIED BY: CLAY WILLIAMS |LAST UPDATE DATE: 09/23/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |ELMO COLLINS RDO | |HFIT 26.73 FITNESS FOR DUTY | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 DECOMMISSIONED | 0 DECOMMISSIONED | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | 3 | N Y 100 POWER OPERATION | 100 POWER OPERATION | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | A SUPERVISOR FAILED A RANDOM DRUG TEST. | | | | THE FOLLOWING FACSIMILE WAS RECEIVED FROM THE LICENSEE: | | | | "THIS NOTIFICATION IS FOR SAN ONOFRE UNITS 1, 2, AND 3 AND IS BEING MADE IN | | ACCORDANCE WITH 10CFR26.73 TO REPORT A CONFIRMED POSITIVE FITNESS-FOR-DUTY | | TEST OF A SUPERVISOR. | | | | "ON SEPTEMBER 19, 1997, AFTER REPORTING FOR HIS NORMALLY SCHEDULED SHIFT | | AND PRIOR TO ENTRY INTO THE PROTECTED AREA (PA), THE SUPERVISOR WAS | | INFORMED HE HAD BEEN SELECTED FOR A RANDOM FITNESS-FOR-DUTY TEST. THE | | PRELIMINARY TEST RESULTS RECEIVED LATER THAT SAME DAY WERE POSITIVE FOR | | ALCOHOL; HOWEVER, THE SUPERVISOR DISPUTED THE TEST RESULTS AND REQUESTED | | THAT THE APPEAL-SAMPLE BE TESTED. PENDING THE APPEAL-SAMPLE TEST RESULTS, | | THE SUPERVISOR'S PA ACCESS WAS IMMEDIATELY TERMINATED AND HE WAS PLACED ON | | INVESTIGATORY SUSPENSION. | | | | "ON MONDAY, SEPTEMBER 22, 1997, EDISON RECEIVED THE APPEAL SAMPLE TEST | | RESULTS AND, AT 1358PDT, VALIDATED THE TEST RESULTS AS POSITIVE. THE | | SUPERVISOR WILL BE REQUIRED TO COMPLETE A SUBSTANCE ABUSE PROGRAM PRIOR TO | | RESUMING DUTIES WITHIN THE PA. | | | | "BECAUSE THE SUPERVISOR DID NOT ENTER THE PA BEFORE OR AFTER BEING TESTED | | ON SEPTEMBER 19, 1997, NO ACTUAL ENTRY OF AN UNAUTHORIZED PERSON INTO THE | | PA OCCURRED. | | | | "THIS REPORT WILL BE DISCUSSED WITH THE NRC RESIDENT INSPECTOR." | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32983 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOK REGION: 3 |NOTIFICATION DATE: 09/23/97 | |UNIT: [1] [ ] [ ] STATE: MI |NOTIFICATION TIME: 17:39 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 09/23/97 | +------------------------------------------------+EVENT TIME: 15:10[EDT]| |NRC NOTIFIED BY: RANDY PTACEK |LAST UPDATE DATE: 09/23/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PATRICK HILAND RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ESF SIGNAL DURING STEAM GENERATOR FILL EVOLUTION. | | | | "UNIT 1 IS MAKING A 4 HOUR NOTIFICATION OF AN ESF ACTUATION PER PARAGRAPH | | 10CFR50.72(b)(2)(ii). THE ESF ACTUATION THAT OCCURRED WAS THE OPENING OF | | THE TDAFP STEAM GENERATOR AFW CONTROL VALVES IN RESPONSE TO ESF SIGNAL, SG | | LO-LO LEVEL IN 2 OUT OF 4 SGs. THIS EVENT OCCURRED WHILE FILLING THE UNIT | | 1 STEAM GENERATORS TO PLACE THEM IN WET LAYUP CONDITIONS WHILE THE UNIT IS | | IN MODE 5. IN THIS SITUATION TWO OF THE GENERATORS HAD BEEN FILLED ABOVE | | THE ACTUATION SETPOINT AND THE OTHER TWO GENERATORS REMAINED BELOW THE | | SETPOINT. AS THE THIRD GENERATOR INDICATED WATER LEVEL EXCEEDED THE | | ACTUATION SETPOINT, THE ESF SIGNAL THAT STARTS THE PUMP AND OPENS THE FLOW | | CONTROL VALVES RESET. THE INDICATED LEVEL THEN FELL BELOW THE ACTUATION | | SETPOINT CAUSING THE AFW CONTROL VALVES TO OPEN. THE TDAFP TRIP AND | | THROTTLE VALVE HAD BEEN MANUALLY DEFEATED SO IT DID NOT OPEN. THE UNIT WAS | | IN MODE 5 AT THE TIME AT APPROXIMATELY 140øF AND 290 PSIG ON RHR COOLING, | | SO THE ACTUATION WAS UNNEEDED AND THE SITUATION POSED NO THREAT TO THE | | HEALTH AND SAFETY OF THE PLANT OR PUBLIC. THE CREW CONTINUED TO FILL THE | | SGs WITH THE MDAFPs, AND CLOSED THE TDAFP VALVES." | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32984 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PALO VERDE REGION: 4 |NOTIFICATION DATE: 09/23/97 | |UNIT: [ ] [2] [ ] STATE: AZ |NOTIFICATION TIME: 17:40 [ET]| |RX TYPE: [1] CE,[2] CE,[3] CE |EVENT DATE: 09/23/97 | +------------------------------------------------+EVENT TIME: 11:39[MST]| |NRC NOTIFIED BY: RAY BUZARD |LAST UPDATE DATE: 09/23/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |ELMO COLLINS RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNIT 2 EXPERIENCED AN UNEXPECTED START OF THE "B" EDG DURING PLANNED | | MAINTENANCE ACTIVITIES. | | | | "AT APPROXIMATELY 1139 MST ON SEPTEMBER 23, 1997, AN ESF ACTUATION OCCURRED | | AT PALO VERDE UNIT 2. SPECIFICALLY, THE 'B' TRAIN EMERGENCY DIESEL | | GENERATOR STARTED AND SOME INDIVIDUAL ESF COMPONENTS ACTUATED. PALO VERDE | | UNIT 2 IS PRESENTLY IN ITS SEVENTH REFUELING OUTAGE WITH ALL NUCLEAR FUEL | | REMOVED FROM THE REACTOR VESSEL AND PLACED IN THE SPENT FUEL POOL. | | | | "PRIOR TO THE EMERGENCY DIESEL GENERATOR STARTING, ACTIVITIES WERE IN | | PROGRESS TO DEENERGIZE THE CHANNEL 'C' 120 VOLT AC VITAL INSTRUMENT AND | | CONTROL DISTRIBUTION PANEL, 2E-PNC-D27 FOR PLANNED MAINTENANCE ACTIVITIES. | | UPON OPENING THE FIRST BREAKER ON 2E-PNC-D27, UNEXPECTED HALF-LEG TRIPS OF | | THE B TRAIN PLANT PROTECTION SYSTEM ESF ACTUATIONS WERE RECEIVED. NORMALLY | | THE ESF COMPONENTS ONLY ACTUATE IN THE EVENT OF A FULL TRIP, NOT A HALF-LEG | | TRIP. EQUIPMENT HAS BEEN QUARANTINED UNTIL A TROUBLESHOOTING PLAN IS | | DEVELOPED AND APPROVED. | | | | "THE 'B' TRAIN EMERGENCY DIESEL GENERATOR POWERS THE CLASS IE 4160 KV BUS | | 2E-PBB-S04. THERE WAS NO GRID DISTURBANCE AND 4160 KV POWER FROM THE | | NORMAL OFFSITE SOURCE WAS NOT LOST. THEREFORE, THE 'B' EMERGENCY DIESEL | | GENERATOR DID NOT CLOSE ONTO THE BUS AND COOLING OF THE SPENT FUEL POOL WAS | | NOT INTERRUPTED. | | | | "THE EVENT DID NOT RESULT IN ANY CHALLENGES TO THE FISSION PRODUCT BARRIER | | OR RESULT IN ANY RELEASES OF RADIOACTIVE MATERIALS. THERE WERE NO ADVERSE | | SAFETY CONSEQUENCES OR IMPLICATIONS AS A RESULT OF THIS EVENT. THE EVENT | | DID NOT ADVERSELY AFFECT THE SAFE OPERATION OF THE PLANT OR HEALTH AND | | SAFETY OF THE PUBLIC. NO TECHNICAL SPECIFICATION ACTIONS WERE ENTERED AS A | | RESULT OF THIS EVENT." | | | | THE 'B' EDG WAS SECURED AND THE LICENSEE INFORMED THE NRC RESIDENT | | INSPECTOR. | +------------------------------------------------------------------------------+