U.S. Nuclear Regulatory Commission Operations Center Event Reports For 08/04/97 - 08/05/97 ** EVENT NUMBERS ** 32591 32717 32718 32719 32720 32721 32722 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32591 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: ROBINSON REGION: 2 |NOTIFICATION DATE: 07/05/97 | |UNIT: [2] [ ] [ ] STATE: SC |NOTIFICATION TIME: 16:37 [ET]| |RX TYPE: [2] W-3-LP |EVENT DATE: 07/05/97 | +------------------------------------------------+EVENT TIME: 16:00[EDT]| |NRC NOTIFIED BY: KEN JONES |LAST UPDATE DATE: 08/04/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |EDWARD MCALPINE 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | CONTAINMENT TEMPERATURE EXCEEDS THE UFSAR INPUT USED IN THE CONTAINMENT | | ANALYSIS. | | | | THE FOLLOWING TEXT IS A PORTION OF A FACSIMILE RECEIVED FROM THE LICENSEE: | | | | "WITH REGARD TO THE DESIGN BASIS OF THE REACTOR CONTAINMENT AND ITS | | VENTILATION SYSTEM, THE UPDATED FINAL SAFETY ANALYSIS REPORT [UFSAR] STATES | | THAT THE CONTAINMENT BUILDING VENTILATION SYSTEM IS DESIGNED TO REMOVE HEAT | | LOADS AND MAINTAIN TEMPERATURE OF 120 DEGREES [F] OR LESS. AS AN INITIAL | | CONDITION FOR THE CONTAINMENT ANALYSIS, THE UFSAR STATES THAT THE | | CONTAINMENT TEMPERATURE IS AT 120 DEGREES F. BASED ON TEMPERATURE | | MEASUREMENTS PERFORMED ON JULY 5 AT 1600 HOURS, THE CONTAINMENT TEMPERATURE | | WAS INDICATED TO BE 120.51 DEGREES F. THEREFORE, THE CONTAINMENT IS NOT | | CONSIDERED TO BE OPERATING WITHIN THE UFSAR DESIGN. THE TECHNICAL | | SPECIFICATIONS DO NOT SPECIFY A MAXIMUM CONTAINMENT TEMPERATURE LIMIT. | | STATION MANAGEMENT HAS IMPOSED AN ADMINISTRATIVE OPERATING RESTRICTION | | THAT REQUIRES THAT THE PLANT BE PLACED IN THE HOT SHUTDOWN CONDITION WITHIN | | 8 HOURS OF EXCEEDING 120 DEGREES F. ACTIONS WILL BE TAKEN TO RESTORE THE | | TEMPERATURE TO WITHIN LIMITS DURING THE 8-HOUR TIME PERIOD. HOWEVER, | | SUFFICIENT TIME WILL BE RESERVED TO ENSURE AN ORDERLY SHUTDOWN BY THE END | | OF THE 8-HOUR TIME PERIOD." | | | | THE LICENSEE NOTED THAT THE WEATHER HAS BEEN EXTREMELY HOT FOR THE PAST | | 4 DAYS WHICH HAS INCREASED LAKE TEMPERATURES. THE CURRENT CONTAINMENT | | TEMPERATURE IS 119.9 DEGREES F AND TRENDING DOWNWARD DUE TO A SLOWLY | | DECREASING CIRCULATING WATER (CW) INLET TEMPERATURES. (THERE IS ABOUT A | | 1-1/2 TO 2-HOUR LAG BETWEEN AN OBSERVED DECREASE IN CW INLET TEMPERATURE | | AND CONTAINMENT TEMPERATURE.) AS A COMPENSATORY MEASURE, THE LICENSEE CAN | | INITIATE A CONTAINMENT PURGE TO REDUCE CONTAINMENT TEMPERATURES. (A | | 0.7-DEGREE F DECREASE IN CONTAINMENT TEMPERATURE WAS OBSERVED WHEN A PURGE | | WAS PERFORMED 4 DAYS AGO.) THE 8-HOUR ADMINISTRATIVE LIMIT WAS ADOPTED | | BASED ON THE GUIDANCE PROVIDED IN THE IMPROVED TECH SPECS WHICH HAS NOT | | BEEN APPROVED. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE AT 2222 EDT ON 07/05/97, FROM DAVID COATES TO S. SANDIN * * * | | | | THE LICENSEE EXITED THE 8-HOUR ADMINISTRATIVE LIMIT AT 2000 EDT. THE | | VOLUMETRIC WEIGHTED TEMPERATURE AVERAGE CALCULATED AT 2200 EDT WAS 119.892 | | DEGREES F. | | | | THE LICENSEE PLANS TO INFORM THE NRC RESIDENT INSPECTOR. THE NRC | | OPERATIONS OFFICER NOTIFIED THE R2DO (ED McALPINE). | | | | * * * UPDATE AT 1527 ON 08/04/97, FROM CHERNOFF RECEIVED BY TROCINE * * * | | | | THE LICENSEE IS RETRACTING THIS EVENT NOTIFICATION BASED UPON CALCULATIONS | | COMPLETED ON 08/01/97. APPARENTLY, THESE CALCULATIONS CONCLUDED THAT THE | | MAXIMUM RECORDED TEMPERATURE INSIDE THE CONTAINMENT ON 07/05/97, WAS LESS | | THAN 120 DEGREES F. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. THE NRC OPERATIONS | | CENTER NOTIFIED THE R2DO (SKINNER). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32717 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOPER REGION: 4 |NOTIFICATION DATE: 08/04/97 | |UNIT: [1] [ ] [ ] STATE: NE |NOTIFICATION TIME: 05:47 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 08/04/97 | +------------------------------------------------+EVENT TIME: 03:50[CDT]| |NRC NOTIFIED BY: MARK KAUL |LAST UPDATE DATE: 08/04/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CHARLES CAIN RDO | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 28 POWER OPERATION | 28 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | SUPPRESSION POOL WATER LEVEL IN EXCESS OF DESIGN BASIS | | | | WHILE PERFORMING AN INSERVICE TEST OF THE HIGH PRESSURE COOLANT INJECTION | | (HPCI) SYSTEM, SUPPRESSION POOL WATER LEVEL INCREASED TO 13'0", WHICH IS 1" | | HIGHER THAN PERMITTED IN THE PLANT TECHNICAL SPECIFICATIONS AND SPECIFIED | | IN THE DESIGN BASIS. (NORMAL SUPPRESSION POOL LEVEL IS 12'9".) THE LICENSEE | | HAS COMPLETED THE HPCI TEST AND IS CURRENTLY PUMPING WATER FROM THE | | SUPPRESSION POOL TO RADWASTE. | | | | THE LICENSEE STATED THAT TECHNICAL SPECIFICATION LIMITING CONDITION FOR | | OPERATION (LCO) 1.0.J WAS ENTERED WHEN SUPPRESSION POOL LEVEL EXCEEDED THE | | TECHNICAL SPECIFICATION LIMIT. THE LCO REQUIRES THAT THE UNIT BE PLACED IN | | HOT SHUTDOWN WITHIN SIX HOURS IF SUPPRESSION POOL LEVEL IS NOT REDUCED | | BELOW THE LIMIT. THE LICENSEE BEGAN REDUCING THE SUPPRESSION POOL LEVEL AT | | 0326 CDT, AND AS OF 0438 CDT, THE LEVEL HAD BEEN LOWERED TO 12'11.4". THE | | LICENSEE ANTICIPATES THAT THE LCO WILL BE EXITED BEFORE IT EXPIRES. THE NRC | | RESIDENT INSPECTOR HAS BEEN INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32718 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: NINE MILE POINT REGION: 1 |NOTIFICATION DATE: 08/04/97 | |UNIT: [ ] [2] [ ] STATE: NY |NOTIFICATION TIME: 07:44 [ET]| |RX TYPE: [1] GE-2,[2] GE-5 |EVENT DATE: 08/04/97 | +------------------------------------------------+EVENT TIME: 07:28[EDT]| |NRC NOTIFIED BY: GARY CORBIN |LAST UPDATE DATE: 08/04/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: UNUSUAL EVENT +-----------------------------+ |10 CFR SECTION: |CLIFFORD ANDERSON RDO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |ROBERT DENNIG/NRR EO | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS |BAGWELL FEMA | |NRCS RCS LEAKAGE |RICHARD BARRETT/AEOD IRD | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 95 POWER OPERATION | 0 HOT SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNIT SHUTDOWN DUE TO EXCESSIVE UNIDENTIFIED RCS LEAKAGE | | | | AT 0557, OPERATORS DISCOVERED INCREASING DRYWELL PRESSURE AND REACTOR | | COOLANT SYSTEM (RCS) UNIDENTIFIED LEAKAGE RATE. AT 0615, A NORMAL SHUTDOWN | | WAS COMMENCED, AND AT 0715, A MANUAL REACTOR SCRAM WAS INITIATED AS PART OF | | THE SHUTDOWN. ALL CONTROL RODS INSERTED, AND ALL SYSTEMS FUNCTIONED AS | | EXPECTED. THE LICENSEE DECLARED AN UNUSUAL EVENT AT 0728 WHEN THE LEAKAGE | | REACHED THE EMERGENCY ACTION LEVEL THRESHOLD OF 10 GPM. | | | | THE LICENSEE REPORTED THAT UNIDENTIFIED LEAKAGE INCREASED TO A PEAK OF | | APPROXIMATELY 10 GPM, AND IT IS CURRENTLY AT 8 GPM. THE LICENSEE INTENDS TO | | PROCEED TO COLD SHUTDOWN AND MAKE A DRYWELL ENTRY TO IDENTIFY THE SOURCE OF | | THE LEAKAGE. THE LICENSEE HAS INFORMED THE STATE OF NEW YORK AND THE NRC | | RESIDENT INSPECTOR. | | | | * * * UPDATE AT 1040 ON 8/4/97, FROM NEWMAN TAKEN BY STRANSKY * * * | | | | THE UNUSUAL EVENT WAS TERMINATED AT 1035. THE LICENSEE REPORTED THAT RCS | | UNIDENTIFIED LEAKAGE IS CURRENTLY 1.2 GPM. BASED UPON CONTAINMENT SAMPLES | | TAKEN BY THE LICENSEE, THE SOURCE OF THE LEAKAGE APPEARS TO BE THE 'B' | | RECIRCULATION PUMP SEAL. THE LICENSEE INTENDS TO MAKE A CONTAINMENT ENTRY | | LATER TODAY. THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED. THE NRC | | OPERATIONS CENTER NOTIFIED THE R1DO (ANDERSON), NRR EO (DENNIG), AND FEMA | | (RISHE). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32719 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HADDAM NECK REGION: 1 |NOTIFICATION DATE: 08/04/97 | |UNIT: [1] [ ] [ ] STATE: CT |NOTIFICATION TIME: 10:03 [ET]| |RX TYPE: [1] W-4-LP |EVENT DATE: 08/04/97 | +------------------------------------------------+EVENT TIME: 09:50[EDT]| |NRC NOTIFIED BY: McMAHON |LAST UPDATE DATE: 08/04/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CLIFFORD ANDERSON 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 N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | SPENT FUEL POOL COOLING SERVICE WATER SYSTEM FAILED TO MEET FLOW TEST | | ACCEPTANCE CRITERION. | | | | WHILE PERFORMING A FLOW TEST OF SPENT FUEL POOL COOLING SERVICE WATER, | | SYSTEM FLOW FAILED TO MEET THE TEST ACCEPTANCE CRITERION OF 855 GPM. | | MAXIMUM FLOW ACHIEVED WAS 820 GPM. THE LICENSEE PLANS TO BACK FLUSH AND | | CLEAN THE HEAT EXCHANGER. THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY | | THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 32720 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: GOODRICH TESTING AND ENGINEERING |NOTIFICATION DATE: 08/04/97 | | CITY: NASHVILLE REGION: 2 |NOTIFICATION TIME: 11:02 [ET]| | COUNTY: STATE: TN |EVENT DATE: 08/04/97 | |LICENSE#: TN R-19192 AGREEMENT: Y |EVENT TIME: 00:00[EDT]| | DOCKET: |LAST UPDATE DATE: 08/04/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |PIERCE SKINNER RDO | | |DON COOL, NMSS EO | +------------------------------------------------+ | |NRC NOTIFIED BY: WOODRUFF (REGION 2) | | |HQ OPS OFFICER: BOB STRANSKY | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NAGR AGREEMENT STATE | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AGREEMENT STATE REPORT OF STOLEN TROXLER MOISTURE/DENSITY GAUGE | | | | THE STATE OF TENNESSEE NOTIFIED NRC REGION 2 OF THE THEFT OF A TROXLER | | MOISTURE/DENSITY GAUGE SOMETIME BETWEEN THE AFTERNOON OF 8/1/97, AND THE | | MORNING OF 8/2/97. AFTER WORK, AN EMPLOYEE OF GOODRICH TESTING AND | | ENGINEERING TOOK A TROXLER MODEL-344O PORTABLE GAUGE (S/N 23732) TO HIS | | PLACE OF RESIDENCE IN A TRUCK. THE NEXT MORNING, WHEN HE ARRIVED AT A | | TEMPORARY JOB SITE, THE GAUGE WAS MISSING FROM THE TRUCK. THERE WERE NO | | OTHER DETAILS REGARDING THE CIRCUMSTANCES OF THE THEFT AVAILABLE AT THE | | TIME OF THIS NOTIFICATION. THE GAUGE CONTAINS AN 8-mCi Cs-137 AND A 40-mCi | | Am-Be SOURCE. | | | | THE STATE HAS NOTIFIED THE LOCAL POLICE DEPARTMENTS, AND A PRESS RELEASE IS | | PLANNED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32721 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VOGTLE REGION: 2 |NOTIFICATION DATE: 08/04/97 | |UNIT: [1] [ ] [ ] STATE: GA |NOTIFICATION TIME: 15:10 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 08/04/97 | +------------------------------------------------+EVENT TIME: 12:55[EDT]| |NRC NOTIFIED BY: JAMES ROBINSON |LAST UPDATE DATE: 08/04/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PIERCE SKINNER 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 +------------------------------------------------------------------------------+ | AUXILIARY FEEDWATER SYSTEM INJECTION INTO ALL FOUR STEAM GENERATORS AND | | SUBSEQUENT POWER INCREASE TO 101.5% DURING SURVEILLANCE TESTING | | | | WHILE PERFORMING A SURVEILLANCE TEST IN ACCORDANCE WITH A NEW REVISION OF | | PROCEDURE 14810-1, TURBINE-DRIVEN AUXILIARY FEEDWATER PUMP INSERVICE TEST | | AND RESPONSE TIME TEST, AN AUXILIARY FEEDWATER ACTUATION OCCURRED AND | | CAUSED AUXILIARY FEEDWATER TO INJECT INTO ALL FOUR STEAM GENERATORS. THE | | ACTUATION SIGNAL WAS A PLANNED PORTION OF THE PROCEDURE. HOWEVER, THE | | ACTION FOR CLOSING THE MANUAL ISOLATION VALVE TO PREVENT INJECTION INTO THE | | STEAM GENERATORS WAS DELETED FROM THE PROCEDURE DURING ITS LAST REVISION. | | LICENSEE OPERATORS RECOGNIZED THIS SITUATION, CLOSED THE MOTOR-OPERATED | | DISCHARGE VALVES FROM THE CONTROL ROOM WITHIN A FEW MINUTES OF THE | | INJECTION, AND SECURED THE AUXILIARY FEEDWATER PUMP. | | | | THERE WERE NO SIGNIFICANT CHANGES IN STEAM GENERATOR WATER LEVEL. HOWEVER, | | THE INJECTION OF COOLER WATER INTO THE STEAM GENERATORS RESULTED IN AN | | INCREASE IN REACTOR POWER FOR A SHORT DURATION. THE HIGHEST INDICATED | | REACTOR POWER WAS 3,596 MWt (100.8% REACTOR POWER). REACTOR ENGINEERING | | PERSONNEL SUBSEQUENTLY REVIEWED THIS TRANSIENT AND DETERMINED (BASED UPON | | CALCULATIONS) THAT THE PEAK REACTOR POWER WAS ACTUALLY 101.5%. | | | | THE AUXILIARY FEEDWATER PUMP IS CURRENTLY SECURED AND IN STANDBY, AND THE | | REACTOR IS CURRENTLY STABLE AT 100% POWER. THE LICENSEE STATED THAT ALL | | SYSTEMS FUNCTIONED AS REQUIRED IN RESPONSE TO THIS TRANSIENT. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32722 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HATCH REGION: 2 |NOTIFICATION DATE: 08/04/97 | |UNIT: [1] [ ] [ ] STATE: GA |NOTIFICATION TIME: 20:07 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 08/03/97 | +------------------------------------------------+EVENT TIME: 23:23[EDT]| |NRC NOTIFIED BY: BRUCE BUTLER |LAST UPDATE DATE: 08/04/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PIERCE SKINNER 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 88 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | FAILURE TO HAVE A BACKUP PRESSURE REGULATOR AVAILABLE WHEN REACTOR WAS LESS | | THAN 80% THERMAL POWER | | | | AT 1540 ON 8/3/97, THE LICENSEE BEGAN TO REDUCE REACTOR POWER FROM 100% DUE | | TO CYCLING OF THE MAIN TURBINE CONTROL VALVES. THE POWER REDUCTION WAS | | CEASED AT 1557 WITH THE REACTOR AT 88%, AND TROUBLESHOOTING WAS COMMENCED. | | THE LICENSEE IDENTIFIED THAT THE IN-SERVICE MAIN TURBINE PRESSURE REGULATOR | | WAS SLOWLY FAILING HIGH. THIS, IN TURN, WAS CAUSING THE MAIN TURBINE | | CONTROL VALVES TO OPEN AND REACTOR PRESSURE TO STEADILY DECREASE AT A VERY | | SLOW RATE. THE LICENSEE AGAIN BEGAN TO REDUCE REACTOR POWER AT 2103 IN | | ORDER TO REMOVE THIS PRESSURE REGULATOR FROM SERVICE, PLACE THE REDUNDANT | | TRAIN IN SERVICE, AND LIMIT THE EFFECTS OF ANY TRANSIENTS THAT MIGHT BE | | RECEIVED. THE POWER REDUCTION WAS CEASED AT 2126 WITH REACTOR POWER AT | | 76%, AND XENON CAUSED POWER TO FURTHER DECREASE TO 73.5%. THE LICENSEE | | DISABLED THE 'B' MAIN TURBINE PRESSURE REGULATOR AT 2323. THE 'A' MAIN | | TURBINE PRESSURE REGULATOR WAS PLACED IN SERVICE, AND POWER ASCENSION WAS | | COMMENCED AT 2330. REACTOR POWER WAS GREATER THAN 80% AT 2342. | | | | SUBSEQUENT REVIEW (ON 8/4/97) DETERMINED THAT UNIT 1 WAS OUTSIDE ITS DESIGN | | BASIS BETWEEN 2323 AND 2342 ON 8/3/97, BECAUSE THERE WAS NO BACKUP PRESSURE | | REGULATOR AVAILABLE WITH THE REACTOR BELOW 80% THERMAL POWER. THIS WAS | | BASED UPON A REVIEW OF THE UNIT 2 FINAL SAFETY ANALYSIS REPORT (FSAR) WHICH | | IMPLIED THAT UNIT 2 WOULD BE OUTSIDE ITS DESIGN BASIS IF A BACKUP PRESSURE | | REGULATOR WAS NOT AVAILABLE WHEN THE REACTOR WAS BELOW 80% THERMAL POWER. | | THIS ITEM IS NOT REFERENCED IN THE UNIT 1 FSAR. HOWEVER, THE LICENSEE | | DECIDED THAT THE SAME CONDITIONS THAT APPLY TO UNIT 2 SHOULD APPLY TO UNIT | | 1 AS WELL. | | | | THE LICENSEE PLANS TO NOTIFY THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+