U.S. Nuclear Regulatory Commission Operations Center Event Reports For 05/02/97 - 05/05/97 ** EVENT NUMBERS ** 32253 32260 32261 32262 32263 32264 32265 32266 32267 32268 32269 32270 32271 32272 32273 +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 32253 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: AUTOMATIC VALVES CORPORATION |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: 05/02/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |KATHLEEN DOLCE (R1) RDO | | |DICK WESSMAN EO | +------------------------------------------------+MARK RING (R3) 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 SOLENOID PILOT VALVES ISSUED BY | | AUTOMATIC VALVES CORPORATION, NOVI, MICHIGAN. | | | | IN SEPTEMBER, 1996, AUTOMATIC VALVES CORPORATION (AVCO) WAS NOTIFIED BY | | VERMONT YANKEE THAT A SCRAM SOLENOID PILOT VALVE WAS MAKING A BUZZING SOUND | | (RATHER THAN A HUMMING SOUND) WHEN ENERGIZED. AVCO DISCOUNTED THE REPORT | | AND TOOK NO ACTION AT THAT TIME BECAUSE ALL AC SOLENOIDS HUM TO SOME EXTENT | | AND THEY ASSUMED THIS NOISE TO BE A NORMAL AC HUM SINCE NO KNOWN PRODUCT OR | | CUSTOMER COMPLAINT FAILURE HAD EVER BEEN RECEIVED BY AVCO DUE TO AC HUM OR | | BUZZ. | | | | ON 04/24/97, WHILE VERMONT YANKEE WAS PERFORMING SCRAM TIME TESTING, THE | | CONTROL ROD ASSOCIATED WITH THE NOISY SCRAM SOLENOID PILOT VALVE #06-11-118 | | (WHICH HAD BEEN NOISY FOR THE LAST SIX MONTHS) HAD A SCRAM TIME THAT WAS | | SLOWER THAN THE OTHER CONTROL RODS THAT WERE BEING TESTED, BUT WAS WITHIN | | THE TECHNICAL SPECIFICATION TIME LIMITS. | | | | AVCO 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 TESTS, AVCO DID NOT USE AUDIBLE NOISE EMANATING FROM | | THE SCRAM SOLENOID PILOT VALVES AS AN ACCEPTANCE CRITERION. AVCO HAS | | CHANGED THEIR PROCEDURES TO USE THIS CRITERION. AVCO HAS SUPPLIED SCRAM | | SOLENOID PILOT VALVES TO 20 - 25 NUCLEAR POWER PLANTS IN THE UNITED STATES. | | | | *** UPDATE AT 1640 ON 05/02/97 BY AVCO TODD HUTCHINS TAKEN BY MacKINNON *** | | | | AFTER INTERVIEWS WITH AVCO INSPECTION PERSONNEL, AVCO MANAGEMENT PERSONNEL | | DETERMINED THAT VALVES AT AVCO HAD BEEN INSPECTED FOR "NOISE" BUT THIS HAD | | BEEN DONE UNOFFICIALLY WITHOUT ANY CONSISTENT ACCEPTANCE/REJECTION | | CRITERIA. DIMENSIONAL DIFFERENCES BETWEEN SOLENOIDS THAT BUZZ AND HUM ARE | | NOT DETECTABLE. THIS WAS CONFIRMED WITH TWO AVCO SOLENOID VALVE | | COMPETITORS. DEFINITIONS FOR ACCEPTABLE AC HUM AND REJECTABLE BUZZ FOR AC | | SOLENOIDS HAVE NOW BEEN ADDED TO IN-PROCESS INSPECTION POINTS AND FINAL | | TEST PROCEDURES AT AVCO. | | | | AVCO RECOMMENDATION: EVEN THOUGH THE SOLENOID VALVE FUNCTIONED, IT WAS | | SIGNIFICANTLY SLOWER DUE TO THE AMOUNT OF METALLIC BY-PRODUCT FROM THE | | BUZZING SOLENOID PLUNGER. REGARDLESS OF THE MANUFACTURER, SOLENOIDS SHOULD | | BE CHECKED FOR BUZZING NOISES AS IT COULD DEGRADE THE PERFORMANCE AND | | POTENTIALLY THE LIFE OF THE VALVE. ANY REBUILDING OF ANY SUPPLIER'S | | SOLENOID VALVES REQUIRES A 'NOISE" TEST. SINCE 1970, AVCO HAS NOT BEEN | | ADVISED OF A SINGLE SAFETY RELATED AVCO PRODUCT FAILURE DUE TO THIS CAUSE. | | VERMONT YANKEE CONFIRMED THIS WITH A CHECK OF THE NUCLEAR PLANT RELIABILITY | | DATA SYSTEM. | | | | AVCO WILL RETEST, RECERTIFY, AND RESHIP AT NO CHARGE ANY SUSPECTED PRODUCT. | | AVCO WILL REPLACE AND RESHIP AT NO CHARGE ANY COMPONENT FOUND TO BE FIELD | | DEFECTIVE. | | | | THE OPERATIONS OFFICER NOTIFIED R1DO (MICHAEL MODES), R2DO (CHUCK CASTO), | | R3DO (MARK RING), R4DO (JOE TAPIA) & NRR VERN HODGE. | | | | NOTE: SEE EVENT #32263 FOR A RELATED EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32260 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DUANE ARNOLD REGION: 3 |NOTIFICATION DATE: 05/02/97 | |UNIT: [1] [ ] [ ] STATE: IA |NOTIFICATION TIME: 09:58 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 05/02/97 | +------------------------------------------------+EVENT TIME: 07:00[CDT]| |NRC NOTIFIED BY: PRY |LAST UPDATE DATE: 05/02/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MARK RING 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 Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LICENSEE NOTIFIED STATE OF IOWA REGARDING SEWAGE DISCHARGE IN EXCESS OF | | PLANT DISCHARGE LIMIT. | | | | AT 0700 (CDT), THE LICENSEE RECEIVED RESULTS OF A ROUTINE SAMPLE OF SEWAGE | | EFFLUENT WHICH INDICATED A FECAL COLIFORM CONCENTRATION IN EXCESS OF THE | | PLANT DISCHARGE LIMIT. THE ACTUAL EFFLUENT CONCENTRATION WAS 17,000 PPM; | | THE LIMIT IS 200 PPM. THE LICENSEE ATTRIBUTED THE HIGH DISCHARGE | | CONCENTRATION TO AN IMBALANCE IN THE SEWAGE TREATMENT SYSTEM. THE LICENSEE | | NOTIFIED THE IOWA STATE DEPARTMENT OF NATURAL RESOURCES OF THE VIOLATION. | | A NEW SAMPLE WILL BE COLLECTED AND ANALYZED. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |HOSPITAL | |EVENT NUMBER: 32261 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: ST JAMES COMMUNITY HOSPITAL |NOTIFICATION DATE: 05/02/97 | | CITY: BUTTE REGION: 4 |NOTIFICATION TIME: 12:40 [ET]| | COUNTY: JEFFERSON STATE: MT |EVENT DATE: 05/02/97 | |LICENSE#: AGREEMENT: N |EVENT TIME: 10:00[MDT]| | DOCKET: |LAST UPDATE DATE: 05/02/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |JOSEPH TAPIA RDO | | |JOSEPHINE PICCONE EO | +------------------------------------------------+RICH BARRETT IRD | |NRC NOTIFIED BY: Dr WIMMER |LINDA HOWELL R4 | |HQ OPS OFFICER: JOHN MacKINNON | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | A PACKAGE CONTAINING IODINE-131 DELIVERED TO A HOSPITAL IN BUTTE, MONTANA | | WAS FOUND TO HAVE A HIGH EXTERNAL RADIATION READING. | | | | AT 1000 (MDT), A PACKAGE CONTAINING 17 mCi OF I-131 WAS SHIPPED BY FEDERAL | | EXPRESS FROM SYNCOR COMPANY, SPOKANE, WA, TO THE ST JAMES COMMUNITY | | HOSPITAL, BUTTE, MT. UPON RECEIPT OF THE PACKAGE, A HOSPITAL MEDICAL | | TECHNOLOGIST IMMEDIATELY SURVEYED THE PACKAGE IN THE HOSPITAL HOT ROOM. | | THE TECHNOLOGIST MEASURED HIGH EXTERNAL RADIATION READINGS (EXPOSURE RATE | | IS UNKNOWN) BUT THERE WAS NO EXTERNAL SURFACE CONTAMINATION ON THE PACKAGE. | | AFTER OPENING THE PACKAGE, THE TECHNOLOGIST DISCOVERED THAT THE LEAD PIG | | THAT WAS SUPPOSED TO CONTAIN THE I-131 CAPSULE WAS EMPTY AND THAT THE I-131 | | CAPSULE WAS CRUSHED UNDERNEATH THE LEAD PIG (THE LEAD PIG IS ABOUT THE SIZE | | OF A 35 MM FILM CAPSULE). THE I-131 IS IN SOLID FORM (POWDER) AND IT | | APPEARS THAT NONE OF THE I-131 IS MISSING. | | | | DR WIMMER IS CONCERNED THAT PEOPLE ASSOCIATED WITH THE DELIVERY OF THIS | | PACKAGE MAY HAVE RECEIVED AN EXPOSURE RATE OF GREATER THAN 2 MR/HR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32262 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SAINT LUCIE REGION: 2 |NOTIFICATION DATE: 05/02/97 | |UNIT: [1] [2] [ ] STATE: FL |NOTIFICATION TIME: 14:57 [ET]| |RX TYPE: [1] CE,[2] CE |EVENT DATE: 05/02/97 | +------------------------------------------------+EVENT TIME: 14:50[EDT]| |NRC NOTIFIED BY: JACK BREEN |LAST UPDATE DATE: 05/02/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CHUCK CASTO 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 Y 100 POWER OPERATION | 100 POWER OPERATION | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | REACTOR COOLANT PUMP OIL COLLECTION SYSTEM DOES NOT MEET APPENDIX "R" | | REQUIREMENTS. | | | | THE REACTOR COOLANT PUMP (RCP) OIL COLLECTION SYSTEM FOR UNITS 1 AND 2 IS | | DESIGNED TO MEET THE REQUIREMENT OF 10 CFR PART 50, APPENDIX "R," SECTION | | III.O, WHICH STATES, "EACH RCP SHALL HAVE AN OIL COLLECTION SYSTEM CAPABLE | | OF COLLECTING LUBE OIL FROM ALL POTENTIAL PRESSURIZED AND UNPRESSURIZED | | LEAKAGE SITES." DURING THE UNIT 2 REFUELING OUTAGE, INSPECTIONS OF RCPs | | REVEALED TWO ADDITIONAL LEAKAGE SITES THAT WERE NOT COLLECTED BY THE OIL | | COLLECTION SYSTEM. BECAUSE THESE IDENTIFIED SITES ARE LOW PRESSURE AND | | LOCATED ABOVE THE NORMAL OIL RESERVOIR LEVEL, ANY RESULTANT LEAKAGE WOULD | | BE SMALL. THE UNIT 1 RCP OIL COLLECTION SYSTEM HAS BEEN EVALUATED AND IS | | DETERMINED TO BE OPERABLE BASED ON THE LIMITED LEAKAGE POSTULATED FROM THE | | AFFECTED OIL LEAKAGE SITES. | | | | THE LICENSEE PLANS TO SUBMIT AN LER ON THIS EVENT TO THE NRC. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32263 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VERMONT YANKEE REGION: 1 |NOTIFICATION DATE: 05/02/97 | |UNIT: [1] [ ] [ ] STATE: VT |NOTIFICATION TIME: 16:36 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 05/02/97 | +------------------------------------------------+EVENT TIME: 15:15[EDT]| |NRC NOTIFIED BY: A WISNIEWSKI |LAST UPDATE DATE: 05/02/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MICHAEL MODES 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 | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AUTOMATIC VALVE CORPORATION SCRAM SOLENOID PILOT VALVES FAILED A SCRAM TIME | | TEST. | | | | ON 04/24/97, SCRAM SOLENOID PILOT VALVE (SSPV) #06-11-118 FAILED A SCRAM | | TIME TEST. PRIOR TO THE SSPV FAILING THE TEST, IT EXHIBITED A BUZZING | | SOUND. THE LICENSEE REPLACED THE FAILED SSPV AND NINE OTHER SSPVs | | EXHIBITING NOISE. THE PLANT HAS 93 SSPVs INSTALLED IN THE SCRAM SYSTEM AND | | 8 SSPVs INSTALLED ON THE MAIN STEAM ISOLATION VALVES (MSIV). | | | | THE LICENSEE SHIPPED THE FAILED VALVE TO THE SUPPLIER, AUTOMATIC VALVE | | CORPORATION, FOR VISUAL INSPECTION, FAILURE ANALYSIS, AND ROOT CAUSE | | DETERMINATION. | | | | THE LICENSEE HAS SUBMITTED A BASIS FOR MAINTAINING OPERATION WHICH INCLUDES | | ADDITIONAL MONITORING OF SSPVs BY PLANT OPERATORS TO THE NRC RESIDENT | | INSPECTOR AND NRC REGION 1. | | | | THE LICENSEE PLANS TO INSPECT THE MSIV SCRAM SOLENOID PILOT VALVES PRIOR TO | | PLANT RESTART. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | NOTE: SEE EVENT REPORT #32253 FOR BACKGROUND INFORMATION. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 32264 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 05/02/97 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 17:12 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 05/01/97 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 16:58[CDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 05/02/97 | | CITY: PADUCAH REGION: 3 +-----------------------------+ | COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION| |LICENSE#: GDP-1 AGREEMENT: Y |MARK RING RDO | | DOCKET: 0707001 |MIKE BELL (NMSS) EO | +------------------------------------------------+ | |NRC NOTIFIED BY: W. G. HALICKS | | |HQ OPS OFFICER: JOHN MacKINNON | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NBNL RESPONSE-BULLETIN | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DOUBLE CONTINGENCY PRINCIPLE VIOLATED DURING THE PROCESS OF TRANSFERRING, | | HANDLING, AND STORING OF FISSILE/POTENTIALLY FISSILE MATERIAL. | | | | THIS EVENT IS REPORTED IN ACCORDANCE WITH NRC BULLETIN 91-01 (24 HOUR). | | | | AT 1658 CDT, PADUCAH DISCOVERED THAT THE DOUBLE CONTINGENCY PRINCIPLE HAD | | BEEN VIOLATED DURING THE PROCESS OF TRANSFERRING, HANDLING, AND STORING OF | | FISSILE/POTENTIALLY FISSILE MATERIAL. THE MATERIAL INVOLVED INCLUDED 12 | | MAXIMUM 550 ML POTENTIALLY FISSILE CONTAINERS WHICH WERE BATCHED INTO A | | SINGLE BATCH AND TRANSPORTED FROM THE C-335 PROCESS BUILDING TO THE C-710 | | LABORATORY FOR ANALYSIS. THE TOTAL VOLUME OF MATERIAL IN THE BATCH WAS 6.6 | | LITERS. THE NUCLEAR CRITICALITY SAFETY EVALUATION (NCSE) FOR TRANSFER, | | HANDLING, AND STORING OF FISSILE/POTENTIALLY FISSILE SAMPLES (GEN-08) | | ANALYZED THIS PROCESS AND DEMONSTRATED THAT THE MAXIMUM SUBCRITICAL VOLUME | | AT AN ENRICHMENT OF 5.5 WT% U-235 FOR SOLIDS, LIQUIDS, AND SLUGGED OIL IS | | 12 LITERS. TO ACCOUNT FOR DOUBLE BATCHING, THE BATCH LIMIT HAD PREVIOUSLY | | BEEN REDUCED TO 5.5 LITERS. THE BATCH LIMITS ESTABLISHED IN THE NUCLEAR | | CRITICALITY SAFETY APPROVAL (NCSA) GEN-08 ARE BASED ON THE SAMPLE CONTENTS | | AND ARE CONTROLLED BY THE BATCH VOLUME. THIS VIOLATION OF THE BATCH VOLUME | | LIMIT RESULTED IN THE LOSS OF ONLY ONE CONTINGENCY. | | | | ALTHOUGH THE BATCH VOLUME WAS EXCEEDED, THE VOLUME OF ALL OF THE SAMPLES | | TOGETHER WAS LESS THAN THE 12 LITERS ANALYZED TO BE SAFE AT AN ENRICHMENT | | OF 5.5 WT% U-235. IN ADDITION, CURRENT OPERATIONS ARE AT OR BELOW 2.0 WT% | | U-235. THEREFORE, A CRITICALITY WAS NOT POSSIBLE IN THIS SITUATION. THE | | SAMPLES WERE SEPARATED INTO APPROPRIATE BATCH SIZES TO RESTORE THE VOLUME | | CONTROL AND DOUBLE CONTINGENCY. THE PLANT SHIFT SUPERINTENDENT AND THE | | NUCLEAR CRITICALITY SAFETY OFFICER WERE NOTIFIED. PADUCAH INITIATED AN | | INVESTIGATION TO IDENTIFY THE CAUSE AND DETERMINE CORRECTIVE ACTIONS. | | | | THE NUCLEAR CRITICALITY SAFETY EVALUATION HAS SHOWN THIS PROCESS TO BE SAFE | | UP TO 12 LITERS. THE VOLUME OF THE MATERIAL INVOLVED WAS 6.6 LITERS. THIS | | EVENT WAS NOT SAFETY SIGNIFICANT. | | | | PADUCAH NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32265 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VERMONT YANKEE REGION: 1 |NOTIFICATION DATE: 05/02/97 | |UNIT: [1] [ ] [ ] STATE: VT |NOTIFICATION TIME: 18:35 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 05/02/97 | +------------------------------------------------+EVENT TIME: 18:05[EDT]| |NRC NOTIFIED BY: A WISNIEWSKI |LAST UPDATE DATE: 05/02/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MICHAEL MODES 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 +------------------------------------------------------------------------------+ | TWO NON-NUCLEAR SAFETY CABLES ARE ROUTED THROUGH BOTH DIVISION 1 AND | | DIVISION 2 MANHOLES. | | | | AT 1805 EDT, THE CONTROL ROOM WAS INFORMED BY ENGINEERING THAT TWO | | NON-NUCLEAR SAFETY CABLES (#C1452C AND #C1453C) ARE ROUTED THROUGH BOTH | | DIVISION 1 AND DIVISION 2 INTAKE STRUCTURE MANHOLES. THIS IS CONTRARY TO | | DIVISIONAL SEPARATION CRITERIA AND PLACES THE PLANT OUTSIDE ITS DESIGN | | BASIS. THIS CONDITION WAS DISCOVERED AS PART OF FOLLOWUP ACTIONS TO SIMILAR | | EVENTS PREVIOUSLY REPORTED TO THE NRC. | | | | THE LICENSEE PLANS TO INFORM THE NRC RESIDENT INSPECTOR. | | | | NOTE: REFER TO SIMILAR EVENT REPORTS #32035, #32057, #32146, AND #32163. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 32266 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 05/02/97 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 18:52 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 05/01/97 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 17:00[EDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 05/02/97 | | CITY: PIKETON REGION: 3 +-----------------------------+ | COUNTY: PIKE STATE: OH |PERSON ORGANIZATION| |LICENSE#: GDP-2 AGREEMENT: N |MARK RING RDO | | DOCKET: 0707002 |MIKE BELL (NMSS) EO | +------------------------------------------------+RICH BARRETT IRD | |NRC NOTIFIED BY: G BARCH | | |HQ OPS OFFICER: JOHN MacKINNON | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NBNL RESPONSE-BULLETIN | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | A MOTHBALLED CONVERTER WITHOUT A DRY AIR OR NITROGEN PURGE CONTAINS 3,966 ñ | | 1,983 GRAMS OF 5.0 WT% U-235. | | | | THIS EVENT IS REPORTED IN ACCORDANCE WITH NRC BULLETIN 91-01 (4 HOUR). | | | | AT 1700 EDT ON 05/01/97, A SURVEY PERFORMED ON A MOTHBALLED CONVERTER | | DETERMINED THAT IT CONTAINED 3,966 ñ 1,983 GRAMS OF 5.0 WT% U-235. THE | | CONVERTER IS ALLOWED TO CONTAIN 800 GRAMS OF 5.0 WT% U-235 WITHOUT A DRY | | AIR OR NITROGEN PURGE AND 8,500 GRAMS OF 5.0 WT% U-235 WITH A DRY AIR OR | | NITROGEN PURGE. | | | | THE CONVERTER IS COMPLETELY SEALED WITH STEEL PLATES WELDED OVER THE | | OPENINGS THAT WERE USED FOR MODERATION CONTROL TO KEEP MOISTURE OUT WHEN | | THE CONVERTER WAS OPERATING. THIS CONVERTER WAS LAST USED 15 YEARS AGO. | | | | SAFETY ANALYSIS REPORT (SAR) SECTION 5.2 STATES THAT EQUIPMENT REMOVED FROM | | THE CASCADE SYSTEM MUST BE MAINTAINED WITH A DRY AIR OR NITROGEN PURGE | | UNTIL THE EQUIPMENT IS DISASSEMBLED. THE REQUIREMENTS OF SAR SECTION 5.2 | | HAVE BEEN IN EFFECT SINCE 3/3/97, WHEN THE NRC STARTED REGULATING GASEOUS | | DIFFUSION PLANTS. THE LICENSEE IS IN VIOLATION OF SAR SECTION 5.2 SINCE A | | DRY AIR OR NITROGEN PURGE HAS NOT BEEN ESTABLISHED IN THE CONVERTER. | | | | TSR SECTION 2.2.3.15 ALLOWS THE LICENSEE TO ESTABLISH A GAS BUFFER OR TO | | REMOVE THE FISSILE MATERIAL FROM THE CONVERTER WITHIN THE NEXT 72 HOURS. | | PORTSMOUTH PLANS TO ESTABLISH A NITROGEN PURGE ON THE CONVERTER BY 5/4/97. | | | | PORTSMOUTH PERSONNEL CONCLUDED THAT THIS CONVERTER DOES NOT CONSTITUTE A | | SIGNIFICANT SAFETY HAZARD AND NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32267 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DIABLO CANYON REGION: 4 |NOTIFICATION DATE: 05/02/97 | |UNIT: [1] [2] [ ] STATE: CA |NOTIFICATION TIME: 19:14 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 05/02/97 | +------------------------------------------------+EVENT TIME: 12:55[PDT]| |NRC NOTIFIED BY: B RYAN |LAST UPDATE DATE: 05/02/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOE TAPIA RDO | |HFIT 26.73 FITNESS FOR DUTY | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | METHAMPHETAMINE FOUND INSIDE THE PLANT PROTECTED AREA. | | | | ON 04/25/97, THE LICENSEE DISCOVERED A SMALL QUANTITY OF WHITE POWDER | | INSIDE A PORTABLE TOILET INSIDE THE PLANT PROTECTED AREA. LICENSEE | | SECURITY PERSONNEL PERFORMED A FIELD TEST OF THE SUBSTANCE. THE TEST | | RESULTS WERE INCONCLUSIVE, AND THE LICENSEE SENT THE SUBSTANCE TO AN | | OFFSITE LABORATORY FOR ADDITIONAL TESTING. | | | | AT 1255 PST ON 05/02/97, THE LICENSEE WAS INFORMED THAT THE LABORATORY | | CONCLUDED THAT THE SUBSTANCE WAS METHAMPHETAMINE. | | | | THE LICENSEE IS INVESTIGATING THIS EVENT. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 32268 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 05/02/97 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 21:00 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 05/01/97 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 21:10[CDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 05/02/97 | | 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 +------------------------------------------------------------------------------+ | ADDITIONAL SPRINKLER SYSTEM DEFICIENCIES IDENTIFIED. | | | | AT 2110 CDT ON 05/01/97, PADUCAH IDENTIFIED ADDITIONAL SPRINKLER | | DEFICIENCIES. IN THE C-331 PROCESS BUILDING, A SYSTEM BRANCH LINE WAS | | DETERMINED TO BE MISSING, AND THREE UPRIGHT SPRINKLER HEADS ON ANOTHER | | SYSTEM WERE FOUND TO BE INSTALLED AT 60 DEGREES FROM VERTICAL IN VIOLATION | | OF APPLICABLE ENGINEERING STANDARDS. THE TWO SYSTEMS INVOLVED WERE | | IMMEDIATELY DECLARED INOPERABLE, AND HOURLY FIRE PATROLS WERE ESTABLISHED | | AS REQUIRED BY TSR 2.4.4.5. IN THE C-335 PROCESS BUILDING, REQUIRED | | SPRINKLER PROTECTION IS NOT PROVIDED UNDER PROCESS GAS PIPING ENCLOSURE | | (DUCT) NEAR COLUMN DD-FF/23-24 ON THE CELL FLOOR. AN HOURLY FIRE PATROL WAS | | ESTABLISHED IN THIS AREA TO PROVIDE COVERAGE REQUIRED BY TSR 2.4.4.5. | | FURTHER INSPECTIONS AND INVESTIGATIONS ARE CURRENTLY UNDERWAY. | | | | THESE IDENTIFIED DEFICIENCIES ARE IN ADDITION TO THOSE PREVIOUSLY | | IDENTIFIED IN EVENT REPORTS #32148, #32162, #32170, #32215, #32222, #32228, | | #32231, #32238, AND #32252. | | | | PADUCAH INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32269 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 05/02/97 | |UNIT: [2] [ ] [ ] STATE: NY |NOTIFICATION TIME: 21:26 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 05/02/97 | +------------------------------------------------+EVENT TIME: 20:35[EDT]| |NRC NOTIFIED BY: SANTINI |LAST UPDATE DATE: 05/02/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MICHAEL MODES 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 +------------------------------------------------------------------------------+ | A SPIKE CAUSED VENTILATION PURGE SUPPLY AND EXHAUST VALVES TO CLOSE. | | | | AT 2035 EDT, VAPOR CONTAINMENT (VC) VENTILATION PURGE SUPPLY AND EXHAUST | | VALVES TRIPPED CLOSED DUE TO A SPIKE (3.47 E-5 æCi/CC) ON GAS PROCESS | | RADIATION MONITOR #R-44. THE ALARM SETPOINT WAS SET AT 3.46 E-5 æCi/CC, | | CALCULATED PER SOP 5.2.4 FOR A LOW SOURCE TERM. THE ALARM SETPOINT SHOULD | | HAVE BEEN SET AT 1.32 E-4 æCi/CC DUE TO A LACK OF A LOW SOURCE TERM. ALL VC | | PURGE SUPPLY AND EXHAUST VALVES CLOSED AS REQUIRED. | | | | THE #R-44 HIGH ALARM WAS RESET, AND THE SETPOINT CHANGED TO 1.32 E-4 | | æCi/CC. VC PURGE SUPPLY AND EXHAUST WERE REESTABLISHED. | | | | THE LICENSEE PLANS TO INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32270 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BROWNS FERRY REGION: 2 |NOTIFICATION DATE: 05/02/97 | |UNIT: [ ] [2] [3] STATE: AL |NOTIFICATION TIME: 22:36 [ET]| |RX TYPE: [1] GE-4,[2] GE-4,[3] GE-4 |EVENT DATE: 05/02/97 | +------------------------------------------------+EVENT TIME: 20:48[CDT]| |NRC NOTIFIED BY: R NACOSTE |LAST UPDATE DATE: 05/02/97 | |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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | 3 | N Y 100 POWER OPERATION | 100 POWER OPERATION | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | 31 OF 100 EMERGENCY SIRENS INOPERABLE DUE TO SEVERE WEATHER. | | | | ELECTRICAL POWER WAS LOST TO 31 OF 100 EMERGENCY SIRENS DUE TO A SEVERE | | WEATHER FRONT PASSING THROUGH THE LOCAL AREA. THE LICENSEE IS WORKING TO | | RESTORE ALL EMERGENCY SIRENS TO OPERABLE STATUS. THE ELECTRICAL GRID IS | | STABLE, AND ALL EMERGENCY CORE COOLING SYSTEMS AND EMERGENCY DIESEL | | GENERATORS ARE OPERABLE. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32271 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OCONEE REGION: 2 |NOTIFICATION DATE: 05/03/97 | |UNIT: [ ] [ ] [3] STATE: SC |NOTIFICATION TIME: 15:45 [ET]| |RX TYPE: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-LP |EVENT DATE: 05/03/97 | +------------------------------------------------+EVENT TIME: 15:04[EDT]| |NRC NOTIFIED BY: NOEL CLARKSON |LAST UPDATE DATE: 05/04/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: UNUSUAL EVENT +-----------------------------+ |10 CFR SECTION: |CHUCK CASTO RDO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |DICK WESSMAN EO | | |CARR FEMA | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | | | | | 3 | N N 0 HOT SHUTDOWN | 0 HOT SHUTDOWN | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNUSUAL EVENT DECLARED DUE TO 2 OF 3 HIGH PRESSURE INJECTION PUMPS BEING | | INOPERABLE. | | | | THE LICENSEE SUSPECTS THAT THE LETDOWN STORAGE TANK WATER LEVEL INDICATIONS | | ARE NOT INDICATING PROPER LEVEL. THE LETDOWN STORAGE TANK SUPPLIES WATER | | TO THE SUCTION OF THE THREE HIGH PRESSURE INJECTION (HPI) PUMPS. | | | | PRESENT REACTOR COOLANT SYSTEM (RCS) PARAMETERS: TEMPERATURE IS 210øF AND | | PRESSURE IS 270 PSIG. THE LOW PRESSURE INJECTION PUMPS ARE TAKING SUCTION | | FROM THE RCS AND DISCHARGING BACK TO THE RCS COLD LEG. THE "3B1" REACTOR | | COOLANT PUMP (RCP) IS THE ONLY OPERATING RCP. CONDENSATE BOOSTER PUMPS ARE | | SUPPLYING WATER TO THE ONCE-THROUGH STEAM GENERATORS, AND STEAM IS BEING | | DUMPED TO THE MAIN CONDENSER. | | | | AT 0930, LOW DISCHARGE PRESSURE WAS INDICATED ON THE "3B" HPI PUMP. THE | | RCP SEAL INJECTION CONTROL VALVE WAS PLACED IN "HAND" (i.e., MANUAL). THE | | STANDBY HPI PUMP ("3A") STARTED AUTOMATICALLY ON LOW RCP SEAL INJECTION | | FLOW. HPI PUMP DISCHARGE PRESSURE RETURNED TO NORMAL, AND RCP SEAL | | INJECTION FLOW INDICATED HIGH. THE "3A" HPI PUMP WAS SECURED. RCP SEAL | | INJECTION WAS ADJUSTED TO NORMAL VALUE. | | | | HPI HEADER DISCHARGE PRESSURE AGAIN INDICATED LOW. THE "3A" HPI PUMP | | AUTOMATICALLY STARTED, AND AMPS WERE CYCLING HIGH. THE "3B" HPI PUMP AMPS | | INDICATED LOW AND WAS SECURED. THE "3A" HPI PUMP AMPS CONTINUED TO CYCLE | | HIGH. THE INDICATED LETDOWN STORAGE TANK LEVEL INCREASED. THE "3A" HPI | | PUMP AMPS INDICATED LOW, AND THE "3A" HPI PUMP WAS SECURED. | | | | THE LICENSEE SUSPECTS THAT THE LETDOWN STORAGE TANK LEVEL INDICATIONS ARE | | ERRONEOUS AND IS INVESTIGATING THE CAUSE AND DEVELOPING RECOVERY ACTIONS. | | | | THE NRC RESIDENT INSPECTORS ARE ON SITE. | | | | AT 1350, NRC HEADQUARTERS AND REGION 2 ENTERED THE MONITORING PHASE OF | | NORMAL EMERGENCY RESPONSE MODE. THE NRC RESPONSE COORDINATION TEAM MEMBER | | NOTIFIED FEMA (BAGWELL), DOE (DUNKIN), EPA (HUDSPETH), USDA (BICKERTON), | | AND HHS (RABB). | | | | AT 1504, THE LICENSEE DECLARED AN UNUSUAL EVENT DUE TO TWO OF THREE HPI | | PUMPS BEING INOPERABLE. THIS SITUATION IS A POTENTIAL DEGRADATION IN THE | | LEVEL OF SAFETY TO UNIT 3. | | | | THE LICENSEE NOTIFIED STATE AND LOCAL OFFICIALS OF THE DECLARATION OF THE | | UNUSUAL EVENT. | | | | * * * UPDATE AT 1900 BY MacKINNON * * * | | | | AT 1900, A COMMISSIONERS' ASSISTANTS BRIEFING WAS HELD. THE BRIEFER WAS | | CHUCK CASTO. PARTICIPANTS INCLUDED (* INDICATES OFFICE DID NOT | | PARTICIPATE): AEOD (BAILEY, ROSENTHAL, QUISSELL), JACKSON (LEE), ROGERS | | (FLEISHMAN), DICUS (LUBENAU), DIAZ (RADDATZ), McGAFFIGAN (BEALL), EDO | | (TRACY), DEDO (JORDAN), EAB (CHAFFEE, GOODWIN), NRR EO (WESSMAN), R2DO | | (CASTO), PAO (BEECHER), CAO (KEELING), SECY (*BATES), OSP (*BANGART), AND | | OIP (*HAUBER). | | | | * * * UPDATE AT 1500 ON 05/04/97 BY MacKINNON * * * | | | | AT 1445 ON 05/04/97, NRC HEADQUARTERS AND NRC REGION 2 EXITED THE | | MONITORING PHASE OF NORMAL EMERGENCY RESPONSE MODE AFTER THE LICENSEE | | SUCCESSFULLY RAN THE "3C" HPI PUMP TAKING SUCTION FROM THE BORATED WATER | | STORAGE TANK. THE OPERATIONS OFFICER NOTIFIED THE R2DO (CASTO), IRD | | (BARRETT), FEMA (RISHE), DOE (DUNKIN), EPA (CHECKAN), USDA (BICKERTON), AND | | HHS (GRAY). | | | | AT 1500 ON 05/04/97, A COMMISSIONERS' ASSISTANTS BRIEFING WAS HELD. THE | | BRIEFER WAS CHUCK CASTO. PARTICIPANTS INCLUDED (* INDICATED OFFICE DID NOT | | PARTICIPATE): JACKSON (LEE), ROGERS (SORENSEN), DICUS (LUBENAU), DIAZ | | (RADDATZ), McGAFFIGAN (BEALL), NRR (MIRAGLIA), NRR EO (WESSMAN), EAB | | (CHAFFEE), PAO (BEECHER), OSP (BANGART), NRR PM (LaBARGE), SRI (SCOTT), | | REGION 2 (HOLLAND, CHRISTENSEN), AEOD (*ROSS, *BARRETT), OIP (*HAUBER), EDO | | (*TRACY), DEDO (*JORDAN), SECY (*HART), AND CAO (*COMBS). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32272 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FERMI REGION: 3 |NOTIFICATION DATE: 05/04/97 | |UNIT: [2] [ ] [ ] STATE: MI |NOTIFICATION TIME: 14:55 [ET]| |RX TYPE: [2] GE-4 |EVENT DATE: 05/04/97 | +------------------------------------------------+EVENT TIME: 11:34[EDT]| |NRC NOTIFIED BY: COSEO |LAST UPDATE DATE: 05/04/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MARK RING RDO | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 2 | N Y 8 STARTUP | 8 STARTUP | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | HPCI SYSTEM DECLARED INOPERABLE DURING A TECH SPEC SURVEILLANCE TEST. | | | | CONTROL ROOM OPERATORS MANUALLY TRIPPED THE HIGH PRESSURE COOLANT INJECTION | | (HPCI) PUMP AT THE CONCLUSION OF A HPCI PUMP AND VALVE OPERABILITY TEST. | | | | DURING THE HPCI PUMP COASTDOWN, THE AUXILIARY OIL PUMP STARTED BRIEFLY AND | | THEN SHUT DOWN. CONTROL ROOM OPERATORS THEN CYCLED THE AUXILIARY OIL PUMP | | CONTROL SWITCH FROM THE "RUN" POSITION TO THE "OFF/RESET" POSITION AND BACK | | TO THE "RUN" POSITION AND THE PUMP STARTED. | | | | CONTROL ROOM OPERATORS DECLARED THE HPCI SYSTEM INOPERABLE. TECH SPEC LCO | | A/S 3.5.1 REQUIRES THE LICENSEE TO RESTORE THE HPCI SYSTEM TO OPERABLE | | STATUS WITHIN 14 DAYS OR TO SHUT THE PLANT DOWN. THE OTHER EMERGENCY CORE | | COOLING SYSTEMS ARE OPERABLE. | | | | THE LICENSEE IS INVESTIGATING THE CAUSE OF THE AUXILIARY OIL PUMP SHUTDOWN. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32273 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DAVIS BESSE REGION: 3 |NOTIFICATION DATE: 05/04/97 | |UNIT: [1] [ ] [ ] STATE: OH |NOTIFICATION TIME: 19:41 [ET]| |RX TYPE: [1] B&W-R-LP |EVENT DATE: 05/04/97 | +------------------------------------------------+EVENT TIME: 17:35[EDT]| |NRC NOTIFIED BY: LARRY MYERS |LAST UPDATE DATE: 05/04/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MARK RING RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION |DICK WESSMAN EO | |AESF 50.72(b)(2)(ii) ESF ACTUATION |RICH BARRETT IRD | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | A/R Y 100 POWER OPERATION | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | MAIN GENERATOR LOCKOUT/MAIN TURBINE TRIP/AUTO REACTOR TRIP DUE TO MAIN | | TRANSFORMER DELUGE SYSTEM ACTUATION FOR UNKNOWN REASONS | | | | THE MAIN TRANSFORMER DELUGE SYSTEM ACTUATED FOR UNKNOWN REASONS AND STARTED | | THE ELECTRICALLY DRIVEN FIRE PUMP. THE FIRE PUMP SPRAYED WATER ONTO THE | | MAIN TRANSFORMER FOR 2 TO 3 MINUTES WHICH CAUSED A DIFFERENTIAL GROUND ON | | THE MAIN TRANSFORMER. THIS CAUSED THE MAIN GENERATOR TO LOCKOUT WHICH | | CAUSED THE MAIN TURBINE TO TRIP. THE REACTOR AUTOMATICALLY TRIPPED FROM | | 100% POWER. ALL CONTROL RODS FULLY INSERTED INTO THE CORE. THE | | MOTOR-DRIVEN AUXILIARY FEEDWATER PUMP AUTOMATICALLY STARTED TO SUPPLY WATER | | TO BOTH STEAM GENERATORS. STEAM IS BEING DUMPED TO THE MAIN CONDENSER. | | | | ALL CODE SAFETY VALVES AND ATMOSPHERIC RELIEF VALVES ON BOTH ONCE-THROUGH | | STEAM GENERATORS LIFTED. THE #SP17B7 CODE SAFETY VALVE ON #1 STEAM | | GENERATOR DID NOT FULLY CLOSE UNTIL THE MAIN STEAM HEADER PRESSURE HAD BEEN | | REDUCED BELOW 970 PSIG. THE NORMAL LIFT SETPOINT FOR THIS SAFETY VALVE | | (DRESSER INDUSTRIES, MODEL #3777QA-RT21) IS 1,050 PSIG. CONTROL ROOM | | OPERATORS TRIED THREE TIMES TO INCREASE PRESSURE IN #1 STEAM GENERATOR, BUT | | EACH TIME, THE SAFETY VALVE STARTED TO OPEN AT 970 PSIG. CONTROL ROOM | | OPERATORS ARE MAINTAINING PRESSURE IN #1 STEAM GENERATOR AT 940 PSIG. | | | | A HIGH RADIATION ALARM ON THE #1 MAIN STEAM LINE ACTUATED. THE LICENSEE | | TOOK RADIATION SURVEYS OF THE MAIN STEAM LINE, MAIN CONDENSER AIR EJECTORS, | | AND OTHER EQUIPMENT. UNUSUAL RADIATION LEVELS WERE NOT OBSERVED. | | | | THREE OFFSITE ELECTRICAL POWER SOURCES ARE AVAILABLE. OFFSITE ELECTRICAL | | POWER IS BEING FED TO THE PLANT THROUGH THE STARTUP TRANSFORMERS. THE | | LICENSEE INSPECTED THE MAIN TRANSFORMER AND OBSERVED NO PHYSICAL DAMAGE. | | | | THE PLANT IS STABLE IN MODE 3 (HOT STANDBY). | | | | THE LICENSEE IS INVESTIGATING THE CAUSES OF THE MAIN TRANSFORMER DELUGE | | SYSTEM ACTUATION, THE HIGH RADIATION ALARM, AND THE CODE SAFETY VALVE LIFT | | PRESSURE ANOMALY. THE LICENSEE WILL REPAIR/RECALIBRATE/REPLACE THE #SP17B7 | | CODE SAFETY VALVE. | | | | THE LICENSEE INFORMED THE LOCAL SHERIFF THAT THE LOUD NOISE COMING FROM | | THE PLANT WAS DUE TO THE CODE SAFETY AND ATMOSPHERIC RELIEF VALVES LIFTING. | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+