U.S. Nuclear Regulatory Commission Operations Center Event Reports For 04/25/97 - 04/28/97 ** EVENT NUMBERS ** 32184 32209 32219 32220 32221 32222 32223 32224 32225 32226 32227 32228 32229 32230 32231 32232 +----------------------------------+ +-----------------------+ |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. | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32209 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: POINT BEACH REGION: 3 |NOTIFICATION DATE: 04/23/97 | |UNIT: [ ] [2] [ ] STATE: WI |NOTIFICATION TIME: 17:09 [ET]| |RX TYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 04/23/97 | +------------------------------------------------+EVENT TIME: 15:15[CDT]| |NRC NOTIFIED BY: SCHROEDER |LAST UPDATE DATE: 04/25/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MONTE PHILLIPS RDO | |DDDD 73.71 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNIT 2 REPORTED AN UNAUTHORIZED ENTRY INTO THE VITAL AREA. COMPENSATORY | | MEASURES WERE NOT NECESSARY. (REFER TO THE HOO LOG FOR ADDITIONAL | | DETAILS.) | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE AT 1446 ON 04/25/97 FROM SCHWALBE TAKEN BY STRANSKY * * * | | | | THE LICENSEE IS RETRACTING THIS NOTIFICATION. UPON FURTHER REVIEW, THE | | LICENSEE HAS DETERMINED THAT THE UNAUTHORIZED ENTRY (TAILGATING) WAS | | UNINTENTIONAL, AND THEREFORE THIS EVENT IS LOGGABLE, BUT NOT REPORTABLE. | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. THE HOO NOTIFIED R3DO | | (PHILLIPS). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32219 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 04/24/97 | |UNIT: [1] [ ] [ ] STATE: CT |NOTIFICATION TIME: 18:08 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 04/24/97 | +------------------------------------------------+EVENT TIME: 17:30[EDT]| |NRC NOTIFIED BY: PRZEKOP |LAST UPDATE DATE: 04/25/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MCFADDEN 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 +------------------------------------------------------------------------------+ | INSUFFICIENT SEPARATION OF SAFETY AND NONSAFETY ELECTRICAL CIRCUITRY | | | | THE LICENSEE REPORTED THAT INADEQUATE SEPARATION OF SAFETY RELATED AND | | NON-SAFETY RELATED CIRCUITRY COULD CAUSE FAILURES OF THE GAS TURBINE, | | EMERGENCY DIESEL GENERATOR, AND FEEDWATER COOLANT INJECTION SYSTEM. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | | | | HOO NOTE: REFER TO AEOD/92-02, INSIGHTS FROM COMMON MODE FAILURE EVENTS, | | AND TO AEOD/92-02, SUPPLEMENT 1, INSIGHTS FROM COMMON MODE | | FAILURE EVENTS. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32220 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BROWNS FERRY REGION: 2 |NOTIFICATION DATE: 04/24/97 | |UNIT: [ ] [2] [ ] STATE: AL |NOTIFICATION TIME: 20:14 [ET]| |RX TYPE: [1] GE-4,[2] GE-4,[3] GE-4 |EVENT DATE: 04/24/97 | +------------------------------------------------+EVENT TIME: 18:17[CDT]| |NRC NOTIFIED BY: BENNETT |LAST UPDATE DATE: 04/25/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BELISLE RDO | |ACCS 50.72(b)(1)(iv) ECCS INJECTION | | |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 | A/R Y 100 POWER OPERATION | 0 HOT SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AUTOMATIC REACTOR SCRAM AND EMERGENCY CORE COOLING SYSTEM INJECTION DUE TO | | CLOSURE OF THE MAIN STEAM ISOLATION VALVES (MSIV) | | | | AT 1814 CDT, THE UNIT SCRAMMED FROM 100% POWER WHEN ALL MSIVs WENT CLOSED. | | ALL CONTROL RODS INSERTED, AND ONE SAFETY/RELIEF VALVE (SRV) AUTOMATICALLY | | LIFTED TO CONTROL REACTOR PRESSURE. OPERATORS MANUALLY INITIATED REACTOR | | CORE ISOLATION COOLING (RCIC) DUE TO LEVEL SHRINKAGE CAUSED BY THE MSIV | | CLOSURE, AND HIGH PRESSURE COOLANT INJECTION (HPCI) AUTOMATICALLY STARTED | | IN RESPONSE TO LOW REACTOR VESSEL WATER LEVEL AT 1817 CDT. OPERATORS | | CONTINUED TO CYCLE THE OTHER 11 SRVs TO CONTROL REACTOR PRESSURE AND | | MINIMIZE LOCAL HEATING OF THE SUPPRESSION POOL. HPCI HAS BEEN SECURED, AND | | RCIC IS BEING USED TO CONTROL REACTOR VESSEL LEVEL. THE UNIT IS CURRENTLY | | STABLE IN HOT SHUTDOWN. | | | | THE LICENSEE STATED THAT THE CAUSE OF THE MSIV CLOSURE IS UNKNOWN. A | | SURVEILLANCE TEST WAS BEING PERFORMED AT THE TIME OF THE EVENT, BUT IT WAS | | UNRELATED TO THE MSIV LOGIC. THE LICENSEE PLANS TO INVESTIGATE THE CAUSE OF | | THE EVENT. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | | | | * * * UPDATE 1926 4/25/97 FROM SMITH TAKEN BY STRANSKY * * * | | | | THE LICENSEE PROVIDED SOME ADDITIONAL INFORMATION REGARDING THE EVENT. THE | | CAUSE OF THE REACTOR SCRAM WAS A TURBINE TRIP DUE TO A SENSED HIGH REACTOR | | VESSEL WATER LEVEL. THE MSIV CLOSURE WAS DUE TO A SENSED HIGH STEAM FLOW | | CONDITION. THE LICENSEE IS STILL INVESTIGATING THE CAUSE OF THE EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32221 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HADDAM NECK REGION: 1 |NOTIFICATION DATE: 04/25/97 | |UNIT: [1] [ ] [ ] STATE: CT |NOTIFICATION TIME: 12:05 [ET]| |RX TYPE: [1] W-4-LP |EVENT DATE: 04/25/97 | +------------------------------------------------+EVENT TIME: 11:44[EDT]| |NRC NOTIFIED BY: MUIK |LAST UPDATE DATE: 04/25/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MCFADDEN 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 +------------------------------------------------------------------------------+ | LICENSEE NOTIFIED THE STATE REGARDING OIL SHEEN ON SITE POND. | | | | THE LICENSEE NOTIFIED THE CONNECTICUT DEPARTMENT OF ENVIRONMENTAL | | PROTECTION REGARDING A SMALL OIL SHEEN ON THE SURFACE OF THE SITE POND. | | THE LICENSEE STATED THAT SEVERAL OUNCES OF OIL HAVE APPARENTLY BEEN | | WASHED INTO THE POND FROM THE ADJACENT SOIL. THE OIL HAS BEEN CONTAINED, | | AND THE LICENSEE IS PREPARING TO CLEAN UP THE POND SURFACE. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 32222 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 04/25/97 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 13:49 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 04/24/97 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 15:40[CDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 04/25/97 | | CITY: PADUCAH REGION: 3 +-----------------------------+ | COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION| |LICENSE#: GDP-1 AGREEMENT: Y |PHILLIPS RDO | | DOCKET: 0707001 |COMBS EO | +------------------------------------------------+CONGEL IRD | |NRC NOTIFIED BY: UNDERWOOD | | |HQ OPS OFFICER: BOB STRANSKY | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |OCBB 76.120(c)(2)(ii) EQUIP DISABLED/FAILS | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ADDITIONAL SPRINKLER SYSTEM DEFICIENCIES IDENTIFIED. | | | | ADDITIONAL DEFICIENCIES WERE DISCOVERED IN SPRINKLER SYSTEMS A-4, A-5, A-8, | | A-16, B-1, B-4, B-12, B-16, C-8, AND D-1 ASSOCIATED WITH THE C-337 PROCESS | | BUILDING. SEVERAL SMALL TRAILERS INSIDE THE BUILDING AND A CONFERENCE ROOM | | VESTIBULE DO NOT HAVE SPRINKLERS INSTALLED, AS REQUIRED. ADDITIONALLY, | | SEVERAL WIRE MESH CAGES AND WORK PLATFORMS DO HAVE SPRINKLERS INSTALLED, | | BUT THE SPRINKLER HEADS DO NOT PROVIDE UNOBSTRUCTED FLOW. AN HOURLY FIRE | | WATCH WAS POSTED FOR THESE AREAS. THE LICENSEE INFORMED THE NRC RESIDENT | | INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32223 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SEABROOK REGION: 1 |NOTIFICATION DATE: 04/25/97 | |UNIT: [1] [ ] [ ] STATE: NH |NOTIFICATION TIME: 14:53 [ET]| |RX TYPE: [1] W-4-LP |EVENT DATE: 04/25/97 | +------------------------------------------------+EVENT TIME: 11:00[EDT]| |NRC NOTIFIED BY: FREEMAN |LAST UPDATE DATE: 04/25/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |McFADDEN RDO | |NLTR LICENSEE 24 HR REPORT | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | DEFICIENCIES DISCOVERED IN IMPLEMENTATION OF ENVIRONMENTAL PROTECTION PLAN | | | | "SECTION 2.G OF THE SEABROOK STATION OPERATING LICENSE REQUIRES AN INITIAL | | NOTIFICATION OF A VIOLATION OF THE REQUIREMENTS OF SECTION 2.C OF THE | | LICENSE WITHIN 24 HOURS. ONE OF THE CONDITIONS CONTAINED IN SECTION 2.C | | REQUIRES THAT SEABROOK STATION BE OPERATED IN ACCORDANCE WITH THE | | ENVIRONMENTAL PROTECTION PLAN. | | | | NORTH ATLANTIC (LICENSEE) HAS IDENTIFIED THREE DEFICIENCIES IN ITS | | IMPLEMENTATION OF APPENDIX B, THE ENVIRONMENTAL PROTECTION PLAN (EPP). | | | | 1. THE EPP ALLOWS NORTH ATLANTIC TO MAKE CHANGES IN STATION DESIGN OR | | OPERATION OR PERFORM TESTS OR EXPERIMENTS AFFECTING THE ENVIRONMENT AS LONG | | AS THE ACTIVITIES DO NOT INVOLVE AN UNREVIEWED ENVIRONMENTAL QUESTION AND | | DO NOT INVOLVE A CHANGE IN THE EPP. NORTH ATLANTIC HAS NO PROGRAM FOR | | CONDUCTING SUCH EVALUATIONS. WHILE DESIGN CHANGES ARE EVALUATED AGAINST A | | LIMITED SET OF ENVIRONMENTAL CRITERIA IN ACCORDANCE WITH THE DESIGN CONTROL | | MANUAL, NOT ALL OF THE CRITERIA REQUIRED BY THE EPP ARE ADDRESSED. FURTHER, | | THERE IS NO REVIEW OF NEW PROCEDURES, PROCEDURE REVISIONS OR MANUAL | | REVISIONS FOR UNREVIEWED ENVIRONMENTAL QUESTIONS OR CHANGES TO THE EPP. | | | | 2. THE EPP REQUIRES THAT 'ANY OCCURRENCE OF AN UNUSUAL OR IMPORTANT EVENT | | THAT INDICATES OR COULD RESULT IN SIGNIFICANT ENVIRONMENTAL IMPACT CAUSALLY | | RELATED TO PLANT OPERATION BE RECORDED AND REPORTED TO THE NRC WITHIN 24 | | HOURS FOLLOWED BY A WRITTEN REPORT PER SUBSECTION 5.4.2.' FOR EVENTS | | REPORTABLE TO OTHER AGENCIES, SUBSECTION 5.4.2 REQUIRES THAT THE NRC BE | | PROVIDED A COPY OF THE REPORT AT THE TIME THAT IT IS SUBMITTED TO ANOTHER | | AGENCY. THE IMPINGEMENT OF HARBOR SEALS BY SEABROOK STATION ON A NUMBER OF | | OCCASIONS BEGINNING IN 1993 ARE VIOLATIONS OF THE MARINE MAMMAL PROTECTION | | ACT AND CAN BE CONSIDERED IMPORTANT EVENTS. ALTHOUGH THE IMPINGEMENTS WERE | | REPORTED TO THE NATIONAL MARINE FISHERIES AGENCY (ORALLY PRIOR TO 1995 AND | | IN WRITING BEGINNING IN 1995), THE NRC WAS NOT PROVIDED A COPY OF THESE | | REPORTS. | | | | 3. THE EPP REQUIRES THAT A COPY OF A PROPOSED CHANGE TO THE NPDES PERMIT BE | | PROVIDED TO THE NRC AT THE SAME TIME THAT IT IS SENT TO THE PERMITTING | | AGENCY AND THAT CHANGES TO THE NPDES PERMIT BE REPORTED TO THE NRC WITHIN | | 30 DAYS OF THEIR APPROVAL. CONTRARY TO THESE REQUIREMENTS, ON 1/13/95 NORTH | | ATLANTIC REQUESTED A CHANGE TO THE NPDES PERMIT TO ALLOW THE USE OF MPA AND | | DID NOT PROVIDE A COPY TO THE NRC. IN ADDITION, WHEN THE PERMIT CHANGE WAS | | GRANTED BY THE EPA ON APRIL 13, 1995, A COPY OF THE CHANGE APPROVAL WAS NOT | | SUBMITTED TO THE NRC." | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 32224 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 04/25/97 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 15:39 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 04/24/97 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 20:56[CDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 04/25/97 | | CITY: PADUCAH REGION: 3 +-----------------------------+ | COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION| |LICENSE#: GDP-1 AGREEMENT: Y |PHILLIPS RDO | | DOCKET: 0707001 |COMBS EO | +------------------------------------------------+CONGEL IRD | |NRC NOTIFIED BY: UNDERWOOD | | |HQ OPS OFFICER: BOB STRANSKY | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |OCBB 76.120(c)(2)(ii) EQUIP DISABLED/FAILS | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AUTOCLAVE DECLARED INOPERABLE DUE TO EXCESSIVELY SLOW CLOSURE TIMES FOR | | ISOLATION VALVES. | | | | THE AUTOCLAVE IN FEED VAPORIZATION FACILITY C-337A WAS DECLARED INOPERABLE | | WHEN VALVES XV-532 (STEAM SAMPLE ISOLATION VALVE) AND CV-533 (STEAM SAMPLE | | BYPASS VALVE) WERE DISCOVERED TO HAVE CLOSURE TIMES IN EXCESS OF THE | | REQUIRED 10 SECONDS. BOTH VALVES APPEAR TO BE STICKING WHEN OPERATED IN THE | | CLOSE DIRECTION. THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 32225 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: U.S. AIR FORCE |NOTIFICATION DATE: 04/25/97 | | CITY: TUSCON REGION: 4 |NOTIFICATION TIME: 17:23 [ET]| | COUNTY: PIMA STATE: AZ |EVENT DATE: 04/24/97 | |LICENSE#: 42-23539-01AF AGREEMENT: Y |EVENT TIME: 17:23[MDT]| | DOCKET: 03028641 |LAST UPDATE DATE: 04/25/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |COLLINS RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: J. HICKS | | |HQ OPS OFFICER: BOB STRANSKY | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |BAE1 20.2202(b)(1) PERS OVEREXPOSURE | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | FOUR INDIVIDUALS POTENTIALLY EXPOSED TO DEPLETED URANIUM. | | | | FOUR MAINTENANCE WORKERS AT THE DAVIS-MONTHAN AIR FORCE BASE WERE POSSIBLY | | EXPOSED TO DEPLETED URANIUM WHEN THEY ATTEMPTED TO USE CHEMICAL CLEANER TO | | DEGREASE A PAINTED COUNTERWEIGHT, FROM WHICH SOME PAINT WAS FLAKING. THE | | ALKALINE SOAP AND BRUSH THAT THEY WERE USING STRIPPED OFF THE PAINT, | | EXPOSING THE DEPLETED URANIUM. ONE INDIVIDUAL WAS FOUND TO HAVE | | CONTAMINATION ON HIS HANDS, AND SOME CONTAMINATION WAS DETECTED ON RAGS | | USED TO CLEAN THE COUNTERWEIGHT. NO AIRBORNE CONTAMINATION WAS DETECTED. | | | | USAF CALCULATIONS DETERMINED THAT NONE OF THE WORKERS WOULD HAVE RECEIVED | | AN UPTAKE IN EXCESS OF 1 ANNUAL LIMIT ON INTAKE (ALI) FOR URANIUM-238 DUE | | TO THIS EVENT. (THE INDIVIDUALS WOULD HAVE HAD TO INGEST AT LEAST 30 GRAMS | | OF URANIUM EACH TO RECEIVE 1 ALI.) THE CONTAMINATED INDIVIDUAL WAS | | DECONTAMINATED, AND BIOASSAYS ARE BEING PERFORMED ON EACH OF THE | | INDIVIDUALS. | | | | THE CALLER STATED THAT THIS BASE IS NOT AUTHORIZED TO CLEAN OR STRIP PAINT | | FROM DEPLETED URANIUM COUNTERWEIGHTS. THE LICENSEE PLANS TO CONTACT NRC | | REGION IV DIRECTLY REGARDING THIS EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |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: 04/25/97 | |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. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32227 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OCONEE REGION: 2 |NOTIFICATION DATE: 04/26/97 | |UNIT: [1] [2] [3] STATE: SC |NOTIFICATION TIME: 12:22 [ET]| |RX TYPE: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-LP |EVENT DATE: 04/26/97 | +------------------------------------------------+EVENT TIME: 11:30[EDT]| |NRC NOTIFIED BY: DAVID NIX |LAST UPDATE DATE: 04/26/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |AL BELISLE 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 COLD SHUTDOWN | 0 COLD SHUTDOWN | | 3 | N Y 100 POWER OPERATION | 100 POWER OPERATION | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | PORTIONS OF THE LOW PRESSURE SERVICE WATER (LPSW) SYSTEM DO NOT MEET OCONEE | | UPDATED FINAL SAFETY ANALYSIS REPORT (UFSAR) DESIGN REQUIREMENTS FOR HIGH | | TRAJECTORY TURBINE GENERATED MISSILES. | | | | THE OCONEE UFSAR, SECTION 3.1.40, REQUIRES THAT ENGINEERED SAFETY FEATURES | | BE PROTECTED FROM TURBINE GENERATED MISSILES BY MEANS OF SHIELDING OR | | SEPARATION. THE OCONEE UFSAR IS NOT SPECIFIC REGARDING THE USE OF | | SEPARATION OR SHIELDING, HOWEVER, THE APPLICATION OF THE SPECIFIC DESIGN | | REQUIREMENTS ARE DELINEATED IN OCONEE INTERNAL DESIGN DOCUMENTS. THE OCONEE | | UFSAR IS ALSO SPECIFIC ABOUT WHAT TYPES OF TURBINE GENERATED MISSILES MUST | | BE DESIGNED FOR, SUCH AS HIGH TRAJECTORY AND LOW TRAJECTORY MISSILES. AS A | | RESULT, IT IS CONSERVATIVELY ASSUMED THAT OCONEE MUST BE DESIGNED FOR BOTH | | HIGH TRAJECTORY AND LOW TRAJECTORY TURBINE MISSILES. | | | | ON 04/26/97, IT WAS CONSERVATIVELY CONCLUDED THAT PORTIONS OF OCONEE'S LPSW | | SYSTEM PIPING ON UNITS 1, 2, AND 3 DOES NOT MEET THE OCONEE UFSAR DESIGN | | REQUIREMENTS FOR HIGH TRAJECTORY TURBINE MISSILES. SPECIFICALLY, THERE ARE | | TWO PORTIONS OF LPSW SYSTEM PIPING WHICH ARE NOT SUFFICIENTLY SEPARATED TO | | PROTECT AGAINST LOSS OF REDUNDANT LPSW SYSTEM TRAINS IF A HIGH TRAJECTORY | | TURBINE MISSILE WERE TO OCCUR. THE LPSW SYSTEM SERVES AS A SAFETY-RELATED | | HEAT SINK DURING CERTAIN DESIGN BASIS ACCIDENTS AND IS CONSIDERED AN | | ENGINEERED SAFEGUARDS SYSTEM. | | | | CURRENT INDUSTRY AND NRC GUIDANCE FOR TURBINE MISSILE DESIGN PERMITS | | CONSIDERATIONS FOR VULNERABLE TARGET AREA AND PROBABILITY OF IMPACT OF A | | TURBINE MISSILE PRIOR TO MANDATING SHIELDING OR SEPARATION PROTECTION. | | OCONEE'S UFSAR CURRENTLY DOES NOT PROVIDE THIS LEVEL OF FLEXIBILITY. THE | | LICENSEE HAS IDENTIFIED THIS ISSUE AS AN UNREVIEWED SAFETY QUESTION AND | | WILL SUBMIT A LICENSE AMENDMENT TO THE NRC BY 04/29/97 TO CLARIFY THE | | TURBINE MISSILE DESIGN CRITERIA IN OCONEE'S UFSAR. IN ADDITION, THE | | LICENSEE WILL REQUEST TO ADOPT CURRENT INDUSTRY AND NRC RECOMMENDED DESIGN | | PRACTICES WITH RESPECT TO TURBINE MISSILES. | | | | THE LICENSEE WILL SUBMIT A LICENSEE EVENT REPORT WHICH WILL PROVIDE DETAILS | | OF THE ROOT CAUSE AND CORRECTIVE ACTIONS FOR THIS EVENT. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 32228 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 04/26/97 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 12:34 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 04/25/97 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 13:00[CDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 04/26/97 | | CITY: PADUCAH REGION: 3 +-----------------------------+ | COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION| |LICENSE#: GDP-1 AGREEMENT: Y |MONTE PHILLIPS RDO | | DOCKET: 0707001 |JOHN HICKEY (NMSS) EO | +------------------------------------------------+ | |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 SPRINKLER SYSTEM DEFICIENCIES IDENTIFIED AT PADUCAH. | | | | ADDITIONAL INSPECTIONS OF THE HIGH PRESSURE FIRE WATER SPRINKLER SYSTEMS IN | | THE PLANT PROCESS BUILDINGS WERE PERFORMED AT PADUCAH. IN THE C-333 PROCESS | | BUILDING, FLOW RESTRICTING ORIFICES WERE DETERMINED TO BE MISSING FROM | | THE INSPECTOR TEST VALVES ON SYSTEMS B-9 AND D-1. IN THE C-335 PROCESS | | BUILDING, FLOW RESTRICTING ORIFICES WERE DETERMINED TO BE MISSING FROM | | THE INSPECTOR TEST VALVES ON SYSTEMS 2, 28, AND 33. THE MISSING ORIFICES | | INVALIDATE THE RESULTS OF ANNUAL TSR SURVEILLANCE TEST #2.4.4.5-2 (HIGH | | PRESSURE FIRE WATER SYSTEM). | | | | THE AFFECTED SPRINKLER SYSTEMS WERE DECLARED INOPERABLE AND HOURLY FIRE | | PATROLS WERE INITIATED 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 REPORTS | | #32148, #32162, #32170, #32215 AND #32222. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32229 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FT CALHOUN REGION: 4 |NOTIFICATION DATE: 04/26/97 | |UNIT: [1] [ ] [ ] STATE: NE |NOTIFICATION TIME: 18:26 [ET]| |RX TYPE: [1] CE |EVENT DATE: 04/26/97 | +------------------------------------------------+EVENT TIME: 16:53[CDT]| |NRC NOTIFIED BY: LEES |LAST UPDATE DATE: 04/26/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: UNUSUAL EVENT +-----------------------------+ |10 CFR SECTION: |COLLINS RDO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |VARGA EO | | |SWITZER FEMA | | |CONGEL IRD | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | UNUSUAL EVENT DECLARED DUE TO INCREASED STAFF AWARENESS DUE TO A CCW LEAK. | | | | WHILE PERFORMING A PLANT MODIFICATION TO ABANDON A WASTE EVAPORATOR, | | MAINTENANCE DEPARTMENT PERSONNEL WERE PREPARING TO CAP A COMPONENT COOLING | | WATER (CCW) SYSTEM PIPE AS PART OF A PLANT MODIFICATION. WHEN THE PIPE | | WAS CUT, IT BEGAN TO LEAK AT A RATE OF APPROXIMATELY 10 GALLONS PER MINUTE. | | | | AT 1635 (CDT), CONTROL ROOM OPERATORS ENTERED PLANT ABNORMAL OPERATING | | PROCEDURE #AOP-11, "LOSS OF COMPONENT COOLING WATER SYSTEM," DUE TO THE | | POTENTIAL LOSS OF CCW CAUSED BY THE LEAK. CONTROL ROOM OPERATORS TRIPPED | | ONE OF THE CCW PUMPS WHICH REDUCED SYSTEM PRESSURE AND THE LEAK RATE TO | | APPROXIMATELY 2 OUNCES PER MINUTE. | | | | AT 1653 (CDT), CONTROL ROOM OPERATORS DECLARED AND TERMINATED AN UNUSUAL | | EVENT DUE TO INCREASED PLANT STAFF AWARENESS (EAL 11.6). | | | | AT 1705 (CDT), MAINTENANCE DEPARTMENT PERSONNEL WELDED A CAP ONTO THE END | | OF THE PIPE TERMINATING THE LEAK. | | | | THE LICENSEE NOTIFIED STATE OFFICIALS AND THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32230 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SUMMER REGION: 2 |NOTIFICATION DATE: 04/27/97 | |UNIT: [1] [ ] [ ] STATE: SC |NOTIFICATION TIME: 00:36 [ET]| |RX TYPE: [1] W-3-LP |EVENT DATE: 04/26/97 | +------------------------------------------------+EVENT TIME: 20:43[EDT]| |NRC NOTIFIED BY: MIKE FOWLKES |LAST UPDATE DATE: 04/27/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |AL BELISLE 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | A/R Y 6 POWER OPERATION | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | -AUTO Rx TRIP FROM 6% POWER DUE TO MAIN FEEDWATER FLOW CONTROLS MALFUNCTION | | | | DURING POWER ESCALATION, CONTROL ROOM OPERATORS WERE MAKING ADJUSTMENTS TO | | MAIN FEEDWATER FLOW. MAIN FEEDWATER FLOW CONTROLS APPEARED NOT TO BE | | FUNCTIONING PROPERLY. THIS RESULTED IN AN ISOLATION OF THE MAIN FEEDWATER | | SYSTEM AND A TRIP OF THE MAIN TURBINE DUE TO AN ACTUAL HIGH HIGH STEAM | | GENERATOR WATER LEVEL SIGNAL. REACTOR OPERATORS MANUALLY REDUCED REACTOR | | POWER FROM 42% POWER. | | | | AT 6% POWER, THE REACTOR PROTECTION SYSTEM AUTOMATICALLY TRIPPED THE | | REACTOR DUE TO AN ACTUAL LOW LOW WATER LEVEL IN THE 'A' STEAM GENERATOR. | | ALL CONTROL RODS INSERTED COMPLETELY. THE EMERGENCY FEEDWATER SYSTEM | | ACTUATED, AS EXPECTED. ALL STEAM GENERATOR WATER LEVELS HAVE RETURNED | | TO THEIR NORMAL RANGE. STEAM IS BEING DUMPED TO THE MAIN CONDENSER. | | THE PLANT IS STABLE IN MODE 3 (HOT STANDBY). | | | | THE LICENSEE IS PERFORMING A POST TRIP REVIEW TO DETERMINE THE CAUSE OF THE | | MAIN FEEDWATER FLOW CONTROL MALFUNCTION. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 32231 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 04/27/97 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 13:53 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 04/26/97 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 14:30[CDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 04/27/97 | | CITY: PADUCAH REGION: 3 +-----------------------------+ | COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION| |LICENSE#: GDP-1 AGREEMENT: Y |MONTE PHILLIPS RDO | | DOCKET: 0707001 |JOHN HICKEY EO | +------------------------------------------------+ | |NRC NOTIFIED BY: UNDERWOOD | | |HQ OPS OFFICER: BOB STRANSKY | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |OCBB 76.120(c)(2)(ii) EQUIP DISABLED/FAILS | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | FIRE SPRINKLER DEFICIENCIES IDENTIFIED IN C-315 AND C-337 BUILDINGS | | | | SEVERAL ADDITIONAL DEFICIENCIES IN THE FIRE SPRINKLER SYSTEM HAVE BEEN | | IDENTIFIED. IN THE C-315 BUILDING, A BRANCH LINE IS MISSING THREE | | SPRINKLER HEADS, AND ANOTHER BRANCH LINE HAS SPRINKLER HEADS LOCATED TOO | | FAR FROM THE CEILING. IN THE C-337 BUILDING, A FLOW RESTRICTING ORIFICE | | FROM THE INSPECTOR'S TEST CONNECTION IS MISSING ON SYSTEM A-5, INVALIDATING | | THE RESULTS OF THE ANNUAL SURVEILLANCE TEST. HOURLY FIRE WATCHES HAVE BEEN | | INITIATED FOR THE AREAS AFFECTED. THE NRC RESIDENT INSPECTOR HAS BEEN | | INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |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: 04/28/97 | |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 STATION UNITERRUPTIBLE POWER SUPPLY #1D. THE LICENSEE PLANS TO REMOVE | | THE #1D POWER SUPPLY 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. | +------------------------------------------------------------------------------+