U.S. Nuclear Regulatory Commission Operations Center Event Reports For 05/01/97 - 05/02/97 ** EVENT NUMBERS ** 32247 32248 32249 32250 32251 32252 32253 32254 32255 32256 32257 32258 32259 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32247 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SOUTH TEXAS REGION: 4 |NOTIFICATION DATE: 05/01/97 | |UNIT: [ ] [2] [ ] STATE: TX |NOTIFICATION TIME: 02:02 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 04/30/97 | +------------------------------------------------+EVENT TIME: 21:58[CDT]| |NRC NOTIFIED BY: MILLIFF |LAST UPDATE DATE: 05/01/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |HARRELL 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 | M/R Y 100 POWER OPERATION | 0 HOT STANDBY | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | MANUAL REACTOR TRIP DUE TO CLOSURE OF FEED REG VALVE. | | | | CONTROL ROOM OPERATORS MANUALLY TRIPPED THE UNIT FROM 100% POWER IN | | ANTICIPATION OF AN AUTOMATIC TRIP DUE TO LOW STEAM GENERATOR (SG) WATER | | LEVEL. ALL CONTROL RODS INSERTED PROPERLY FOLLOWING THE TRIP, AND ALL | | SYSTEMS FUNCTIONED AS EXPECTED. THE AUXILIARY FEEDWATER SYSTEM | | AUTOMATICALLY STARTED AND SUPPLIED WATER TO THE STEAM GENERATORS. | | | | THE LICENSEE REPORTED THAT LEVEL IN THE 'D' SG BEGAN DECREASING WHEN THE | | MAIN FEEDWATER REGULATING VALVE FOR THAT SG CLOSED FOR UNKNOWN REASONS. | | OPERATORS WERE UNABLE TO GET THE VALVE TO RESPOND TO EITHER AUTOMATIC OR | | MANUAL CONTROLS. WHEN THE WATER LEVEL IN THE 'D' SG DECREASED TO 35%, | | OPERATORS MANUALLY TRIPPED THE UNIT IN ANTICIPATION OF AN AUTOMATIC TRIP AT | | 33% LEVEL. THE LICENSEE IS INVESTIGATING THE CAUSE OF THE FEED REG VALVE | | MALFUNCTION. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32248 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 05/01/97 | |UNIT: [2] [ ] [ ] STATE: NY |NOTIFICATION TIME: 04:33 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 05/01/97 | +------------------------------------------------+EVENT TIME: 03:08[EDT]| |NRC NOTIFIED BY: GOETCHIUS |LAST UPDATE DATE: 05/01/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DOLCE RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | |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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 2 | N N 0 HOT SHUTDOWN | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | SAFETY INJECTION DUE TO STUCK OPEN MSSV DURING TESTING. | | | | WHILE TESTING THE MAIN STEAM SAFETY VALVES (MSSV) AS PART OF REFUELING | | OUTAGE ACTIVITIES, ONE MSSV STUCK OPEN, THEN SUBSEQUENTLY RESEATED, CAUSING | | A SAFETY INJECTION SIGNAL DUE TO STEAM GENERATOR DIFFERENTIAL PRESSURE. | | NEITHER REACTOR COOLANT SYSTEM (RCS) PRESSURE NOR TEMPERATURE DECREASED | | SIGNIFICANTLY DUE TO THE STUCK MSSV, AND NO INJECTION OF WATER TO THE RCS | | OCCURRED. (THIS IS AN INTERMEDIATE HEAD SAFETY INJECTION PLANT.) | | | | OPERATORS ENTERED EMERGENCY OPERATING PROCEDURE 'E0' IN RESPONSE TO THE | | EVENT. THE LICENSEE REPORTED THAT ALL SYSTEMS FUNCTIONED AS EXPECTED, | | EXCEPT THAT THE '25' FAN COOLER UNIT AND '23' AUXILIARY BOILER FEED PUMP | | DID NOT AUTOMATICALLY START IN RESPONSE TO THE ESFAS SIGNAL. THIS EQUIPMENT | | WAS MANUALLY STARTED. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED OF THIS EVENT BY THE LICENSEE. | | | | * * * UPDATE 0529 EDT 5/1/97 FROM GOETCHIUS TAKEN BY STRANSKY * * * | | | | THE LICENSEE HAS ENTERED TECHNICAL SPECIFICATION 3.0.3. THE '25' FAN COOLER | | UNIT HAS BEEN DECLARED INOPERABLE (BUT REMAINS AVAILABLE), AND THE | | EMERGENCY DIESEL GENERATOR FOR THE OTHER ESFAS TRAIN IS CURRENTLY OUT OF | | SERVICE FOR MAINTENANCE. THE LICENSEE HAS 30 HOURS TO EITHER DECLARE THE | | FAN COOLER UNIT OPERABLE OR TO REDUCE RCS TEMPERATURE TO <350øF IN ORDER TO | | COMPLY WITH THE TECHNICAL SPECIFICATION. THE NRC RESIDENT INSPECTOR WILL BE | | INFORMED. NOTIFIED R1DO (DOLCE). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32249 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 05/01/97 | |UNIT: [2] [ ] [ ] STATE: NY |NOTIFICATION TIME: 04:33 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 05/01/97 | +------------------------------------------------+EVENT TIME: 02:20[EDT]| |NRC NOTIFIED BY: GOETCHIUS |LAST UPDATE DATE: 05/01/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DOLCE RDO | |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 N 0 HOT SHUTDOWN | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | SPURIOUS STEAM GENERATOR BLOWDOWN ISOLATION | | | | AT 0220 EDT, STEAM GENERATOR BLOWDOWN ISOLATION RADIATION MONITOR 'R49' | | SPIKED, CAUSING A STEAM GENERATOR BLOWDOWN ISOLATION. OPERATORS CONFIRMED | | THAT THE RADIATION MONITOR SPIKE WAS SPURIOUS, AND THEN RESET THE | | ISOLATION. THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 32250 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: COOPER ENERGY SERVICES |NOTIFICATION DATE: 05/01/97 | | CITY: GROVE CITY REGION: 1 |NOTIFICATION TIME: 11:40 [ET]| | COUNTY: STATE: PA |EVENT DATE: 05/01/97 | |LICENSE#: AGREEMENT: N |EVENT TIME: 11:40[EDT]| | DOCKET: |LAST UPDATE DATE: 05/01/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |CHUCK CASTO (REG II) RDO | | | | +------------------------------------------------+MARK RING (REGIII) RDO | |NRC NOTIFIED BY: R. M. COTE |JOE TAPIA (REG IV) RDO | |HQ OPS OFFICER: JOHN MacKINNON |VERN HODGE (RIVB) NRR | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |CCCC 21.21 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THIS IS AN UPDATE TO A 10 CFR PART 21 SUBMITTED BY COOPER ENERGY SERVICES | | JUNE 19, 1991. | | | | COOPER ENERGY SERVICES, (CES), A DIVISION OF COOPER CAMERON CORPORATION, | | HEREBY NOTIFIES THE NRC OF A RE-EMPHASIS OF A PREVIOUSLY REPORTED POTENTIAL | | DEFECT IN A COMPONENT OF A DSRV AND DSR ENTERPRISE STANDBY DIESEL GENERATOR | | SYSTEM. THERE EXISTS A POTENTIAL PROBLEM WITH INTAKE AND EXHAUST POWER | | VALVE SPRINGS WHICH COULD RESULT IN ENGINE NON-AVAILABILITY. | | | | THE SPECIFIC SPRINGS UNDER DISCUSSION ARE MANUFACTURED BY ASSOCIATED SPRING | | IN CORRY, PENNSYLVANIA. THEY ARE INSTALLED AS A SUBCOMPONENT OF SPARE | | CYLINDER HEADS (4 SPRINGS PER CYLINDER HEAD) OR PROVIDED AS INDIVIDUAL | | SPARE COMPONENTS BY CES. 10 CFR 21 REPORT # 157 WAS ISSUED BY COOPER ENERGY | | SERVICES ON JUNE 19, 1991 TO DESCRIBE SURFACE DEFICIENCIES FOUND ON VALVE | | SPRINGS IN CES' INVENTORY. THESE DEFICIENCIES, CHARACTERIZED BY DRAW MARKS | | EXCEEDING THE DEPTH ALLOWED BY SPECIFICATION, WERE NOTED ON SPRINGS FROM A | | 1986 MANUFACTURING LOT. THERE HAD BEEN NO REPORTED FAILURE OF VALVE SPRINGS | | IN NUCLEAR OR COMMERCIAL SERVICE. ACTION WAS TAKEN TO INSPECT ALL SPRINGS | | IN CES' INVENTORY, ENHANCE SUPPLIER INSPECTION PROCEDURES AND RECOMMEND | | PERIODIC INSPECTION OF ALL SPRINGS IN SERVICE. | | | | DURING THE SUMMER OF 1996 A BROKEN VALVE SPRING WAS FOUND AT DUKE POWER'S | | CATAWBA STATION DURING A ROUTINE MAINTENANCE INSPECTION. NO AFFECT ON | | ENGINE PERFORMANCE HAD BEEN NOTED. THIS SPRING, RECENTLY RETURNED TO CES' | | FOR ANALYSIS, WAS FOUND TO BE OF THE SAME 1986 VINTAGE AS THOSE PREVIOUSLY | | DESCRIBED IN REPORT # 157. CES HAS REVIEWED THIS FAILURE AND BELIEVES IT | | TO BE AN ISOLATED CASE BUT IS ISSUING REPORT #157 AMENDMENT 1 TO INFORM | | THOSE AFFECTED OF THIS FAILURE AND TO RE-EMPHASIZE THE RECOMMENDED | | CORRECTIVE ACTION. | | | | IT IS RECOMMENDED THAT THE SUBJECT SPRINGS BE INSPECTED ON A PERIODIC | | BASIS, SUCH AS DURING REFUELING OUTAGES. ANY SPRINGS WITH A VISIBLE DRAW | | MARK ON ITS I.D. OR ANY PHYSICAL ANOMALY OF CONCERN SHOULD BE REMOVED, | | DISCARDED AND REPLACED. THIS INSPECTION SHOULD BE IN EACH PLANT'S | | MECHANICAL MAINTENANCE PROCEDURES AND SHOULD BE CONSIDERED TO APPLY TO ALL | | VALVE SPRINGS ON ENTERPRISE ENGINES REGARDLESS OF THEIR ORIGINAL | | MANUFACTURER. | | | | IT SHOULD ALSO BE NOTED THAT A CORRECTION SHOULD BE MADE TO THE ORIGINAL 10 | | CFR PART 21 REPORT # 157 WORDING PAGE 2, PARA. 5 TO READ AS FOLLOWS, 'THE | | NUMBER OF OPERATING HOURS IS OF CONCERN AS THE FATIGUE FAILURE RESULTING | | FROM SUCH AN INDICATION SHOULD OCCUR WITHIN APPROXIMATELY 740 HOURS (1E+7 | | OPERATING CYCLES)." | | | | PLANTS AFFECTED ARE: GRAND GULF, RIVER BEND, SHEARON HARRIS, CATAWBA, SAN | | ONOFRE, PERRY, COMANCHE PEAK, AND VOGTLE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32251 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MAINE YANKEE REGION: 1 |NOTIFICATION DATE: 05/01/97 | |UNIT: [1] [ ] [ ] STATE: ME |NOTIFICATION TIME: 13:49 [ET]| |RX TYPE: [1] CE |EVENT DATE: 05/01/97 | +------------------------------------------------+EVENT TIME: 10:00[EDT]| |NRC NOTIFIED BY: ETHAN BRAND |LAST UPDATE DATE: 05/01/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |KATHLEEN DOLCE RDO | |AINB 50.72(b)(2)(iii)(B) POT RHR 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 +------------------------------------------------------------------------------+ | NEW ENGINEERING ANALYSIS INDICATES THAT THE COMPONENT COOLING WATER PUMPS | | (CCP) COULD BE DISABLED BY A MAIN STEAM LINE HIGH ENERGY BREAK. | | | | THE PREVIOUS ENGINEERING ANALYSIS FOR THE TURBINE BUILDING HIGH ENERGY LINE | | BREAK DETERMINED THAT TEMPERATURES WOULD BE LESS THAN 200øF IN THE VICINITY | | OF THE CCPs (WHICH SUPPORT BOTH TRAINS OF THE RESIDUAL HEAT REMOVAL SYSTEM | | HEAT EXCHANGERS). SINCE THE TEMPERATURE IN THE VICINITY OF THE CCPs WAS | | LESS THAN 200øF, THE CCPs WERE NOT ENVIRONMENTALLY QUALIFIED. | | | | A NEW PRELIMINARY ENGINEERING ANALYSIS SHOWS THAT THE TEMPERATURES IN THE | | VICINITY OF THE CCPs DURING A 14" MAIN STEAM LINE HIGH ENERGY BREAK WOULD | | BE APPROXIMATELY 280øF. SINCE THE CCPs ARE NOT ENVIRONMENTALLY QUALIFIED, | | THIS POSTULATED EVENT COULD DISABLE BOTH TRAINS OF THE RESIDUAL HEAT | | REMOVAL SYSTEM. THIS CONDITION WILL BE ADDRESSED PRIOR TO STARTUP. | | | | THE NRC RESIDENT INSPECTOR WILL BE NOTIFIED BY THE LICENSEE OF THIS EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 32252 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 05/01/97 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 15:13 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 04/30/97 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 17:00[CDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 05/01/97 | | CITY: PADUCAH REGION: 3 +-----------------------------+ | COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION| |LICENSE#: GDP-1 AGREEMENT: Y |MARK RING RDO | | DOCKET: 0707001 | | +------------------------------------------------+ | |NRC NOTIFIED BY: MATT MAURER | | |HQ OPS OFFICER: JOHN MacKINNON | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |OCBB 76.120(c)(2)(ii) EQUIP DISABLED/FAILS | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ADDITIONAL DEFICIENCIES FOUND IN FIRE SPRINKLER SYSTEM IN BUILDING C-315 | | | | ON 4/30/97, AN ADDITIONAL INSPECTION OF THE SPRINKLER SYSTEM IN THE C-315 | | (SURGE AND WASTE) BUILDING WAS PERFORMED. THIS INSPECTION DETERMINED THAT A | | MAJORITY OF THE SPRINKLER HEADS INSTALLED ON THE SECOND FLOOR OF THE C-315 | | BUILDING WERE LOCATED TOO FAR FROM THE CEILING. THESE DEFICIENCIES ARE | | SIMILAR TO THOSE DOCUMENTED IN NRC EVENT NOTIFICATION #32231. | | | | THE C-315 SPRINKLER SYSTEM WAS DECLARED INOPERABLE ON 4/26/97 DUE TO | | DEFICIENCIES DOCUMENTED IN NRC EVENT NOTIFICATION #32231. HOURLY FIRE | | PATROLS OF THE AFFECTED AREA ARE BEING PERFORMED AS REQUIRED BY TSR | | 2.4.4.5. FURTHER INSPECTIONS ARE ONGOING AT THIS TIME. | | | | THESE DEFICIENCIES ARE IN ADDITION TO THOSE IDENTIFIED IN NRC EVENT | | NOTIFICATION # 32148, 32162, 32170, 32215, 32222, 32231 AND 32238. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT NOTIFICATION. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 32253 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: AUTOMATIC VALVES |NOTIFICATION DATE: 05/01/97 | | CITY: NOVI REGION: 3 |NOTIFICATION TIME: 16:14 [ET]| | COUNTY: STATE: MI |EVENT DATE: 04/25/97 | |LICENSE#: AGREEMENT: N |EVENT TIME: 00:00[EDT]| | DOCKET: |LAST UPDATE DATE: 05/01/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |KATHLEEN DOLCE (RI) RDO | | |DICK WESSMAN EO | +------------------------------------------------+MARK RING (REG III) RDO | |NRC NOTIFIED BY: TODD HUTCHINS |VERN HODGE (RVIB) NRR | |HQ OPS OFFICER: JOHN MacKINNON |AL CHAFFEE NRR | +------------------------------------------------+RICH BARRETT IRD | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |CCCC 21.21 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | PART 21 REPORT REGARDING FAILURE OF SCRAM SOLENOIDS. | | | | AUTOMATIC VALVES LOCATED AT 41144 VINCENTI COURT, NOVI, MI WILL BE ISSUING | | A PART 21 REPORT ON MAY 2, 1997. | | | | IN SEPTEMBER OF 1996, AUTOMATIC VALVES WAS NOTIFIED BY VERMONT YANKEE THAT | | A SCRAM SOLENOID PILOT VALVE WAS MAKING A BUZZING SOUND. AUTOMATIC VALVES | | DISCOUNTED THE REPORT AT THAT TIME BECAUSE THE NOISE WAS THOUGHT TO BE AN | | AC HUM. ON 4/25/97, WHEN VERMONT YANKEE PERFORMED SCRAM TIME TESTING, THE | | CONTROL ROD ASSOCIATED WITH THE NOISY SCRAM SOLENOID PILOT VALVE (WHICH HAD | | BEEN NOISY FOR THE LAST SIX MONTHS) HAD A SCRAM TIME THAT WAS SLOWER THAN | | THE OTHER CONTROL RODS THAT WERE TESTED, BUT WAS WITHIN THE TECHNICAL | | SPECIFICATION TIME LIMITS. | | | | AUTOMATIC VALVE HAS DETERMINED THAT THE NOISE WAS DUE TO METALLIC VIBRATION | | WITHIN THE SCRAM SOLENOID PILOT VALVE WHICH CAUSED THE VALVE PERFORMANCE TO | | DEGRADE. DURING PAST ACCEPTANCE TESTING, AUTOMATIC VALVE DID NOT USE | | AUDIBLE NOISE EMANATING FROM THE SCRAM SOLENOID PILOT VALVES AS AN | | ACCEPTANCE CRITERION. AUTOMATIC VALVE HAS CHANGED THEIR PROCEDURES TO USE | | THIS CRITERION. AUTOMATIC VALVES HAS SUPPLIED SCRAM SOLENOID PILOT VALVES | | TO BETWEEN 20 TO 25 NUCLEAR POWER PLANTS IN THE UNITED STATES. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 32254 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: THEDA CLARK HOSPITAL |NOTIFICATION DATE: 05/01/97 | | CITY: NEENAH REGION: 3 |NOTIFICATION TIME: 16:25 [ET]| | COUNTY: STATE: WI |EVENT DATE: 12/20/96 | |LICENSE#: 48-094094-01 AGREEMENT: N |EVENT TIME: 00:00[CDT]| | DOCKET: |LAST UPDATE DATE: 05/01/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |MARK RING RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: ED MARLEWSKI | | |HQ OPS OFFICER: JOHN MacKINNON | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |LADM 35.33(a) MED MISADMINISTRATION | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | MEDICAL MISADMINISTRATION | | | | ON DECEMBER 20, 1996, A PATIENT WAS TO HAVE RECEIVED A DOSE OF 9.4 mCi OF | | I-131. THE DOSE VIAL CONTAINED TWO CAPSULES OF I-131. THE PATIENT WAS TO | | HAVE RECEIVED BOTH CAPSULES OF THE I-131, BUT THE TECHNOLOGIST INCORRECTLY | | THOUGHT THAT EACH I-131 CAPSULE CONTAINED 9.4 mCi AND ONLY ADMINISTERED ONE | | CAPSULE TO THE PATIENT. THE REMAINING I-131 CAPSULE WAS RETURNED TO ITS | | LEAD CONTAINER AND PLACED IN STORAGE. | | | | THE MISADMINISTRATION WAS DISCOVERED TODAY WHEN THE REMAINING CAPSULE WAS | | FOUND IN ITS LEAD CONTAINER. THE PATIENT'S DOCTOR IS SEMI-RETIRED, AND IF | | THE DOCTOR CANNOT BE CONTACTED BY TOMORROW MORNING, THE RADIATION SAFETY | | OFFICER WILL INFORM THE PATIENT THAT SHE ONLY RECEIVED 50% OF THE DOSE THAT | | SHE WAS PRESCRIBED. | | | | NRC REGION 3 (MICHAEL LAFRANZO) WAS NOTIFIED OF THIS EVENT BY THE RADIATION | | SAFETY OFFICER. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32255 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 05/01/97 | |UNIT: [1] [ ] [ ] STATE: CT |NOTIFICATION TIME: 17:00 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 05/01/97 | +------------------------------------------------+EVENT TIME: 16:55[EDT]| |NRC NOTIFIED BY: DONOVAN |LAST UPDATE DATE: 05/01/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |KATHLEEN DOLCE RDO | |KSNM 70.52(a) LOSS OF SNM/CRIT |AL CHAFFEE EO | | |MCPEEK (IAT) NRR | | |ROBERT WARREN (IAT) NMSS | | |R. BARRETT (MGR) IRD | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | SMALL AMOUNT OF PLUTONIUM UNACCOUNTED FOR DURING AN AUDIT OF THE QUALITY | | ASSURANCE PROGRAM AT MILLSTONE UNIT 1. | | | | THE LOCATION OF A PLUTONIUM CHECK SOURCE (SERIAL #8089) IS NOT KNOWN, AND | | HAS NOT BEEN ACCOUNTED FOR PROPERLY. | | | | CONTRARY TO THE REQUIREMENTS OF 10 CFR 70.51(c), THE LICENSEE CANNOT | | ACCOUNT FOR A SMALL SOURCE CONTAINING APPROXIMATELY 0.0014 æCi OF Pu-239. | | THE STATUS OF THIS SOURCE IN THE HEALTH PHYSICS SOURCE TRACKING DATABASE IS | | LISTED AS DISPOSED WITH THE PHYSICAL LOCATION LISTED AS N/A. ADDITIONAL | | INFORMATION ON THE SOURCE'S LOCATION OR DISPOSAL HISTORY HAS NOT BEEN | | IDENTIFIED. THIS SOURCE CONTAINS SUBSTANTIALLY LESS THAN ONE GRAM OF | | PLUTONIUM (APPROX. 3E-08 GRAMS), BUT IT IS STILL CONSIDERED SPECIAL NUCLEAR | | MATERIAL AND IS REQUIRED TO BE CONTROLLED AND ACCOUNTED FOR AS SUCH. THE | | LICENSEE THINKS THAT THIS CHECK SOURCE WAS LOST BACK IN THE 1970s AND WAS | | PROBABLY DISPOSED OF AS RADIOACTIVE MATERIAL. | | | | THE NRC RESIDENT INSPECTOR WILL BE NOTIFIED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32256 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SURRY REGION: 2 |NOTIFICATION DATE: 05/01/97 | |UNIT: [1] [2] [ ] STATE: VA |NOTIFICATION TIME: 17:25 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 05/01/97 | +------------------------------------------------+EVENT TIME: 16:46[EDT]| |NRC NOTIFIED BY: W WEBSTER |LAST UPDATE DATE: 05/01/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CHUCK CASTO 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 1 STARTUP | 1 STARTUP | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | MORE THAN 25% OF THE EMERGENCY NOTIFICATION SIRENS INOPERABLE DUE TO | | THUNDERSTORMS. | | | | DURING POLLING OF THE EMERGENCY WARNING SYSTEM, THE LICENSEE DISCOVERED | | THAT 18 SIRENS HAD LOST POWER AND 2 SIRENS DID NOT RESPOND. THIS REPRESENTS | | GREATER THAN 25% (20 OF 61 SIRENS) EMERGENCY SIRENS UNAVAILABLE. | | | | LOCAL THUNDERSTORMS HAD PASSED THROUGH THE AREA WITHIN THE PREVIOUS HOUR. | | UTILITY PERSONNEL HAVE BEEN CONTACTED TO INVESTIGATE THIS PROBLEM. | | | | THE NRC RESIDENT INSPECTOR WILL BE NOTIFIED OF THIS EVENT BY THE LICENSEE. | | | | * * * UPDATE ON 05/01/97 @ 1840 ET BY WEBSTER TAKEN BY MACKINNON * * * | | | | GREATER THAN 75% OF THE EMERGENCY SIRENS HAVE BEEN RETURNED TO SERVICE. | | TWELVE EMERGENCY SIRENS ARE STILL INOPERABLE, AND THE LICENSEE IS | | CONTINUING EFFORTS TO RETURN THEM TO SERVICE. | | | | THE NRC RESIDENT INSPECTOR WILL BE NOTIFIED BY THE LICENSEE OF THIS UPDATE. | | THE NRC OPERATIONS CENTER NOTIFIED THE R2DO (CASTO). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32257 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: TURKEY POINT REGION: 2 |NOTIFICATION DATE: 05/01/97 | |UNIT: [3] [ ] [ ] STATE: FL |NOTIFICATION TIME: 18:06 [ET]| |RX TYPE: [3] W-3-LP,[4] W-3-LP |EVENT DATE: 05/01/97 | +------------------------------------------------+EVENT TIME: 17:30[EDT]| |NRC NOTIFIED BY: ADAMS |LAST UPDATE DATE: 05/01/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CHUCK CASTO RDO | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | LOW LEVELS OF RADIOACTIVITY FOUND ON PAINTING EQUIPMENT THAT HAD BEEN USED | | AT TURKEY POINT. | | | | TURKEY POINT WAS INFORMED TODAY BY COMED THAT PAINTING EQUIPMENT TO BE USED | | AT THE BRAIDWOOD NUCLEAR POWER PLANT WAS FOUND TO BE CONTAMINATED AT VERY | | LOW LEVELS WHEN SURVEYED WITH A TOOL MONITOR (EBERLINE PRM-6 FRISKER) | | DURING ITS RECEIPT INSPECTION AT THE SITE. BRAIDWOOD PERSONNEL BELIEVE THAT | | THE EQUIPMENT MAY HAVE COME FROM TURKEY POINT. THE EQUIPMENT IS OWNED BY A | | FLORIDA CONTRACTOR, POWER SYSTEMS ENERGY SERVICES, INC. AS A COURTESY, THE | | STATE OF FLORIDA DEPARTMENT OF HEALTH, OFFICE OF RADIATION CONTROL WAS | | NOTIFIED. | | | | WHEN SURVEYED AT BRAIDWOOD, CONTAMINATION LEVELS OF 100 TO 500 CORRECTED | | COUNTS PER MINUTE WERE DETECTED. THIS CORRESPONDS TO CONTAMINATION LEVELS | | OF 1,000 TO 5,000 DISINTEGRATIONS PER MINUTE (DPM). TECHNIQUES AND | | INSTRUMENTATION USED AT TURKEY POINT FOR SURVEYING EQUIPMENT FOR RELEASE DO | | NOT HAVE THE CAPABILITY TO CONSISTENTLY DETECT CONTAMINATION LEVELS LESS | | THAN 5,000 DPM. THE PRIMARY RADIOACTIVE MATERIALS DETECTED WERE COBALT-58, | | COBALT-60, etc. (STANDARD ACTIVATION PRODUCTS). | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 32258 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 05/01/97 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 22:20 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 05/01/97 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 13:50[CDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 05/01/97 | | CITY: PADUCAH REGION: 3 +-----------------------------+ | COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION| |LICENSE#: GDP-1 AGREEMENT: Y |MARK RING RDO | | DOCKET: 0707001 | | +------------------------------------------------+ | |NRC NOTIFIED BY: W. F. CAGE | | |HQ OPS OFFICER: JOHN MacKINNON | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |OCBB 76.120(c)(2)(ii) EQUIP DISABLED/FAILS | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE INSTALLED ACTUATORS ON AUTOCLAVES ARE RATED AT 40 PSIG INSTEAD OF BEING | | RATED AT 80 PSIG. | | | | ON MAY 1, 1997, IT WAS DISCOVERED (DURING AN INVESTIGATION INTO NRC EVENT | | NOTIFICATION #32224) THAT THE XV-532 AND CV-533 VALVES ON AUTOCLAVE 2 NORTH | | AND 2 SOUTH IN BUILDING C-333-A (FEED VAPORIZATION FACILITY) AND AUTOCLAVE | | 1 EAST AT BUILDING C-337-A (FEED VAPORIZATION FACILITY) AND THE CV-533 | | VALVE ON AUTOCLAVE 1 WEST AT C-337-A WERE DISCOVERED TO HAVE ACTUATORS THAT | | MAY NOT BE CAPABLE OF SERVING THEIR CONTAINMENT SAFETY FUNCTION. | | SPECIFICALLY, THE INSTALLED AIR ACTUATORS (DESIGNED TO CLOSE ON LOSS OF | | AIR) ARE RATED AT A 40 PSIG OPERATING PRESSURE, ALTHOUGH THE MANUFACTURER | | STATED THAT A 80 PSIG ACTUATOR IS REQUIRED. THE XV-532 AND CV-533 VALVES | | ARE THE INNER AND OUTER CONTAINMENT VALVES ON THE STEAM SAMPLE HEADER AND | | ARE REQUIRED BY THE TSR TO CLOSE WITHIN 10 SECONDS. | | | | AUTOCLAVES 2 NORTH AND 2 SOUTH IN C-333-A WERE IN MODE 6 (OUT OF SERVICE) | | AND INOPERABLE AT THE TIME OF DISCOVERY. AUTOCLAVES 1 EAST AND 1 WEST AT | | C-337-A WERE IN MODE 5 (HEATING) AT THE TIME OF DISCOVERY. AUTOCLAVE 1 EAST | | WAS PLACED IN MODE 2 (AUTOCLAVE OPEN) WITHIN 1 HOUR AS REQUIRED BY TSR | | 2.2.3.1B. AUTOCLAVE WEST WILL FINISH THE EXISTING OPERATING CYCLE AND THEN | | BE PLACED IN MODE 2 AS REQUIRED BY TSR 2.2.3.1A. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32259 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: QUAD CITIES REGION: 3 |NOTIFICATION DATE: 05/01/97 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 23:50 [ET]| |RX TYPE: [1] GE-3,[2] GE-3 |EVENT DATE: 05/01/97 | +------------------------------------------------+EVENT TIME: 19:30[CDT]| |NRC NOTIFIED BY: MacLENNAN |LAST UPDATE DATE: 05/01/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RING 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 +------------------------------------------------------------------------------+ | HPCI SYSTEM DECLARED INOPERABLE. | | | | THE LICENSEE IDENTIFIED THAT A TECHNICAL SPECIFICATION REQUIRED | | SURVEILLANCE INTERVAL HAD BEEN EXCEEDED. THE HIGH PRESSURE COOLANT | | INJECTION (HPCI) TURBINE EXHAUST CHECK VALVE HAD BEEN REPLACED, AND THE | | HPCI SYSTEM HAD BEEN TESTED ON 4/26/97. A VISUAL EXAMINATION VT-2-1, | | REQUIRED BY ASME SECTION XI, WAS NOT PERFORMED AT THAT TIME. QUAD CITIES | | TECHNICAL SPECIFICATIONS REQUIRE THAT HPCI TESTING MEET ASME SECTION XI | | REQUIREMENTS. THE HPCI SYSTEM WAS DECLARED INOPERABLE DUE TO A MISSED | | SURVEILLANCE AT 1930 ON 5/1/97. THE LICENSEE IS CURRENTLY PREPARING TO | | PERFORM THE VISUAL EXAMINATION. THE NRC RESIDENT INSPECTOR HAS BEEN | | INFORMED. | +------------------------------------------------------------------------------+