U.S. Nuclear Regulatory Commission Operations Center Event Reports For 01/16/97 - 01/17/97 ** EVENT NUMBERS ** 31601 31602 31603 31604 31605 31606 31607 31608 31609 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31601 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 01/16/97 | |UNIT: [ ] [ ] [3] STATE: CT |NOTIFICATION TIME: 08:20 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 01/16/97 | +------------------------------------------------+EVENT TIME: 07:55[EST]| |NRC NOTIFIED BY: GERBER |LAST UPDATE DATE: 01/16/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DAVID SILK RDO | |AINB 50.72(b)(2)(iii)(B) POT RHR INOP | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | | | | | 3 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | A HIGH ENERGY LINE BREAK DOOR WAS FOUND UNLATCHED. | | | | THE HIGH ENERGY LINE BREAK DOOR TO THE SWITCHGEAR ROOM WAS FOUND UNLATCHED. | | THIS CONDITION HAD THE POTENTIAL TO AFFECT CLASS 1E ELECTRICAL LOADS, WHICH | | IN TURN COULD AFFECT SHUTDOWN COOLING. THERE WERE NO ACTUATIONS OR SIGNALS | | WHICH CAUSED THE DOOR TO UNLATCH AND THEY ARE INVESTIGATING WHY THE DOOR | | WAS UNLATCHED. THE DOOR WAS IMMEDIATELY LATCHED AFTER BEING DISCOVERED | | UNLATCHED. | | | | THE RESIDENT INSPECTOR, STATE AND LOCAL AGENCIES WERE NOTIFIED. | | | | NOTE: SEE SIMILAR EVENTS #31589, #31603 & #31606. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31602 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SOUTH TEXAS REGION: 4 |NOTIFICATION DATE: 01/16/97 | |UNIT: [1] [2] [ ] STATE: TX |NOTIFICATION TIME: 09:55 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 01/15/97 | +------------------------------------------------+EVENT TIME: 15:58[CST]| |NRC NOTIFIED BY: PINZON |LAST UPDATE DATE: 01/16/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOSEPH TAPIA RDO | |NLTR LICENSEE 24 HR REPORT | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | INCORRECT TOLERANCES WERE USED TO DETERMINE THE ALARM SETPOINTS FOR AREA | | HIGH-HIGH TEMPERATURE SWITCHES. | | | | ON 01/15/97 AT 15:58, A REVIEW OF INCORRECT TOLERANCES INVOLVING THE AREA | | HIGH-HIGH TEMPERATURE SWITCHES DETERMINED THAT THIS CONDITION WAS | | REPORTABLE. AS A RESULT OF USING THESE INCORRECT TOLERANCES, THE ACTUAL | | ROOM TEMPERATURES COULD HAVE EXCEEDED THE TECHNICAL SPECIFICATION LIMITS(TS | | 3.7-13) BY 5øF. | | | | THE AREA HIGH-HIGH TEMPERATURE INSTRUMENTS ARE ON/OFF SWITCHES THAT ALARM | | IN THE CONTROL ROOM. CREDIT FOR SATISFYING THE TS LIMITS IS BASED ON THE | | ABSENCE OF AN ALARM. BUT WITH THIS INCORRECT TOLERANCE, THE SURVEILLANCE | | REQUIREMENT WOULD NOT HAVE IDENTIFIED A CONDITION IN WHICH THE TEMPERATURE | | LIMITS WERE EXCEEDED. | | | | THE LICENSEE BELIEVES THAT THE SAFETY SIGNIFICANCE OF THIS CONDITION IS | | MINIMAL. THE STATUS OF THE ROOM AREA HIGH-HIGH ALARMS ARE LOGGED EVERY 8 | | HRS. BECAUSE OPERATIONS PERSONNEL TOUR THESE ROOMS AT LEAST ONCE EVERY | | EIGHT HOURS, IT WOULD BE UNLIKELY THAT AN ABNORMAL ROOM TEMPERATURE | | EXCEEDED THE TECHNICAL SPECIFICATION TEMPERATURE LIMIT. | | | | THIS CONDITION IS BEING REPORTED AS A VIOLATION OF THE PLANT OPERATING | | LICENSES NO. NPF-76 AND NPF-80(2G) SECTION 2.C(2), 24 HOUR REPORTS. | | | | THE RESIDENT INSPECTOR WAS NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31603 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 01/16/97 | |UNIT: [ ] [ ] [3] STATE: CT |NOTIFICATION TIME: 11:31 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 01/16/97 | +------------------------------------------------+EVENT TIME: 11:30[EST]| |NRC NOTIFIED BY: KULTERMAN |LAST UPDATE DATE: 01/16/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DAVID SILK RDO | |AINB 50.72(b)(2)(iii)(B) POT RHR INOP | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | | | | | 3 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LOSS OF INTEGRITY TO THE CABLE SPREADING ROOM DUE TO THE HIGH ENERGY LINE | | BREAK DOOR BEING UNLATCHED. | | | | THIS CONDITION, WHICH OCCURRED ON 1/15/97, COULD LEAD TO A SITUATION WHERE | | A HIGH ENERGY BREAK COULD POSSIBLY AFFECT THE BREAKER LOCATED IN THE CABLE | | SPREADING ROOM WHICH CONTROLS RHR PUMP OPERATION. THIS WOULD RESULT IN THE | | FAILURE OF THE PUMP. THE DOOR WAS IMMEDIATELY LATCHED AND A CONTINUOUS | | WATCH WAS ESTABLISHED TO VERIFY IT REMAINS LATCHED. THE UNLATCHED DOOR WAS | | DUE TO A PROBLEM WITH BOTH THE LATCHING MECHANISM AND PERSONNEL OPERATING | | THE DOOR. THE LICENSEE WILL CONDUCT PERSONNEL TRAINING ON OPERATION OF THIS | | TYPE OF DOOR. | | | | THE RESIDENT INSPECTOR, STATE AND LOCAL AGENCIES WERE NOTIFIED. | | | | NOTE: SEE SIMILAR EVENTS #31589, #31601 & #31606. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31604 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 01/16/97 | |UNIT: [2] [ ] [ ] STATE: NY |NOTIFICATION TIME: 11:42 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 01/16/97 | +------------------------------------------------+EVENT TIME: 10:05[EST]| |NRC NOTIFIED BY: MICHELE SAVINO |LAST UPDATE DATE: 01/16/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DAVID SILK 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 Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNEXPECTED ESF ACTUATION DURING I&C TESTING. | | | | UNIT 2 EXPERIENCED AN UNEXPECTED ESF ACTUATION. BOTH MOTOR DRIVEN | | AUXILIARY FEEDWATER (AFW) PUMPS AUTO STARTED AND STEAM GENERATOR BLOWDOWN | | ISOLATED. I&C PERSONNEL WERE PERFORMING A REACTOR PROTECTION MODULE TEST ON | | TRAIN "B" AT THE TIME. THE TEST WAS IMMEDIATELY SUSPENDED AND OPERATORS | | VERIFIED THAT THE PLANT WAS STABLE. APPROXIMATELY SIX MINUTES LATER, BOTH | | AFW PUMPS WERE SECURED AND RETURNED TO STANDBY AND STEAM GENERATOR BLOWDOWN | | UNISOLATED. THE LICENSEE VERIFIED STEAM GENERATOR WATER LEVELS, WHICH HAD | | RISEN DUE TO INCREASED FLOW FROM THE AFPs, HAD RETURNED TO NORMAL. THE | | CAUSE OF THE ESF ACTUATION IS UNDER INVESTIGATION. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 31605 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: PARADYME CORP, LARGO, FL |NOTIFICATION DATE: 01/16/97 | | CITY: LARGO REGION: 2 |NOTIFICATION TIME: 11:58 [ET]| | COUNTY: STATE: FL |EVENT DATE: 12/04/96 | |LICENSE#: FL G-0018-1 AGREEMENT: Y |EVENT TIME: 12:00[EST]| | DOCKET: |LAST UPDATE DATE: 01/16/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |DAVID VERRELLI RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: CHARLIE ADAMS, FL BRC | | |HQ OPS OFFICER: DICK JOLLIFFE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NAGR AGREEMENT STATE | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - AGREEMENT STATE REPORT OF A STOLEN STATIC ELIMINATOR DEVICE - | | | | AT 1158 ON 01/16/97, CHARLIE ADAMS, FLORIDA BUREAU OF RADIATION CONTROL | | (BRC), NOTIFIED THE NRC OPERATIONS OFFICER THAT ON 01/03/97, SANDI | | STRAITON, PARADYME CORPORATION RADIATION SAFETY OFFICER, NOTIFIED THE | | FLORIDA BRC THAT A STATIC ELIMINATOR DEVICE (NUCLEAR IONIZING AIR GUN) | | HAD BEEN STOLEN FROM PARADYME'S LARGO, FLORIDA FACILITY ON 12/04/96. | | THE UNDAMAGED DEVICE, CONTAINING A 10 mCi POLONIUM-210 SOURCE, WAS LEASED | | FROM NRD CORPORATION. THE DEVICE MODEL NUMBER IS P-2051 AND SERIAL NUMBER | | IS 84847. THE FLORIDA BRC INCIDENT NUMBER IS FL 97-001. | | | | THE FLORIDA LICENSEE ALSO NOTIFIED THE LOCAL POLICE AND NRC REGION 2 (DICK | | WOODRUFF) AND IS INVESTIGATING THE THEFT. | | | | SEE THE HOO LOG FOR CONTACT ADDRESSES AND TELEPHONE NUMBERS. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31606 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 01/16/97 | |UNIT: [ ] [ ] [3] STATE: CT |NOTIFICATION TIME: 13:12 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 01/16/97 | +------------------------------------------------+EVENT TIME: 12:30[EST]| |NRC NOTIFIED BY: DON GERBER |LAST UPDATE DATE: 01/16/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN WHITE RDO | |AINB 50.72(b)(2)(iii)(B) POT RHR INOP | | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | | | | | 3 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - 3 VITAL AREA PERSONNEL ACCESS DOORS LEFT OPEN AND 1 LEFT UNLATCHED - | | | | LICENSEE PERSONNEL DISCOVERED THREE PERSONNEL ACCESS DOORS LEFT OPEN AND | | ONE UNLATCHED. THESE OPEN/UNLATCHED DOORS ARE HIGH ENERGY LINE BREAK DOORS | | THAT AFFECT PRESSURIZATION AND VENTILATION CAPABILITY OF THE CONTROL ROOM | | AND VITAL SWITCHGEAR ROOMS. | | | | LICENSEE PERSONNEL CLOSED AND LATCHED ALL FOUR DOORS AND POSTED A | | CONTINUOUS WATCH ON ALL FOUR DOORS. | | | | THE LICENSEE IS INVESTIGATING THIS SITUATION. | | | | THE LICENSEE NOTIFIED STATE AND LOCAL OFFICIALS AND THE NRC RESIDENT | | INSPECTOR. | | | | NOTE: SEE SIMILAR EVENTS #31589, #31601 AND #31603. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31607 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SOUTH TEXAS REGION: 4 |NOTIFICATION DATE: 01/16/97 | |UNIT: [1] [2] [ ] STATE: TX |NOTIFICATION TIME: 14:30 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 01/15/97 | +------------------------------------------------+EVENT TIME: 16:42[CST]| |NRC NOTIFIED BY: JAIRO PINZON |LAST UPDATE DATE: 01/16/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOSEPH TAPIA RDO | |NLTR LICENSEE 24 HR REPORT | | |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 | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - TS LCO A/Ss 3.0.3 & 4.0.3 ENTERED DUE TO A FAILED TS SURVEILLANCE TEST - | | | | DURING A REVIEW OF TECH SPEC REQUIREMENTS FOR GENERIC LETTER 96-01, THE | | LICENSEE DISCOVERED THAT THE TECH SPEC SURVEILLANCE TEST FOR THE AUTOMATIC | | SWITCHOVER TO CONTAINMENT SUMP (TECH SPEC 4.3.2.1, TABLE 4.3-2, ITEM 7.a) | | DID NOT ADEQUATELY TEST ALL LOGIC CONTACTS TO FULLY MEET THE SURVEILLANCE | | REQUIREMENTS. | | | | DURING THE TEST, THE AUTOMATIC SIGNAL FOR SWITCHOVER TO CONTAINMENT SUMP | | RECIRCULATION IS INITIATED FROM THE SOLID STATE PROTECTION SYSTEM AND | | EACH MINI-FLOW VALVE AND CONTAINMENT SUMP ISOLATION SUCTION VALVE STATUS | | IS VERIFIED IN THE CONTROL ROOM. | | | | HOWEVER, THE VALVE STATUS CONTACTS FOR THE MINI-FLOW VALVES ARE DIFFERENT | | THAN THE CONTACTS USED FOR THE MINI-FLOW VALVE INTERLOCK LOGIC AND THE | | LOGIC STATUS WAS NOT VERIFIED DURING THE TEST. | | | | AT 1642 (CST) ON 01/15/97, DUE TO THE PERFORMANCE OF THE INADEQUATE TECH | | SPEC SURVEILLANCE TEST, THE LICENSEE ENTERED TECH SPEC LCO A/S 3.0.3 FOR | | BOTH UNITS WHICH ALLOWS 1 HOUR TO CORRECT THE PROBLEM OR REQUIRES THAT BOTH | | UNITS BE SHUT DOWN TO AT LEAST HOT STANDBY MODE WITHIN THE NEXT 6 HOURS. | | | | THE LICENSEE ALSO ENTERED TECH SPEC LCO A/S 4.0.3 FOR BOTH UNITS WHICH | | ALLOWS DELAYING FOR 24 HOURS THE ACTION REQUIRED BY TECH SPEC LCO A/S 3.0.3 | | (TO SHUT BOTH UNITS DOWN) TO COMPLETE THE TESTING OF THE LOGIC CONTACTS | | ASSOCIATED WITH THE SAFETY INJECTION PUMP MINI-FLOW ISOLATION VALVES. | | | | AT 1100 (CST) ON 01/16/97, AFTER SATISFACTORILY TESTING ALL LOGIC CONTACTS, | | THE LICENSEE EXITED TECH SPEC LCO A/Ss 4.0.3 AND 3.0.3. | | | | THE LICENSEE IS REPORTING THIS EVENT AS A VIOLATION OF THE PLANT OPERATING | | LICENSES NPF-76 AND NPF-80 (2G) SECTION 2.C(2), 24 HOUR REPORTS. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31608 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOK REGION: 3 |NOTIFICATION DATE: 01/16/97 | |UNIT: [1] [ ] [ ] STATE: MI |NOTIFICATION TIME: 16:53 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 01/12/97 | +------------------------------------------------+EVENT TIME: 13:47[EST]| |NRC NOTIFIED BY: RANDY PTACEK |LAST UPDATE DATE: 01/16/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRUCE BURGESS 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 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | -TECH SPEC 3.0.3 APPLICABLE FOR 1 MINUTE WHILE ADJUSTING ACCUMULATOR LEVELS | | | | ON 01/09/97, OPERATING PROCEDURE 01 OHP 4021.008.004, "ADJUSTING THE LEVEL | | OF ACCUMULATORS", WAS REVISED. | | | | AT 1347 (CST) ON 01/12/97, WHILE ADJUSTING ACCUMULATOR LEVELS IN ACCORDANCE | | WITH THIS REVISED OPERATING PROCEDURE, THE SAFETY INJECTION (SI) PUMP | | DISCHARGE CROSS-TIE VALVE WAS CLOSED BEFORE THE RESIDUAL HEAT REMOVAL (RHR) | | DISCHARGE CROSS-TIE VALVES WERE OPENED AS DIRECTED BY THE REVISED | | PROCEDURE. | | | | AT 1557 (CST) ON 01/16/97, DURING A SIMULATOR TRAINING SCENARIO RUN USING | | THE REVISED PROCEDURE, THE LICENSEE DISCOVERED THAT THE FOUR LOOP INJECTION | | REQUIREMENT HAD NOT BEEN MET FOR APPROXIMATELY ONE MINUTE DURING THE | | PERFORMANCE OF THIS PROCEDURE WHILE THE RHR DISCHARGE CROSS-TIE VALVES WERE | | CLOSED AND THE SI PUMP DISCHARGE CROSS-TIE VALVE WAS CLOSED. TECH SPEC | | LCO A/S 3.0.3 WAS APPLICABLE DURING THIS ONE MINUTE PERIOD DUE TO THE LOSS | | OF FOUR LOOP INJECTION CAPABILITY. | | | | THE LICENSEE HAS REVISED THIS PROCEDURE TO CORRECT THIS SITUATION. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31609 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MAINE YANKEE REGION: 1 |NOTIFICATION DATE: 01/17/97 | |UNIT: [1] [ ] [ ] STATE: ME |NOTIFICATION TIME: 01:40 [ET]| |RX TYPE: [1] CE |EVENT DATE: 01/17/97 | +------------------------------------------------+EVENT TIME: 01:00[EST]| |NRC NOTIFIED BY: MCDOUGOLD |LAST UPDATE DATE: 01/17/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN WHITE RDO | |ADAS 50.72(b)(2)(i) DEG/UNANALYZED COND | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE HAS IDENTIFIED SEVEN POSITIVE SIPPING INDICATIONS OUT OF 64 | | FUEL ASSEMBLIES. | | | | THE LICENSEE'S FUEL SIPPING OPERATIONS HAVE IDENTIFIED 7 POSITIVE SIPPING | | INDICATIONS OUT OF 64 WESTINGHOUSE "FIRST RUN" FUEL ASSEMBLIES. THERE ARE | | 4 MORE WESTINGHOUSE ASSEMBLIES TO BE TESTED. THESE FUEL ASSEMBLIES HAVE | | BEEN RUN DURING THIS CYCLE ONLY. CYCLE 15 HAS BEEN RUN FOR APPROXIMATELY 7 | | MONTHS. ABB/CE IS ASSISTING THE LICENSEE IN THE FUEL SIPPING PROCESS. | | THIRTY TWO ABB/CE FUEL ASSEMBLIES IN CLOSE PROXIMITY TO THE WESTINGHOUSE | | FUEL WERE ALSO SIPPED, BUT WERE FOUND TO HAVE NO INDICATIONS. THESE FUEL | | ASSEMBLIES WILL BE TRANSFERRED FROM THE REFUELING CAVITY TO THE SPENT FUEL | | POOL FOR FURTHER TESTING BY THE ULTRASONIC TEST METHOD TO IDENTIFY PIN | | LOCATION. THE DEFECTIVE PINS WILL THEN BE REMOVED FROM THEIR FUEL | | ASSEMBLIES. THE RESIDENT INSPECTOR AND STATE AGENCIES WILL BE INFORMED. | +------------------------------------------------------------------------------+