U.S. Nuclear Regulatory Commission Operations Center Event Reports For 04/01/97 - 04/02/97 ** EVENT NUMBERS ** 31692 32059 32060 32061 32062 32063 32064 32065 +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 31692 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: VICTOREEN, INC. |NOTIFICATION DATE: 01/30/97 | | CITY: CLEVELAND REGION: 3 |NOTIFICATION TIME: 14:12 [ET]| | COUNTY: STATE: OH |EVENT DATE: 01/27/97 | |LICENSE#: AGREEMENT: N |EVENT TIME: 00:00[EST]| | DOCKET: |LAST UPDATE DATE: 04/01/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |IAN BARNES RDO | | | | +------------------------------------------------+VERN HODGE, RVIB NRR | |NRC NOTIFIED BY: LINDA S. NASH | | |HQ OPS OFFICER: LEIGH TROCINE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |CCCC 21.21 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | VICTOREEN INC. MADE A 10 CFR PART 21 NOTIFICATION REGARDING A DIGITAL | | DISPLAY UNIT. | | | | VICTOREEN INC. LOCATED AT 6000 COCHRAN ROAD IN CLEVELAND, OHIO, MADE A 10 | | CFR PART 21 NOTIFICATION THAT THEIR DIGITAL DISPLAY IN THE DIABLO CANYON | | NUCLEAR POWER PLANT CONTROL ROOM (RDU), FOR SAFETY-RELATED MONITOR R44B, | | STOPPED UPDATING (i.e, DISPLAY FROZEN). FURTHER TESTING DETERMINED THAT | | ALTHOUGH THE ALARM RELAY CHANGED STATE AFTER INPUTTING A TEST SIGNAL, THE | | RELAY OUTPUT AT THE RDU DID NOT. THIS IS AN UNIDENTIFIED FAILURE CONDITION | | IN THE DESIGN. | | | | *** UPDATE ON 04/01/97 @ 1800EST TAKEN FROM A FAX BY MACKINNON *** | | | | THE EVENT DESCRIBED HAS BEEN REPLICATED, IDENTIFYING THE POTENTIAL FOR A | | "LOCK UP" TO OCCUR. FURTHER ANALYSIS OF THE RADIATION DISPLAY UNIT (RDU) | | OPERATION HAS IDENTIFIED THAT A MOMENTARY LOSS OF AC POWER MAY RESULT IN A | | "LOCK UP." THIS WAS SIMULATED BY RAPIDLY TOGGLING THE AC POWER SWITCH ON | | AND OFF. BY RAPIDLY CYCLING THE AC POWER SWITCH, A "LOCK UP" CONDITION WAS | | PRODUCED APPROXIMATELY ONE OUT OF 10 TIMES. | | | | TO CORRECT THE ABOVE MENTIONED "LOCK UP" PROBLEM, VICTOREEN HAS IMPLEMENTED | | FIVE MODIFICATIONS TO THE TEST OF THE RDU. SEE FACSIMILE FOR THE FIVE | | MODIFICATIONS. | | | | MANDATORY UPGRADE IS REQUIRED ON THE PG&E/DIABLO CANYON 1,2, MODEL 960 | | MONITOR INSTALLATIONS, SAFETY RELATED RDU ESFAS OUTPUTS. | | | | SALEM 2, INDIAN POINT 2, AND THREE MILE ISLAND UNIT 1 HAVE MODEL 960 | | MONITOR INSTALLATIONS, BUT NO SAFETY RELATED ESFAS OUTPUTS AT RDU. NO | | UPGRADES ARE REQUIRED. R1DO (BARKLEY) & R4DO (POWERS) NOTIFIED. | | | | EVENT WRITE UP AND FACSIMILE SENT TO VERN HODGE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32059 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PILGRIM REGION: 1 |NOTIFICATION DATE: 04/01/97 | |UNIT: [1] [ ] [ ] STATE: MA |NOTIFICATION TIME: 03:59 [ET]| |RX TYPE: [1] GE-3 |EVENT DATE: 04/01/97 | +------------------------------------------------+EVENT TIME: 03:49[EST]| |NRC NOTIFIED BY: M. MANTSENFEL |LAST UPDATE DATE: 04/01/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: UNUSUAL EVENT +-----------------------------+ |10 CFR SECTION: |BARKLEY RDO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |MARSH EO | | |KNUPP FEMA | | |BARRETT IRD | | |AXELSON R1 | | |MIRAGLIA NRR | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNUSUAL EVENT DECLARED DUE TO LOSS OF ALL OFFSITE POWER. | | | | AT 0257 EST, THE 345kV OFFSITE POWER SUPPLY WAS LOST DUE TO A FAULT | | OFFSITE. THE LICENSEE HAD PREVIOUSLY STARTED AND LOADED BOTH SAFETY-RELATED | | EMERGENCY DIESEL GENERATORS AFTER OBSERVING PERTURBATIONS IN THE OFFSITE | | ELECTRICAL DISTRIBUTION SYSTEM. THE 24kV ALTERNATE OFFSITE POWER WAS LOST | | AT 0349 EST, AT WHICH TIME THE LICENSEE DECLARED AN UNUSUAL EVENT, DUE TO | | THE INABILITY TO PROVIDE OFFSITE ELECTRICAL POWER TO THE 'A5' AND 'A6' | | SAFETY-RELATED ELECTRICAL BUSSES. | | | | SHUTDOWN COOLING WAS LOST FOR APPROXIMATELY 10 MINUTES WHEN THE 345kV LINE | | WAS LOST, BUT HAS BEEN RESTORED [SEE EN 32060]. CURRENT REACTOR VESSEL | | WATER TEMPERATURE IS 89øF. SPENT FUEL POOL COOLING WAS ALSO LOST AT 0257 | | EST, AND HAS NOT YET BEEN RESTORED. THE LICENSEE REPORTED THAT THE CURRENT | | SPENT FUEL POOL TEMPERATURE IS 82øF, AND HAS NOT INCREASED APPRECIABLY. IT | | IS BEING MONITORED HOURLY. EFFORTS ARE UNDERWAY TO PROVIDE TEMPORARY POWER | | TO THE SPENT FUEL POOL COOLING PUMPS. THE BLACKOUT DIESEL GENERATOR IS | | RUNNING, BUT IS NOT LOADED AT THIS TIME. | | | | THE LICENSEE ESTIMATES THAT POWER WILL NOT BE RESTORED FOR ANOTHER 4-5 | | HOURS. THE NRC RESIDENT INSPECTORS HAVE BEEN INFORMED BY THE LICENSEE. | | | | * * * UPDATE 0410 4/1/97: CONFERENCE CALL REGARDING PILGRIM EVENT * * * | | PARTICIPANTS: MARSH (NRR EO), BARRETT (AEOD), BARKLEY (R1DO), AXELSON (R1), | | CONTE (R1), HEHL (R1), KAUFMAN (R1), LAURA (R1), KORONA (R1), MIRAGLIA | | (NRR), MOHSENI (RCT). AGENCY WILL ENTER MONITORING PHASE OF NORMAL MODE DUE | | TO CONTINUED INCLEMENT WEATHER IN THE VICINITY OF THE SITE. | | | | * * * UPDATE 1000 4/1/97: COMMISSIONERS' ASSISTANTS BRIEFING REGARDING | | PILGRIM EVENT AND RELATED SEABROOK EVENT [SEE EN 32061]. PARTICIPANTS: | | ROSS, BARRETT, OTHERS (AEOD); CHAFFEE, DENNIG, GOODWIN (NRR); BEECHER | | (OPA); KEELING (OCA); DEAN, JORDAN (EDO); HILTZ (JACKSON); BEALL | | (MCGAFFIGAN); SORENSON, FLEISHMAN (ROGERS); LOPEZ-OTIN, RADDATZ (DIAZ); | | MARKLEY (DICUS); ROGGE, CONTE, HEHL, RULAND, OTHERS (REGION I); KORONA, | | LAURA (PILGRIM SITE). | | | | * * * UPDATE ON 04/01/97 @ 2245 EST BY PERITO TAKEN BY MACKINNON * * * | | | | BOTH OFFSITE 345 KV POWER LINES HAVE BEEN ENERGIZED. LICENSEE IS PREPARING | | TO ENERGIZE THE STARTUP TRANSFORMER WITHIN THE NEXT COUPLE OF HOURS. R1DO | | (BARKLEY) & NRR EO (HANNON) NOTIFIED. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS UPDATE BY THE LICENSEE. | | | | * * * UPDATE 2400EST 4/1/97 FROM MIKE PERITO TO S.SANDIN * * * | | | | THE LICENSEE TERMINATED THE UNUSUAL EVENT AT 2345EST ON 4/1/97 AFTER | | RESTORING ALL SOURCES OF OFFSITE POWER. THE STARTUP TRANSFORMER IS IN THE | | PROCESS OF BEING RETURNED TO SERVICE AT THIS TIME. THE LICENSEE INFORMED | | STATE AND LOCAL AGENCIES AND THE NRC RESIDENT INSPECTOR. | | | | THE NRC EXITED THE MONITORING PHASE OF NORMAL MODE AT 2400EST. NOTIFIED | | R1DO(BARKLEY), EO(HANNON), FEMA(CANUPP) AND IRD(RUBIN). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32060 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PILGRIM REGION: 1 |NOTIFICATION DATE: 04/01/97 | |UNIT: [1] [ ] [ ] STATE: MA |NOTIFICATION TIME: 04:20 [ET]| |RX TYPE: [1] GE-3 |EVENT DATE: 04/01/97 | +------------------------------------------------+EVENT TIME: 02:57[EST]| |NRC NOTIFIED BY: M. MANTSENFEL |LAST UPDATE DATE: 04/01/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BARKLEY 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 N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | SHUTDOWN COOLING ISOLATION DUE TO LOSS OF OFFSITE POWER. | | | | THE SHUTDOWN COOLING SUCTION ISOLATION VALVE AUTOMATICALLY CLOSED WHEN | | OFFSITE POWER WAS LOST, CAUSING THE RUNNING SHUTDOWN COOLING PUMP TO TRIP. | | THE LICENSEE STATED THAT THE VALVE CLOSURE APPEARS TO BE SPURIOUS. THE | | SHUTDOWN COOLING SYSTEM WAS RESTORED WITHIN 10 MINUTES, WITH NO APPRECIABLE | | INCREASE IN REACTOR VESSEL TEMPERATURE. THE NRC RESIDENT INSPECTOR HAS BEEN | | INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32061 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SEABROOK REGION: 1 |NOTIFICATION DATE: 04/01/97 | |UNIT: [1] [ ] [ ] STATE: NH |NOTIFICATION TIME: 10:04 [ET]| |RX TYPE: [1] W-4-LP |EVENT DATE: 04/01/97 | +------------------------------------------------+EVENT TIME: 09:50[EST]| |NRC NOTIFIED BY: M. DAVID |LAST UPDATE DATE: 04/01/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BARKLEY 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 | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TECHNICAL SPECIFICATION REQUIRED SHUTDOWN DUE TO LOSS OF 2 OF 3 OFFSITE | | POWER SOURCES. | | | | THE LICENSEE IS COMMENCING A PLANT SHUTDOWN AT 3-5% PER HOUR DUE TO THE | | UNAVAILABILITY OF TWO OF THE THREE OFFSITE POWER SOURCES. THE LICENSEE | | REPORTED THAT THE LOCAL GRID IS EXPERIENCING SOME GRID VOLTAGE | | FLUCTUATIONS, BUT STATED THAT THE LOAD DISPATCHER HAS INFORMED THEM THAT | | THE GRID IS STABLE. THE NRC RESIDENT INSPECTOR WILL BE INFORMED BY THE | | LICENSEE. | | | | *** UPDATE ON 04/01/97 @ 1325 EST BY M. DAVID TAKEN BY MACKINNON *** | | | | SECOND INDEPENDENT OFFSITE POWER SUPPLY RESTORED TO SERVICE AT 1323 EST. | | LICENSEE EXITED TECHNICAL SPECIFICATION 3.8.1.1 (WHICH REQUIRES TWO | | INDEPENDENT OFFSITE POWER SOURCES). THE LICENSEE IS INCREASING REACTOR | | POWER FROM 95% TO 100%. LICENSEE IS WORKING ON RESTORING THE THIRD | | INDEPENDENT OFFSITE POWER SOURCE (SCOBIE LINE). R1DO (RICH BARKLEY) AND NRR | | EO (CHAFFEE) NOTIFIED. | | | | THE NRC RESIDENT INSPECTOR WAS INFORMED OF THIS UPDATE BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32062 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FARLEY REGION: 2 |NOTIFICATION DATE: 04/01/97 | |UNIT: [1] [ ] [ ] STATE: AL |NOTIFICATION TIME: 11:35 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 04/01/97 | +------------------------------------------------+EVENT TIME: 06:30[CST]| |NRC NOTIFIED BY: RAY MARTIN |LAST UPDATE DATE: 04/01/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DAVE VERRELLI RDO | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DURING STEAM GENERATOR TUBE INSPECTION IT WAS FOUND THAT MORE THAN 1% OF | | STEAM GENERATOR "1B" TUBES WERE FOUND TO BE DEFECTIVE. | | | | THE LICENSEE IS PERFORMING A STEAM GENERATOR (SG) INSPECTION PROGRAM AS | | PART OF THE CURRENT REFUELING OUTAGE ACTIVITIES. MORE THAN 1% OF THE SG | | TUBES IN THE "1B" STEAM GENERATOR HAVE BEEN FOUND TO BE DEFECTIVE. THUS THE | | "1B" SG INSPECTION RESULTS MEET THE C-3 CATEGORY (TECHNICAL SPECIFICATION | | 3.4.6.5.c). THE GENERAL AREA OF DEGRADATION IS IN THE SLUDGE PILE AND THE | | TUBE EXPANSION AREA OF THE TUBE SHEET. THE C-3 RESULTS PER TECH SPEC | | 4.4.6.5.c REQUIRE NOTIFICATION OF THE NRC PURSUANT TO 10CFR50.73. | | | | AT THIS TIME THE CAUSE IS THOUGHT TO BE A COMBINATION OF OUTSIDE DIAMETER | | AND INSIDE DIAMETER STRESS CORROSION CRACKING, PRIMARILY IN THE TUBE | | EXPANSION AREA OF THE TUBE SHEET AND SLUDGE PILE AREA. | | | | THE "1B" SG WAS FOUND TO BE IN CATEGORY C-3 AS A RESULT OF AN ON GOING | | INSPECTION. THE INSPECTION PROGRAM PERCENT COMPLETE FOR THE THREE SGs IS | | APPROXIMATELY "1A" 0%, "1B" 66%, & "1C" 0%. CURRENT PERCENT TUBES WITH | | DEFECTS IN THE "1B" SG IS 3.5% OF THE TUBES IN THE PLANNED INSPECTION. THE | | PLANNED INSPECTION INCLUDES 100% OF THE 3223 INSERVICE TUBES. CATEGORY C-3 | | IS MORE THAN 1% OF THE TUBES INSPECTED FOUND DEFECTIVE. | | | | PLANNED INSPECTION INCLUDES 100% OF ALL TUBES IN EACH SG. PURSUANT TO | | TECHNICAL SPECIFICATIONS PLUG OR REPAIR DEFECTIVE TUBES AS REQUIRED. IT IS | | ANTICIPATED THAT "1A" AND "1C" SGs MAY BE FOUND TO MEET THE CONDITIONS OF | | CATEGORY C-3. THIS INFORMATION WILL BE INCLUDED IN A LICENSEE EVENT REPORT. | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32063 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 04/01/97 | |UNIT: [2] [ ] [ ] STATE: NY |NOTIFICATION TIME: 14:44 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 04/01/97 | +------------------------------------------------+EVENT TIME: 14:00[EST]| |NRC NOTIFIED BY: CORNAX |LAST UPDATE DATE: 04/01/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RICH BARKLEY RDO | |AESS 50.72(b)(1)(v) EMERGENCY SIREN INOP | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | GREATER THAN 10% OF THE ALERT NOTIFICATION SIRENS ARE INOPERABLE DUE TO | | STORM INDUCED POWER OUTAGES. | | | | DUE TO STORM INDUCED OUTAGES IN THE FOUR COUNTIES AROUND THE PLANT, GREATER | | THAN 10% OF THE ALERT NOTIFICATION SYSTEM SIRENS HAVE BEEN DECLARED | | INOPERABLE. THE INOPERABLE SIRENS ARE AS FOLLOWS: 30 OF 77 IN WESTCHESTER | | COUNTY, 9 OF 50 IN ROCKLAND, 9 OF 16 IN ORANGE AND 8 OF 10 IN PUTNAM | | COUNTIES. THIS IS DUE TO LOCAL POWER OUTAGES. IT IS ESTIMATED THAT POWER | | WILL BE RESTORED TO THE SIRENS IN 8 TO 12 HOURS. ALL COUNTY EMERGENCY | | MANAGEMENT DIRECTORS HAVE BEEN NOTIFIED. BACKUP ROUTE ALERTING PLANS HAVE | | BEEN IMPLEMENTED. | | | | THE NRC RESIDENT INSPECTOR WILL BE NOTIFIED BY THE LICENSEE OF THIS EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32064 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 04/01/97 | |UNIT: [ ] [3] [ ] STATE: NY |NOTIFICATION TIME: 15:56 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 04/01/97 | +------------------------------------------------+EVENT TIME: 14:57[EST]| |NRC NOTIFIED BY: DAVIS |LAST UPDATE DATE: 04/01/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RICH BARKLEY RDO | |AESS 50.72(b)(1)(v) EMERGENCY SIREN INOP | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 3 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | POSSIBLY UP TO 30% OF THE ALERT NOTIFICATION SIRENS ARE INOPERABLE DUE TO | | STORM INDUCED POWER OUTAGES. | | | | THE CONTROL ROOM WAS NOTIFIED BY CONSOLIDATED EDISON THAT POSSIBLY UP TO | | 30% OF THEIR ALERT NOTIFICATION SIRENS WERE INOPERABLE DUE TO STORM INDUCED | | POWER OUTAGES. CONSOLIDATED EDISON IS TAKING CORRECTIVE ACTIONS TO RESTORE | | POWER TO THE INOPERABLE SIRENS. THE TIME WHEN ALL SIRENS WILL BE RESTORED | | TO SERVICE HAS NOT YET BEEN IDENTIFIED. | | | | THE NRC RESIDENT INSPECTOR WILL BE NOTIFIED BY THE LICENSEE OF THIS EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32065 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 04/01/97 | |UNIT: [1] [ ] [ ] STATE: CT |NOTIFICATION TIME: 16:43 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 04/01/97 | +------------------------------------------------+EVENT TIME: 16:15[EST]| |NRC NOTIFIED BY: KLINIKOWSKI |LAST UPDATE DATE: 04/01/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RICH BARKLEY RDO | |AINC 50.72(b)(2)(iii)(C) POT UNCNTRL RAD REL | | |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 +------------------------------------------------------------------------------+ | LOSS OF SECONDARY CONTAINMENT COULD OCCUR DURING PURGING/VENTING OPERATIONS | | USING THE 18" ATMOSPHERIC CONTROL VALVES. | | | | DURING PRIMARY CONTAINMENT VENT AND PURGE OPERATIONS USING THE STANDBY GAS | | TREATMENT SYSTEM, A POSSIBILITY EXISTS THAT THE SEQUENCING OF THE | | ATMOSPHERIC CONTROL AND STANDBY GAS TREATMENT SYSTEM (SG-1A & B) WILL | | CREATE A TEMPORARY FLOW PATH BETWEEN THE PRIMARY CONTAINMENT AND THE | | REACTOR BUILDING PRIOR TO ISOLATION OF THE ATMOSPHERIC CONTROL VALVES. THE | | FLOW ESCAPING INTO THE REACTOR BUILDING THROUGH THIS PATH COULD BE | | SUFFICIENT TO LIFT THE BLOW OUT PANELS AND CAUSE A LOSS OF SECONDARY | | CONTAINMENT, ESPECIALLY IF PURGING/VENTING WAS CONDUCTED WITH THE 18" | | ATMOSPHERIC CONTROL VALVES. THIS CONDITION WAS DISCOVERED DURING A REVIEW | | OF STANDBY GAS TREATMENT VENT/PURGE OPERATIONS FOR PTSCR 1-11-94 WHILE | | PREPARING FOR A TECHNICAL SPECIFICATION CHANGE REQUEST TO ALLOW | | PURGING/VENTING OF PRIMARY CONTAINMENT THROUGH THE REACTOR BUILDING | | VENTILATION SYSTEM (WHEN PRIMARY CONTAINMENT INTEGRITY IS REQUIRED). | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED BY THE LICENSEE OF THIS EVENT. | +------------------------------------------------------------------------------+