U.S. Nuclear Regulatory Commission Operations Center Event Reports For 03/06/96 - 03/07/96 ** EVENT NUMBERS ** 30069 30070 30071 30072 30073 30074 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30069 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 03/06/96 | |UNIT: [2] [ ] [ ] STATE: NY |NOTIFICATION TIME: 11:19 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 03/06/96 | +------------------------------------------------+EVENT TIME: 11:14[EST]| |NRC NOTIFIED BY: SANTINI |LAST UPDATE DATE: 03/06/96 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LARRY DOERFLEIN RDO | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 2 | N N 0 HOT SHUTDOWN | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | NOTIFIED OFFSITE AUTHORITIES THAT A BUS SPILLED ò 5 gallons OF DIESEL FUEL | | OIL ONTO THE ROADWAY. SOME OF THE DIESEL FUEL OIL ENTERED THE STORM DRAIN | | SYSTEM. | | | | INDIAN POINT UNIT 2 WAS NOTIFIED BY INDIAN POINT UNIT 3 THAT ò 5 gallons OF | | DIESEL FUEL OIL SPILLED ONTO THE ROADWAY BETWEEN UNITS 2 AND 3. THE DIESEL | | FUEL OIL CAME FROM A WESTCHESTER BEELINE BUS. THE SPILL OCCURRED BETWEEN | | 0600 & 0900. SOME OF THE DIESEL FUEL OIL ENTERED LICENSEE STORM DRAIN | | SYSTEM. CLEAN UP OF THE SPILL IS IN PROGRESS. LICENSEE NOTIFIED THE | | FOLLOWING AGENCIES OF THE OIL SPILL: UNITED STATES COAST GUARD NATIONAL | | RESPONSE CENTER, NEW YORK DEPARTMENT OF ENVIRONMENTAL CONSERVATION, | | INTERSTATE SANITARY COMMISSION, WESTCHESTER COUNTY DEPARTMENT OF HEALTH, | | AND THE WESTCHESTER COUNTY EMERGENCY OPERATION CENTER. | | | | RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE. | | | | * * * UPDATE AT 1719 ON 3/6/96 BY LIJOI TAKEN BY WEAVER * * * | | | | WHEN THE BUS RETURNED IN THE AFTERNOON, IT AGAIN SPILLED DIESEL FUEL OIL. | | THE LICENSEE MADE ANOTHER SET OF OFFSITE NOTIFICATIONS. THE SPILL HAS BEEN | | CONTAINED AND IS BEING CLEANED UP. THE HOO NOTIFIED THE R1DO (DOERFLEIN). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30070 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SUSQUEHANNA REGION: 1 |NOTIFICATION DATE: 03/06/96 | |UNIT: [1] [2] [ ] STATE: PA |NOTIFICATION TIME: 14:00 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 03/06/96 | +------------------------------------------------+EVENT TIME: 13:50[EST]| |NRC NOTIFIED BY: GRANT FERNSLER |LAST UPDATE DATE: 03/06/96 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LAWRENCE DOERFLEIN 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 Y 100 POWER OPERATION | 100 POWER OPERATION | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | A POTENTIAL CONTAINMENT BYPASS PATHWAY HAS PREVIOUSLY EXISTED ON BOTH UNITS | | | | "ON 3/6/96, ADDITIONAL EVALUATION OF A DESIGN CONDITION HAS CONCLUDED THAT | | IT WOULD HAVE RESULTED IN THE PLANT BEING IN A DEGRADED CONDITION DUE TO | | SOME PAST LLRT RESULTS, WHILE THE PLANT WAS SHUTDOWN, IN WHICH THE DESIGN | | BASIS WOULD HAVE BEEN EXCEEDED. SPECIFICALLY, FSAR SECTION 6.2.3.2.3 | | DISCUSSES THE NEED TO EITHER ELIMINATE POTENTIAL BYPASS LEAKAGE PATHWAY OR | | ACCOUNT FOR THE CONTRIBUTION OF THE PATHWAY IN THE ACCIDENT DOSE ANALYSIS. | | PP&L's EVALUATION CONCLUDED THAT, FOLLOWING A POSTULATED DESIGN BASIS LARGE | | BREAK LOCA/LOOP, THE WATER SEAL DESCRIBED IN THE FSAR FOR THE FEEDWATER | | PENETRATION WILL BE EXHAUSTED IN LESS THAN FIVE MINUTES. THUS, THE | | REQUIREMENTS OF FSAR 6.2.3.2.3 WOULD NOT HAVE BEEN MET IN THE PAST. THIS | | CONDITION IS APPLICABLE TO BOTH UNIT 1 AND UNIT 2. | | | | "SECONDARY CONTAINMENT OPERABILITY, WITH RESPECT TO BYPASS LEAKAGE, IS | | MAINTAINED BASED ON CURRENT VALVE LLRT DATA, AND IS WITHIN DESIGN BASIS | | BYPASS LEAKAGE ASSUMPTION OF 2360 SCCM FOR BOTH UNIT 1 AND UNIT 2, THUS | | MEETING FSAR 6.2.3.2.3 REQUIREMENTS." | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30071 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MCGUIRE REGION: 2 |NOTIFICATION DATE: 03/06/96 | |UNIT: [ ] [2] [ ] STATE: NC |NOTIFICATION TIME: 15:50 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 03/06/96 | +------------------------------------------------+EVENT TIME: 15:12[EST]| |NRC NOTIFIED BY: L. BROWN |LAST UPDATE DATE: 03/06/96 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |KERRY LANDIS RDO | |AUNA 50.72(b)(1)(ii)(A) UNANALYZED COND OP | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | EDGs INOPERABLE WHEN THE DIESEL ROOM TEMPERATURE IS < 70øF. | | | | INVESTIGATIONS FOLLOWING A EDG TRIP WHICH OCCURRED DURING A MONTHLY | | SURVEILLANCE ON 2/6/96, REVEALED THAT THE EDGs ARE INOPERABLE WHEN THE | | DIESEL ROOM TEMPERATURE IS BELOW 70øF. THE EDGs ARE SUSCEPTIBLE TO LOW | | LUBE OIL PRESSURE TRIPS WHEN THE ROOM TEMPERATURE IS BELOW 70øF. THE | | LICENSEE BELIEVES THE LENGTH OF THE SENSING LINE TO THE LUBE OIL PRESSURE | | SENSOR IS ONE OF THE CAUSES OF THIS PROBLEM. AN INVESTIGATION INTO THE | | PLANT'S LOGS IS BEING CONDUCTED TO DETERMINE THE AMOUNT OF TIME THAT WAS | | SPENT IN THIS CONDITION. ALTHOUGH THE DIESEL ROOMS HAVE SOME STRIP | | HEATING, THIS DID NOT MAINTAIN THE ROOM TEMPERATURE ABOVE 70øF UNDER ALL | | CONDITIONS. | | | | CURRENT DIESEL ROOM TEMPERATURES ARE GREATER THAN 75øF, SO ALL OF THE EDGs | | ARE OPERABLE. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | | | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30072 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HOPE CREEK REGION: 1 |NOTIFICATION DATE: 03/06/96 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 17:01 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 01/20/92 | +------------------------------------------------+EVENT TIME: 12:00[EST]| |NRC NOTIFIED BY: MIKE MOHNEY |LAST UPDATE DATE: 03/06/96 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LAWRENCE DOERFLEIN RDO | |ADEG 50.72(b)(1)(ii) DEGRAD COND DURING OP | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | VENTILATION DAMPERS INSTALLED BACKWARDS | | | | THE LICENSEE ORIGINALLY IDENTIFIED THIS PROBLEM BACK IN JANUARY OF 1992. | | THIS REPORT IS BEING MADE BECAUSE THEY HAVE CONCLUDED THAT A 50.72 REPORT | | SHOULD HAVE BEEN MADE BACK IN 1992. DAMPERS IN THE VENTILATION SYSTEM ARE | | USED IN VARIOUS SAFETY RELATED PUMP ROOMS AND OTHER AREAS TO PREVENT A | | STEAM LINE BREAK IN ONE ROOM OR AREA FROM DEGRADING OTHER SAFETY RELATED | | EQUIPMENT. SOME OF THESE DAMPERS WERE INSTALLED BACKWARDS DURING INITIAL | | CONSTRUCTION. IN 1992, THE LICENSEE CONDUCTED AN ENGINEERING EVALUATION | | WHICH INDICATED THAT THESE DAMPERS WOULD MEET THEIR DESIGN FUNCTION AS | | INSTALLED. | | | | UPON PREPARING WORK PACKAGES TO PROPERLY INSTALL THE DAMPERS, THE LICENSEE | | DISCOVERED THAT A 50.72 WAS NOT MADE IN 1992. THE PLANT IS CURRENTLY IN | | MODE 4. THE DAMPERS WILL BE FIXED PRIOR TO LEAVING MODE 4. THE PLANT IS | | SCHEDULED TO START UP ON 3/12/96. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30073 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: WASHINGTON NUCLEAR REGION: 4 |NOTIFICATION DATE: 03/06/96 | |UNIT: [2] [ ] [ ] STATE: WA |NOTIFICATION TIME: 19:30 [ET]| |RX TYPE: [2] GE-5 |EVENT DATE: 03/06/96 | +------------------------------------------------+EVENT TIME: 15:31[PST]| |NRC NOTIFIED BY: STEVE BERRY |LAST UPDATE DATE: 03/06/96 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BLAIR SPITZBERG 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 2 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | REACTOR BUILDING STACK RADIATION MONITOR INOPERABLE | | | | REACTOR BUILDING STACK RADIATION MONITOR #PRM-RE1B WAS DECLARED INOPERABLE | | WHEN THE LICENSEE DISCOVERED THAT THE GAS CALIBRATION FACTOR HAD BEEN | | NONCONSERVATIVELY SET. PRM-RE1B IS A MID-RANGE MONITOR IN THE REACTOR | | BUILDING STACK AND IT IS REQUIRED BY TECH SPECS. AN INCORRECT GROSS COUNT | | RATE HAD BEEN USED IN THE CALCULATION FOR THE GAS CALIBRATION FACTOR. THE | | CALIBRATION WAS DONE DURING THE LAST REFUELING OUTAGE IN THE SPRING OF | | 1995. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30074 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DAVIS BESSE REGION: 3 |NOTIFICATION DATE: 03/07/96 | |UNIT: [1] [ ] [ ] STATE: OH |NOTIFICATION TIME: 01:04 [ET]| |RX TYPE: [1] B&W-R-LP |EVENT DATE: 03/07/96 | +------------------------------------------------+EVENT TIME: 00:39[EST]| |NRC NOTIFIED BY: JIM McGEE |LAST UPDATE DATE: 03/07/96 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |THOMAS BURDICK RDO | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | | |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 +------------------------------------------------------------------------------+ | -EMERGENCY TS AMENDMENT REQUEST DUE TO MISSING HPI SYSTEM HIGH POINT VENT- | | | | APPROXIMATELY 5 YEARS AGO, THE PIPING OF THE HIGH PRESSURE INJECTION (HPI) | | SYSTEM, TRAIN 2, WAS RECONFIGURED AND A HIGH POINT VENT WAS ELIMINATED | | DURING A PLANT MODIFICATION. | | | | AT 2342 ON 03/06/96, AFTER REVIEWING PLANT LOGS, LICENSEE DETERMINED THAT | | HPI SYSTEM, TRAIN 2, HAD BEEN INOPERABLE SINCE 1354 ON 03/04/96 DUE TO THE | | INABILITY TO COMPLY WITH THE LITERAL WORDING OF TECH SPEC SURVEILLANCE | | REQUIREMENT 4.5.2.b FOR VENTING THE HIGH POINT OF HPI SYSTEM LINE #1-2. | | TECH SPEC LCO A/S 3.5.2 REQUIRES LICENSEE TO RESTORE AN INOPERABLE | | EMERGENCY CORE COOLING (ECC) SYSTEM TRAIN TO OPERABLE STATUS WITHIN | | 72 HOURS OR TO PLACE THE PLANT IN HOT SHUTDOWN MODE WITHIN THE FOLLOWING | | 12 HOURS. LICENSEE DETERMINED THAT HPI SYSTEM, TRAIN 2, IS FUNCTIONAL | | BASED ON A FORWARD FLOW TEST PERFORMED IN OCT 94 AND AN ULTRASONIC TEST | | PERFORMED ON 03/06/96 WHICH VERIFIED THAT HPI SYSTEM LINE #1-2 IS FILLED | | WITH WATER. | | | | LICENSEE ALSO DETERMINED THAT ECC SYSTEM, TRAIN 1, HAD BEEN INOPERABLE DUE | | TO MAINTENANCE ACTIVITIES FROM 0930 TO 1952 ON 03/04/96 AND FROM 0516 TO | | 1244 ON 03/05/96 AND THAT TECH SPEC LCO A/S 3.5.2 WAS APPLICABLE DURING | | THESE TIMES. | | | | LICENSEE ALSO DETERMINED THAT 1 OF 2 EDGs (#1) WAS INOPERABLE BUT | | FUNCTIONAL DUE TO MAINTENANCE ACTIVITIES FROM 0930 TO 1952 ON 03/04/96. | | TECH SPEC LCO A/S 3.8.1.1 REQUIRES LICENSEE TO DETERMINE THAT THE OTHER | | ECC SYSTEMS ARE OPERABLE AND TO RESTORE THE INOPERABLE EDG TO OPERABLE | | STATUS WITHIN 72 HOURS OR TO PLACE THE PLANT IN HOT STANDBY MODE WITHIN | | THE NEXT 6 HOURS AND HOT SHUTDOWN MODE WITHIN THE FOLLOWING 6 HOURS. | | | | TECH SPEC LCO A/S 3.0.5 REQUIRES LICENSEE TO RESTORE 1 OF 2 INOPERABLE | | TRAINS OF ECC SYSTEM TO OPERABLE STATUS WITHIN 2 HOURS OR PLACE THE PLANT | | IN HOT STANDBY MODE WITHIN THE NEXT 6 HOURS AND HOT SHUTDOWN MODE WITHIN | | THE FOLLOWING 6 HOURS. TECH SPEC LCO A/S 3.0.3 REQUIRES LICENSEE TO | | RESTORE 1 OF 2 INOPERABLE ECC SYSTEMS TO OPERABLE STATUS WITHIN 1 HOUR | | OR PLACE THE PLANT IN HOT STANDBY MODE WITHIN THE NEXT 6 HOURS AND HOT | | SHUTDOWN MODE WITHIN THE FOLLOWING 6 HOURS. | | | | THUS, AT 0039 ON 03/07/96, LICENSEE DETERMINED THAT TECH SPEC LCO A/Ss | | 3.0.5 AND 3.0.3 HAD BEEN APPLICABLE FOR 5 HOURS, 58 MINUTES ON 03/04/96 | | AND TECH SPEC LCO A/S 3.0.3 HAD BEEN APPLICABLE FOR 7 HOURS, 28 MINUTES | | ON 03/05/96. | | | | ON 03/06/96, LICENSEE DISCUSSED THIS SITUATION WITH REGION 3 AND NRR AND | | REQUESTED AND TRANSMITTED AN EMERGENCY TECH SPEC AMENDMENT ON THIS ISSUE TO | | NRR DAVIS BESSE PROJECT MANAGER LINDA GUNDRUM. | | | | LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+