U.S. Nuclear Regulatory Commission Operations Center Event Reports For 09/11/97 - 09/12/97 ** EVENT NUMBERS ** 32907 32908 32909 32910 32911 32912 32913 32914 32915 32916 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32907 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: LASALLE REGION: 3 |NOTIFICATION DATE: 09/11/97 | |UNIT: [1] [2] [ ] STATE: IL |NOTIFICATION TIME: 10:34 [ET]| |RX TYPE: [1] GE-5,[2] GE-5 |EVENT DATE: 09/11/97 | +------------------------------------------------+EVENT TIME: 08:20[CDT]| |NRC NOTIFIED BY: WILLIAM BARTLETT |LAST UPDATE DATE: 09/11/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRENT CLAYTON 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 COLD SHUTDOWN | 0 COLD SHUTDOWN | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - FITNESS-FOR-DUTY REPORT - | | | | A LICENSED NUCLEAR STATION OPERATOR WAS CONFIRMED POSITIVE FOR DRUGS. THE | | COMMONWEALTH EDISON EMPLOYEE WAS GIVEN A PRE-ACCESS DRUG SCREEN TEST (HAD | | BEEN OFF SITE MORE THAN 60 DAYS). THE FIRST TEST WAS INCONCLUSIVE, AND THE | | RETEST WAS POSITIVE. AFTER A MEDICAL REVIEW OF THE DRUG TESTS AND OF THE | | EMPLOYEE, THE EMPLOYEE WAS CONFIRMED POSITIVE FOR DRUGS. THE EMPLOYEE'S | | ACCESS BADGE WAS PLACED ON HOLD, AND HE IS NOT ALLOWED ACCESS INTO THE | | PROTECTED AREA. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32908 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MCGUIRE REGION: 2 |NOTIFICATION DATE: 09/11/97 | |UNIT: [1] [2] [ ] STATE: NC |NOTIFICATION TIME: 10:53 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 09/11/97 | +------------------------------------------------+EVENT TIME: 10:20[EDT]| |NRC NOTIFIED BY: AL YODER |LAST UPDATE DATE: 09/11/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CAUDLE JULIAN RDO | |ADEG 50.72(b)(1)(ii) DEGRAD COND DURING OP | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DENSITY FOR THE BORAFLEX IN UNIT 1 AND 2 SPENT FUEL POOLS FOUND TO BE BELOW | | INPUT ASSUMPTIONS IN THE SAFETY ANALYSIS | | | | TECHNICAL SPECIFICATION 3.9.13 SPENT FUEL STORAGE IS POTENTIALLY | | NON-CONSERVATIVE DUE TO POTENTIAL BORAFLEX DEGRADATION. PRELIMINARY VENDOR | | RESULTS FROM BORAFLEX TESTING SHOWED BELOW THE INPUT ASSUMPTION IN THE | | SAFETY ANALYSIS. WITH CONSERVATISMS SUCH AS BORON AND CURRENT LOADING | | CONFIGURATION, Keff < 0.95 IS BEING MET. FINAL BORAFLEX TESTING RESULTS | | WILL DETERMINE ACTUAL REPORTABILITY. THE LICENSEE IS ADDING BORON TO THE | | UNIT 1 AND UNIT 2 SPENT FUEL POOLS TO INCREASE THE BORON CONCENTRATION. | | | | THE NRC RESIDENT INSPECTOR WILL BE NOTIFIED OF THE EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 32909 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 09/11/97 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 14:18 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 09/11/97 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 03:00[CDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 09/11/97 | | CITY: PADUCAH REGION: 3 +-----------------------------+ | COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION| |LICENSE#: GDP-1 AGREEMENT: Y |BRENT CLAYTON RDO | | DOCKET: 0707001 |FRED COMBS, NMSS EO | +------------------------------------------------+ | |NRC NOTIFIED BY: W. F. CAGE | | |HQ OPS OFFICER: STEVE SANDIN | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |OCBA 76.120(c)(2)(i) ACCID MT EQUIP FAILS | | |OCBB 76.120(c)(2)(ii) EQUIP DISABLED/FAILS | | |OCBC 76.120(c)(2)(iii) REDUNDANT EQUIP INOP | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | FREEZER SUBLIMER DECLARED INOPERABLE DUE TO TRIPPED RCW PUMP. | | | | THE FOLLOWING TEXT IS A PORTION OF A FACSIMILE RECEIVED FROM PADUCAH: | | | | "ON 9/11/97 AT 0300 CDT, THE RECIRCULATING WATER (RCW) PUMP FOR THE C-333 | | UNIT 2, CELL 2 FREEZER-SUBLIMER WAS DISCOVERED TRIPPED DURING | | TROUBLESHOOTING OF AN RCW TEMPERATURE ALARM. THIS WAS DISCOVERED WHEN THE | | FREEZER SUBLIMER WAS IN MODE F/S 3 (COLD STANDBY). THE RCW PUMP IS | | REQUIRED BY TSR 2.4.3.1 TO BE AVAILABLE AND OPERABLE WHEN THE FREEZER | | SUBLIMER IS IN MODE F/S 3. THE FREEZER SUBLIMER WAS DECLARED INOPERABLE | | AND PLACED OUT OF SERVICE (MODE F/S 6) IN ACCORDANCE WITH TSR 2.4.3.1." | | | | "THIS EVENT IS REPORTABLE PER PROCEDURE UE2-RA-RE1030, APPENDIX D, CRITERIA | | J.1, SAFETY EQUIPMENT FAILURE." | | | | THE FREEZER SUBLIMER ALLOWS FOR REDUCTION/ADDITION OF PROCESS STREAM BY | | REMOVAL OF UF6 WITH A CHANGE OF STATE. THE RCW PUMP IS DEDICATED TO A | | PARTICULAR FREEZER SUBLIMER UNIT AND DOES NOT AFFECT ANY OTHER PLANT | | EQUIPMENT. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32910 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: TURKEY POINT REGION: 2 |NOTIFICATION DATE: 09/11/97 | |UNIT: [3] [ ] [ ] STATE: FL |NOTIFICATION TIME: 14:23 [ET]| |RX TYPE: [3] W-3-LP,[4] W-3-LP |EVENT DATE: 09/11/97 | +------------------------------------------------+EVENT TIME: 13:55[EDT]| |NRC NOTIFIED BY: CRAIG MOWREY |LAST UPDATE DATE: 09/11/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CAUDLE JULIAN 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 3 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DISCOVERY OF A GAP IN THE UNIT 3 CONTAINMENT RECIRCULATION SUMP SCREENS | | GREATER THAN THE 1/4-INCH MESH SIZE SPECIFIED BY DESIGN | | | | DURING A PLANNED UNIT 4 REFUELING INSPECTION OF THE EMERGENCY CORE COOLING | | SYSTEM CONTAINMENT RECIRCULATION SUMP SCREENS, GAPS WERE FOUND THAT | | EXCEEDED THE 1/4-INCH MESH SIZE SPECIFIED IN THE UNIT'S UPDATED FINAL | | SAFETY ANALYSIS REPORT. THE SCREENS ARE REQUIRED TO PREVENT MATERIAL | | GREATER THAN 1/4-INCH FROM ENTERING THE EMERGENCY CORE COOLING SYSTEMS | | DURING THE RECIRCULATION PHASE FOLLOWING A LOSS OF COOLANT ACCIDENT. | | | | AS PART OF THE CORRECTIVE ACTION, THE UNIT 3 SUMP SCREENS WERE INSPECTED | | THIS AFTERNOON. A GAP EXCEEDING 1/4" WAS FOUND. BECAUSE THE GAP FOUND | | EXCEEDED THAT SPECIFIED BY DESIGN, THE PLANT WAS OPERATED OUTSIDE THE | | DESIGN BASIS. | | | | AN EVALUATION IS IN PROGRESS TO DETERMINE THE ACTUAL SAFETY SIGNIFICANCE OF | | THE DISCOVERIES (ON BOTH UNIT 3 AND UNIT 4). THE GAP ON UNIT 3 HAS BEEN | | REPAIRED. THE LICENSEE PLANS TO REPAIR THE GAPS ON UNIT 4 PRIOR TO PLACING | | UNIT 4 IN MODE 4. (UNIT 4 IS CURRENTLY IN MODE 6 AS PART OF A REFUELING | | OUTAGE.) | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32911 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BYRON REGION: 3 |NOTIFICATION DATE: 09/11/97 | |UNIT: [ ] [2] [ ] STATE: IL |NOTIFICATION TIME: 14:46 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 09/11/97 | +------------------------------------------------+EVENT TIME: 13:00[CDT]| |NRC NOTIFIED BY: STEVEN PIERSON |LAST UPDATE DATE: 09/11/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRENT CLAYTON RDO | |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 Y 99 POWER OPERATION | 88 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNIT 2 COMMENCED A TECH SPEC REQUIRED SHUTDOWN AFTER DETERMINING THAT | | SCHEDULED MAINTENANCE ON A CENTRIFUGAL CHARGING PUMP (CCP) WOULD NOT BE | | COMPLETED WITHIN THE 72 HOURS ALLOWED BY TECHNICAL SPECIFICATIONS. | | | | THE FOLLOWING TEXT IS A PORTION OF A FACSIMILE RECEIVED FROM THE LICENSEE: | | | | "UNIT 2 HAS INITIATED A SHUTDOWN REQUIRED BY TECH SPEC 3.1.2.4. CENTRIFUGAL | | CHARGING PUMP '2B' BECAME INOPERABLE AT 2000 CDT ON 9/8/97 FOR SCHEDULED | | MAINTENANCE. THE PUMP SEAL LEAKAGE WAS NOT ABLE TO BE VERIFIED WITHIN | | ALLOWABLE LIMITS PRIOR TO STATION ADMINISTRATIVE PROCEDURE REQUIRED | | SHUTDOWN TO COMPLY WITH TECH SPEC 3.1.2.4. THE SHUTDOWN WAS INITIATED AT | | 1300 CDT ON 9/11/97. THE STATION INTENDS TO BE IN MODE 3 PRIOR TO REACHING | | THE TECH SPEC ACTION TIME OF 2000 CDT ON 9/11/97." | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE 1650 EDT ON 9/11/97 FROM STEVEN PIERSON TO S. SANDIN * * * | | | | UNIT 2 EXITED THE LCO A/S AT 1525 CDT WITH THE UNIT AT 77% POWER AFTER | | DECLARING THE '2B' CCP OPERABLE. THE LICENSEE INTENDS TO RETURN TO FULL | | POWER OPERATION. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. THE NRC OPERATIONS | | CENTER NOTIFIED THE R3DO (CLAYTON). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32912 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: TURKEY POINT REGION: 2 |NOTIFICATION DATE: 09/11/97 | |UNIT: [3] [4] [ ] STATE: FL |NOTIFICATION TIME: 17:35 [ET]| |RX TYPE: [3] W-3-LP,[4] W-3-LP |EVENT DATE: 09/11/97 | +------------------------------------------------+EVENT TIME: 16:10[EDT]| |NRC NOTIFIED BY: CRAIG MOWREY |LAST UPDATE DATE: 09/11/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CAUDLE JULIAN RDO | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION |SUSAN SHANKMAN, NMSS EO | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 3 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | 4 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LICENSEE NOTIFIED STATE OF FLORIDA CONCERNING ARRIVAL ON SITE OF | | CONTRACTOR'S TRAILER WITH LOW LEVELS OF CONTAMINATION. | | | | THE FOLLOWING TEXT IS A PORTION OF A FACSIMILE RECEIVED FROM THE LICENSEE: | | | | "WHILE SURVEYING A SNUBBER TESTING TRAILER ARRIVING ON SITE FOR THE CURRENT | | UNIT 4 REFUELING OUTAGE, TURKEY POINT HEALTH PHYSICS PERSONNEL DISCOVERED | | LOW LEVELS OF CONTAMINATION. THE OWNER OF THE TRAILER IS NOT LICENSED TO | | RECEIVE BYPRODUCT MATERIAL. THE SURVEY IS NOT YET COMPLETE. THE HIGHEST | | LEVELS OF FIXED CONTAMINATION DISCOVERED SO FAR ARE ABOUT 3,000 | | DISINTEGRATIONS PER MINUTE (FOUND WITH A BETA SCINTILLATION PROBE). THE | | HIGHEST LEVELS OF SMEARABLE CONTAMINATION DISCOVERED SO FAR ARE ABOUT 80 | | DISINTEGRATIONS PER MINUTE PER 100 SQUARE CENTIMETERS (COUNTED WITH AN MDA | | SCALAR). FLORIDA POWER & LIGHT COMPANY HAS NOTIFIED THE STATE OF FLORIDA, | | DEPARTMENT OF HEALTH, BUREAU OF RADIATION CONTROL, OF THE DISCOVERY. THE | | TRAILER IS NOW BEING HELD INSIDE THE TURKEY POINT RADIATION CONTROLLED | | AREA." | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32913 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: LASALLE REGION: 3 |NOTIFICATION DATE: 09/11/97 | |UNIT: [1] [2] [ ] STATE: IL |NOTIFICATION TIME: 18:13 [ET]| |RX TYPE: [1] GE-5,[2] GE-5 |EVENT DATE: 09/11/97 | +------------------------------------------------+EVENT TIME: 15:00[CDT]| |NRC NOTIFIED BY: JIM SPIELER |LAST UPDATE DATE: 09/11/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRENT CLAYTON 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 | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LICENSEE IDENTIFIED A NON-CONSERVATIVE VALVE CLOSURE TIME USED IN A HIGH | | ENERGY LINE BREAK ANALYSIS. | | | | THE FOLLOWING TEXT IS A PORTION OF A FACSIMILE RECEIVED FROM THE LICENSEE: | | | | "[THE LICENSEE] DISCOVERED THAT THE ORIGINAL HIGH ENERGY LINE BREAK (HELB) | | ANALYSIS FOR THE UNIT 1 REACTOR WATER CLEAN UP (RWCU) ROOM MAY NOT BE | | CONSERVATIVE. THIS IS BECAUSE THE EVENT IS TERMINATED BY CLOSURE OF | | PRIMARY CONTAINMENT ISOLATION VALVES '1G33-F001' AND '1G33-F004', AND THE | | ANALYSIS USED A CLOSURE TIME OF 18 SECONDS WHILE ACTUAL VALVE CLOSURE TIME | | IS APPROXIMATELY LESS THAN OR EQUAL TO 30 SECONDS. A PRELIMINARY | | ASSESSMENT OF SIGNIFICANCE OF THIS HAS DETERMINED THAT IT WILL INCREASE THE | | PEAK TEMPERATURE IN ADJACENT REACTOR BUILDING AREAS FROM 145 DEGREES F TO | | APPROXIMATELY 160 DEGREES F FOR A VERY SHORT TIME PERIOD (i.e., A FEW | | MINUTES). THIS IN TURN WILL IMPACT THE ENVIRONMENTAL QUALIFICATION OF | | COMPONENTS LOCATED IN THESE AREAS. BECAUSE THE DURATION OF THIS | | TEMPERATURE EXCURSION IS VERY SHORT, THE IMPACT UPON ENVIRONMENTAL | | QUALIFICATION IS EXPECTED TO BE SMALL, POSSIBLY NEGLIGIBLE. THIS ISSUE IS | | CONSIDERED TO ALSO BE APPLICABLE TO UNIT 2; HOWEVER, THIS HAS NOT BEEN | | CONFIRMED AT THIS TIME." | | | | THIS CONDITION WAS DISCOVERED BY ENGINEERING DURING A DESIGN REVIEW. AN | | ONGOING INVESTIGATION WILL IDENTIFY THE COMPONENTS AFFECTED IN THE ADJACENT | | REACTOR BUILDING AREAS AND APPROPRIATE CORRECTIVE ACTIONS. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32914 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOK REGION: 3 |NOTIFICATION DATE: 09/11/97 | |UNIT: [1] [2] [ ] STATE: MI |NOTIFICATION TIME: 19:50 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 09/11/97 | +------------------------------------------------+EVENT TIME: 16:15[EDT]| |NRC NOTIFIED BY: MARY BETH DePUYDT |LAST UPDATE DATE: 09/11/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRENT CLAYTON 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 | | 2 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LICENSEE IDENTIFIED THAT BOTH UNITS HAD OPERATED THEIR RHR SYSTEM CONTRARY | | TO THE DESCRIPTION IN THE FSAR. | | | | THE FOLLOWING TEXT IS A PORTION OF A FACSIMILE RECEIVED FROM THE LICENSEE: | | | | "AT 1615 EDT, WITH UNITS 1 AND 2 SHUTDOWN IN MODE 5, IT WAS DETERMINED THAT | | BOTH UNITS HAVE OPERATED CONTRARY TO THE DESIGN BASIS FOR THE RESIDUAL HEAT | | REMOVAL (RHR) SYSTEM AS DESCRIBED IN THE FSAR. FSAR CHAPTER 9, SECTION | | 9.3, DESCRIBES THE INTERLOCKS ASSOCIATED WITH THE RHR SUCTION VALVES FROM | | THE REACTOR COOLANT SYSTEM (RCS). THE SUCTION LINE VALVES ARE INTERLOCKED | | THROUGH SEPARATE CHANNELS OF THE RCS SYSTEM PRESSURE SIGNALS TO PROVIDE | | AUTOMATIC CLOSURE OF BOTH VALVES WHENEVER RCS PRESSURE EXCEEDS RHR DESIGN | | PRESSURE. THE FSAR STATES THAT THE INTERLOCK MAY BE DEFEATED WHEN THE RCS | | IS OPEN TO ATMOSPHERE. HOWEVER, FOR A NUMBER OF YEARS THIS INTERLOCK HAS | | BEEN PROCEDURALLY DEFEATED ON BOTH UNITS TO PREVENT INADVERTENT CLOSURE AND | | LOSS OF RHR SUCTION DURING SHUTDOWN COOLING OPERATION BY OPENING THE VALVES | | AND RACKING OUT THEIR BREAKERS IN MODE 4. | | | | THE OVER PRESSURE PROTECTION AFFORDED BY THE AUTOMATIC CLOSURE FUNCTION | | DESCRIBED IN THE FSAR WAS DEFEATED WITHOUT A SAFETY EVALUATION BEING | | PERFORMED. THIS LOSS OF AUTOMATIC CLOSURE FUNCTION REPRESENTS AN | | UNANALYZED CONDITION AND IS, THEREFORE, REPORTABLE. | | | | PLANS ARE TO DEGAS, DEPRESSURIZE, AND OPEN THE RCS ON BOTH UNITS TO | | ATMOSPHERE. DEGAS WILL START ON UNIT 1, AND WHEN COMPLETED, THE UNIT WILL | | PROCEED TO DEPRESSURIZE WHILE UNIT 2 STARTS DEGAS PROCEDURES. WHEN THE RCS | | IS OPEN TO ATMOSPHERE ON BOTH UNITS, THE PLANT WILL BE IN COMPLIANCE WITH | | THE FSAR." | | | | THIS CONDITION WAS IDENTIFIED BY THE LICENSEE DURING AN ONGOING NRC | | ARCHITECT/ENGINEER INSPECTION. | | | | THE LICENSEE PLANS TO INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32915 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOK REGION: 3 |NOTIFICATION DATE: 09/11/97 | |UNIT: [1] [2] [ ] STATE: MI |NOTIFICATION TIME: 19:56 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 09/11/97 | +------------------------------------------------+EVENT TIME: 19:30[EDT]| |NRC NOTIFIED BY: RANDY PTACEK |LAST UPDATE DATE: 09/11/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRENT CLAYTON RDO | |AINC 50.72(b)(2)(iii)(C) POT UNCNTRL RAD REL | | |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 N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | 2 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | OVER PRESSURE PROTECTION OF THE COMPONENT COOLING WATER SYSTEM PIPING NOT | | IN ACCORDANCE WITH THE ANSI CODE REQUIREMENTS | | | | THE FOLLOWING TEXT IS A PORTION OF A FACSIMILE RECEIVED FROM THE LICENSEE: | | | | "CHAPTER 9.5 OF THE FSAR STATES: 'THE RELIEF VALVE ON THE COMPONENT | | [COOLING WATER] SURGE TANK IS SIZED TO RELIEVE THE MAXIMUM FLOW RATE OF | | WATER THAT WOULD ENTER THE SURGE TANK FOLLOWING A RUPTURE OF A REACTOR | | COOLANT THERMAL BARRIER COOLING COIL. THE SET PRESSURE ASSURES THAT THE | | DESIGN PRESSURE OF THE COMPONENT COOLING SYSTEM IS NOT EXCEEDED.' | | | | THE PIPING DESIGN CODE AT THE COOK PLANT IS B31.1. B31.1 STATES THAT AN | | INTERCEPTING STOP VALVE CANNOT BE LOCATED BETWEEN THE SOURCE OF PRESSURE | | AND THE PRESSURE RELIEF DEVICE CREDITED FOR PROTECTING THE PIPE. IN THIS | | INSTANCE, THE PRESSURE SOURCE IS THE RUPTURED THERMAL BARRIER; THE PRESSURE | | RELIEF DEVICE IS A SAFETY RELIEF VALVE ON THE SURGE TANK. CONTRARY TO THE | | CODE REQUIREMENT, THERE ARE MANUAL VALVES MAINTAINED OPEN BETWEEN THE TWO. | | THESE VALVES WERE NOT CONTROLLED IN ACCORDANCE WITH OR EXEMPTED FROM B31.1. | | | | AN EVALUATION IS BEING PERFORMED TO DETERMINE THE MOST EFFECTIVE METHOD OF | | ESTABLISHING AND MAINTAINING THE CODE REQUIREMENT. A CONDITION REPORT HAS | | BEEN WRITTEN TO INITIATE AN INVESTIGATION INTO THIS EVENT AND DETERMINE THE | | APPROPRIATE PREVENTATIVE ACTIONS." | | | | THIS CONDITION WAS IDENTIFIED IN RESPONSE TO AN ONGOING NRC | | ARCHITECT/ENGINEER DESIGN INSPECTION. | | | | THE LICENSEE PLANS TO INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32916 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PERRY REGION: 3 |NOTIFICATION DATE: 09/11/97 | |UNIT: [1] [ ] [ ] STATE: OH |NOTIFICATION TIME: 23:58 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 09/11/97 | +------------------------------------------------+EVENT TIME: 23:10[EDT]| |NRC NOTIFIED BY: M DAMMANN |LAST UPDATE DATE: 09/11/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRENT CLAYTON RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 21 POWER OPERATION | 21 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LOST REACTOR PROTECTION SYSTEM (RPS) BUS "A" WHILE ON ITS ALTERNATE POWER | | SUPPLY CAUSED SEVERAL ENGINEERED SAFETY FEATURE (ESF) ACTUATIONS TO OCCUR. | | | | WHILE RPS BUS "A" WAS ON ITS ALTERNATE POWER SUPPLY ITS ELECTRICAL | | PROTECTION ASSEMBLY (EPA) BREAKERS OPENED FOR UNKNOWN REASON. THE OPENING | | OF RPS BUS "A" ALTERNATE EPA BREAKERS CAUSED SEVERAL ESF TRAIN "A" | | ACTUATIONS WHICH INCLUDED: 1/2 SCRAM SIGNAL, 1/2 MAIN STEAM ISOLATION | | VALVE ISOLATION SIGNAL, REACTOR WATER CLEANUP ISOLATION, SEVERAL | | CONTAINMENT ISOLATION VALVES ISOLATED, ETC. | | | | RPS BUS "A" WAS TRANSFERRED TO ITS NORMAL POWER SUPPLY, AND RESTORATION OF | | SYSTEMS ISOLATED BY THE LOSS OF RPS BUS "A" HAS COMMENCED. THE REASON WHY | | RPS BUS "A" WAS ON ITS ALTERNATE POWER SUPPLY IS BECAUSE RPS BUS "A" NORMAL | | POWER SUPPLY HAD BEEN TAKEN OUT OF SERVICE FOR MAINTENANCE. | | | | THE LICENSEE IS INVESTIGATING WHY RPS BUS "A" ALTERNATE BUS EPA BREAKERS | | OPENED. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+