U.S. Nuclear Regulatory Commission Operations Center Event Reports For 12/09/94 - 12/12/94 ** EVENT NUMBERS ** 28123 28124 28125 28126 28127 28128 28129 28130 28131 28132 28133 28134 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28123 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: NINE MILE POINT REGION: 1 |NOTIFICATION DATE: 12/09/94 | |UNIT: [ ] [2] [ ] STATE: NY |NOTIFICATION TIME: 09:46 [ET]| |RX TYPE: [1] GE-2,[2] GE-5 |EVENT DATE: 12/09/94 | +------------------------------------------------+EVENT TIME: 09:08[EST]| |NRC NOTIFIED BY: DAN CIFONELLI |LAST UPDATE DATE: 12/09/94 | |HQ OPS OFFICER: WILLIAM HUFFMAN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: UNUSUAL EVENT +-----------------------------+ |10 CFR SECTION: |PETER ESELGROTH RDO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |CHRIS GRIMES EO | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS |EARL FEMA | |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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 100 POWER OPERATION | 95 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | -UNUSUAL EVENT DUE TO AN INCREASE IN UNIDENTIFIED REACTOR COOLANT LEAK RATE | | | | THE UNIDENTIFIED REACTOR COOLANT LEAK RATE HAS INCREASED FROM 0.9 GPM TO | | 3.6 GPM WITHIN THE LAST 24 HOURS. THIS LEAK RATE IS DETERMINED BY | | CALCULATING THE LEAKAGE INTO THE DRYWELL FLOOR DRAIN. THERE HAS ALSO | | BEEN A CORRESPONDING INCREASE IN THE DRYWELL RADIATION LEVELS MEASURED | | ON THE PARTICULATE RAD MONITOR. THE LEAK IS CURRENTLY STABLE AT 3.6 GPM. | | | | PER TECHNICAL SPECIFICATION 3.4.3.2, ACTION STATEMENT (f), IF THE | | UNIDENTIFIED LEAK RATE INCREASES MORE THAN 2 GPM WITHIN A 24 HOUR PERIOD, | | THE SOURCE OF THE LEAKAGE MUST BE IDENTIFIED WITHIN 4 HOURS OR THE PLANT | | SHALL BE PLACED IN HOT SHUTDOWN CONDITION WITHIN THE NEXT 12 HOURS AND | | COLD SHUTDOWN CONDITION WITHIN THE NEXT 24 HOURS. | | | | THE LICENSEE IS UNABLE TO IDENTIFY THE SOURCE OF THE LEAKAGE AND IS, | | THEREFORE, PERFORMING A CONTROLLED PLANT SHUTDOWN. PER THIS LICENSEE'S | | EMERGENCY ACTION LEVELS, A TECH SPEC REQUIRED SHUTDOWN CONSTITUTES AN | | UNUSUAL EVENT. THE UNUSUAL EVENT WAS DECLARED AT 0908 EST AND WILL BE | | TERMINATED WHEN THE PLANT REACHES COLD SHUTDOWN CONDITION. | | | | THE NRC RESIDENT INSPECTOR AND STATE & LOCAL OFFICIALS HAVE BEEN INFORMED. | | | | * * * UPDATE FROM CIFONELLI TO HUFFMAN AT 10:30 * * * | | | | BASED ON THE MOST RECENT DRYWELL LEAK RATE DATA, THE LEAK HAS DECREASED | | TO 4 GPM. THE LICENSEE CONTINUES TO MONITOR THE LEAK RATE CLOSELY. | | LEAK RATE DATA IS BEING UPDATED EVERY SIX MINUTES. THE LICENSEE STATES | | THAT THERE MAY BE A CORRELATION BETWEEN MANIPULATION OF THE "B" RECIRC | | FLOW CONTROL VALVE AND THE LEAK RATE INCREASE. THE REACTOR IS CURRENTLY | | AT 75% POWER. | | | | HOO NOTIFIED R1DO ESELGROTH AND NRR EO CHRIS GRIMES. | | | | * * * UPDATE AT 1507 BY CIFONELLI ENTERED BY HOO JOLLIFFE * * * | | | | THE DRYWELL FLOOR DRAIN LEAK RATE DECREASED TO APPROXIMATELY 2 GPM. | | THE OFFGAS SYSTEM ISOLATED AND THE MAIN CONDENSER VACUUM STARTED TO | | DECREASE. | | | | CONSEQUENTLY, AT 1418, CONTROL ROOM OPERATORS MANUALLY SCRAMMED UNIT 2 | | FROM 23% POWER. ALL CONTROL RODS INSERTED COMPLETELY. STEAM IS BEING | | DUMPED TO THE MAIN CONDENSER. THE FOLLOWING ESF ISOLATIONS OCCURRED: | | PCIS GROUP 4 - RHR SYSTEM SAMPLE LINES AND REJECT LINES TO RAD WASTE SYSTEM | | PCIS GROUP 5 - SHUTDOWN COOLING SYSTEM. | | | | THE DRYWELL FLOOR DRAIN LEAK RATE INCREASED TO APPROXIMATELY 5 GPM AND IS | | HOLDING STEADY. | | | | UNIT 2 IS STABLE IN CONDITION 3 (HOT SHUTDOWN). | | | | LICENSEE INTENDS TO COOL UNIT 2 DOWN TO CONDITION 4 (COLD SHUTDOWN), | | DEINERT THE DRYWELL, AND LOCATE AND REPAIR THE LEAK. | | | | LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | HOO NOTIFIED R1DO ESELGROTH AND NRR EO CHRIS GRIMES. | | | | ***UPDATE AT 18:25 FROM WEAVER TO GOULD*** | | THE NOUE WAS TERMINATED AT 18:00. THE DRYWELL FLOOR DRAIN LEAKAGE IS 3.5 | | GPM AND DECREASING AS REACTOR PRESSURE LOWERS. THE RI, STATE AND LOCAL | | AGENCIES WERE NOTIFIED. | | | | NOTIFIED RDO ESELGROTH, EO THOMAS & FEMA WITSBERGER | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 28124 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: BERTHOLD SYSTEMS, INC. |NOTIFICATION DATE: 12/09/94 | | CITY: ALIQUIPPA REGION: 1 |NOTIFICATION TIME: 11:08 [ET]| | COUNTY: STATE: PA |EVENT DATE: 12/09/94 | |LICENSE#: 37-21226-01 AGREEMENT: N |EVENT TIME: 11:08[EST]| | DOCKET: |LAST UPDATE DATE: 12/09/94 | | +-----------------------------+ | |PERSON ORGANIZATION| | | | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: C.FERRIN (VIA FACSIMILE) | | |HQ OPS OFFICER: WILLIAM HUFFMAN | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |CCCC 21.21 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | POSSIBLE DEFECT IN A SOURCE SHIELD SHUTTER MECHANISM. | | | | BERTHOLD SYSTEMS, PROCESS CONTROL INSTRUMENTS DIVISION, ALIQUIPPA | | PENNSYLVANIA, REPORTS A POSSIBLE MANUFACTURING DEFECT IN THERE MODEL | | LB-7400 SERIES SOURCE SHIELDS. THESE SHIELDS HOLD CESIUM OR COBALT SOURCES | | USED WITH BERTHOLD DENSITY, LEVEL, OR ON-LINE BELT ANALYZER SYSTEMS. | | | | THE DEFECT MAY CAUSE THE ON-OFF SHUTTER MECHANISM OF THE SHIELD TO BIND IN | | ITS HOUSING. | | | | THE LICENSEE IS CURRENTLY INFORMING ALL ITS CUSTOMERS WHO MAY HAVE | | INSTALLED THESE DEVICES. LONG TERM CORRECTIVE PLANS ARE STILL BEING | | FORMULATED. | | | | A COPY OF THIS REPORT HAS BEEN SENT TO NRR/TQMB (HAASS) AND NMSS (RAMSEY). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28125 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CALVERT CLIFFS REGION: 1 |NOTIFICATION DATE: 12/09/94 | |UNIT: [1] [2] [ ] STATE: MD |NOTIFICATION TIME: 11:47 [ET]| |RX TYPE: [1] CE,[2] CE |EVENT DATE: 12/09/94 | +------------------------------------------------+EVENT TIME: 11:00[EST]| |NRC NOTIFIED BY: CRAIG SLY |LAST UPDATE DATE: 12/09/94 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: | | |CCCC 21.21 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | - HEAT TRANSFER FROM RCS METAL TO Rx COOLANT NOT MODELED IN SAFETY ANALYSIS | | | | DURING A REVIEW OF THE UFSAR SAFETY ANALYSIS CONCERNING CONTAINMENT | | PRESSURE RESPONSE, LICENSEE DETERMINED THAT THE ANALYSIS OF THE LONG TERM | | COOLING PHASE OF A LOCA DID NOT MODEL HEAT TRANSFER FROM REACTOR COOLANT | | SYSTEM METAL COMPONENTS TO THE REACTOR COOLANT. | | | | WHEN THE Rx COOLANT SYSTEM METAL SENSIBLE HEAT IS INCLUDED, THIS RESULTS | | IN REACTOR COOLANT WITH A HIGHER ENTHALPY FLOWING FROM THE REACTOR COOLANT | | SYSTEM BREAK INTO CONTAINMENT AND LEADS TO SLIGHTLY HIGHER CONTAINMENT | | TEMPERATURES FOR SEVERAL DAYS AFTER THE CONTAINMENT TEMPERATURE PEAK. | | | | THIS OMISSION INCREASES THE POST ACCIDENT LOAD ON THE SERVICE WATER SYSTEM | | WHICH REMOVES HEAT FROM CONTAINMENT VIA THE CONTAINMENT AIR COOLERS. | | | | HOWEVER, THE LICENSEE DOES NOT HAVE AN OPERABILITY CONCERN BECAUSE | | ULTIMATE HEAT SINK TEMPERATURES ARE LOW ENOUGH TO ENSURE FULL COMPLIANCE | | WITH CURRENT PLANT DESIGN AND LICENSING BASIS. | | | | LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28126 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PILGRIM REGION: 1 |NOTIFICATION DATE: 12/09/94 | |UNIT: [1] [ ] [ ] STATE: MA |NOTIFICATION TIME: 12:03 [ET]| |RX TYPE: [1] GE-3 |EVENT DATE: 12/09/94 | +------------------------------------------------+EVENT TIME: 11:03[EST]| |NRC NOTIFIED BY: HAISLET |LAST UPDATE DATE: 12/09/94 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PETER ESELGROTH 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 +------------------------------------------------------------------------------+ | - RCIC SYSTEM INOPERABLE DUE TO LEAKING RCIC STEAM LINE ISOLATION VALVE - | | | | LICENSEE HAS DECLARED THE RCIC SYSTEM INOPERABLE DUE TO A SMALL | | BODY-TO-BONNET LEAK IN THE RCIC STEAM LINE ISOLATION VALVE #MO-1301-17. | | | | LICENSEE HAS ISOLATED THE LEAK BY CLOSING THE RCIC STEAM LINE ISOLATION | | VALVE #MO-1301-16 LOCATED UPSTREAM OF THE #17 VALVE. | | | | LICENSEE IS DETERMINING CORRECTIVE ACTIONS. | | | | LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28127 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SALEM REGION: 1 |NOTIFICATION DATE: 12/09/94 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 13:48 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 12/09/94 | +------------------------------------------------+EVENT TIME: 13:28[EST]| |NRC NOTIFIED BY: BOB GALLAHER |LAST UPDATE DATE: 12/09/94 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PETER ESELGROTH RDO | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 92 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - LICENSEE SHUTTING UNIT 1 DOWN FROM 100% DUE TO 2 OF 2 INOPERABLE SECs - | | | | THE #1A SAFEGUARDS EQUIPMENT CABINET (SEC) FAILED DURING A TECH SPEC | | SURVEILLANCE TEST. WHILE TROUBLESHOOTING THE #1A SEC, THE #1B SEC | | DEVELOPED A TEST FAULT THAT WOULD NOT CLEAR. LICENSEE DECLARED 2 OF 2 SECs | | INOPERABLE. THE SECs SUPPLY POWER TO POST-ACCIDENT ECCS EQUIPMENT. | | | | AT 1328, LICENSEE ENTERED TECH SPEC LCO A/S 3.0.3 AND BEGAN SHUTTING UNIT 1 | | DOWN FROM 100% POWER AT 25% POWER PER HOUR. | | | | LICENSEE IS ATTEMPTING TO REPAIR BOTH SECs. THEY HAVE IDENTIFIED A PROBLEM | | WITH THE PUSH BUTTONS ON BOTH SECs STICKING IN THE "INSERTED" POSITION. | | LICENSEE IS MAKING AN OPERABILITY DETERMINATION ON THESE SECs. IF THE SECs | | ARE NOT REPAIRED AND DECLARED OPERABLE IN TIME, UNIT 1 WILL BE PLACED IN | | HOT STANDBY MODE WITHIN 6 HOURS (OF 1328) AND COLD SHUTDOWN MODE WITHIN THE | | FOLLOWING 30 HOURS. | | | | LICENSEE'S EMERGENCY PLAN DOES NOT REQUIRE THEM TO DECLARE AN EMERGENCY | | DUE TO THIS TECH SPEC REQUIRED PLANT SHUTDOWN. | | | | LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE AT 1730 BY GALLAHER ENTERED BY HOO JOLLIFFE * * * | | | | AT 1700, LICENSEE RESTORED BOTH SECs TO OPERABLE STATUS AND TERMINATED THE | | PLANT SHUTDOWN AT 52% POWER. LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | HOO NOTIFIED R1DO ESELGROTH. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28128 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PEACH BOTTOM REGION: 1 |NOTIFICATION DATE: 12/09/94 | |UNIT: [2] [3] [ ] STATE: PA |NOTIFICATION TIME: 15:51 [ET]| |RX TYPE: [2] GE-4,[3] GE-4 |EVENT DATE: 12/09/94 | +------------------------------------------------+EVENT TIME: 14:45[EST]| |NRC NOTIFIED BY: JOHN BOUCK |LAST UPDATE DATE: 12/09/94 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PETER ESELGROTH RDO | |AINA 50.72(b)(2)(iii)(A) POT UNABLE TO SAFE SD | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | - OFFGAS FLOW BYPASSED THE MAIN STACK FOR 3.5 HOURS DUE TO AN OPEN DOOR - | | | | FROM ABOUT 1000 TO 1330 ON 11/29/94, THE OFFGAS FLOW BYPASSED THE MAIN | | STACK WHEN THE DOOR BETWEEN THE STACK PLENUM AND THE STACK EQUIPMENT | | ROOM WAS OPEN WHILE THE STACK EQUIPMENT ROOM OUTSIDE DOOR WAS ALSO OPEN. | | THESE DOORS WERE OPEN TO FACILITATE THE ERECTION OF SCAFFOLDING IN THE | | MAIN STACK. | | | | DURING THIS PERIOD, APPROXIMATELY 99% OF THE OFFGAS FLOW EXITED THE STACK | | THROUGH THE EQUIPMENT ROOM AT THE BASE OF THE STACK. THIS RESULTED IN | | AN UNANTICIPATED POTENTIAL HIGHER OFFSITE DOSE RATE HAD A DESIGN BASIS | | ACCIDENT (LOCA) OCCURRED [21.3 REM (THYROID) & 1.55 REM (WHOLE BODY)]. | | UFSAR LIMITS ARE 14.8 REM (THYROID) & 0.655 REM (WHOLE BODY). | | | | THIS CONSTITUTES A LOSS OF SAFETY FUNCTION OF THE MAIN STACK DUE TO THE | | ELEVATED RELEASE RATES. THE POTENTIAL RISE IN DOSE RATES WERE WELL BELOW | | 10CFR100 LIMITS [300 REM (THYROID) & 25 REM (WHOLE BODY)]. | | | | LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28129 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SOUTH TEXAS REGION: 4 |NOTIFICATION DATE: 12/10/94 | |UNIT: [1] [2] [ ] STATE: TX |NOTIFICATION TIME: 07:26 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 12/09/94 | +------------------------------------------------+EVENT TIME: 10:00[CST]| |NRC NOTIFIED BY: LOUIS PETER |LAST UPDATE DATE: 12/10/94 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |IAN BARNES 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 +------------------------------------------------------------------------------+ | LICENSEE DISCOVERED THAT ACCEPTANCE CRITERIA FOR SURVEILLANCE TESTING OF 64 | | CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTION DEVICES WAS NOT IN | | ACCORDANCE WITH DESIGN DOCUMENTS. | | | | "THIS NOTIFICATION IS REQUIRED DUE TO INADEQUATE ACCEPTANCE CRITERIA FOR | | TECHNICAL SPECIFICATION SURVEILLANCE 4.8.4.1.A.2 ON CONTAINMENT PENETRATION | | CONDUCTOR OVERCURRENT PROTECTION DEVICES, SPECIFICALLY MOLDED CASE MAGNETIC | | BREAKERS." | | | | "THIS EVENT IS BEING REPORTED PER ITEM "2G" OF LICENSE NUMBER NPF-76 FOR | | SOUTH TEXAS PROJECT UNIT 1 AND LICENSE NUMBER NPF-80 FOR SOUTH TEXAS | | PROJECT UNIT 2." | | | | "NO NUCLEAR SAFETY HAZARD EXISTS BECAUSE THE BREAKERS OVERCURRENT | | PROTECTION DEVICES PROVIDE ADEQUATE ACCEPTABLE CONTAINMENT PENETRATION | | PROTECTION MARGINS EVEN WHEN ADJUSTED TO THEIR MAXIMUM SETTINGS. THE TEST | | METHODOLOGY, FIELD SETTINGS AND PAST ACCEPTANCE CRITERIA FOR THESE BREAKER | | OVERCURRENT DEVICES PROVIDE ASSURANCE OF THE CONTAINMENT ELECTRICAL | | PENETRATION PROTECTIVE FUNCTION." | | | | "THE TEST METHODOLOGY IS CONSISTENT WITH THE WORDING OF TECHNICAL | | SPECIFICATION SURVEILLANCE REQUIREMENT 4.8.4.1.A.2 AND THE METHODOLOGY OF | | NEMA AB-2, 1980." | | | | "THE ACCEPTANCE CRITERIA FOR ADJUSTABLE MAGNETIC BREAKERS APPLIED IN THE | | PAST DOES NOT COMPLY WITH THAT INTENDED BY THE TECHNICAL SPECIFICATION AS | | AMPLIFIED THROUGH THE STATEMENTS IN THE BASES DOCUMENTS, IN THAT TOLERANCES | | WERE APPLIED TO AN ALLOWABLE RANGE OF SETTINGS AS OPPOSED TO APPLYING THE | | TOLERANCE TO THE SPECIFIC SETTING USED DURING EACH SURVEILLANCE TEST. USE | | OF THE TOLERANCE AROUND A SPECIFIC SETTING AS INTENDED BY THE TECHNICAL | | SPECIFICATION SURVEILLANCE REQUIREMENT WILL RESULT IN TIGHTER ACCEPTANCE | | BANDS AND RESULT IN REJECTING BREAKERS WE HAD PREVIOUSLY CONSIDERED | | ACCEPTABLE." | | | | UNIT BREAKER COMPONENT NOUN | | | | 1 E1CI\B3 CV-MOV-23 L\D ICIV | | 1 E1A2\J1 RC-MOV-1A PZR PORV BLOCK VALVE | | 1 E1B1\D3 SI-MOV-19B B LHSI HOT LEG INJECTION | | 1 E1C1\C1 CC-MOV-129 B RHR ICIV | | 1 E1B5\A2 RH-MOV-067B B RHR MINIFLOW | | 1 E1C1\C2 CC-MOV-147 B RCFC ICIV | | 1 E1A1\C3 SI-MOV-31A A LHSI COLD LEG INJECTION | | 1 E1B1\T1 CC-MOV-68 A RCFC ICIV | | 1 E1B1\U2 RA-MOV-3 RT-8011 ICIV | | 1 E1B1\J2 RC-MOV-1B PZR PORV BLOCK VALVE | | 1 E1C1\A3 SI-MOV-19C C LHSI HOT LEG INJECTION | | 1 E1C1\A2 SI-MOV-8C C HHSI HOT LEG INJECTION | | 1 E1A1\G3 CC-MOV-189 C RHR ICIV | | 1 E1C5\A3 RH-MOV-67C C MINIFLOW | | 1 1K1\K1 CC-MOV-374 RCP 1B THERMAL BARRIER HX ISOL | | 1 1J1\F3 CC-MOV-339 RCP 1A THERMAL BARRIER HX ISOL | | 1 1K1\B1 CC-MOV-356 RCP 1D THERMAL BARRIER HX ISOL | | 1 1L1\G1 CC-MOV-390 RCP 1C THERMAL BARRIER HX ISOL | | 1 E1A4\A2 CV-MOV-82 EXCESS LETDOWN | | 1 E1B5\B1 VFN037 RX CAVITY EXH FAN 11B | | 1 E1A1\E3 CV-MOV-3 NORMAL CHARGING | | 1 E1B4\F1 SI-MOV-39B B ACCUM DISCH | | 1 E1A4\E3 SI-MOV-39A A ACCUM DISCH | | 1 E1C2\R2 CV-MOV-14 L/D ORIFICE ISOL | | 1 1J1\B2 FAN 11A CNTMT CRBN UNIT | | 1 1J1\C4 SUMP PP. A CNTMT SEC SUMP | | 1 E1A4\A3 CC-MOV-63 12A RCFC OUTLET | | 1 E1A1\B2 CC-MOV-60 12A RCFC INLET | | 1 E1B1\N3 CC-MOV-146 11B RCFC OUTLET | | 1 E1C2\C2 CC-MOV-200 12C RCFC INLET | | 1 E1C2\J2 CV-MOV-6 ALT CHRG ISOL | | 1 E1B1\J1 HC-MOV-8 NORM PURGE SPLY ICIV | | 1 E1A1\J3 HC-MOV-9 NORM PURGE EXH ICIV | | | | 2 E2C2\E4 CV-MOV-77 RCP SEAL RETURN ICIV | | 2 E2B1\F3 HC-MOV-5 SUPPLE. RCB PURGE EXH ICIV | | 2 E2B1\F2 HC-MOV-3 SUPPLE. RCB PURGE SUPPLY ICIV | | 2 E2A1\H2 CC-MOV-208 C RCFC ICIV | | 2 E2B1\T1 CC-MOV-68 A RCFC ICIV | | 2 E2C1\C2 CC-MOV-147 B RCFC ICIV | | 2 E2B1\H3 CC-MOV-49 A RHR HX ICIV | | 2 E2B1\A4 SI-MOV-31B B LHSI COLD LEG INJECTION | | 2 E2A4\E3 SI-MOV-39A A ACCUM DISCH | | 2 E2C1\R2 CV-MOV-468 LETDOWN ISOL | | 2 E2A2\J1 RC-MOV-1A PZR PORV BLOCK VALVE | | 2 E2C1\A3 SI-MOV-19C C LHSI HOT LEG INJECTION | | 2 E2C1\D1 SI-MOV-31C C LHSI COLD LEG INJECTION | | 2 E2B1\C3 SI-MOV-8B B HHSI HOT LEG INJECTION | | 2 E2B1\C1 SI-MOV-6B B HHSI COLD LEG INJECTION | | 2 E2B1\N3 CC-MOV-146 21B RCFC ISOLATION | | 2 E2B1\X4 CC-MOV-143 22B RCFC ISOLATION | | 2 E2B1\P3 CC-MOV-139 22B RCFC ISOLATION | | 2 E2A2\V1 HCFN029 CTMT CUBICLE EXHAUST FAN 22A | | 2 E2A1\J3 HC-MOV-9 RCB NORMAL PURGE EXH ICIV | | 2 E2A4\A2 CV-MOV-82 EXCESS L/D ISOLATION | | 2 E2B2\J1 HC-MOV-8 RCB NORMAL PURGE SUPPLY ICIV | | 2 E2B2\J2 CV-MOV-83 EXCESS L/D ISOLATION | | 2 E2C2\R2 CV-MOV-14 L/D ORIFICE ISOLATION | | 2 2A5\B5 FN017 CRDM VENT FAN 21A | | 2 2J1\B2 VFN029 CTMT CARBON FILTER SUPPLY FAN 21A | | 2 2K1\C4 VFN020 CTMT CARBON FILTER SUPPLY FAN 22A | | 2 2K1\G3 21A LIFT PUMP RCP 2A OIL LIFT PUMP | | 2 2J1\F3 CC-MOV-339 RCP 2A THERMAL BARRIER HX ISOL | | 2 2L1\G1 CC-MOV-0390 RCP 2C THERMAL BARRIER HX ISOL | | 2 2K1\B1 CC-MOV-0356 RCP 2D THERMAL BARRIER HX ISOL | | | | PROBLEM WAS DISCOVERED DURING SURVEILLANCE TESTING AND AFFECTS 64 BREAKERS | | PLACING BOTH UNITS IN THE 72 HOUR TS LCO A/S 3.8.4.1 ACTION A. THE LICENSEE | | INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28130 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SEABROOK REGION: 1 |NOTIFICATION DATE: 12/10/94 | |UNIT: [1] [ ] [ ] STATE: NH |NOTIFICATION TIME: 10:40 [ET]| |RX TYPE: [1] W-4-LP |EVENT DATE: 12/10/94 | +------------------------------------------------+EVENT TIME: 10:06[EST]| |NRC NOTIFIED BY: STRICKLAND |LAST UPDATE DATE: 12/10/94 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PETER ESELGROTH RDO | |AENS 50.72(b)(1)(v) ENS INOPERABLE | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | UNEXPECTED LOSS OF ENS AND COMMERCIAL PHONE SERVICE THROUGH PORTSMOUTH, NH | | SWITCHBOARD DURING PLANNED ELECTRICAL MAINTENANCE OFFSITE. | | | | THE LICENSEE IN PREPARATION FOR PLANNED ELECTRICAL MAINTENANCE BETWEEN | | 0700-1100 12/10/94 IN AN OUT BUILDING OFFSITE, EXPERIENCED A LOSS OF ENS | | AND OUTGOING COMMERCIAL TELEPHONE LINES THROUGH THE PORTSMOUTH, NH. | | SWITCHBOARD. THE DEDICATED NUCLEAR ALERT SYSTEM AND MANCHESTER, NH. | | SWITCHBOARD WERE UNAFFECTED. THE LICENSEE IS EXPEDITING MAINTENANCE AND | | WILL VERIFY TELEPHONE OPERABILITY WHEN MAINTENANCE IS COMPLETED. THE | | LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE 1127EST 12/10/94 FROM STRICKLAND TO S.SANDIN * * * | | TELEPHONE COMMUNICATIONS REESTABLISHED AFTER INSTALLATION OF TEMPORARY | | POWER SUPPLY. HOO NOTIFIED R1DO ESELGROTH. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 28131 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: BECTEL/PARSONS BRINKERHOFF |NOTIFICATION DATE: 12/10/94 | | CITY: BOSTON REGION: 1 |NOTIFICATION TIME: 12:51 [ET]| | COUNTY: STATE: MA |EVENT DATE: 12/10/94 | |LICENSE#: 20-28645-01 AGREEMENT: N |EVENT TIME: 11:15[EST]| | DOCKET: |LAST UPDATE DATE: 12/10/94 | | +-----------------------------+ | |PERSON ORGANIZATION| | |PETER ESELGROTH RDO | | |MALCOLM KNAPP EO | +------------------------------------------------+ | |NRC NOTIFIED BY: DOBOSZ | | |HQ OPS OFFICER: CHAUNCEY GOULD | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE REPORTED THAT A TROXLER DENSITY GAUGE WAS POSSIBLY DAMAGED AT | | A CONSTRUCTION SITE. | | | | THIS OCCURRED WHEN A TEN WHEELER TRUCK RAN OVER THE GAUGE AT THE CENTRAL | | ARTERY TUNNEL PROJECT CONSTRUCTION SITE IN BOSTON. THE GAUGE WAS IN THE | | BACK SCATTER MODE WHICH MEANS THAT THE SOURCE ROD WAS OUTSIDE OF ITS SEALED | | COMPARTMENT, BUT INSIDE THE GAUGE WHEN IT WAS HIT. THE TRUCK IS STILL | | RESTING ON THE GAUGE. ALL PERSONNEL HAVE BEEN EVACUATED FROM THE IMMEDIATE | | AREA OF THE GAUGE AND THAT AREA HAS BEEN SECURED. THE GAUGE CONTAINED 2 | | SOURCES, CS-137(8.0 MILLICURIES) AND AM-241:BE(40.0 MILLICURIES). THE | | LICENSEE CONTACTED THE LOCAL FIRE DEPARTMENT. THEY HAVE NOT YET DETERMINED | | IF THE SOURCE WAS COMPLETELY DESTROYED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28132 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VERMONT YANKEE REGION: 1 |NOTIFICATION DATE: 12/11/94 | |UNIT: [1] [ ] [ ] STATE: VT |NOTIFICATION TIME: 09:53 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 12/11/94 | +------------------------------------------------+EVENT TIME: 09:15[EST]| |NRC NOTIFIED BY: BRYAN COKE |LAST UPDATE DATE: 12/11/94 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PETER ESELGROTH RDO | |AARC 50.72(b)(1)(v) OTHER ASMT/COMM INOP | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 DEDICATED LAND LINE TO THE STATE OF NEW HAMPSHIRE IS NOT FUNCTIONING | | PROPERLY. | | | | WHILE PERFORMING A MONTHLY COMMUNICATIONS CHECK, IT WAS DISCOVERED THAT THE | | STATE OF NEW HAMPSHIRE WAS UNABLE TO CALL THE SITE ON THE NUCLEAR ALERT | | SYSTEM PHONE. THE SITE IS ABLE TO CONTACT THEM, HOWEVER, THE SIGNAL IS | | WEAK. THE NEW HAMPSHIRE EMERGENCY MANAGEMENT DEPARTMENT CONTACTED THE | | TELEPHONE COMPANY NYNEX. NYNEX IDENTIFIED THAT THE PROBLEM WAS RELATED TO A | | CABLE AND THAT REPAIRS WOULD BE COMPLETED TODAY. THE LICENSEE WILL INFORM | | THE STATE OF VERMONT AND THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28133 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: GRAND GULF REGION: 2 |NOTIFICATION DATE: 12/11/94 | |UNIT: [1] [ ] [ ] STATE: MS |NOTIFICATION TIME: 14:05 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 12/11/94 | +------------------------------------------------+EVENT TIME: 10:34[CST]| |NRC NOTIFIED BY: McDONALD |LAST UPDATE DATE: 12/11/94 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |THOMAS PEEBLES 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 +------------------------------------------------------------------------------+ | - RWCU SYSTEM DIVISION 1 ISOLATION ACTUATION INSTRUMENTATION INOPERABLE - | | | | AT 1034 (CST), 6 OF 6 RWCU SYSTEM ISOLATION VALVES CLOSED WHEN THE PLANT | | RECEIVED A SPURIOUS RWCU SYSTEM ISOLATION SIGNAL DUE TO FAILED DIVISION 1 | | RILEY MAIN STEAM LINE PIPE TUNNEL DIFFERENTIAL TEMPERATURE LEAK DETECTION | | SWITCH (#E31-N605A). | | | | AT 1049 (CST), CONTROL ROOM OPERATORS BYPASSED THE SWITCH, RESET THE | | ISOLATION SIGNAL, AND OPENED THE RWCU SYSTEM ISOLATION VALVES. | | | | TECH SPEC LCO A/S #94-1587 REQUIRES LICENSEE TO RESTORE THE DIVISION 1 | | RWCU SYSTEM ISOLATION ACTUATION INSTRUMENTATION TO OPERABLE STATUS | | WITHIN 6 HOURS OR SHUT THE PLANT DOWN. | | | | LICENSEE EXPECTS TO REPLACE THE SWITCH AND RESTORE THE ACTUATION | | INSTRUMENTATION TO OPERABLE STATUS WITHIN 6 HOURS. | | | | LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28134 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOK REGION: 3 |NOTIFICATION DATE: 12/11/94 | |UNIT: [ ] [2] [ ] STATE: MI |NOTIFICATION TIME: 20:37 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 12/11/94 | +------------------------------------------------+EVENT TIME: 17:06[EST]| |NRC NOTIFIED BY: ROGER WEST |LAST UPDATE DATE: 12/11/94 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRUCE JORGENSEN 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | A/R Y 19 POWER OPERATION | 0 HOT STANDBY | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - AUTO Rx TRIP FROM 19% DUE TO AUTO MAIN TURBINE TRIP FOR UNKNOWN REASONS - | | | | WHILE INCREASING POWER FOLLOWING A REFUELING OUTAGE, THE REACTOR AUTO | | TRIPPED FROM 19% DUE TO AN AUTO TRIP OF THE MAIN TURBINE POSSIBLY DUE TO | | A SPURIOUS MOISTURE SEPARATOR HIGH LEVEL SIGNAL. | | | | ALL CONTROL RODS INSERTED COMPLETELY. THE MAIN FEEDWATER SYSTEM ISOLATED | | AND THE AUX FEEDWATER SYSTEM STARTED, AS EXPECTED. STEAM IS BEING DUMPED | | TO THE MAIN CONDENSER. | | | | Rx COOLANT SYSTEM COOLED DOWN 10 F DEGREES BELOW NOMINAL NO LOAD | | TEMPERATURE; CONTROL ROOM OPERATORS QUICKLY CORRECTED THIS CONDITION BY | | ISOLATING MINOR STEAM FLOW PATHS. | | | | UNIT 2 IS STABLE IN MODE 3 (HOT SHUTDOWN). | | | | LICENSEE IS INVESTIGATING THE CAUSE OF THE MAIN TURBINE TRIP. | | | | LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+