U.S. Nuclear Regulatory Commission Operations Center Event Reports For 08/31/95 - 09/01/95 ** EVENT NUMBERS ** 29263 29264 29265 29266 29267 29268 +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 29263 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: ABB COMBUSTION ENGINEERING |NOTIFICATION DATE: 08/31/95 | | CITY: WINDSOR REGION: 1 |NOTIFICATION TIME: 10:47 [ET]| | COUNTY: STATE: CT |EVENT DATE: 08/31/95 | |LICENSE#: AGREEMENT: N |EVENT TIME: 00:00[EDT]| | DOCKET: |LAST UPDATE DATE: 08/31/95 | | +-----------------------------+ | |PERSON ORGANIZATION| | | | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: MOLNAR |VERN HODGE NRR | |HQ OPS OFFICER: JOSEPH SEBROSKY | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |CCCC 21.21 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ABB COMBUSTION ENGINEERING (CE) OF WINDSOR, CONNECTICUT, REPORTED A DEFECT | | IN A REACTOR PROTECTION SYSTEM (RPS) SUB-COMPONENT IN ACCORDANCE WITH 10 | | CFR PART 21. | | | | THE DEFECT WAS THE PRESENCE OF A HARD WIRED CONNECTION IN EACH OF THE FOUR | | CONTAINMENT HIGH PRESSURE TRIP LOGIC CIRCUITS PROVIDED TO CONSUMERS POWER | | COMPANY FOR THE PALISADES NUCLEAR POWER PLANT. THE DEFECT CAUSES THE RPS | | TO BE UNABLE TO TRIP THE REACTOR ON A VALID HIGH CONTAINMENT PRESSURE | | SIGNAL. THE PROBLEM HAS BEEN CORRECTED AT PALISADES, AND CE HAS NO REASON | | TO BELIEVE THAT THIS REPORTABLE CONDITION APPLIES TO ANY OTHER PLANT FOR | | WHICH CE DESIGNED THE NUCLEAR STEAM SUPPLY SYSTEM. | | | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29264 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PERRY REGION: 3 |NOTIFICATION DATE: 08/31/95 | |UNIT: [1] [ ] [ ] STATE: OH |NOTIFICATION TIME: 12:25 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 08/31/95 | +------------------------------------------------+EVENT TIME: 11:42[EDT]| |NRC NOTIFIED BY: RUSS KEARNEY |LAST UPDATE DATE: 08/31/95 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PATRICK HILAND RDO | |ACCS 50.72(b)(1)(iv) ECCS INJECTION | | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | A/R Y 100 POWER OPERATION | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | REACTOR SCRAM DUE TO A MAIN TURBINE TRIP | | | | AT 11:42, A REACTOR SCRAM OCCURRED DUE TO THE TRIP OF THE MAIN TURBINE AND | | GENERATOR. ACTUATION OF THE SCRAM WAS COMPLETE, AND ALL RODS FULLY | | INSERTED. REACTOR VESSEL LEVEL DECREASED TO LEVEL 2 (130 INCHES ABOVE THE | | TOP OF THE ACTIVE FUEL) AND WAS RECOVERED WITHIN 2 MINUTES BY THE | | MOTOR-OPERATED FEEDWATER PUMP, HIGH PRESSURE CORE SPRAY (HPCS) SYSTEM, AND | | REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM. IN ADDITION, THE REACTOR | | RECIRCULATION PUMPS TRIPPED, AS EXPECTED, DUE TO THE LEVEL 2 SIGNAL. | | | | THE LICENSEE IS CONTINUING TO INVESTIGATE THE CAUSE OF THE MAIN TURBINE | | TRIP WHICH CAUSED THE REACTOR SCRAM. AT THIS TIME, THE LICENSEE BELIEVES | | THAT RCIC MAY HAVE RECEIVED A START SIGNAL DUE TO THE LOSS OF THE DIVISION | | 2 INVERTER (1E12K701). A RCIC ACTUATION SIGNAL IN TURN GENERATES AUTOMATIC | | TRIP SIGNALS FOR THE MAIN TURBINE AND THE FEEDWATER PUMP TURBINES. | | | | DIVISION 1 REMAINS FULLY INTACT, AND HPCS REMAINS OPERABLE AND AVAILABLE. | | THE LICENSEE BELIEVES THAT DIVISION 2 EQUIPMENT WOULD BE CAPABLE OF BEING | | OPERATED MANUALLY BUT WOULD NOT AUTOMATICALLY ACTUATE IF REQUIRED. | | | | THE PLANT IS CURRENTLY STABLE AND REACTOR VESSEL LEVEL IS BEING MAINTAINED | | BY THE MOTOR-DRIVEN FEEDWATER PUMP. HPCS AND RCIC SYSTEM INJECTIONS HAVE | | BEEN TERMINATED. REACTOR PRESSURE IS BEING MAINTAINED BY THE TURBINE | | BYPASS VALVES, AND THE MAIN CONDENSER IS AVAILABLE AS A HEAT SINK. | | | | IN ADDITION, THE LEVEL 2 ISOLATIONS WERE VERIFIED WITH THE EXCEPTION OF A | | CONTAINMENT RADIATION MONITOR OUTBOARD ISOLATION VALVE (1D17F081A). THIS | | VALVE WAS EXPECTED TO CLOSE BUT DID NOT. THE INBOARD ISOLATION VALVE DID | | ACTUATE AND CLOSE, AND THE NON-SAFETY-RELATED RADIATION MONITOR WAS SHUT | | DOWN. THE LICENSEE TRIED TO MANUALLY CLOSE VALVE 1D17F081A FROM THE | | CONTROL ROOM WITH NO RESPONSE. THE LICENSEE'S INVESTIGATION IS ONGOING. | | | | THE LICENSEE HAS NOTIFIED THE NRC RESIDENT INSPECTOR AND PLANS TO ISSUE A | | PRESS RELEASE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29265 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOK REGION: 3 |NOTIFICATION DATE: 08/31/95 | |UNIT: [1] [ ] [ ] STATE: MI |NOTIFICATION TIME: 13:36 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 08/31/95 | +------------------------------------------------+EVENT TIME: 10:15[EDT]| |NRC NOTIFIED BY: ROGER WEST |LAST UPDATE DATE: 08/31/95 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PATRICK HILAND 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 N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | IMPROPER INSTALLATION OF THE SEAL ASSEMBLIES ON ELECTRICAL CONNECTIONS TO | | TWO REACTOR VESSEL HEAD VENT SOLENOID VALVES. | | | | THE LICENSEE DISCOVERED THAT SEAL ASSEMBLIES ON ELECTRICAL CONNECTIONS TO | | TWO UNIT 1 REACTOR VESSEL HEAD VENT SOLENOID VALVES HAD BEEN IMPROPERLY | | INSTALLED. THIS RESULTED IN THE LACK OF A MOISTURE BARRIER SUCH THAT BOTH | | VALVES COULD HAVE FAILED UNDER ACCIDENT CONDITIONS. EACH OF TWO REACTOR | | VESSEL HEAD VENT FLOW PATHS CONTAINS ONE OF THE AFFECTED VALVES. FAILURE | | OF BOTH VALVES WOULD RENDER THE REACTOR VESSEL HEAD VENT UNAVAILABLE FOR | | ACCIDENT MITIGATION. | | | | THE ROOT CAUSE OF THE INSTALLATION ERRORS IS CURRENTLY UNDETERMINED, AND | | THE LICENSEE IS CONTINUING TO INVESTIGATE THE STATUS OF OTHER CONNECTIONS | | IN THE REACTOR VESSEL HEAD VENT SYSTEM AND IN THE PRESSURIZER HEAD VENT | | SYSTEM. THIS IS AN ENVIRONMENTAL QUALIFICATION ISSUE. AT THE TIME OF THIS | | NOTIFICATION, THE LICENSEE DID NOT KNOW WHEN THE IMPROPER INSTALLATIONS | | OCCURRED, AND UNIT 1 WAS NOT IN ANY TECHNICAL SPECIFICATION LIMITING | | CONDITIONS FOR OPERATION. | | | | THE LICENSEE HAS NOTIFIED THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE AUGUST 31, 1995 20:05 EDT FROM: WEST BY: SCARFO * * * | | | | THE FOLLOWING IS THE TEXT OF A FACSIMILE SUBMITTED BY THE LICENSEE: | | | | "BASED UPON FURTHER EVALUATION OF THE STATUS OF THE SEAL ASSEMBLIES ON | | ELECTRICAL CONNECTIONS TO REACTOR VESSEL HEAD VENT SOLENOID VALVES AND | | PRESSURIZER VENT SOLENOID VALVES, IT HAS BEEN DETERMINED THAT THE | | ASSEMBLIES FOR ALL VENT SOLENOID VALVES ON BOTH UNITS WERE IMPROPERLY | | INSTALLED, THEREBY INVALIDATING THE ENVIRONMENTAL QUALIFICATION BASIS. ON | | UNIT 2, WHICH IS CURRENTLY IN MODE 3, DECLARATION OF VALVE INOPERABILITY | | HAS RESULTED IN ENTRY INTO A 72-HOUR ACTION STATEMENT. UNIT 1 IS IN A MODE | | IN WHICH THE VENT VALVE TECHNICAL SPECIFICATION DOES NOT APPLY. ACTIVITIES | | CONTINUE TO CORRECT THE SEAL ASSEMBLY INSTALLATION AND RESTORE THE VENT | | VALVES TO OPERABLE STATUS. | | | | APPLICABLE TECHNICAL SPECIFICATIONS IN UNIT 2 ARE 3.4.12.1 "REACTOR VESSEL | | HEAT VENTS", AND 3.4.12.2 "PRESSURIZER STEAM SPACE VENTS". ACTIONS | | STATEMENTS (b) OF BOTH SPECIFICATIONS ALLOW 72 HOURS TO RESTORE OPERABILITY | | (FOLLOWING REMOVAL OF POWER FROM THE VALVE ACTUATORS)." | | | | END OF TEXT. | | | | THE LICENSEE HAS INFORMED THE NRC RESIDENT INSPECTOR. THE NRC OPERATIONS | | CENTER NOTIFIED THE R3DO (HILAND). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29266 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CRYSTAL RIVER REGION: 2 |NOTIFICATION DATE: 08/31/95 | |UNIT: [3] [ ] [ ] STATE: FL |NOTIFICATION TIME: 15:51 [ET]| |RX TYPE: [3] B&W-L-LP |EVENT DATE: 08/31/95 | +------------------------------------------------+EVENT TIME: 15:00[EDT]| |NRC NOTIFIED BY: W. BANDHAUER/L. MOFFATT |LAST UPDATE DATE: 08/31/95 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GEORGE AL BELISLE 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 3 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DISCOVERY OF A NONCONSERVATIVE EMERGENCY FEEDWATER INITIATION AND CONTROL | | (EFIC) SYSTEM REACTOR COOLANT SYSTEM NATURAL CIRCULATION SETPOINT. | | | | DURING AN ONGOING SETPOINT VERIFICATION EVALUATION, THE LICENSEE DISCOVERED | | THAT THE EFIC SYSTEM REACTOR COOLANT SYSTEM NATURAL CIRCULATION SETPOINT | | WAS NONCONSERVATIVE AND OUTSIDE THE DESIGN BASIS. THE LICENSEE CURRENTLY | | CONSIDERS THE EFIC SYSTEM TO BE OPERABLE FOR THE NATURAL CIRCULATION | | SETPOINT BECAUSE THE EMERGENCY OPERATING PROCEDURES HAVE SUFFICIENT | | GUIDANCE TO ASSURE NATURAL CIRCULATION. TECHNICAL SPECIFICATIONS DO NOT | | ADDRESS THIS SETPOINT. | | | | THE EXISTING SETPOINT IS ON A PERCENTAGE OF FULL RANGE STEAM GENERATOR | | LEVEL BETWEEN 63% AND 65%, AND THE PROPOSED NEW SETPOINT WILL BE 75%. THE | | LICENSEE IS NOT AWARE OF ANY OTHER SETPOINTS THAT ARE AFFECTED AND STATED | | THAT THIS SHOULD NOT AFFECT ANY OTHER LEVEL INDICATIONS. A WORST CASE | | ACCIDENT SCENARIO INVOLVING A STEAM LINE BREAK/FEEDWATER LINE BREAK LOSS OF | | COOLANT ACCIDENT INSIDE CONTAINMENT AND ITS AFFECT ON THE TRANSMITTERS | | INSIDE CONTAINMENT WOULD AFFECT THIS PARTICULAR SETPOINT. IF THE REACTOR | | COOLANT PUMPS ARE OFF FOR SOME REASON, THE EFIC SYSTEM WOULD CONTROL AT A | | PARTICULAR SETPOINT. IF ONE OF THE REACTOR COOLANT PUMPS IS RUNNING, IT | | WOULD CONTROL AT A DIFFERENT SETPOINT. ONLY THE SETPOINT THAT IS | | AUTOMATICALLY SELECTED WHEN ALL OF THE REACTOR COOLANT PUMPS ARE OFF IS | | AFFECTED. THIS IS A NON-TECHNICAL SPECIFICATION FUNCTION. | | | | THE LICENSEE HAS NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29267 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOPER REGION: 4 |NOTIFICATION DATE: 08/31/95 | |UNIT: [1] [ ] [ ] STATE: NE |NOTIFICATION TIME: 16:12 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 08/31/95 | +------------------------------------------------+EVENT TIME: 14:15[CDT]| |NRC NOTIFIED BY: D. S. BILLESBACH |LAST UPDATE DATE: 08/31/95 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PHIL HARRELL 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 96 POWER OPERATION | 96 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DISCOVERY OF THE EMERGENCY BATTERY LIGHTING (EBL) BEING OUTSIDE THE DESIGN | | BASIS OF THE PLANT. | | | | IN NOVEMBER 1994, EBL RELIABILITY WAS CALLED INTO QUESTION DUE TO POOR | | MAINTENANCE CONTROLS AND A LACK OF DESIGN BASIS INFORMATION. THIS WAS | | REPORTED TO THE NRC IN LICENSEE EVENT REPORT NO. 94-034. IN JANUARY AND | | FEBRUARY 1995, THE APPENDIX R AND STATION BLACKOUT UNITS DESIGN BASES WERE | | VERIFIED AND THE EBLs UPGRADED UNDER EQUIPMENT SPECIFICATION CHANGE NO. | | 94-075 TO ADDRESS RELIABILITY AND UNDER DESIGN CHANGE NO. 94-075 TO ADDRESS | | DESIGN BASIS REQUIREMENTS (ADDITIONAL UNITS). IN THE SIX MONTHS SINCE | | COMPLETION OF THE UPGRADE, REPEAT FAILURES OF THE EBLs HAVE BEEN NOTED | | PRIMARILY INVOLVING FAILURE OF THE CHARGING CARDS. DUE TO CONCERNS WITH | | THE RELIABILITY OF THE CHARGING CARDS, THE OPERABILITY OF THE EBLs CANNOT | | BE ASSURED TO BE WITHIN THE COOPER NUCLEAR STATION DESIGN BASIS OF 10 CFR | | PART 50, APPENDIX R, SECTION III.J, FOR PROVIDING 8 HOURS OF ILLUMINATION. | | | | A COMPENSATORY MEASURE HAS BEEN IMPLEMENTED TO PROVIDE ALL ON-WATCH | | OPERATORS WITH FLASHLIGHTS TO USE DURING A POSTULATED DESIGN BASIS LOSS OF | | LIGHTING. IN ADDITION, OPERATIONS PERSONNEL WILL BE INFORMED OF THESE | | MEASURES PRIOR TO ASSUMING THE WATCH. | | | | THE LICENSEE HAS NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29268 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OCONEE REGION: 2 |NOTIFICATION DATE: 08/31/95 | |UNIT: [1] [2] [3] STATE: SC |NOTIFICATION TIME: 23:10 [ET]| |RX TYPE: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-LP |EVENT DATE: 08/31/95 | +------------------------------------------------+EVENT TIME: 23:01[EDT]| |NRC NOTIFIED BY: ROY SMITH |LAST UPDATE DATE: 09/01/95 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GEORGE AL BELISLE 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 | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | 3 | N Y 100 POWER OPERATION | 100 POWER OPERATION | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TECHNICAL SPECIFICATION REQUIRED SHUTDOWN BECAUSE A 72-HOUR LIMITING | | CONDITION FOR OPERATION FOR AN INOPERABLE BACKUP POWER SUPPLY WAS EXCEEDED. | | | | AT 22:01, THE LICENSEE EXCEEDED A LIMITING CONDITION FOR OPERATION TIME | | LIMIT BECAUSE 1 OF 2 BACKUP POWER SUPPLIES (THE OVERHEAD KEOWEE BACKUP | | POWER SUPPLY) WAS INOPERABLE FOR MORE THAN 72 HOURS. AS A RESULT, THE | | APPLICABLE TECHNICAL SPECIFICATION ACTION STATEMENT REQUIRES THE AFFECTED | | UNITS (ALL 3 UNITS) TO BE IN HOT SHUTDOWN WITHIN 12 HOURS AND COLD SHUTDOWN | | WITHIN THE FOLLOWING 48 HOURS. ACCORDINGLY, THE LICENSEE COMMENCED A | | SHUTDOWN OF UNIT 3 AT 23:01, AND THE LICENSEE CURRENTLY PLANS TO STAGGER | | THE UNIT SHUTDOWNS. UNIT 3 WILL BE SHUT DOWN FIRST FOLLOWED BY UNITS 1 AND | | 2, RESPECTIVELY. THERE HAD BEEN NO ENGINEERING SAFEGUARDS FEATURES | | ACTUATIONS OR REACTOR PROTECTIVE SYSTEM ACTUATIONS AS OF THE TIME OF THIS | | NOTIFICATION. | | | | PRIOR TO COMMENCEMENT OF THE UNIT 3 SHUTDOWN, THE LICENSEE WAS IMPLEMENTING | | A NUCLEAR STATION MODIFICATION TO THE OVERHEAD KEOWEE BACKUP POWER SUPPLY | | AND WAS NOT ABLE TO COMPLETE THE MODIFICATION WITHIN THE 72-HOUR ALLOTTED | | TIME FRAME. AS A RESULT, THE LICENSEE BACKED OUT OF THE MODIFICATION AND | | WAS REQUIRED TO TEST THE BACKUP POWER SUPPLY BEFORE RETURNING IT TO | | OPERABLE STATUS. TESTING IS CURRENTLY IN PROGRESS TO RETURN THE INOPERABLE | | BACKUP POWER SUPPLY TO AN OPERABLE STATUS. | | | | THE LICENSEE HAS NOTIFIED THE NRC RESIDENT INSPECTOR. | | | | * * * 00:17 SEPTEMBER 1, 1995, UPDATE FROM SMITH RECEIVED BY GOULD * * * | | | | AT 23:30 ON AUGUST 31, 1995, THE NRC REGION II OFFICE GRANTED A NOTICE OF | | ENFORCEMENT DISCRETION TO THE LICENSEE TO ALLOW 24 HOURS (IN LIEU OF 12 | | HOURS) TO SEQUENTIALLY BRING ALL 3 UNITS TO HOT SHUTDOWN. TESTING OF THE | | BACKUP POWER SUPPLY IS CURRENTLY ONGOING, AND THE UNIT 3 POWER REDUCTION IS | | STILL IN PROGRESS. UNIT 3 IS CURRENTLY OPERATING AT 90% REACTOR POWER, AND | | UNITS 1 AND 2 ARE BOTH CURRENTLY OPERATING AT 100% REACTOR POWER. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. THE NRC OPERATIONS | | CENTER NOTIFIED THE R2DO (BELISLE). | | | | ***UPDATE AT 02:44 ON 9/1/95 BY SNOWDEN TO GOULD*** THE B/U EMERGENCY POWER | | SUPPLY WAS RETURNED TO SERVICE AND THE LCO WAS EXITED AT 02:30. UNITS 1 & 2 | | ARE AT 100% AND UNIT 3 IS AT 75%. THE RI WAS INFORMED. | +------------------------------------------------------------------------------+