U.S. Nuclear Regulatory Commission Operations Center Event Reports For 08/01/97 - 08/04/97 ** EVENT NUMBERS ** 32709 32710 32711 32712 32713 32714 32715 32716 32717 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32709 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HOPE CREEK REGION: 1 |NOTIFICATION DATE: 08/01/97 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 14:07 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 07/31/97 | +------------------------------------------------+EVENT TIME: 17:30[EDT]| |NRC NOTIFIED BY: MIKE MOHNEY |LAST UPDATE DATE: 08/01/97 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CLIFFORD ANDERSON RDO | |NLTR LICENSEE 24 HR REPORT | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 89 POWER OPERATION | 89 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | APPENDIX "R" LIGHTING DID NOT MEET TEST REQUIREMENTS | | | | THE LICENSEE DISCOVERED THAT THE EMERGENCY LIGHTING EIGHT HOUR FUNCTIONAL | | TEST HAD NOT BEEN PERFORMED SINCE NOVEMBER 1994. UFSAR SECTION 9.5.3.2.2, | | EMERGENCY LIGHTING, REQUIRES THIS TEST TO BE PERFORMED EVERY 18 MONTHS; | | THEREFORE, THIS TEST SHOULD HAVE BEEN PERFORMED BY JUNE 1996. TESTING | | COMMENCED ON AUGUST 1, 1997, AT 0200. THE RESULTS OF THE TESTS HAVE SHOWN | | THAT 15 OF 50 APPENDIX "R" LIGHTS TESTED THUS FAR DID NOT MEET THE | | SPECIFIED EIGHT HOUR PERFORMANCE REQUIREMENTS. TESTING AND REQUIRED | | REPAIRS OF THE REMAINDER OF THE APPENDIX R LIGHTS ARE UNDERWAY. HAND HELD | | FLASHLIGHTS AND PORTABLE EIGHT HOUR LIGHTS ARE BEING USED AS A TEMPORARY | | COMPENSATORY MEASURE. A ROOT CAUSE EVALUATION OF THIS EVENT IS UNDERWAY IN | | ACCORDANCE WITH THE CORRECTIVE ACTION PROGRAM. PSE&G HAS DETERMINED THAT | | THE FAILURE TO IMPLEMENT THIS TEST AS DESCRIBED IN THE UFSAR IS A FAILURE | | TO EFFECTIVELY IMPLEMENT THE PROVISIONS OF LICENSE CONDITION 2.C(7). ALL | | OTHER FIRE DETECTION AND SUPPRESSION SYSTEMS ARE FULLY FUNCTIONAL. THIS | | NOTIFICATION ADDRESSES ONLY EMERGENCY LIGHTING ISSUES. THERE IS CURRENTLY | | NO ADVERSE IMPACT ON PLANT OPERATIONS. "B" STATION SERVICE WATER PUMP AND | | THE "B" CONTROL ROOM CHILLER WERE OUT OF SERVICE FOR CORRECTIVE | | MAINTENANCE. THE COMBINATION OF THE OUT OF SERVICE EQUIPMENT WOULD NOT | | AFFECT PLANT RESPONSE. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 32710 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: MICHIGAN DEPARTMENT OF TRANS |NOTIFICATION DATE: 08/01/97 | | CITY: DETROIT REGION: 3 |NOTIFICATION TIME: 15:06 [ET]| | COUNTY: STATE: MI |EVENT DATE: 08/01/97 | |LICENSE#: 21-03039-01 AGREEMENT: N |EVENT TIME: 00:00[EDT]| | DOCKET: |LAST UPDATE DATE: 08/01/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |WAYNE KROPP RDO | | |FRED COMBS EO | +------------------------------------------------+ | |NRC NOTIFIED BY: ROB BECKON | | |HQ OPS OFFICER: DOUG WEAVER | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NDAM DAMAGE MEASURE GAUGE | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TWO MOISTURE DENSITY GAUGES DAMAGED AT CONSTRUCTION SITES | | | | TWO MOISTURE DENSITY GAUGES WERE REPORTED DAMAGED AT TWO SEPARATE | | CONSTRUCTION SITES. ONE EVENT OCCURRED SEVERAL WEEKS AGO NEAR DETROIT, MI. | | THE OTHER EVENT TOOK PLACE ON 7/30/97 IN ST. JOHNS, MI. THE SOURCE RODS IN | | BOTH GAUGES WERE LOCKED WHEN THE GAUGES WERE "BUMPED". SURVEYS ON THE | | GAUGES DID NOT DETECT ANY LEAKAGE. | | | | THIS EVENT WAS REPORTED BY THE MICHIGAN DEPARTMENT OF TRANSPORTATION. THE | | GAUGE FROM ST. JOHN'S HAS BEEN RETURNED TO SERVICE. THE OTHER GAUGE HAS | | BEEN REMOVED FOR SERVICE FOR REPAIR (BROKEN HANDLE). | | | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32711 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OYSTER CREEK REGION: 1 |NOTIFICATION DATE: 08/01/97 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 15:38 [ET]| |RX TYPE: [1] GE-2 |EVENT DATE: 08/01/97 | +------------------------------------------------+EVENT TIME: 13:40[EDT]| |NRC NOTIFIED BY: DAVID BRAC |LAST UPDATE DATE: 08/01/97 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CLIFFORD ANDERSON RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | M/R Y 100 POWER OPERATION | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TURBINE GENERATOR EXCITER FIRE AND A MANUAL REACTOR SCRAM | | | | SHORTLY AFTER COMPLETING AN INSPECTION OF THE MAIN EXCITER, A FIRE OCCURRED | | IN INSULATION ABOVE THE MAIN EXCITER. OPERATORS MANUALLY INITIATED THE | | CARBON DIOXIDE FIRE SUPPRESSION SYSTEM AND EXTINGUISHED THE FIRE. THE FIRE | | LASTED APPROXIMATELY FIVE MINUTES. THE CAUSE OF THE FIRE IS UNKNOWN. | | | | CONTROL ROOM OPERATORS MANUALLY TRIPPED THE REACTOR UPON HEARING ABOUT THE | | FIRE IN THE MAIN EXCITER. ALL CONTROL RODS FULLY INSERTED, HOWEVER, POWER | | WAS LOST TO THE "C" AND "D" EMERGENCY BUSES. BOTH EMERGENCY DIESEL | | GENERATORS STARTED AND LOADED AS EXPECTED. THE EMERGENCY BUSES ARE BEING | | POWERED FROM OFFSITE POWER AND THE DIESELS HAVE BEEN RETURNED TO STANDBY. | | THE EMERGENCY BUSES SHOULD HAVE TRANSITIONED TO OFFSITE POWER WITHOUT | | CAUSING THE EDGs TO START. THE CAUSE OF THIS PROBLEM IS BEING | | INVESTIGATED. THE LOSS OF POWER TO THE EMERGENCY BUSES ALSO CAUSED THE | | MAIN STEAM ISOLATION VALVES TO CLOSE AND THE STANDBY GAS TREATMENT SYSTEM | | TO START. | | | | AFTER THE EDGs PICKED UP THE EMERGENCY BUSES, THE CONTROL ROD DRIVE (CRD) | | PUMPS DID NOT START AUTOMATICALLY AS EXPECTED. THE PUMPS WERE STARTED | | MANUALLY AND CONTINUE TO RUN. | | | | DECAY HEAT IS BEING REMOVED BY THE ISOLATION CONDENSERS AND THE PLANT IS | | BEING COOLED DOWN TO COLD SHUTDOWN. INVENTORY IS BEING MAINTAINED BY THE | | CRD PUMPS WITH THE FEED PUMP AVAILABLE IF NECESSARY. | | | | THE LICENSEE IS INVESTIGATING THE CAUSE OF THE FIRE AND THE SYSTEM | | ANOMALIES THAT OCCURRED DURING THIS EVENT. THE NRC RESIDENT INSPECTOR WAS | | INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32712 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SEQUOYAH REGION: 2 |NOTIFICATION DATE: 08/01/97 | |UNIT: [1] [ ] [ ] STATE: TN |NOTIFICATION TIME: 22:02 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 08/01/97 | +------------------------------------------------+EVENT TIME: 19:38[EDT]| |NRC NOTIFIED BY: BILL HARRIS |LAST UPDATE DATE: 08/01/97 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PIERCE SKINNER 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 | M/R Y 100 POWER OPERATION | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | MANUAL REACTOR TRIP - LOSS OF CONTROL AIR CAUSED A LOSS OF STEAM GENERATOR | | LEVELS | | | | A MANUAL REACTOR TRIP WAS INITIATED DUE TO LOWERING STEAM GENERATOR LEVELS | | AND IMPENDING LOSS OF FEEDWATER. AT APPROXIMATELY 1930, ABOUT EIGHT | | MINUTES PRIOR TO THE TRIP, A CONTROL AIR LEAK DEVELOPED WHEN MAINTENANCE | | WORKERS CUT A PORTION OF THE CONTROL AIR HEADER IN PREPARATION FOR A SYSTEM | | MODIFICATION. THE HEADER BEING CUT WAS PRESSURIZED DUE TO A LEAKING | | CLEARANCE BOUNDARY VALVE. THE LOSS OF CONTROL AIR RESULTED IN NUMEROUS | | CONTROLLER MALFUNCTIONS CAUSING THE S/G LEVEL TRANSIENTS. FOLLOWING THE | | REACTOR TRIP, OPERATORS SUCCESSFULLY ISOLATED THE LEAK AND RESTORED CONTROL | | AIR PRESSURE. | | | | THE PLANT EXPERIENCED A BALANCE OF PLANT RUNBACK TO LESS THAN 80% POWER | | PRIOR TO THE REACTOR TRIP. THIS RUNBACK WAS CAUSED BY LOSS OF FLOW FROM A | | HEATER DRAIN TANK WHICH WAS A RESULT OF THE LOSS OF CONTROL AIR TO A HEATER | | DRAIN TANK OUTLET VALVE. | | | | THE PLANT IS STABLE IN MODE 3. ALL CONTROL RODS FULLY INSERTED AND ALL | | THREE AUXILIARY FEEDWATER PUMPS STARTED AS EXPECTED. STEAM IS BEING DUMPED | | TO THE MAIN CONDENSER AS NECESSARY TO REMOVE DECAY HEAT. | | | | THE CONTROL AIR SYSTEM AT SEQUOYAH IS COMMON TO BOTH UNITS. UNIT 2 ALSO | | EXPERIENCED A RUNBACK. HOWEVER, THE FEED WATER TRANSIENT WAS MUCH LESS | | SEVERE, AND DID NOT REQUIRE A REACTOR TRIP. THE LOSS OF LOAD ON THE | | CONTROL AIR SYSTEM SUBSEQUENT TO THE UNIT 1 TRIP AND THE RAPID ISOLATION OF | | THE LEAK ENABLED UNIT 2 TO STAY ON LINE. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 32713 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 08/02/97 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 00:09 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 08/01/97 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 16:25[CDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 08/02/97 | | CITY: PADUCAH REGION: 3 +-----------------------------+ | COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION| |LICENSE#: GDP-1 AGREEMENT: Y |WAYNE KROPP RDO | | DOCKET: 0707001 |JOHN HICKEY EO | +------------------------------------------------+ | |NRC NOTIFIED BY: MAURER | | |HQ OPS OFFICER: BOB STRANSKY | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |OCBB 76.120(c)(2)(ii) EQUIP DISABLED/FAILS | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | 24-HOUR REPORT | | | | "ON 8/1/97 AT 1625 HOURS, THE C-333-A FACILITY AUTOCLAVE POSITION 4 NORTH | | STEAM CONTROLLER WAS DISCOVERED TO BE INOPERABLE DURING CYLINDER HEELING | | OPERATIONS (MODE 5), TSR LCO 2.2.3.3 REQUIRES THE AUTOCLAVE STEAM PRESSURE | | CONTROL SYSTEM TO BE OPERABLE WHEN THE AUTOCLAVE IS IN MODE 5. THE | | AUTOCLAVE WAS DECLARED INOPERABLE AND REMOVED FROM SERVICE AT 1631 HOURS. | | TROUBLESHOOTING AND A SYSTEM ENGINEERING EVALUATION OF THE FAILURE HAVE | | BEEN INITIATED." | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32714 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 08/02/97 | |UNIT: [ ] [2] [ ] STATE: CT |NOTIFICATION TIME: 09:24 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 08/02/97 | +------------------------------------------------+EVENT TIME: 09:00[EDT]| |NRC NOTIFIED BY: R. BARRON |LAST UPDATE DATE: 08/02/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CLIFFORD ANDERSON 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 +------------------------------------------------------------------------------+ | EDG AUTOSTART DURING TROUBLESHOOTING | | | | THE 'A' EMERGENCY DIESEL GENERATOR (EDG) WAS INADVERTENTLY STARTED DURING | | TROUBLESHOOTING ACTIVITIES. THE LICENSEE PLANS TO LOAD THE EDG AND PERFORM | | A FOUR HOUR RUN. THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32715 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SAN ONOFRE REGION: 4 |NOTIFICATION DATE: 08/02/97 | |UNIT: [ ] [2] [3] STATE: CA |NOTIFICATION TIME: 16:15 [ET]| |RX TYPE: [1] W-3-LP,[2] CE,[3] CE |EVENT DATE: 07/31/97 | +------------------------------------------------+EVENT TIME: 19:00[PDT]| |NRC NOTIFIED BY: CLAY WILLIAMS |LAST UPDATE DATE: 08/02/97 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CHARLES CAIN RDO | |NLTR LICENSEE 24 HR REPORT | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | 3 | N Y 100 POWER OPERATION | 100 POWER OPERATION | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | 24 HOUR REPORT RELATING TO THE PHYSICAL SECURITY PLAN | | | | THE LICENSEE DISCOVERED THAT TWO ASPECTS OF THEIR INTRUSION DETECTION | | SYSTEM DO NOT COMPLY WITH THE PHYSICAL SECURITY PLAN. COMPENSATORY | | MEASURES WERE TAKEN AS NECESSARY. COMPLETE DETAILS ARE AVAILABLE IN THE | | HOO LOG. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32716 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HOPE CREEK REGION: 1 |NOTIFICATION DATE: 08/03/97 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 05:04 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 08/03/97 | +------------------------------------------------+EVENT TIME: 03:36[EDT]| |NRC NOTIFIED BY: PRICE |LAST UPDATE DATE: 08/03/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CLIFFORD ANDERSON 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 88 POWER OPERATION | 88 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LOSS OF RPS BUS CAUSES SEVERAL CONTAINMENT ISOLATIONS | | | | A 1/2 SCRAM SIGNAL AND SEVERAL CONTAINMENT ISOLATIONS OCCURRED WHEN THE 'B' | | REACTOR PROTECTION SYSTEM (RPS) MOTOR GENERATOR (M/G) SET TRIPPED DUE TO AN | | ELECTRICAL FAULT. THE FOLLOWING CONTAINMENT ISOLATIONS OCCURRED: OUTBOARD | | REACTOR WATER CLEANUP (RWCU) SYSTEM, OUTBOARD REACTOR RECIRCULATION SAMPLE | | SYSTEM, AND OUTBOARD MAIN STEAMLINE DRAINS. THE LICENSEE HAS REPOWERED THE | | 'B' RPS BUS FROM ITS ALTERNATE SUPPLY, AND TROUBLESHOOTING OF THE M/G SET | | IS UNDERWAY. THE LICENSEE HAS REOPENED THE RECIRC SAMPLE VALVES AND MAIN | | STEAM LINE DRAINS, AND RECOVERY OF THE RWCU SYSTEM IS CURRENTLY IN | | PROGRESS. THE NRC RESIDENT INSPECTOR WILL BE INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |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 | | ONE INCH 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, 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. | +------------------------------------------------------------------------------+