U.S. Nuclear Regulatory Commission Operations Center Event Reports For 03/18/97 - 03/19/97 ** EVENT NUMBERS ** 31964 31965 31966 31967 31968 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31964 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: LASALLE REGION: 3 |NOTIFICATION DATE: 03/18/97 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 01:53 [ET]| |RX TYPE: [1] GE-5,[2] GE-5 |EVENT DATE: 03/17/97 | +------------------------------------------------+EVENT TIME: 23:00[CST]| |NRC NOTIFIED BY: DAVE SHELDON |LAST UPDATE DATE: 03/18/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PATRICK HILAND RDO | |ADAS 50.72(b)(2)(i) DEG/UNANALYZED COND | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - FIRE PROTECTION SYSTEM HANGERS FOUND MISSING FROM CABLE SPREADING ROOM - | | | | UNIT 1 IS IN CONDITION 4 (COLD SHUTDOWN) IN A MAINTENANCE OUTAGE THAT BEGAN | | IN SEPTEMBER 1996, AND UNIT 2 IS DEFUELED IN CONDITION 5 (REFUELING) IN A | | REFUELING OUTAGE THAT BEGAN IN SEPTEMBER 1996. ON MARCH 17, 1997, THE | | LICENSEE DISCOVERED SEVERAL MISSING OR DISCONNECTED PIPE SUPPORTS FOR THE | | 1-1/4 TO 3-INCH DIAMETER FIRE PROTECTION SYSTEM PIPING IN THE UNIT 1 | | DIVISION 2 ELECTRICAL CABLE SPREADING ROOM. ALTHOUGH THE FIRE PROTECTION | | SYSTEM FOR THIS ROOM IS OPERABLE FROM A FIRE PROTECTION STANDPOINT, | | LICENSEE ENGINEERING PERSONNEL ARE UNCERTAIN OF THE CAPABILITY OF THE | | PIPING SYSTEM TO REMAIN INTACT DURING A SEISMIC EVENT. | | | | AS A RESULT, THE LICENSEE CONSERVATIVELY CONSIDERS ALL UNIT 1 DIVISION 2 | | SYSTEMS AND COMPONENTS TO BE INOPERABLE. THESE SYSTEMS AND COMPONENTS, | | CURRENTLY INOPERABLE FOR SCHEDULED MAINTENANCE ACTIVITIES, INCLUDE THE 'B' | | AND 'C' TRAINS OF THE RESIDUAL HEAT REMOVAL SYSTEM, 'A' TRAIN OF THE | | CONTROL ROOM VENTILATION SYSTEM, 'A' TRAIN OF THE AUXILIARY ELECTRICAL | | EQUIPMENT ROOM VENTILATION SYSTEM, STANDBY GAS TREATMENT SYSTEM, AND | | HYDROGEN RECOMBINER SYSTEM. | | | | LICENSEE ENGINEERING PERSONNEL ARE PERFORMING ANALYSES TO DETERMINE THE | | ADEQUACY OF THE AS-FOUND UNIT 1 DIVISION 2 FIRE PROTECTION SYSTEM PIPE | | SUPPORTS AND PLAN TO INSTALL DISCONNECTED AND/OR MISSING SUPPORTS. LICENSEE | | PERSONNEL ARE INSPECTING FIRE PROTECTION SYSTEM PIPING IN THE REMAINING | | UNIT 1 SAFETY-RELATED AREAS AND THE FIRE PROTECTION SYSTEM PIPING IN UNIT 2 | | SAFETY-RELATED AREAS FOR SIMILAR DISCREPANCIES. | | | | THE LICENSEE WILL SUBMIT AN LER AND WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31965 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MCGUIRE REGION: 2 |NOTIFICATION DATE: 03/18/97 | |UNIT: [1] [ ] [ ] STATE: NC |NOTIFICATION TIME: 08:33 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 03/18/97 | +------------------------------------------------+EVENT TIME: 07:45[EST]| |NRC NOTIFIED BY: DENNIS McCORKLE |LAST UPDATE DATE: 03/18/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |AL BELISLE RDO | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | | |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 | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | HISTORICAL OPERABILITY CONCERN REGARDING A FEEDWATER CONTAINMENT ISOLATION | | VALVE FOR THE 'D' STEAM GENERATOR | | | | FEEDWATER ISOLATION VALVE 1CF-26 (A CONTAINMENT ISOLATION VALVE FOR STEAM | | GENERATOR 'D') IS REQUIRED TO CLOSE WHEN ANY OF THE FOLLOWING THREE | | CONDITIONS OCCUR: (1) RECEIPT OF A SAFETY INJECTION SIGNAL TO PREVENT | | CONTINUED FEEDWATER ADDITION TO A FAULTED STEAM GENERATOR FOLLOWING A STEAM | | LINE OR FEEDWATER LINE BREAK, (2) SAFETY-RELATED LOW T(ave) WITH A REACTOR | | TRIP TO PREVENT OVER COOLING OF THE REACTOR COOLING SYSTEM, AND (3) A | | HIGH-HIGH LEVEL IN THE 'DOGHOUSES' TO PREVENT FLOODING. THIS VALVE IS ALSO | | SUBJECT TO TECHNICAL SPECIFICATION 3/4.6.3 AND 10 CFR PART 50, APPENDIX | | 'A,' TO GENERAL DESIGN CRITERIA 57. | | | | AT 0220 ON NOVEMBER 27, 1996, VALVE 1CF-26 WAS DECLARED INOPERABLE BUT WAS | | NOT LOGGED UNDER CONTAINMENT ISOLATION TECHNICAL SPECIFICATION 3.6.3. THE | | VALVE REMAINED OPEN FOR EXTENDED PERIODS OF TIME IN EXCESS OF THE ACTION | | STATEMENT FOR TECHNICAL STATEMENT 3.6.3. | | | | AT THIS TIME, THE UNIT IS NOT IN A TECHNICAL SPECIFICATION LIMITING | | CONDITION FOR OPERATION AS A RESULT OF THIS ISSUE DUE TO THE CURRENT MODE | | OF OPERATION. UNIT 1 IS CURRENTLY SHUTDOWN AND DEFUELED AS PART OF A | | REFUELING OUTAGE. IT WAS OPERATING AT 100% REACTOR POWER WHEN THE EVENT | | OCCURRED. THIS EVENT WAS DETERMINED TO BE REPORTABLE AT 0745 ON MARCH 18, | | 1997. | | | | IN ACCORDANCE WITH 10 CFR 50.73 (a)(2)(v) AND 10 CFR 50 (a)(2)(ii), THE | | LICENSEE PLANS TO ISSUE A LICENSEE EVENT REPORT. THE LICENSEE ALSO PLANS | | TO NOTIFY THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31966 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: POINT BEACH REGION: 3 |NOTIFICATION DATE: 03/18/97 | |UNIT: [1] [2] [ ] STATE: WI |NOTIFICATION TIME: 12:34 [ET]| |RX TYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 03/18/97 | +------------------------------------------------+EVENT TIME: 09:34[CST]| |NRC NOTIFIED BY: KING |LAST UPDATE DATE: 03/18/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |HILAND RDO | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | INFORMATION CALL RELATED TO ONSITE FATALITY | | | | A CONTRACT EMPLOYEE IN THE CLEAN MAINTENANCE SHOP SUFFERED AN APPARENT | | HEART ATTACK. THE INDIVIDUAL WAS TRANSPORTED OFFSITE TO THE LOCAL HOSPITAL | | WHERE HE WAS PRONOUNCED DEAD. THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31967 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FARLEY REGION: 2 |NOTIFICATION DATE: 03/18/97 | |UNIT: [1] [2] [ ] STATE: AL |NOTIFICATION TIME: 13:33 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 03/18/97 | +------------------------------------------------+EVENT TIME: 12:30[CST]| |NRC NOTIFIED BY: DON GRISSETTE |LAST UPDATE DATE: 03/18/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRUNO URYC 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DISCOVERY THAT WESTINGHOUSE 600-VOLT SWITCHGEAR BREAKERS HAVE NOT BEEN | | SEISMICALLY QUALIFIED IN ANY POSITION OTHER THAN THE 'CONNECTED' OR | | 'DISCONNECTED' POSITIONS | | | | ON MARCH 18, 1997, AN ENGINEERING EVALUATION CONCLUDED THAT A CONDITION | | EXISTED THAT ALONE COULD HAVE PREVENTED THE FULFILLMENT OF THE SAFETY | | FUNCTION OF SYSTEMS NEEDED TO SHUTDOWN THE REACTOR AND MAINTAIN IT IN A | | SHUTDOWN CONDITION. WESTINGHOUSE 600-VOLT SWITCHGEAR BREAKERS HAVE NOT | | BEEN SEISMICALLY QUALIFIED IN ANY POSITION OTHER THAN THE 'CONNECTED' OR | | 'DISCONNECTED' POSITIONS. THE POTENTIAL EXISTS FOR IMPACT FROM | | UNRESTRAINED BREAKERS IN THE 'REMOVED' POSITION TO CAUSE RELAY CHATTER IN | | ADJACENT BREAKER CUBICLES THAT COULD COMPROMISE SAFETY-RELATED EQUIPMENT | | OPERATIONS. ADMINISTRATIVE CONTROLS HAVE BEEN PROVIDED TO PREVENT THIS | | CONDITION FROM OCCURRING. THIS NOTIFICATION IS TO ADDRESS PAST UNKNOWN | | CONDITIONS. | | | | THE CAUSE OF THE EVENT IS CONSIDERED TO BE PERSONNEL ERROR IN THAT THE | | ORIGINAL DESIGNERS FAILED TO CONSIDER THE SEISMIC QUALIFICATION OF THESE | | BREAKERS IN OTHER THAN THE 'CONNECTED' OR 'DISCONNECTED' POSITIONS. THE | | AFFECTED SAFETY-RELATED 600-VOLT SWITCHGEAR BREAKERS ARE CURRENTLY IN THE | | 'CONNECTED' OR 'DISCONNECTED' POSITION OR ARE COMPLETELY REMOVED FROM THE | | BREAKER CUBICLES. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 31968 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 03/18/97 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 22:52 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 03/18/97 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 00:00[CST]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 03/18/97 | | CITY: PADUCAH REGION: 3 +-----------------------------+ | COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION| |LICENSE#: GDP-1 AGREEMENT: Y |HILAND RDO | | DOCKET: 0707001 | | +------------------------------------------------+ | |NRC NOTIFIED BY: CAGE | | |HQ OPS OFFICER: BOB STRANSKY | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |OCBB 76.120(c)(2)(ii) EQUIP DISABLED/FAILS | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | 24-HOUR REPORT - TWO OF THREE CRITICALITY DETECTION MODULES INOPERABLE | | | | THE FOLLOWING IS TEXT OF A FACSIMILE RECEIVED FROM THE CERTIFICATE HOLDER: | | | | "DURING A WALK-THROUGH OF C-337-A BY THE SENIOR NRC RESIDENT INSPECTOR AND | | THE FACILITY MANAGER, IT WAS DISCOVERED THAT TWO OF THE THREE DETECTION | | MODULES IN THE CRITICALITY ACCIDENT ALARM SYSTEM FOR 'N' CLUSTER WERE FOUND | | TO HAVE METER INDICATIONS LESS THAN 9.5 mR. A METER READING OF 9.5 mR OR | | GREATER IS REQUIRED ON AT LEAST TWO OF THE MODULES FOR THE CLUSTER TO BE | | OPERABLE. TSR LCO 2.2.4.3.a REQUIRES THAT 'THE CRITICALITY ACCIDENT ALARM | | SHALL BE OPERABLE IN AREAS, EQUIPMENT, OR PROCESSES WHICH CONTAIN GREATER | | THAN 700 GRAMS OF U235 AT AN ENRICHMENT GREATER THAN OR EQUAL TO 1.0 WT % | | U235.' THIS CLUSTER WAS DETERMINED TO BE INOPERABLE. AS REQUIRED BY TSR, | | LCO ACTIONS WERE IMPLEMENTED IMMEDIATELY. THEY INCLUDE: A.1.1 DISCONTINUE | | MOVEMENT OF CYLINDERS CONTAINING UF6 ENRICHED TO GREATER THAN OR EQUAL TO | | 1.0 WT % U235; A.1.2 PLACE AUTOCLAVES PROCESSING CYLINDERS CONTAINING UF6 | | ENRICHED TO GREATER THAN OR EQUAL TO 1.0 WT % U235 IN MODE 2; A.1.3 | | DISCONTINUE MOVEMENT OF URANIUM ENRICHED TO GREATER THAN OR EQUAL TO 1.0 WT | | % U235; A.2.1 EVACUATE AREA WITHIN THE AREA APPLICABLE TO THIS LCO NOT | | COVERED BY CRITICALITY ACCIDENT DETECTION; A.2.2 RESTRICT ACCESS TO AREA | | EVACUATED IN A.2.1; AND A.3 PROVIDE PERSONNEL ALLOWED INTO THE AREA THAT | | WOULD BE RESTRICTED UNDER ACTION A.2.1 WITH AN ALTERNATE MEANS OF | | CRITICALITY ALARM NOTIFICATION, SUCH AS A DEVICE THAT WILL ALARM ON SENSING | | A 10 mR/HR DOSE RATE -- IMMEDIATELY. ACTION B.1.2 RESTORE CRITICALITY | | ACCIDENT DETECTION TO OPERABLE STATUS -- PRIOR TO REINITIATING ACTIVITIES. | | THE ACTIONS REQUIRING IMMEDIATE ACTION WERE COMPLETED AT 1455 [CST]." | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED OF THIS NOTIFICATION. | +------------------------------------------------------------------------------+