U.S. Nuclear Regulatory Commission Operations Center Event Reports For 06/18/97 - 06/19/97 ** EVENT NUMBERS ** 32490 32496 32504 32505 32506 32507 32508 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32490 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 06/16/97 | |UNIT: [ ] [3] [ ] STATE: NY |NOTIFICATION TIME: 11:04 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 06/16/97 | +------------------------------------------------+EVENT TIME: 10:45[EDT]| |NRC NOTIFIED BY: MESSINA/O'DONNELL |LAST UPDATE DATE: 06/18/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: UNUSUAL EVENT +-----------------------------+ |10 CFR SECTION: |RON BELLAMY RDO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |BOB DENNIG EO | | |STINEDURF FEMA | | |Dr BARRETT (MGR) IRD | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 3 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LOSS OF OFFSITE POWER FOR 44 MINUTES. | | | | INDIAN POINT UNIT 3 HAS BEEN SHUTDOWN FOR A REFUELING OUTAGE SINCE | | 05/14/97. PLANT CONDITIONS: 1) OFFSITE POWER BEING SUPPLIED TO THE PLANT | | LOADS FROM THEIR STATION AUXILIARY TRANSFORMER, 2) EMERGENCY DIESEL | | GENERATOR 31 WAS OUT OF SERVICE FOR MAINTENANCE (SUPPLIES POWER TO VITAL | | BUSES 2A & 3A), 3) THE REACTOR CORE WAS BEING COOLED BY RHR COOLING AND THE | | SPENT FUEL POOL BY THE SPENT FUEL POOL COOLING PUMP, AND 4) 119 FUEL | | ASSEMBLIES HAD BEEN OFFLOADED FROM THE REACTOR CORE TO THE SPENT FUEL POOL | | AND 74 FUEL ASSEMBLIES WERE STILL IN THE REACTOR CORE. | | | | ACCORDING TO THE LICENSEE, INDIAN POINT UNIT 2 (CONSOLIDATED EDISON CO) WAS | | SWITCHING ELECTRICAL LOADS IN THE SWITCHYARD WHEN INDIAN POINT UNIT 2 | | PERSONNEL APPARENTLY APPLIED A LARGE GROUND BY MISTAKE WHICH CAUSED A LOSS | | OF OFFSITE POWER TO INDIAN POINT UNIT 3 STATION AUXILIARY TRANSFORMER. | | | | ON THE A LOSS OF OFFSITE POWER EMERGENCY DIESEL 32 AUTOMATICALLY STARTED | | BUT DID NOT LOAD TO ITS 480 VAC VITAL BUS "6A" BECAUSE IT BLEW A CONTROL | | POWER FUSE. EMERGENCY DIESEL GENERATOR 33 STARTED AND LOADED ONTO ITS 480 | | VAC VITAL BUS (5A). VITAL BUS "5A" SUPPLIES POWER TO ONE COMPONENT COOLING | | WATER PUMP AND ONE SERVICE WATER PUMP. THE SPENT FUEL COOLING WATER PUMP | | WAS PLACED BACK IN SERVICE AT 1058 EDT AFTER ITS MOTOR CONTROL CENTER WAS | | RESET AND POWER WAS SUPPLIED TO IT FROM VITAL BUS "5A". SPENT FUEL POOL | | TEMPERATURE INCREASED FROM 95 TO 96 DEGREES F DURING THE LOSS OF SPENT FUEL | | POOL COOLING PUMP. THE RESIDUAL HEAT REMOVAL PUMP WAS RESTORED TO SERVICE | | SHORTLY AFTER 1104 ET. THERE WAS NO NOTICEABLE INCREASE IN THE REACTOR | | COOLANT SYSTEM TEMPERATURE DURING THIS EVENT. | | | | THE NRC RESIDENT INSPECTOR WAS IN CONTROL ROOM DURING DURING THE LOSS OF | | OFFSITE POWER. | | | | * * * UPDATE 1224 6/16/97 FROM MESSINA TAKEN BY STRANSKY * * * | | | | THE UNUSUAL EVENT WAS TERMINATED AT 1211. THE NRC RESIDENT INSPECTOR HAS | | BEEN INFORMED. NOTIFIED R1DO (BELLAMY), EO (DENNIG), FEMA (STINEDURF). | | | | * * * UPDATE 1804 6/18/97 FROM ROKES TAKEN BY STRANSKY * * * | | | | THE LICENSEE WISHES TO CORRECT SOME OF THE INFORMATION PROVIDED IN THE | | INITIAL REPORT. THE POWER INTERRUPTION OCCURRED WHEN A CONSOLIDATED EDISON | | EMPLOYEE WORKING AT THE BUCHANAN SUBSTATION (NOT THE IP 2 SWITCHYARD) | | MISAPPLIED A GROUND ON A 138kV FEEDER, CAUSING A LOSS OF POWER FROM THE | | SUBSTATION TO THE IP 3 STATION AUXILIARY TRANSFORMER. | | | | ADDITIONALLY, EMERGENCY DIESEL GENERATOR 32 DID START AND LOAD TO EMERGENCY | | BUS 6A; HOWEVER, LOADS DID NOT SEQUENCE OR AUTOMATICALLY START DUE TO A | | BLOWN FUSE IN A POTENTIAL TRANSFORMER. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED OF THESE CHANGES BY THE | | LICENSEE. NOTIFIED R1DO (BELLAMY). | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32496 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PRAIRIE ISLAND REGION: 3 |NOTIFICATION DATE: 06/17/97 | |UNIT: [1] [ ] [ ] STATE: MN |NOTIFICATION TIME: 12:13 [ET]| |RX TYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 06/17/97 | +------------------------------------------------+EVENT TIME: 10:27[CDT]| |NRC NOTIFIED BY: HUEBNER |LAST UPDATE DATE: 06/18/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CREED 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 33 POWER OPERATION | 43 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | S/G LEVEL INCREASED BEYOND ANALYZED LIMITS DURING AFW SYSTEM TESTING | | | | WHILE PERFORMING AUXILIARY FEEDWATER PUMP TESTING, THE WATER LEVEL IN STEAM | | GENERATOR 'A' INCREASED BEYOND THE ANALYZED LIMIT OF 49% NARROW RANGE | | (ACTUAL LEVEL INCREASED TO 49.9%). STEAM GENERATOR LEVELS ARE LIMITED | | DURING OPERATION TO ENFORCE STEAM GENERATOR MASS LIMITS BECAUSE OF | | CONTAINMENT PRESSURIZATION CONCERNS. THE LICENSEE STATED THAT THE | | FEEDWATER CONTROL SYSTEM DID NOT REACT QUICKLY ENOUGH TO THE ADDITION OF | | COLD WATER TO THE STEAM GENERATORS FROM THE AFW SYSTEM. | | | | THE RESTRICTIVE S/G LEVEL LIMITS WERE RECENTLY ADOPTED AT PRAIRIE ISLAND, | | AND THIS WAS THE FIRST TEST OF THE AFW SYSTEM SINCE THEN. THE LICENSEE | | PLANS TO REEVALUATE THE TEST PROCEDURE TO ADDRESS THE S/G LEVEL CONTROL | | ISSUE. THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | | | | * * * UPDATE 1400 6/18/97 FROM EPPEN TAKEN BY STRANSKY * * * | | THE LICENSEE IS RETRACTING THIS NOTIFICATION. AFTER FURTHER INVESTIGATION, | | THE LICENSEE DETERMINED THAT THE 49% LEVEL LIMIT CITED IN THE INITIAL | | REPORT WAS AN ADMINISTRATIVE LIMIT, AND THAT THE MAXIMUM ALLOWABLE LEVEL IS | | 61% AT 33% POWER. THEREFORE, THE STEAM GENERATOR LEVEL REMAINED WITHIN THE | | ACCEPTABLE BAND OF OPERATION. THE NRC RESIDENT HAS BEEN INFORMED. NOTIFIED | | R3DO (LANKSBURY). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32504 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 06/18/97 | |UNIT: [ ] [3] [ ] STATE: NY |NOTIFICATION TIME: 04:03 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 06/18/97 | +------------------------------------------------+EVENT TIME: 01:56[EDT]| |NRC NOTIFIED BY: DAVIS |LAST UPDATE DATE: 06/18/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: | | |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 N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE PLANT HAD AN AUTO START OF THE "32" EMERGENCY DIESEL GENERATOR(EDG) DUE | | TO BUS "6A" BEING DE-ENERGIZED. | | | | THIS OCCURRED WHEN THE 480V SAFEGUARDS BUS "6A" NORMAL FEED BREAKER OPENED. | | WHEN THIS OCCURRED "32" EDG AUTO STARTED AND RE-ENERGIZED BUS "6A". THE | | "36" SERVICE WATER PUMP AND "33" COMPONENT COOLING WATER PUMP WERE STRIPPED | | ON UNDERVOLTAGE AND RESTARTED ON NON-SI BLACKOUT LOGIC. THE "32" COMPONENT | | COOLING WATER PUMP(OFF BUS "2A") AUTO STARTED ON LOW PRESSURE. RHR COOLING | | AND SPENT FUEL PIT COOLING WERE NOT LOST DURING THIS EVENT. PEOPLE WERE | | WORKING IN THE AREA NEAR BUS "6A", BUT THE CAUSE OF ITS NORMAL FEED BREAKER | | OPENING IS NOT YET KNOWN AND IS STILL BEING INVESTIGATED. AT 0243 THE 480V | | SAFEGUARDS BUS WAS RETURNED TO ITS NORMAL FEED AND THE EDG WAS SECURED. | | THE RESIDENT INSPECTOR WAS NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32505 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: TURKEY POINT REGION: 2 |NOTIFICATION DATE: 06/18/97 | |UNIT: [3] [4] [ ] STATE: FL |NOTIFICATION TIME: 15:05 [ET]| |RX TYPE: [3] W-3-LP,[4] W-3-LP |EVENT DATE: 06/18/97 | +------------------------------------------------+EVENT TIME: 14:35[EDT]| |NRC NOTIFIED BY: MILLER |LAST UPDATE DATE: 06/18/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LESSER 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 | | 4 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNITS OUTSIDE DESIGN BASIS DUE TO 10CFR50 APPENDIX R ISSUE | | | | THE FOLLOWING IS TEXT OF A FACSIMILE SUBMITTED BY THE LICENSEE: | | "THE REACTOR COOLANT PUMP (RCP) OIL COLLECTION SYSTEM FOR UNITS 3 AND 4 IS | | INTENDED TO BE DESIGNED TO MEET THE REQUIREMENTS OF 10 CFR PART 50, | | APPENDIX R, SECTION III.O, WHICH STATES, 'SUCH COLLECTION SYSTEMS SHALL BE | | CAPABLE OF COLLECTING LUBE OIL FROM ALL POTENTIAL PRESSURIZED AND | | UNPRESSURIZED LEAKAGE SITES IN THE REACTOR COOLANT PUMP LUBE OIL SYSTEM.' | | DURING PREPARATION FOR A MODIFICATION TO THE LUBE OIL FILL CONNECTION, | | ADDITIONAL POTENTIAL LEAKAGE SITES WERE IDENTIFIED THAT ARE NOT COLLECTED | | BY THE OIL COLLECTION SYSTEM. BECAUSE THESE POTENTIAL LEAKAGE SITES ARE | | EITHER UNPRESSURIZED OR LOW PRESSURE, ANY POSTULATED LEAKAGE WOULD NOT BE | | IN QUANTITIES SUFFICIENT TO SUSTAIN A FIRE. THEREFORE, THE PROBABILITY AND | | EFFECT OF A POSTULATED FIRE ARE MINIMAL. THE OIL COLLECTION SYSTEM HAS BEEN | | EVALUATED AND DETERMINED TO BE OPERABLE, BASED ON THE EXTREMELY SMALL | | LIKELIHOOD OF A FIRE. NO ACTUAL LEAKAGE HAS BEEN OBSERVED FROM ANY OF THE | | UNCOLLECTED POTENTIAL LEAKAGE SITES." | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 32506 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: CIBA SPECIALTY CHEMICALS |NOTIFICATION DATE: 06/18/97 | | CITY: NEWPORT REGION: 1 |NOTIFICATION TIME: 15:58 [ET]| | COUNTY: NEW CASTLE STATE: DE |EVENT DATE: 06/18/97 | |LICENSE#: 07-20696-01 AGREEMENT: N |EVENT TIME: 00:00[EDT]| | DOCKET: |LAST UPDATE DATE: 06/18/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |BELLAMY RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: J. BURKE | | |HQ OPS OFFICER: BOB STRANSKY | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |IBBE 30.50(b)(2)(i) ACCID MIT EQUIP FAILS | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DAMAGED SHUTTER ON PROCESS GAUGE | | | | THE LICENSEE REPORTED THAT THE SHUTTER ON A GAUGE USED ON A PROCESS LINE | | HAS AN INOPERABLE SHUTTER. THE GAUGE IS A RONAN MODEL SA1 (SER #9586GG), | | WHICH CONTAINS A 0.05Ci Cs-137 SEALED SOURCE. THE GAUGE IS CURRENTLY | | INSTALLED ON A PROCESS VESSEL THAT IS IN SERVICE. THE LICENSEE PLANS TO | | REPAIR THE SHUTTER. NRC REGION I HAS BEEN CONTACTED REGARDING THIS EVENT. | | | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 32507 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 06/18/97 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 16:21 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 06/18/97 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 14:30[CDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 06/18/97 | | CITY: PADUCAH REGION: 3 +-----------------------------+ | COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION| |LICENSE#: GDP-1 AGREEMENT: Y |LANKSBURY RDO | | DOCKET: 0707001 | | +------------------------------------------------+ | |NRC NOTIFIED BY: CAGE | | |HQ OPS OFFICER: BOB STRANSKY | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |DDDD 73.71 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | SECURITY EVENT RELATED TO POTENTIAL COMPROMISE OF CLASSIFIED DOCUMENT. | | IMMEDIATE COMPENSATORY ACTIONS TAKEN UPON DISCOVERY. THE NRC RESIDENT | | INSPECTOR HAS BEEN INFORMED. REFER TO THE HOO LOG FOR ADDITIONAL DETAILS | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32508 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HOPE CREEK REGION: 1 |NOTIFICATION DATE: 06/18/97 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 22:25 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 06/18/97 | +------------------------------------------------+EVENT TIME: 20:15[EDT]| |NRC NOTIFIED BY: PIKE |LAST UPDATE DATE: 06/18/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BELLAMY 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | HIGH PRESSURE COOLANT INJECTION SYSTEM INOPERABLE | | | | THE FOLLOWING IS TEXT OF A FACSIMILE SUBMITTED BY THE LICENSEE: | | "ON MONDAY, 6/16/97, WHILE PERFORMING A ROUTINE HPCI VALVE SURVEILLANCE | | TEST, THE HPCI FULL FLOW TEST RETURN VALVE, 1BJHV-F008, FAILED TO STROKE | | OPEN. THE VALVE HAD BEEN PREVIOUSLY STROKED SEVERAL HOURS EARLIER FOR THE | | SAME TEST WITHOUT A PROBLEM. TROUBLESHOOTING INDICATED A LIMIT SWITCH | | ASSOCIATED WITH ONE OF THE HPCI INJECTION VALVES, 1BJHV-8278, WAS PROVIDING | | A FALSE SIGNAL INTO THE FULL FLOW TEST RETURN VALVE'S CONTROL CIRCUITRY | | WHICH PREVENTED THE VALVE FROM OPENING DUE TO VALVE INTERLOCKS. THE INITIAL | | EVALUATION OF THIS CONDITION CONCLUDED THAT THE HPCI SYSTEM REMAINED | | OPERABLE BUT DEGRADED SINCE THE CONDITION WOULD NOT PREVENT HPCI FROM | | AUTOMATICALLY INJECTING INTO THE REACTOR PRESSURE VESSEL BUT DID PREVENT | | THE USE OF THE HPCI SYSTEM IN THE FULL FLOW TEST MODE OF OPERATION. | | | | THE FOLLOWING DAY, THE A & C RESIDUAL HEAT REMOVAL (RHR) SYSTEMS WERE | | REMOVED FROM SERVICE TO CONDUCT SCHEDULED MAINTENANCE ACTIVITIES WHICH | | PLACED THE PLANT IN A 72 HOUR LIMITING CONDITION OF OPERATION (LCO). THIS | | LCO COMMENCED ON 6/17/97 @ 0501. THE A RHR SYSTEM WAS RETURNED TO OPERABLE | | STATUS ON 6/18/97 @0040, APPROXIMATELY 20 HOURS LATER. THE C RHR SYSTEM WAS | | RESTORED TO AN OPERABLE 6/18/97 @ 2047. | | | | CONTINUED STATION REVIEW OF THE CONTROL PROBLEMS EXPERIENCED WITH THE HPCI | | SYSTEM INDICATED THAT THE PROBLEM WAS NOT ISOLATED TO A SINGLE LIMIT | | SWITCH. A SECOND LIMIT SWITCH ASSOCIATED WITH THE 1BJHV-8278 INJECTION | | VALVE WAS ALSO DETERMINED TO BE MISOPERATING. SINCE WE ARE NOW UNCERTAIN | | ABOUT THE EXTENT OF THE PROBLEM WITH THE INJECTION VALVE, WE NO LONGER HAVE | | REASONABLE ASSURANCE OF OPERABILITY AND THE HPCI SYSTEM HAS BEEN DECLARED | | INOPERABLE. ADDITIONAL TROUBLESHOOTING WILL BE PERFORMED TO BETTER | | DETERMINE THE IMPACT ON THE OPERABILITY OF THE SYSTEM. | | | | SINCE THIS FAILURE OF THE INJECTION VALVE LIMIT SWITCHES MOST LIKELY | | OCCURRED WHILE CONDUCTING THE VALVE STROKES ON 6/16/97, THE HPCI SYSTEM WAS | | EFFECTIVELY INOPERABLE FROM THAT TIME FORWARD. WE ARE CURRENTLY IN A 14 DAY | | LCO FOR THE HPCI SYSTEM AS OF 6/16/97 @0330. THEREFORE, FOR A PERIOD OF | | TIME THE HPCI SYSTEM WAS INOPERABLE IN CONJUNCTION WITH THE A & C RHR | | SYSTEM OUTAGES. THIS PLACED THE STATION IN A CONDITION THAT IS NOT | | SPECIFICALLY ADDRESSED BY THE ASSOCIATED ACTION REQUIREMENTS AND THEREFORE | | TECH SPEC 3.0.3 WOULD HAVE APPLIED AND A UNIT SHUTDOWN WOULD HAVE BEEN | | COMMENCED IAW THE TECH SPEC REQUIREMENTS." | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+