U.S. Nuclear Regulatory Commission Operations Center Event Reports For 02/10/97 - 02/11/97 ** EVENT NUMBERS ** 31598 31623 31757 31758 31759 31760 31761 31762 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31598 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: NINE MILE POINT REGION: 1 |NOTIFICATION DATE: 01/15/97 | |UNIT: [ ] [2] [ ] STATE: NY |NOTIFICATION TIME: 18:01 [ET]| |RX TYPE: [1] GE-2,[2] GE-5 |EVENT DATE: 01/15/97 | +------------------------------------------------+EVENT TIME: 17:15[EST]| |NRC NOTIFIED BY: R. ORZELL |LAST UPDATE DATE: 02/10/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DAVID SILK RDO | |AINC 50.72(b)(2)(iii)(C) POT UNCNTRL RAD REL | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | STANDBY GAS TREATMENT SYSTEM UNABLE TO FULFILL ITS SAFETY FUNCTION. | | | | THE FOLLOWING IS TEXT OF A FACSIMILE SUBMITTED BY THE LICENSEE: | | | | "FROM 12/11/96 TO 12/13/96, NINE MILE POINT UNIT 2 STANDBY GAS TREATMENT | | SYSTEM WAS IN A CONDITION THAT COULD HAVE PREVENTED THE FULFILLMENT OF THE | | SAFETY FUNCTIONS OF STRUCTURES OR SYSTEMS NEEDED TO CONTROL THE RELEASE OF | | RADIOACTIVE MATERIAL. SPECIFICALLY BOTH STANDBY GAS TREATMENT SYSTEM DECAY | | HEAT REMOVAL VALVES WERE FAILED IN THE OPEN POSITION WHICH WOULD HAVE | | PREVENTED THE ABILITY TO MAINTAIN PHYSICAL SEPARATION OF THE STANDBY GAS | | TRAINS AS REQUIRED BY REG GUIDE 1.52. NINE MILE POINT UNIT 2 ENGINEERING IS | | CONTINUING TO EVALUATE THIS CONDITION." | | | | THE NRC RESIDENT INSPECTOR WILL BE INFORMED BY THE LICENSEE. | | | | * * * UPDATE AT 1103 ON 02/10/97 BY ROY GREEN ENTERED BY JOLLIFFE * * * | | | | LICENSEE ENGINEERING ANALYSIS HAS DETERMINED THAT BOTH TRAINS OF THE | | STANDBY GAS TREATMENT SYSTEM HAD BEEN OPERABLE AT ALL TIMES THROUGHOUT THIS | | EVENT WITH THE DECAY HEAT REMOVAL VALVES FAILED OPEN. | | | | THUS, THE LICENSEE DESIRES TO RETRACT THIS EVENT AND HAS NOTIFIED THE NRC | | RESIDENT INSPECTOR. | | | | THE HOO NOTIFIED R1DO RON BELLAMY. | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31623 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PEACH BOTTOM REGION: 1 |NOTIFICATION DATE: 01/20/97 | |UNIT: [ ] [3] [ ] STATE: PA |NOTIFICATION TIME: 17:15 [ET]| |RX TYPE: [2] GE-4,[3] GE-4 |EVENT DATE: 01/20/97 | +------------------------------------------------+EVENT TIME: 15:05[EST]| |NRC NOTIFIED BY: BOB FRANSSEN |LAST UPDATE DATE: 02/10/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN WHITE RDO | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 3 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | HIGH PRESSURE CORE INJECTION (HPCI) DECLARED INOPERABLE | | | | DURING ROUTINE SURVEILLANCE TESTING ON HPCI, A LEAK FROM THE HPCI GLAND | | SEAL CONDENSER WAS DISCOVERED. HPCI SUCTION ISOLATION VALVES WERE CLOSED | | AND THE HPCI AUXILIARY OIL PUMP WAS PLACED IN PULL TO LOCK POSITION. | | LICENSEE ENTERED TECHNICAL SPECIFICATION 3.5.1 (14 DAYS TO RETURN HPCI TO | | SERVICE OR SHUTDOWN). ALL OTHER EMERGENCY CORE COOLING SYSTEMS AND RCIC ARE | | FULLY OPERABLE IF NEEDED. LICENSEE HAS CALLED IN MAINTENANCE AND | | ENGINEERING TO RESTORE HPCI TO SERVICE. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. | | | | * * * UPDATE AT 1058 ON 02/10/97 BY DAVE FOSS ENTERED BY JOLLIFFE * * * | | | | LICENSEE EVALUATION HAS DETERMINED THAT THE HPCI SYSTEM WAS CAPABLE OF | | PERFORMING ITS SAFETY FUNCTION WITH THE LEAKING GLAND SEAL CONDENSER. | | THE LEAK FROM THE GLAND SEAL CONDENSER WAS WELL WITHIN THE LEAKAGE RATE | | THAT COULD HAVE AFFECTED HPCI SYSTEM OPERABILITY. THE LICENSEE CONSIDERS | | REMOVING THE HPCI SYSTEM FROM SERVICE IN ORDER TO REPAIR THE LEAK TO BE A | | PREPLANNED MAINTENANCE ACTIVITY. | | | | THUS, THE LICENSEE DESIRES TO RETRACT THIS EVENT AND HAS NOTIFIED THE NRC | | RESIDENT INSPECTOR. | | | | THE HOO NOTIFIED R1DO RON BELLAMY. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31757 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: ROBINSON REGION: 2 |NOTIFICATION DATE: 02/10/97 | |UNIT: [2] [ ] [ ] STATE: SC |NOTIFICATION TIME: 14:56 [ET]| |RX TYPE: [2] W-3-LP |EVENT DATE: 02/10/97 | +------------------------------------------------+EVENT TIME: 12:45[EST]| |NRC NOTIFIED BY: CROOK |LAST UPDATE DATE: 02/10/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CAUDLE JULIAN RDO | |HFIT 26.73 FITNESS FOR DUTY | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | - FITNESS FOR DUTY EVENT - | | | | AT 1245, THE LICENSEE DISCOVERED THAT A ROBINSON/DARLINGTON COUNTY FOSSIL | | GENERATING PLANT SUPERVISOR WAS FOUND TO BE UNFIT FOR DUTY, AFTER | | PERFORMING RANDOM TESTING FOR AN ILLEGAL SUBSTANCE. BECAUSE THIS PERSON | | ALSO HAD ROBINSON STEAM ELECTRIC PLANT UNIT # 2 UNESCORTED ACCESS | | AUTHORIZATION, THIS SUPERVISOR'S NUCLEAR UNESCORTED ACCESS AUTHORIZATION | | WAS TERMINATED. A REVIEW OF THE INDIVIDUALS ACTIVITIES INSIDE THE UNIT 2 | | PROTECTED AREA HAS BEEN INITIATED. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 31758 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: SHEFFIELD STEEL, SAND SPRINGS, OK |NOTIFICATION DATE: 02/10/97 | | CITY: SAND SPRING REGION: 4 |NOTIFICATION TIME: 16:15 [ET]| | COUNTY: TULSA STATE: OK |EVENT DATE: 02/07/97 | |LICENSE#: 35-19883-01 AGREEMENT: N |EVENT TIME: 12:00[CST]| | DOCKET: |LAST UPDATE DATE: 02/10/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |LINDA HOWELL, REG 4 RDO | | |DON COOL, NMSS EO | +------------------------------------------------+STUART RUBIN IRD | |NRC NOTIFIED BY: CHUCK CAIN (REGION 4) |HUDSPETH, NAT RES CR EPA | |HQ OPS OFFICER: JOHN MacKINNON |MARC DAPAS, REG 3 RDO | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | GAUGE CONTAINING 200 mCi CESIUM-137 FOUND IN SCRAPYARD IN SAND SPRING, OK. | | | | AT 1200 (CST) ON 02/07/97, A RAILCAR FROM JOPLIN, MO, ENTERING THE | | SHEFFIELD STEEL SCRAPYARD IN SAND SPRING, OK, ACTUATED A RADIATION MONITOR. | | THE RAILCAR WAS PUSHED OUTSIDE THE SCRAPYARD WHERE IT BECAME DERAILED. | | THE SCRAP METAL WAS OFFLOADED FROM THE DERAILED RAILCAR ONTO SEVERAL TRUCKS | | AND HAULED BACK INTO THE SCRAPYARD. | | | | RADIATION WAS FOUND TO BE COMING FROM A LEVEL MEASURING GAUGE ATTACHED | | TO A SCRAP I-BEAM INSIDE THE RAILCAR. THE GAUGE CONTAINS A 200 mCi | | CESIUM-137 SOURCE. THE CONTACT RADIATION READING OF THE SOURCE WAS | | 200 MR/HR. THE OPEN SHUTTER ON THE GAUGE WAS CLOSED TO REDUCE THE | | RADIATION COMING FROM THE GAUGE. PEOPLE MAY HAVE BEEN EXPOSED TO | | RADIATION FROM THIS GAUGE. | | | | THE GAUGE WAS MADE BY TEXAS NUCLEAR COMPANY, SERIAL #B2829, MODEL #5190. | | TEXAS NUCLEAR IS DETERMINING THE OWNER OF THE GAUGE. | | | | AT 1130 (CST) ON 02/10/97, DOUG STRICKLAND, SHEFFIELD STEEL COMPANY, | | NOTIFIED CHUCK CAIN, NRC REGION 4 OF THIS EVENT. AT 1515 (CST) ON 02/10/97, | | CHUCK CAIN NOTIFIED THE HEADQUARTERS OPERATIONS OFFICER OF THIS EVENT. | | NRC REGION 4 NOTIFIED THE STATE OF OKLAHOMA AND NRC REGION 3, AND WILL SEND | | AN INSPECTOR TO SHEFFIELD STEEL SCRAPYARD TO INVESTIGATE THIS INCIDENT. | | | | REGION 4 WILL ISSUE PRELIMINARY NOTIFICATION #PNO-IV-97-10 ON THIS EVENT. | | | | SEE THE HOO LOG FOR CALL BACK TELEPHONE NUMBERS. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31759 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DRESDEN REGION: 3 |NOTIFICATION DATE: 02/10/97 | |UNIT: [ ] [2] [3] STATE: IL |NOTIFICATION TIME: 17:10 [ET]| |RX TYPE: [1] GE-1,[2] GE-3,[3] GE-3 |EVENT DATE: 02/10/97 | +------------------------------------------------+EVENT TIME: 15:35[CST]| |NRC NOTIFIED BY: R STOBERT |LAST UPDATE DATE: 02/10/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MARC DAPAS RDO | |DDDD 73.71 UNSPECIFIED PARAGRAPH | | | |JOHN DAVIDSON (IAT) NMSS | | |NANCY ERVIN (IAT) NRR | | |STUART RUBIN IRD | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 70 POWER OPERATION | 70 POWER OPERATION | | 3 | N Y 73 POWER OPERATION | 73 POWER OPERATION | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - SECURITY EVENT - | | | | ACTUAL TAMPERING WITH SECURITY EQUIPMENT. IMMEDIATE COMPENSATORY MEASURES | | WERE TAKEN UPON DISCOVERY. SECURITY GUARD'S SITE ACCESS AUTHORIZATION WAS | | REVOKED. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR AND REGION 3 SECURITY | | OFFICER OF THIS EVENT. | | | | SEE HOO LOG BOOK FOR FURTHER DETAILS. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31760 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CATAWBA REGION: 2 |NOTIFICATION DATE: 02/10/97 | |UNIT: [1] [2] [ ] STATE: SC |NOTIFICATION TIME: 20:58 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 02/10/97 | +------------------------------------------------+EVENT TIME: 18:35[EST]| |NRC NOTIFIED BY: G HAMILTON |LAST UPDATE DATE: 02/10/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CAUDLE JULIAN RDO | |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 Y 100 POWER OPERATION | 100 POWER OPERATION | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | A SINGLE FAILURE OF A POWER SUPPLY WHICH WOULD CAUSE THE LOSS OF 2 S/G | | PORVs COULD LIMIT THE ABILITY TO COOL DOWN AND DEPRESSURIZE THE PLANT | | WITHIN THE CURRENT UFSAR TIME LIMIT. | | | | DURING A DOSE ANALYSIS REVIEW OF THE CATAWBA UPDATED FINAL SAFETY ANALYSIS | | REPORT (UFSAR), CHAPTER 15, ACCIDENT ANALYSIS, THE LICENSEE DISCOVERED THAT | | THE POTENTIAL EXISTS FOR A MORE LIMITING SINGLE FAILURE WITH REGARDS TO THE | | ANALYSIS FOR A STEAM GENERATOR TUBE RUPTURE ACCIDENT. A SINGLE FAILURE OF | | THE VITAL BATTERY POWER SUPPLY WOULD CAUSE THE FAILURE OF THE POWER | | OPERATED RELIEF VALVES (PORVs) FOR STEAM GENERATORS (S/Gs) #1 & #3 OR | | S/Gs #2 & #4. THIS MORE LIMITING SINGLE FAILURE AFFECTS THE ABILITY TO | | COOL THE PLANT DOWN IN A TIMELY MANNER USING THE S/G PORVs. EVALUATION OF | | THIS SITUATION HAS IDENTIFIED THAT THE ABILITY OF THE OPERATORS TO COOL | | DOWN AND DEPRESSURIZE THE PLANT WITHIN THE ALLOTTED TIME SPECIFIED IN THE | | CURRENT ANALYSIS, WITH MARGIN TO OVERFILL THE MAIN STEAM LINES, MAY NOT BE | | ASSURED. CATAWBA TECH SPECS CURRENTLY REQUIRE ONLY 3 OF 4 S/G PORVs TO BE | | OPERABLE WITH TECH SPEC ACTION TIMES APPLICABLE FOR 1 AND 2 INOPERABLE | | PORVs. AN ONGOING LICENSEE EVALUATION HAS DETERMINED THAT IT MAY BE | | NECESSARY TO REQUIRE ALL 4 S/G PORVs TO BE OPERABLE WITH TECH SPEC ACTION | | TIMES COMPARABLE TO THE CURRENT TECH SPEC. THIS WILL ENSURE THAT S/G | | OVERFILL AND DOSE ANALYSES REMAIN BOUNDED WITHIN THE CURRENT ACCIDENT | | ANALYSIS. CATAWBA IS CURRENTLY ADMINISTRATIVELY MAINTAINING ALL 4 S/G PORVs | | OPERABLE. EVALUATIONS ARE IN PROGRESS TO DETERMINE CORRECTIVE ACTIONS. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | IT IS UNKNOWN AT THIS TIME IF McGUIRE HAS THIS SAME SITUATION. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31761 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: ZION REGION: 3 |NOTIFICATION DATE: 02/10/97 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 23:55 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 02/10/97 | +------------------------------------------------+EVENT TIME: 22:27[CST]| |NRC NOTIFIED BY: DON NOLDIN |LAST UPDATE DATE: 02/10/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MARC DAPAS RDO | |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 Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - TECH SPEC REQUIRED UNIT 1 SHUTDOWN DUE TO HIGH RWST BORON CONCENTRATION - | | | | ZION TECH SPECS REQUIRE THE REFUELING WATER STORAGE TANK (RWST) BORON | | CONCENTRATION TO BE 2400 TO 2600 PPM. THE BORON CONCENTRATION OF A SAMPLE | | OF THE RWST WATER TESTED AT 2603.7 PPM. THE LICENSEE PUMPED 9000 GALLONS | | OF PURE WATER INTO THE RWST TO DILUTE THE BORON CONCENTRATION. THE BORON | | CONCENTRATION OF A SUBSEQUENT SAMPLE TESTED AT HIGHER THAN 2603.7 PPM. | | | | TECH SPEC LCO A/S 3.8.1.G REQUIRES THE LICENSEE TO SHUT UNIT 1 DOWN TO | | HOT SHUTDOWN MODE WITHIN 4 HOURS WITH THE RWST BORON CONCENTRATION OUT | | OF THE SPECIFIED TECH SPEC RANGE. UNIT 2 IS IN MODE 5 (COLD SHUTDOWN) | | IN A REFUELING OUTAGE. | | | | CONTROL ROOM OPERATORS BEGAN REDUCING POWER TO SHUT UNIT 1 DOWN. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE AT 0201 ON 02/11/97 BY DON NOLDIN ENTERED BY JOLLIFFE * * * | | | | THE LICENSEE RAN THE #1A CONTAINMENT SPRAY PUMP ON RECIR MODE TO MIX THE | | WATER IN THE RWST. SEVERAL RWST SAMPLES TESTED AT 2510 TO 2540 PPM BORON | | CONCENTRATION. AT 0001 (CST) ON 02/11/97, CONTROL ROOM OPERATORS STOPPED | | THE POWER REDUCTION ON UNIT 1 AT 44% POWER & EXITED THE TECH SPEC LCO A/S. | | THE LICENSEE IS DETERMINING WHETHER TO INCREASE POWER OR COASTDOWN TO A | | REFUELING OUTAGE. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. THE HOO NOTIFIED R3DO | | MARC DUPAS. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31762 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CLINTON REGION: 3 |NOTIFICATION DATE: 02/11/97 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 05:36 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 02/10/97 | +------------------------------------------------+EVENT TIME: 21:30[CST]| |NRC NOTIFIED BY: TIM HOLLAND |LAST UPDATE DATE: 02/11/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MARC DAPAS RDO | |AARC 50.72(b)(1)(v) OTHER ASMT/COMM INOP | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - SPDS DECLARED INOPERABLE BUT FUNCTIONAL FOR LONGER THAN 8 HOURS - | | | | THE LICENSEE REMOVED THE SAFETY PARAMETER DISPLAY SYSTEM (SPDS) FROM | | SERVICE FOR LONGER THAN 8 HOURS TO PERFORM MAINTENANCE ON THE UN- | | INTERRUPTABLE POWER SUPPLY FOR THE #1A BUS THAT POWERS THE SPDS. | | | | THE SPDS IN INOPERABLE BUT FUNCTIONAL. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+