U.S. Nuclear Regulatory Commission Operations Center Event Reports For 04/28/97 - 04/29/97 ** EVENT NUMBERS ** 32055 32184 32208 32226 32232 32233 32234 32235 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32055 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SEQUOYAH REGION: 2 |NOTIFICATION DATE: 03/31/97 | |UNIT: [1] [2] [ ] STATE: TN |NOTIFICATION TIME: 14:01 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 03/31/97 | +------------------------------------------------+EVENT TIME: 13:07[EST]| |NRC NOTIFIED BY: SIMMONS |LAST UPDATE DATE: 04/28/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DAVE VERRELLI RDO | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | | |NLCO TECH SPEC LCO A/S | | |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 N 0 REFUELING | 0 REFUELING | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | BOTH TRAINS OF THE AUXILIARY BUILDING GAS TREATMENT SYSTEM (ABGTS) WERE | | DECLARED INOPERABLE. UNIT 2 ENTERED TECHNICAL SPECIFICATION 3.0.3, AND | | UNIT 1 STOPPED MOVING FUEL PER TECHNICAL SPECIFICATION 3.9.12. | | | | AUXILIARY BUILDING SECONDARY CONTAINMENT ENCLOSURE (ABSCE) BREACH OF 78.54 | | SQUARE INCHES EXCEEDS THE MAXIMUM ALLOWABLE BREACH ALLOWED PER PROCEDURE, | | WHICH IS CURRENTLY 50.5 SQUARE INCHES. UNIT 1 IS IN MODE 6 (REFUELING), | | AND 50.2 SQUARE INCHES WAS ALLOCATED FOR ABSCE BREACHES ASSOCIATED WITH | | OUTAGE ACTIVITIES. THE ADDITIONAL BREACH OF 78.54 SQUARE INCHES RAISES THE | | TOTAL ABSCE BREACH TO 128.74 SQUARE INCHES. BECAUSE OF THIS, BOTH TRAINS | | OF ABGTS WERE DECLARED INOPERABLE AT 1307 EST. | | | | UNIT 2 ENTERED TECHNICAL SPECIFICATION 3.0.3 FOR NONCOMPLIANCE WITH | | TECHNICAL SPECIFICATION LIMITING CONDITION OF OPERATION 3.7.8 (ABGTS DURING | | MODES 1, 2, 3, AND 4), AND UNIT 1 STOPPED FUEL MOVEMENT PER TECHNICAL | | SPECIFICATION 3.9.12. THE SHIFT SUPERVISOR FOR UNIT 2 IS CURRENTLY | | DISCUSSING A PLANT SHUTDOWN WITH HIS SHIFT CREW. UNIT 2 REACTOR POWER WILL | | BE DECREASED SLOWLY. AT 2007 EST, UNIT 2 IS REQUIRED TO BE IN MODE 3 (HOT | | STANDBY). ALL EMERGENCY CORE COOLING SYSTEMS AND THE EMERGENCY DIESEL | | GENERATORS ARE FULLY OPERABLE. ENGINEERING IS CURRENTLY DETERMINING IF THE | | ABGTS CAN HANDLE AN ABSCE BREACH OF 128.74 SQUARE INCHES. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. | | | | * * * 1529 MARCH 31, 1997, UPDATE FROM SIMMONS TAKEN BY MACKINNON * * * | | | | THE LICENSEE COMMENCED A UNIT SHUTDOWN PER TECHNICAL SPECIFICATION 3.0.3 AT | | 1407 EST. REACTOR POWER HAS BEEN REDUCED TO 98%. AT THIS TIME, A COMPLETE | | SHUTDOWN IS NOT EXPECTED TO BE REQUIRED BECAUSE EFFORTS ARE UNDERWAY TO | | RETURN THE ABGTS TO AN OPERABLE CONDITION. | | | | THE R2DO (DAVE VERRELLI) WAS NOTIFIED BY THE NRC OPERATIONS CENTER. THE | | NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. | | | | * * * 1631 MARCH 31, 1997, UPDATE FROM SIMMONS TAKEN BY MACKINNON * * * | | | | THE ABGTS WAS DECLARED OPERABLE AT 1620 EST. UNIT 2 EXITED TECHNICAL | | SPECIFICATION 3.0.3 AND TECHNICAL SPECIFICATION 3.7.8. REACTOR POWER FOR | | UNIT 2 HAD BEEN DECREASED TO 94%. REACTOR POWER WILL BE INCREASED TO 100%. | | UNIT 1 EXITED TECHNICAL SPECIFICATION 3.9.12 AT 1620 EST. | | | | THE R2DO (DAVE VERRELLI) WAS NOTIFIED BY THE NRC OPERATIONS CENTER. THE | | NRC RESIDENT INSPECTOR WAS NOTIFIED BY THE LICENSEE OF THIS UPDATE. | | | | * * * 1422 APRIL 28, 1996, UPDATE FROM WEBB RECEIVED BY TROCINE * * * | | | | THE LICENSEE IS RETRACTING THIS EVENT NOTIFICATION. | | | | THE LICENSEE DETERMINED THAT SUFFICIENT MARGIN EXISTED TO ALLOW CONTINUED | | OPERABILITY OF THE ABGTS DUE TO THE PERFORMANCE OF NEW CALCULATIONS BASED | | ON ACTUAL PLANT CONDITIONS AT THE TIME OF THE EVENT. THE TOTAL BREACHED | | AREA WAS 113.49 SQUARE INCHES, AND THE NEW DATA SUPPORTS A MAXIMUM OF 122.6 | | SQUARE INCHES. AS A RESULT, THE LICENSEE IS RETRACTING THIS EVENT | | NOTIFICATION. | | | | THE LICENSEE PLANS TO NOTIFY THE NRC RESIDENT INSPECTOR. THE NRC | | OPERATIONS CENTER NOTIFIED THE R2DO (BELISLE). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32184 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BRAIDWOOD REGION: 3 |NOTIFICATION DATE: 04/21/97 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 09:32 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 04/21/97 | +------------------------------------------------+EVENT TIME: 07:15[CDT]| |NRC NOTIFIED BY: R YURKOVIH |LAST UPDATE DATE: 04/28/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MONTE PHILLIPS 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 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | GREATER THAN 1% OF UNIT 1 STEAM GENERATOR #1B TUBES ARE DEFECTIVE. | | | | ON 04/01/97, THE LICENSEE INITIATED AN INSERVICE INSPECTION OF 100% OF THE | | TUBES OF UNIT 1 STEAM GENERATOR #1B. | | | | TECHNICAL SPECIFICATION SURVEILLANCE REQUIREMENT 4.4.5.2.C REQUIRES THAT | | THE RESULTS OF EACH SAMPLE INSPECTION BE CLASSIFIED INTO 1 OF 3 CATEGORIES. | | A STEAM GENERATOR WILL BE CLASSIFIED AS CATEGORY C-3 IF MORE THAN 10% OF | | THE TOTAL TUBES INSPECTED ARE DEGRADED OR MORE THAN 1% OF THE INSPECTED | | TUBES ARE DEFECTIVE. A STEAM GENERATOR TUBE IS CONSIDERED DEGRADED IF | | IT HAS AN IMPERFECTION OF GREATER THAN OR EQUAL TO 20% NOMINAL TUBE WALL | | THICKNESS. A STEAM GENERATOR TUBE IS CONSIDERED DEFECTIVE IF IT HAS AN | | IMPERFECTION GREATER THAN OR EQUAL TO 40% NOMINAL TUBE WALL OR EXCEEDS THE | | 3.0 VOLT INTERIM PLUGGING CRITERIA. | | | | ON 04/21/97, THE RESULTS OF THE SAMPLE INSPECTION CAUSED STEAM GENERATOR 1B | | TO BE CLASSIFIED AS CATEGORY C-3 BASED ON GREATER THAN 1% OF THE INSERVICE | | TUBES BEING DEFECTIVE. THE NUMBER OF INSERVICE TUBES IS 4154 WITH THE | | ACTUAL NUMBER OF DEFECTIVE TUBES BEING 62. THESE TUBES ARE CONSIDERED | | DEFECTIVE MAINLY DUE TO CIRCUMFERENTIAL CRACK-LIKE INDICATIONS AT THE HOT | | LEG TOP-OF-TUBESHEET ROLL TRANSITION REGION AND AXIAL CRACK-LIKE | | INDICATIONS WITHIN THE HOT LEG TUBE SUPPORT PLATES GREATER THAN 3.0 VOLTS | | INTERIM PLUGGING CRITERIA. STEAM GENERATORS #1A, #1C, AND #1D DATA HAS NOT | | BEEN ANALYZED AT THIS TIME. ALL FOUR UNIT 1 STEAM GENERATORS ARE SCHEDULED | | TO BE REPLACED IN 1998. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE AT 0953 ON 04/23/97 FROM ALEXANDER TAKEN BY JOLLIFFE * * * | | | | GREATER THAN 1% OF UNIT 1 STEAM GENERATOR #1A TUBES ARE DEFECTIVE. | | | | ON 04/01/97, A STEAM GENERATOR TUBE INSERVICE INSPECTION WAS INITIATED ON | | UNIT 1 IN ACCORDANCE WITH TECHNICAL SPECIFICATION REQUIREMENT 4.4.5.0 AND | | 100% OF THE INSERVICE TUBES WERE SELECTED FOR INSPECTION. THE ABOVE | | DESCRIPTION OF CATEGORY C-3 WAS CORRECTED TO STATE THAT STEAM GENERATOR #1A | | WILL BE CLASSIFIED AS CATEGORY C-3 IF MORE THAN 10% OF THE TOTAL TUBES | | INSPECTED ARE DEGRADED OR MORE THAN 1% OF INSPECTED TUBES ARE DEFECTIVE. | | | | AT 0730 CDT ON 04/23/97, THE RESULTS OF THE SAMPLE INSPECTION CAUSED STEAM | | GENERATOR #1A TO BE CLASSIFIED AS CATEGORY C-3 BASED ON GREATER THAN 1% OF | | THE INSERVICE TUBES BEING DEFECTIVE. THE NUMBER OF INSERVICE TUBES IS 3986 | | WITH THE ACTUAL NUMBER OF DEFECTIVE TUBES BEING 124. THESE TUBES ARE | | CONSIDERED DEFECTIVE MAINLY DUE TO CIRCUMFERENTIAL CRACK-LIKE INDICATIONS | | AT THE HOT LEG TOP-OF-TUBESHEET ROLL TRANSITION REGION AND AXIAL CRACK-LIKE | | INDICATIONS WITHIN THE HOT LEG TUBE SUPPORT PLATES GREATER THAN THE 3.0 | | VOLT INTERIM PLUGGING CRITERIA. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. THE HOO NOTIFIED R3DO | | MONTE PHILLIPS. | | | | * * * UPDATE AT 2308 ON 04/23/97 FROM ALEXANDER TAKEN BY GOULD * * * | | | | GREATER THAN 1% OF UNIT 1 STEAM GENERATOR #1D TUBES ARE DEFECTIVE. | | | | AT 2100 CDT ON 04/23/97, THE RESULTS OF THE SAMPLE INSPECTION CAUSED STEAM | | GENERATOR #1D TO BE CLASSIFIED AS CATEGORY C-3 BASED ON GREATER THAN 1% OF | | THE INSERVICE TUBES BEING DEFECTIVE. THE NUMBER OF INSERVICE TUBES IS 4153 | | WITH THE ACTUAL NUMBER OF DEFECTIVE TUBES BEING 179. THESE TUBES ARE | | CONSIDERED DEFECTIVE MAINLY DUE TO CIRCUMFERENTIAL CRACK-LIKE INDICATIONS | | AT THE HOT LEG TOP-OF-TUBESHEET ROLL TRANSITION REGION AND AXIAL CRACK-LIKE | | INDICATIONS WITHIN THE HOT LEG TUBE SUPPORT PLATES GREATER THAN THE 3.0 | | VOLT INTERIM PLUGGING CRITERIA. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. THE HOO NOTIFIED R3DO | | MONTE PHILLIPS. | | | | * * * UPDATE AT 0022 ON 04/28/97 FROM ALEXANDER TAKEN BY JOLLIFFE * * * | | | | GREATER THAN 1% OF UNIT 1 STEAM GENERATOR #1C TUBES ARE DEFECTIVE. | | | | AT 2230 CDT ON 04/27/97, THE RESULTS OF THE SAMPLE INSPECTION CAUSED STEAM | | GENERATOR #1C TO BE CLASSIFIED AS CATEGORY C-3 BASED ON GREATER THAN 1% OF | | THE INSERVICE TUBES BEING DEFECTIVE. THE NUMBER OF INSERVICE TUBES IS 3662 | | WITH THE ACTUAL NUMBER OF DEFECTIVE TUBES BEING 101. THESE TUBES ARE | | CONSIDERED DEFECTIVE MAINLY DUE TO CIRCUMFERENTIAL CRACK-LIKE INDICATIONS | | AT THE HOT LEG TOP-OF-TUBESHEET ROLL TRANSITION REGION AND AXIAL CRACK-LIKE | | INDICATIONS WITHIN THE HOT LEG TUBE SUPPORT PLATES GREATER THAN THE 3.0 | | VOLT INTERIM PLUGGING CRITERIA. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. THE HOO NOTIFIED R3DO | | MONTE PHILLIPS. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 32208 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: WESTERN ATLAS LOGGING SERVICES |NOTIFICATION DATE: 04/23/97 | | CITY: BATON ROUGE REGION: 4 |NOTIFICATION TIME: 17:18 [ET]| | COUNTY: STATE: LA |EVENT DATE: 04/23/97 | |LICENSE#: LA-2187-LO1 AGREEMENT: Y |EVENT TIME: 16:45[CDT]| | DOCKET: |LAST UPDATE DATE: 04/28/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |ELMO COLLINS RDO | | |JOHN HICKEY, NMSS EO | +------------------------------------------------+FRANK CONGEL, AEOD IRD | |NRC NOTIFIED BY: LARKIN-NRC STATE PROGRAMS | | |HQ OPS OFFICER: CHAUNCEY GOULD | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NAGR AGREEMENT STATE | | |NINF INFORMATION ONLY | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | POTENTIAL OCCUPATIONAL EXPOSURE TO AN INDIVIDUAL AT THE WESTERN ATLAS | | LOGGING SERVICES FACILITY IN BROUSSARD, LOUISIANA | | | | THE POTENTIAL EXPOSURE OCCURRED ON APRIL 17, 1997, WHEN A TEMPORARY | | CONTRACT EMPLOYEE SERVICED A SOURCE CONTAINER THAT CONTAINED A 5-CURIE | | AMERICIUM/BERYLLIUM NEUTRON SOURCE. THERE WAS NO RADIOACTIVE MATERIAL | | RELEASE, BUT THE EMPLOYEE HANDLED THE SOURCE AND PUT IT IN HIS POCKET. THE | | DOSE TO THE INDIVIDUAL IS CALCULATED TO BE 4 AND 6 REM ACCORDING TO AN OAK | | RIDGE NATIONAL LABORATORY CONSULTANT. BLOOD WORK HAS BEEN PERFORMED | | LOCALLY AND THE RESULTS WERE SENT TO THE OAK RIDGE NATIONAL LABORATORY | | CONSULTANT. THE LICENSEE IS STILL INVESTIGATING THIS INCIDENT AND PLANS TO | | PREPARE A MORE DETAILED REPORT. | | | | * * * 1600 APRIL 28, 1997, UPDATE BY TROCINE * * * | | | | A COMMISSIONERS' ASSISTANTS BRIEFING WAS CONDUCTED WITH THE LOUISIANA | | DEPARTMENT OF RADIATION CONTROL AT 1600 EDT ON APRIL 28, 1997. | | NOTIFICATIONS INCLUDED (*INDICATES OFFICE DID NOT PARTICIPATE): AEOD | | (*ROSS); IRD MANAGER (BAILEY, *BARRETT, AND *CONGEL); JACKSON (SMITH); | | ROGERS (SORENSEN); DICUS (TAYLOR); DIAZ (RADDATZ); McGAFFIGAN (SCHLUETER); | | DEDO (JORDAN); DEDR REGION (BIAMONTE); DEDR MATERIALS (ENG); NMSS EO (COMBS | | AND COOL); NMSS (HOLAHAN, PAPERIELLO, PICCONE, AND SMITH); R4DO (*HARRELL); | | REGION 4 (HACKNEY, HOWELL, LEONARDI, MERSCHOFF, SCARANO, AND WHITTEN); PAO | | (BEECHER); CAO (GERKE AND MADDEN); SECY (HART); STATE PROGRAMS (BANGART, | | LARKINS, AND LOHAUS); INTERNATIONAL PROGRAMS (UPSHAW); AND THE LOUISIANA | | DEPARTMENT OF RADIATION CONTROL (RICHARD PENROD AND BILL SPELL). | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32226 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BIG ROCK POINT REGION: 3 |NOTIFICATION DATE: 04/25/97 | |UNIT: [1] [ ] [ ] STATE: MI |NOTIFICATION TIME: 21:36 [ET]| |RX TYPE: [1] GE-1 |EVENT DATE: 04/25/97 | +------------------------------------------------+EVENT TIME: 18:30[EDT]| |NRC NOTIFIED BY: MADISON |LAST UPDATE DATE: 04/28/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PHILLIPS 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 +------------------------------------------------------------------------------+ | VENT VALVE ON CONTROL ROD DRIVE SYSTEM PIPING COULD LIFT UNDER HIGH REACTOR | | PRESSURE CONDITION. | | | | DURING A REVIEW OF NRC INFORMATION NOTICE 96-68, THE LICENSEE HAS | | DETERMINED THAT A VENT VALVE ON THE CONTROL ROD DRIVE SYSTEM (CV-NC11A) | | MAY NOT REMAIN CLOSED AGAINST A SYSTEM PRESSURE IN EXCESS OF 1585 PSIG. | | THIS DETERMINATION WAS BASED UPON CONTROL AIR PRESSURE SUPPLIED TO THE | | VALVE, AND THE SIZE OF THE AIR DIAPHRAGM IN THE VALVE. THE LICENSEE | | PLANS TO MODIFY THE SYSTEM TO ENSURE THAT THE VALVE WILL REMAIN CLOSED. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE AT 11:30 ON 02/28/97, FROM M. BOURASSA TO BAILEY * * * | | | | THE LICENSEE IS RETRACTING THIS NOTIFICATION BECAUSE THE PRIMARY VENT VALVE | | (CV-NC11) IN THE SAME SYSTEM (CONTROL ROD DRIVE SYSTEM - SCRAM DUMP TANK | | VENT VALVES) WAS PROPERLY SET, AND WOULD NOT HAVE LIFTED UNDER A HIGH | | REACTOR PRESSURE CONDITION. THEREFORE, THE MISADJUSTMENT COULD HAVE ONLY | | AFFECTED ONE OF THE TWO PRIMARY ISOLATION VALVES DURING A HIGH REACTOR | | PRESSURE EVENT. | | | | THIS EVENT WOULD ALSO NOT BE REPORTABLE UNDER 10 CFR 50.72(b)(2)(iii), IN | | THAT FAILURE OF THE ONE VALVE ALONE WOULD NOT HAVE PREVENTED FULFILLMENT OF | | THE SYSTEM'S SAFETY FUNCTION. FURTHERMORE, A GENERIC ISSUE WITH THE VALVES | | DOES NOT EXIST. | | | | FOLLOWING THE REVIEW OF THE SAFETY-SIGNIFICANCE OF THIS EVENT WITH RESPECT | | TO 10 CFR 50.72(b)(2)(i), THE BIG ROCK POINT STAFF HAS CONCLUDED THAT A | | SIGNIFICANT DEGRADATION OF THE PRIMARY SYSTEM AS DESCRIBED IN NUREG 1022 | | DID NOT (AND DOES NOT) EXIST. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. THE OPERATIONS CENTER | | INFORMED THE R3DO (M. RING). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32232 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CLINTON REGION: 3 |NOTIFICATION DATE: 04/28/97 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 04:38 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 04/28/97 | +------------------------------------------------+EVENT TIME: 04:00[CDT]| |NRC NOTIFIED BY: MARSHALL FUNKHOUSER |LAST UPDATE DATE: 04/29/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MONTE PHILLIPS 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 N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | -SPDS & ERDS INOPERABLE FOR 24 HOURS DUE TO PLANNED MAINTENANCE ACTIVITIES- | | | | AT 0400 (CDT) ON 04/28/97, THE LICENSEE PLANS TO DECLARE THE SAFETY | | PARAMETER DISPLAY SYSTEM (SPDS) INOPERABLE DUE TO THE LOSS OF POWER FROM | | THE #1D STATION UNINTERRUPTIBLE POWER SUPPLY (UPS). THE LICENSEE PLANS | | TO REMOVE THE #1D UPS FROM SERVICE FOR PLANNED MAINTENANCE ACTIVITIES. | | POWER TO THE PLANT EMERGENCY RESPONSE DATA SYSTEM (ERDS) ALSO WILL BE | | LOST DURING THIS TIME. | | | | THE LICENSEE PLANS TO RESTORE ALL SYSTEMS TO NORMAL WITHIN 24 HOURS. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE AT 0433 ON 04/29/97 BY FUNKHOUSER ENTERED BY JOLLIFFE * * * | | | | AT 0330 (CDT) ON 04/29/97, THE LICENSEE COMPLETED THE PLANNED MAINTENANCE | | ACTIVITIES ON THE #1D UPS, RESTORED THE #1D UPS TO SERVICE, AND DECLARED | | THE SPDS AND ERDS OPERABLE. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | | | | THE HOO NOTIFIED R3DO MONTE PHILLIPS. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32233 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HARRIS REGION: 2 |NOTIFICATION DATE: 04/28/97 | |UNIT: [1] [ ] [ ] STATE: NC |NOTIFICATION TIME: 14:07 [ET]| |RX TYPE: [1] W-3-LP |EVENT DATE: 04/28/97 | +------------------------------------------------+EVENT TIME: 11:36[EDT]| |NRC NOTIFIED BY: KEITH HOLBROOK |LAST UPDATE DATE: 04/28/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |AL BELISLE 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 N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ASSISTANCE REQUESTED FROM AN OFFSITE FIRE DEPARTMENT DUE TO A FIRE IN A | | SWITCHGEAR ROOM THAT WAS QUICKLY EXTINGUISHED WITH MINIMAL DAMAGE TO PLANT | | EQUIPMENT | | | | AT 1036 ON APRIL 28, 1997, A FIRE WAS REPORTED IN THE A-SA BATTERY ROOM, | | AND THE HOLLY SPRINGS FIRE DEPARTMENT WAS CONTACTED FOR ASSISTANCE AT 1040. | | THE FIRE WAS EXTINGUISHED WITHIN 3 MINUTES BY A TECHNICIAN USING A CO2 FIRE | | EXTINGUISHER. AT 1047, FOLLOWING CONFIRMATION THAT THE FIRE WAS | | EXTINGUISHED, THE HOLLY SPRINGS FIRE DEPARTMENT WAS NOTIFIED THAT THEIR | | ASSISTANCE WAS NO LONGER REQUIRED. THE FIRE ORIGINATED IN A TEST CABLE | | CONNECTED TO THE BATTERY AND RESULTED IN MINOR DEFORMATION OF THE CASING OF | | ONE BATTERY CELL. THE LICENSEE PLANS TO HAVE THIS DAMAGE EVALUATED BY | | ENGINEERING GROUP PERSONNEL. | | | | AT THE TIME OF THE FIRE, THE BATTERY WAS DISCONNECTED FROM THE PLANT | | ELECTRICAL DISTRIBUTION SYSTEM. IN ADDITION, THE PLANT WAS IN A REFUELING | | OUTAGE WITH THE CORE OFF-LOADED AND THE REACTOR COOLANT SYSTEM DRAINED. | | | | THE LICENSEE'S EMERGENCY PLAN REQUIRES THAT THE WAKE COUNTY AND NORTH | | CAROLINA WARNING POINTS BE CONTACTED FOLLOWING THE DISPATCH OF ANY FIRE | | TRUCK. A FIRE TRUCK WAS DISPATCHED BUT WAS RECALLED BEFORE IT ARRIVED | | ONSITE. AS A RESULT, THE LICENSEE NOTIFIED THE WAKE COUNTY AND STATE OF | | NORTH CAROLINA WARNING POINTS. THE LICENSEE ALSO NOTIFIED THE NRC RESIDENT | | INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32234 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SALEM REGION: 1 |NOTIFICATION DATE: 04/28/97 | |UNIT: [1] [2] [ ] STATE: NJ |NOTIFICATION TIME: 14:46 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 04/28/97 | +------------------------------------------------+EVENT TIME: 12:48[EDT]| |NRC NOTIFIED BY: LARRY CURRAN |LAST UPDATE DATE: 04/28/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |KATHLEEN DOLCE 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 N 0 REFUELING | 0 REFUELING | | 2 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | OFFSITE NOTIFICATION OF THE RELEASE OF APPROXIMATELY ONE OUNCE OF OIL TO | | THE DELAWARE RIVER | | | | AT 1248, A SMALL OIL SHEEN WAS OBSERVED IN A COVE ON THE DELAWARE RIVER. | | THE SHEEN WAS EMANATING FROM THE DISCHARGE OUTFALL FOR THE OIL/WATER | | SEPARATOR (DSN-489) WHICH SERVES BOTH SALEM UNITS 1 AND 2. THE TOTAL OIL | | RELEASED WAS APPROXIMATELY 1 OUNCE. ALL OF THE OIL WAS CONTAINED AND | | CLEANED UP. THE OIL SHEEN DID NOT REACH NAVIGABLE WATERS. THE CAUSE OF | | THE RELEASE IS UNDER INVESTIGATION. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR, THE LOWER ALLOWAYS CREEK | | TOWNSHIP, THE STATE OF NEW JERSEY, AND THE NATIONAL RESPONSE CENTER. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32235 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DIABLO CANYON REGION: 4 |NOTIFICATION DATE: 04/28/97 | |UNIT: [1] [2] [ ] STATE: CA |NOTIFICATION TIME: 19:34 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 04/28/97 | +------------------------------------------------+EVENT TIME: 16:27[PDT]| |NRC NOTIFIED BY: STEVE HIETT |LAST UPDATE DATE: 04/28/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PHIL HARRELL 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | OUTSIDE DESIGN BASIS ISSUE INVOLVING REACTOR COOLANT PUMP (RCP) LIFT OIL | | PUMP INSTRUMENTATION TUBING CONFIGURATION | | | | THE LICENSEE RECENTLY IDENTIFIED THAT CERTAIN PARTS OF THE UNIT 1 RCP LUBE | | OIL COLLECTION SYSTEM DO NOT MEET THE 10 CFR 50.48, APPENDIX R, | | REQUIREMENTS TO SHIELD ALL POTENTIAL OIL LIFT PUMP AND ASSOCIATED LEAKS. | | THE SHIELD (A SHEET METAL HOUSING) WAS DESIGNED TO CONTAIN ALL POTENTIAL | | HIGH PRESSURE LEAKS ASSOCIATED WITH THE LIFT PUMP AND PIPING. IT WAS | | DISCOVERED THAT A SHORT SECTION OF THE INSTRUMENT LINES (USED FOR | | CALIBRATION OF THE LIFT PUMP SWITCHES) ON EACH LIFT PUMP WAS NOT ENCLOSED | | IN THE SHIELDING. | | | | BASED UPON THE INSPECTION TO DATE, THERE IS NO INDICATION THAT THE TUBING | | OF CONCERN IS LEAKING OR COMPROMISED. THE OIL LIFT PUMP IS ONLY RUN FOR | | APPROXIMATELY TWO MINUTES BEFORE THE RCP IS STARTED AND FOR APPROXIMATELY | | ONE MINUTE AFTER THE STARTING OF THE RCP. THE LIFT PUMP IS ONLY IN | | OPERATION DURING RCP STARTS AND NOT DURING NORMAL RCP OPERATION. (THERE IS | | ONE LIFT PUMP PER RCP.) | | | | THE CONFIGURATION WAS IDENTIFIED ON ALL FOUR UNIT 1 RCPs DURING A WALKDOWN | | DURING THE CURRENT UNIT 1 REFUELING OUTAGE. PLANS HAVE BEEN INITIATED TO | | RETURN THE UNIT 1 LIFT PUMP SYSTEM TO ITS DOCUMENTED DESIGN CONFIGURATION | | AND IN COMPLIANCE WITH APPENDIX R REQUIREMENTS DURING THE CURRENT REFUELING | | OUTAGE. UNIT 2 HAS NOT BEEN INSPECTED YET. HOWEVER, THIS CONDITION IS | | BELIEVED TO EXIST IN UNIT 2 AS WELL. | | | | THE LICENSEE PLANS TO NOTIFY THE NRC RESIDENT INSPECTOR AND PLANS TO ISSUE | | A LICENSEE EVENT REPORT WITHIN 30 DAYS. | +------------------------------------------------------------------------------+