U.S. Nuclear Regulatory Commission Operations Center Event Reports For 02/07/97 - 02/10/97 ** EVENT NUMBERS ** 31575 31746 31747 31748 31749 31750 31751 31752 31753 31754 31755 31756 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31575 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DIABLO CANYON REGION: 4 |NOTIFICATION DATE: 01/11/97 | |UNIT: [1] [2] [ ] STATE: CA |NOTIFICATION TIME: 02:56 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 01/10/97 | +------------------------------------------------+EVENT TIME: 23:45[PST]| |NRC NOTIFIED BY: DAVID PIERCE |LAST UPDATE DATE: 02/08/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CHRIS VANDENBURGH 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 +------------------------------------------------------------------------------+ | THE LICENSEE DISCOVERED DURING A GENERIC LETTER 96-06 REVIEW, A CONDITION | | WHICH COULD RENDER PASS SAMPLING CAPABILITY INOPERABLE. | | | | "AS PART OF OUR GL96-06, WE'VE IDENTIFIED SOME CONTAINMENT PENETRATIONS | | THAT WOULD BE POTENTIALLY SUBJECT TO OVER-PRESSURIZATION. WHILE | | CONTAINMENT INTEGRITY WOULD BE MAINTAINED, WE CANNOT CONCLUSIVELY | | DEMONSTRATE THAT FUNCTIONALITY OF THE RCS HOT LEG SAMPLING SYSTEM IS | | ASSURED POST-LOCA. | | | | THE UNIT 1 LICENSE CONDITION 2.C.(6)e, "POST ACCIDENT SAMPLING," REQUIRES | | POST ACCIDENT SAMPLING CAPABILITY IN ACCORDANCE WITH NUREG-0737, ITEM | | II.B.3 THIS LICENSE CONDITION REQUIRES THE CAPABILITY TO PROMPTLY OBTAIN | | SAMPLES OF THE REACTOR COOLANT UNDER DEGRADED CORE CONDITIONS AND PERFORM | | RADIOISOTOPIC AND CHEMICAL ANALYSIS ON THE SAMPLES. | | | | THE ABOVE MENTIONED CONDITIONS RENDER THE INSIDE CONTAINMENT PASS SAMPLE | | POINTS INOPERABLE. THE PASS RHR PUMP DISCHARGE SAMPLE POINTS, WHICH ARE | | LOCATED OUTSIDE CONTAINMENT, ARE NOT AFFECTED BY THIS CONDITION. | | | | WHILE THIS ISSUE IS NOT REALLY A CONCERN FOR A LARGE BREAK LOCA, IT IS A | | CONCERN FOR SMALL TO MEDIUM SIZE LOCAs. IT IS NOT A CONCERN FOR THE LBLOCA | | BECAUSE IN THIS CASE EVEN IF THE SYSTEM WAS TOTALLY FUNCTIONAL, THERE WOULD | | BE INSUFFICIENT PRESSURE LEFT IN THE RCS TO PROVIDE SUFFICIENT DRIVING HEAD | | IN ORDER TO EVEN OBTAIN A SAMPLE. IN THE CASE OF SBLOCA, WE KNOW THAT THE | | CONTAINMENT WILL BE HOT ENOUGH FOR A LONG ENOUGH PERIOD OF TIME TO | | POTENTIALLY CAUSE THE OVER-PRESSURIZATION BEFORE WE CAN SUFFICIENTLY COOL | | DOWN TO PLACE RHR IN SERVICE. ONCE RHR IS IN SERVICE (>3 HOURS AT 100øF/HR | | COOLDOWN RATE), WE CAN USE THE RHR SAMPLE POINTS TO ASSESS RCS CONDITIONS. | | | | IN ACCORDANCE WITH UNIT 1 LICENSE CONDITION 2.G, PG&E IS CONSERVATIVELY | | REPORTING THAT UNIT 1 LICENSE CONDITION 2.C.(6)e AND UNITS 1 & 2 TECHNICAL | | SPECIFICATION 6.8.4.e HAVE NOT BEEN MET TO THIS POTENTIALLY DEGRADED PASS | | CAPABILITY." | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE AT 1516 EST ON 2/8/97 FROM MAGRUDER TAKEN BY KARSCH * * * | | | | THE LICENSEE IS RETRACTING THIS EVENT BASED ON FURTHER ANALYSIS WHICH | | SHOWS THAT THE SAMPLE VALVES WOULD REMAIN OPERABLE FOLLOWING AN | | OVERPRESSURIZATION. THE VALVE PLUG AREA IS SMALLER THAT THE STEM AREA, | | AND THUS THERE IS NO NET DOWNWARD FORCE ACTING ON THE VALVE PLUG. THERE | | IS NO MECHANISM PREVENTING THE VALVE FROM OPENING ON DEMAND AFTER AN | | INITIATING EVENT. THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | THE HOO NOTIFIED R4DO (HARRELL). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31746 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: WATTS BAR REGION: 2 |NOTIFICATION DATE: 02/07/97 | |UNIT: [1] [ ] [ ] STATE: TN |NOTIFICATION TIME: 04:36 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 02/07/97 | +------------------------------------------------+EVENT TIME: 01:20[EST]| |NRC NOTIFIED BY: PAT McGINNIS |LAST UPDATE DATE: 02/07/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CAUDLE JULIAN 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 +------------------------------------------------------------------------------+ | INADVERTENT START OF A MOTOR-DRIVEN AUXILIARY FEEDWATER PUMP DURING TESTING | | | | DURING PERFORMANCE OF AN ENGINEERED SAFEGUARD ACTUATION TEST ON THE 'A' | | MOTOR-DRIVEN AUXILIARY FEEDWATER PUMP, THE PUMP WAS INADVERTENTLY STARTED. | | THIS ACTUATION OCCURRED WHEN THE PERSONNEL INVOLVED IN THE TEST WERE | | ENSURING THAT THE RELAY TO BE ACTUATED WAS CORRECTLY IDENTIFIED AS TO ITS | | LOCATION AND STATE. AFTER LOCATING THE CORRECT RELAY, THE RELAY WAS | | INADVERTENTLY TOUCHED ON THE MANUAL ACTUATION BAR. THIS CAUSED THE RELAY | | TO PICKUP AND START THE 'A' AUXILIARY FEEDWATER PUMP. THE PUMP WAS | | SECURED, AND THE TEST WAS SUBSEQUENTLY PERFORMED SATISFACTORILY. | | | | ACCORDING TO THE GUIDANCE OF NUREG 1022, THIS ACTUATION WAS INVALID BECAUSE | | IT WAS NOT INITIATED IN RESPONSE TO ACTUAL PLANT CONDITIONS AND BECAUSE | | THERE WAS NOT A NEED FOR THE SAFETY FUNCTION. HOWEVER, IN ACCORDANCE WITH | | NUREG 1022, VOLUNTARY REPORTING IS REQUIRED BECAUSE THE SYSTEM (PRESSURIZED | | WATER REACTOR AUXILIARY FEEDWATER) IS LISTED IN TABLE 2. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31747 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DUANE ARNOLD REGION: 3 |NOTIFICATION DATE: 02/07/97 | |UNIT: [1] [ ] [ ] STATE: IA |NOTIFICATION TIME: 12:20 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 02/07/97 | +------------------------------------------------+EVENT TIME: 10:43[CST]| |NRC NOTIFIED BY: DAVID MANKIN |LAST UPDATE DATE: 02/07/97 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |THOMAS KOZAK 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 Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AS A RESULT OF ANALYSIS OF THE ANNUAL SURVEILLANCE TEST RESULTS FOR THE | | STANDBY GAS TREATMENT SYSTEM HEPA FILTER'S EFFICIENCY, THE LICENSEE | | DETERMINED THAT BOTH TRAINS "A" AND "B" FAILED. THEIR EFFICIENCY WAS BELOW | | THE TECH SPEC LIMIT OF 99.9%. THIS COULD HAVE RESULTED IN FAILURE TO | | MITIGATE THE CONSEQUENCES OF AN ACCIDENT. THE LICENSEE HAS CORRECTED THE | | PROBLEM BY ADDING CHARCOAL TO BOTH FILTERS. BOTH TRAINS ARE NOW | | OPERATIONAL. THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31748 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HADDAM NECK REGION: 1 |NOTIFICATION DATE: 02/07/97 | |UNIT: [1] [ ] [ ] STATE: CT |NOTIFICATION TIME: 12:58 [ET]| |RX TYPE: [1] W-4-LP |EVENT DATE: 02/07/97 | +------------------------------------------------+EVENT TIME: 12:53[EST]| |NRC NOTIFIED BY: MIKE QUINN |LAST UPDATE DATE: 02/07/97 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MICHAEL MODES 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 +------------------------------------------------------------------------------+ | THE LICENSEE'S CALCULATIONS FOR CONTROL ROOM HABITABILITY WERE NOT | | SUBJECTED TO THEIR QUALITY ASSURANCE PROCEDURE FOR CALCULATIONS. THE | | LICENSEE HAS DETERMINED THAT THE CALCULATIONS SHOULD HAVE BEEN REVIEWED PER | | THE QA PROCEDURE, AND THE FACT THAT THEY WERE NOT IS A REPORTABLE EVENT. | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR AND STATE AND LOCAL | | GOVERNMENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 31749 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: U.S. ARMY |NOTIFICATION DATE: 02/07/97 | | CITY: ROCK ISLAND REGION: 3 |NOTIFICATION TIME: 16:05 [ET]| | COUNTY: STATE: IL |EVENT DATE: 02/07/97 | |LICENSE#: BML12-0072213 AGREEMENT: Y |EVENT TIME: 06:00[CST]| | DOCKET: |LAST UPDATE DATE: 02/07/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |THOMAS KOZAK RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: JEFF HAVENNER | | |HQ OPS OFFICER: RUDY KARSCH | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |BAB2 20.2201(a)(1)(ii) LOST/STOLEN LNM>10X | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNITED STATES ARMY, ROCK ISLAND, ILLINOIS. TWO MATERIALS LICENSES APPLY: | | BML12-00722-13 AND BML12-00722-14. | | | | THE LICENSEE REPORTED 61 MODEL M43A1 CHEMICAL AGENT DETECTORS WHICH CONTAIN | | 250 æCi OF Am-241 ARE MISSING FROM EIGHT ARMY INSTALLATIONS. THIRTY | | CHEMICAL AGENT MONITORS CONTAINING 12 mCi OF Ni-63 MAY BE MISSING FROM ONE | | ARMY INSTALLATION. THE LICENSEE DETERMINED THAT THESE INSTRUMENTS ARE | | MISSING BASED UPON AN INVENTORY RECORDS SEARCH. HOWEVER, THE LICENSEE | | THINKS THAT SOME OF THE MISSING INSTRUMENTS MAY HAVE BEEN SENT TO OTHER | | ARMY INSTALLATIONS. FURTHER DETAILS ARE RECORDED IN THE HOO LOG. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31750 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PRAIRIE ISLAND REGION: 3 |NOTIFICATION DATE: 02/07/97 | |UNIT: [ ] [2] [ ] STATE: MN |NOTIFICATION TIME: 16:28 [ET]| |RX TYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 02/03/97 | +------------------------------------------------+EVENT TIME: 12:00[CST]| |NRC NOTIFIED BY: DOUG SMITH |LAST UPDATE DATE: 02/07/97 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |THOMAS KOZAK 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 N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | A HEAVY LOAD WAS TRANSPORTED OVER THE UNIT 2 OPEN FUELED REACTOR VESSEL IN | | VIOLATION OF THE UFSAR. | | | | ON 02/03/97, A REACTOR COOLANT PUMP ROTOR (HEAVY LOAD) WAS TRANSPORTED OVER | | THE OPEN UNIT 2 FUELED REACTOR VESSEL WITH THE CONTAINMENT AIRLOCKS OPEN | | AND A CONTAINMENT PURGE IN PROGRESS. THE ROTOR WAS OVER THE OPEN REACTOR | | VESSEL FOR ABOUT 15 MINUTES. THE UNIT 2 UFSAR SECTION 12.2.12.1.4 STATES | | THAT CONTAINMENT WILL BE ISOLATED DURING THE TRANSPORT OF HEAVY LOADS OVER | | THE OPEN REACTOR VESSEL. THE ROTOR WAS MOVED BACK TO ITS PREVIOUS POSITION | | ON 02/05/97 IN COMPLIANCE WITH UNIT 2 UFSAR REQUIREMENTS. | | | | THE LICENSEE DETERMINED THIS EVENT TO BE REPORTABLE TO THE NRC AT 1450 | | (CST) ON 02/07/97. THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31751 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 02/07/97 | |UNIT: [ ] [ ] [3] STATE: CT |NOTIFICATION TIME: 17:14 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 02/07/97 | +------------------------------------------------+EVENT TIME: 17:07[EST]| |NRC NOTIFIED BY: JEFF LANGEN |LAST UPDATE DATE: 02/07/97 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GENE KELLY 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 N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE DETERMINED THAT THE LOOP "B" RHR SYSTEM SUPPORTS ARE NOT IN | | COMPLIANCE WITH DESIGN DRAWINGS AND MIGHT NOT WITHSTAND SEISMIC LOADS. | | THE AFFECTED SUPPORTS ARE BEING REWORKED TO RESTORE THEM TO DESIGN | | SPECIFICATIONS. THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR, AND | | STATE AND LOCAL GOVERNMENT OFFICIALS. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31752 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 02/07/97 | |UNIT: [ ] [ ] [3] STATE: CT |NOTIFICATION TIME: 17:47 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 02/07/97 | +------------------------------------------------+EVENT TIME: 17:40[EST]| |NRC NOTIFIED BY: JEFF LANGEN |LAST UPDATE DATE: 02/07/97 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GENE KELLY 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 N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE DETERMINED THAT THE WATER LEVEL IN THEIR CONTAINMENT | | RECIRCULATION SUMP WOULD HAVE TO RISE NINE INCHES HIGHER THAN THEY | | PREVIOUSLY THOUGHT BEFORE THEY COULD ACHIEVE FULL RATED RECIRC FLOW | | FOLLOWING A LARGE BREAK LOCA. THIS COULD DELAY THE ON-SET OF FULL FLOW | | FOR SEVERAL MINUTES UNTIL THE SUMP LEVEL REACHED THE VORTEX SUPPRESSOR | | ELEVATION. THIS CONDITION HAS EXISTED SINCE ORIGINAL PLANT START-UP. | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR, AND STATE AND LOCAL | | GOVERNMENT OFFICIALS. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 31753 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: U.S. ARMY |NOTIFICATION DATE: 02/07/97 | | CITY: SPARTA REGION: 3 |NOTIFICATION TIME: 18:32 [ET]| | COUNTY: STATE: WI |EVENT DATE: 02/06/97 | |LICENSE#: AGREEMENT: N |EVENT TIME: 12:30[CST]| | DOCKET: |LAST UPDATE DATE: 02/07/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |THOMAS KOZAK RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: BETTY PETERSON | | |HQ OPS OFFICER: RUDY KARSCH | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |IBAE 30.50(b)(1)(iii) ACCESS DENIED OTHER | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | BROKEN TRITIUM GUN SIGHTS WERE FOUND IN AN ARMS ROOM. SWIPES INDICATED | | 9000 DPM. THE ROOM HAS BEEN CLOSED. FURTHER SURVEYS AND CLEANUP WILL BE | | CONDUCTED ON 02/10/97. NO PERSONNEL WERE CONTAMINATED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31754 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SEABROOK REGION: 1 |NOTIFICATION DATE: 02/07/97 | |UNIT: [1] [ ] [ ] STATE: NH |NOTIFICATION TIME: 18:48 [ET]| |RX TYPE: [1] W-4-LP |EVENT DATE: 02/07/97 | +------------------------------------------------+EVENT TIME: 17:00[EST]| |NRC NOTIFIED BY: MIKE DAVID |LAST UPDATE DATE: 02/07/97 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GENE KELLY RDO | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | THE LICENSEE NOTIFIED THE NEW HAMPSHIRE PUBLIC UTILITY COMMISSION THAT A | | WORKER SLIPPED AND FELL FROM A LADDER IN A NON-NUCLEAR AREA OF THE PLANT. | | SHE WAS TRANSPORTED OFFSITE FOR MEDICAL ATTENTION. THE LICENSEE INFORMED | | THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 31755 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: E.I. DUPONT CYREL MANUF FACILITY |NOTIFICATION DATE: 02/07/97 | | CITY: PARLIN REGION: 1 |NOTIFICATION TIME: 19:59 [ET]| | COUNTY: MIDDLESEX STATE: NJ |EVENT DATE: 05/10/96 | |LICENSE#: 29-02-06501 AGREEMENT: N |EVENT TIME: 00:00[EST]| | DOCKET: 03005271 |LAST UPDATE DATE: 02/07/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |GENE KELLY RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: BOB PEYTON | | |HQ OPS OFFICER: RUDY KARSCH | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE SHUTTER ON AN NDC COMPANY MODEL 102 THICKNESS GAGE WAS STICKING OPEN. | | THE LICENSEE CONTINUED OPERATIONS. HOWEVER, SECONDARY SHIELDS WERE USED IF | | PEOPLE NEEDED TO WORK AROUND THE EQUIPMENT. THE GAGE CONTAINS LESS THAN | | 150 æCi OF Am-241. THE GAGE WAS SENT BACK TO THE MANUFACTURER FOR REPAIR | | ON 01/30/97. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31756 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HOPE CREEK REGION: 1 |NOTIFICATION DATE: 02/07/97 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 22:34 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 02/07/97 | +------------------------------------------------+EVENT TIME: 20:16[EST]| |NRC NOTIFIED BY: JESSE PIKE |LAST UPDATE DATE: 02/07/97 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GENE KELLY 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 +------------------------------------------------------------------------------+ | TROUBLESHOOTING A REACTOR BUILDING EXHAUST RAD MONITOR (RBE RM) CAUSED AN | | INADVERTENT "B" CHANNEL PRIMARY CONTAINMENT ISOLATION. THE "A" RBE RM WAS | | INOPERABLE DUE TO FAILURE OF ITS ALARM CIRCUITRY. VARIOUS CONTAINMENT | | ISOLATION VALVES CLOSED AND SEVERAL NON-CLASS 1E LOADS WERE SHED. ALL | | SYSTEMS OPERATED AS EXPECTED. THE LICENSEE IS TROUBLESHOOTING TO DETERMINE | | WHY THE UNEXPECTED ESF ACTUATION OCCURRED. THE LICENSEE WILL INFORM THE | | NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+