U.S. Nuclear Regulatory Commission Operations Center Event Reports For 02/05/97 - 02/06/97 ** EVENT NUMBERS ** 31729 31730 31731 31732 31733 31734 31735 31736 31737 31738 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31729 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SAINT LUCIE REGION: 2 |NOTIFICATION DATE: 02/05/97 | |UNIT: [ ] [2] [ ] STATE: FL |NOTIFICATION TIME: 07:37 [ET]| |RX TYPE: [1] CE,[2] CE |EVENT DATE: 02/05/97 | +------------------------------------------------+EVENT TIME: 06:42[EST]| |NRC NOTIFIED BY: DICK CZARNECKI |LAST UPDATE DATE: 02/05/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CAUDLE JULIAN RDO | |DDDD 73.71 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - SITE ACCESS BADGE GRANTED TO POSSIBLE UNAUTHORIZED INDIVIDUAL - | | | | IMMEDIATE COMPENSATORY MEASURES WERE TAKEN UPON DISCOVERY. (REFER TO THE | | HOO LOG FOR DETAILS.) | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | | | | ***UPDATE ON 02/05/97, @ 1720 EST BY CZARNECKI TAKEN BY MACKINNON*** | | | | THIS EVENT REPORT IS BEING DOWNGRADED TO A LOGGABLE EVENT. BASED UPON | | FURTHER INVESTIGATIONS, DISCUSSIONS WITH THE NRC REGION II PERSONNEL, AND A | | REVIEW OF THE MOST RECENT DOCKETED NRC PERSONNEL ACCESS LETTER; FLORIDA | | POWER AND LIGHT HAS DETERMINED THAT THE INDIVIDUAL WAS AUTHORIZED ACCESS TO | | THE SITE. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS UPDATE BY THE LICENSEE. THE | | NRC OPERATIONS CENTER NOTIFIED THE R2DO (CAUDLE JULIAN). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31730 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: KEWAUNEE REGION: 3 |NOTIFICATION DATE: 02/05/97 | |UNIT: [1] [ ] [ ] STATE: WI |NOTIFICATION TIME: 10:47 [ET]| |RX TYPE: [1] W-2-LP |EVENT DATE: 02/05/97 | +------------------------------------------------+EVENT TIME: 08:00[CST]| |NRC NOTIFIED BY: GARY HARRINGTON |LAST UPDATE DATE: 02/05/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |THOMAS KOZAK RDO | |ADAS 50.72(b)(2)(i) DEG/UNANALYZED COND |ROBERT DENNIG, NRR EO | | |STUART RUBIN, IRD AEOD | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | IDENTIFICATION OF WELD DEFECTS IN GREATER THAN 80% OF A SAMPLE POPULATION | | FOLLOWING THE USE OF A NEW WELDING PROCESS WHICH UTILIZES A LASER MACHINE | | TO REPAIR SLEEVED STEAM GENERATOR TUBES THAT HAVE BEEN IN USE | | | | DURING THE CURRENT REFUELING OUTAGE, WELD REPAIRS WERE MADE TO SLEEVED | | STEAM GENERATOR TUBES USING A NEW LASER WELDING PROCESS. APPROXIMATELY | | 1,200 TUBES WERE REPAIRED IN THE 'A' STEAM GENERATOR, AND APPROXIMATELY 700 | | TUBES WERE REPAIRED IN THE 'B' STEAM GENERATOR. DURING VARIOUS STAGES OF | | THE REPAIR PROCESS, THE REPAIRS WERE DEEMED TO BE ACCEPTABLE USING BOTH | | ULTRASONIC AND EDDY CURRENT EXAMINATION TECHNIQUES. SUBSEQUENT TO THE | | ACCEPTANCE OF THESE REPAIRS AND THE FILLING OF THE STEAM GENERATOR | | SECONDARY SIDES, SEVERAL TUBES LEAKED. | | | | AFTER IDENTIFYING THE LEAKING TUBES, FURTHER ULTRASONIC EXAMINATIONS WERE | | PERFORMED ON A SAMPLING OF THE LEAKING TUBES. (THE SAMPLE POPULATION WAS | | APPROXIMATELY 30 TUBES TOTAL.) THESE EXAMINATIONS REVEALED POTENTIAL WELD | | DEFECTS IN GREATER THAN 80% OF THE SAMPLE POPULATION, AND THESE POTENTIAL | | WELD DEFECTS WERE NOT PREVIOUSLY IDENTIFIED AS PART OF THE WELD PROCESS. | | THE UNIT IS NOT IN A TECHNICAL SPECIFICATION LIMITING CONDITION FOR | | OPERATION AS A RESULT OF THIS ISSUE DUE TO THE CURRENT MODE OF OPERATION. | | | | THE WELDS IN QUESTION WERE MADE UTILIZING A NEW WELDING PROCESS BEING | | PERFORMED THROUGH WESTINGHOUSE. LICENSEE REPRESENTATIVES HAVE HAD SEVERAL | | DISCUSSIONS WITH THE NRC REGIONAL AND HEADQUARTERS PERSONNEL REGARDING THIS | | PROCESS, AND THE LICENSEE ALSO STATED THAT THERE WAS STILL AN OUTSTANDING | | TECHNICAL SPECIFICATION RESOLUTION FOR ACCEPTANCE OF THE LICENSEE'S CURRENT | | APPLICATION OF THIS PARTICULAR PROCESS. ALTHOUGH THIS ISSUE MAY HAVE SOME | | POTENTIAL GENERIC IMPACT, THE LICENSEE BELIEVES THAT IT IS UTILIZING A | | UNIQUE APPLICATION OF THE PROCESS IN THAT THIS IS THE FIRST TIME THIS | | PROCESS WAS USED TO REPAIR SLEEVED TUBES THAT HAVE BEEN IN USE. THE | | LICENSEE BELIEVES THAT THE NEW WELDING PROCESS HAS PREVIOUSLY BEEN USED | | DURING THE INSTALLATION OF SLEEVES BUT THAT IT HAS NOT PREVIOUSLY BEEN USED | | TO REPAIR SLEEVES THAT HAVE BEEN IN PLACE. | | | | THE LICENSEE IS CONTINUING TO ANALYZE EXAMINATION DATA TO DETERMINE | | CORRECTIVE ACTION NEEDS, AND THE LICENSEE HAS NOTIFIED THE NRC RESIDENT | | INSPECTOR. A TELEPHONE CONFERENCE CALL HAS ALSO BEEN SCHEDULED WITH THE | | NRC's OFFICE OF NUCLEAR REACTOR REGULATION THIS AFTERNOON. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31731 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 02/05/97 | |UNIT: [1] [ ] [ ] STATE: CT |NOTIFICATION TIME: 14:21 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 02/05/97 | +------------------------------------------------+EVENT TIME: 14:00[EST]| |NRC NOTIFIED BY: JAMES BAURE |LAST UPDATE DATE: 02/05/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MICHAEL MODES RDO | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | FAILURE TO ASSUME THAT A SINGLE FAILURE OF THE AUTOMATIC PRESSURE RELIEF | | VALVES MIGHT INVOLVE MORE THAN ONE RELIEF VALVE DURING A SMALL BREAK LOCA | | | | THE FOLLOWING TEXT IS FROM A FACSIMILE SENT IN BY THE LICENSEE: | | | | "ADVERSE CONDITION REPORT (ACR) #11575 CONCERNS THE FUNCTIONAL REQUIREMENTS | | OF THE FEEDWATER COOLANT INJECTION (FWCI)/AUTOMATIC PRESSURE RELIEF (APR) | | SYSTEMS TO MITIGATE THE CONSEQUENCES OF A DESIGN BASIS ACCIDENT AND REPORTS | | THAT THE APR SYSTEM IS VULNERABLE TO SINGLE FAILURES WHICH MAY INVALIDATE | | PREVIOUS ASSUMPTIONS OF THE OPERATING CYCLE 15 SMALL BREAK LOSS OF COOLANT | | ACCIDENT (SBLOCA) ANALYSIS. DURING THE CORRECTIVE ACTION AND RESOLUTION | | PROCESS OF ACR #11575, IT WAS DISCOVERED THAT LOCA ANALYSES PERFORMED IN | | THE MID 1970s AND SUBSEQUENT ANALYSES TO SHOW COMPLIANCE WITH THE | | REQUIREMENTS OF 10 CFR 50.46 AND 10 CFR PART 50, APPENDIX K, WERE BASED ON | | THE ASSUMPTION THAT DIVERSE SYSTEMS, FWCI AND APR, WERE INDEPENDENTLY | | CAPABLE OF MITIGATING THE CONSEQUENCES OF A SBLOCA COINCIDENT WITH A | | POSTULATED FAILURE OF A SINGLE APR VALVE. THE ANALYSIS FAILED TO RECOGNIZE | | THE SINGLE FAILURE VULNERABILITY OF THE APR SYSTEM AND POTENTIAL LOSS OF | | MORE THAN ONE APR VALVE AND THAT BOTH APR AND FWCI ARE REQUIRED TO SATISFY | | LONG TERM COOLING REQUIREMENTS PER CRITERION #5 OF 10 CFR 50.46." | | | | THE LICENSEE SAFETY ANALYSIS DEPARTMENT WILL REVISE THE LOCA ANALYSIS | | (10 CFR 50.46 AND 10 CFR PART 50, APPENDIX A) BASED ON UNIT 1 SPECIFIC | | DESIGN CONFIGURATIONS AND TAKING INTO ACCOUNT ANY DESIGN MODIFICATION | | IDENTIFIED FOR CORRECTIVE ACTION FOR ACR #11575. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR AND THE APPLICABLE STATE | | AND LOCAL OFFICIALS OF THIS EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31732 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOK REGION: 3 |NOTIFICATION DATE: 02/05/97 | |UNIT: [1] [2] [ ] STATE: MI |NOTIFICATION TIME: 14:35 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 02/05/97 | +------------------------------------------------+EVENT TIME: 13:35[EST]| |NRC NOTIFIED BY: M DEPUYDT |LAST UPDATE DATE: 02/05/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |TOM KOZAK 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 97 POWER OPERATION | 97 POWER OPERATION | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | POSSIBLE SAFETY INJECTION PUMP RUNOUT IF THE ACCUMULATOR FILL LINE IS OPEN | | AND A LARGE BREAK LOSS OF COOLANT ACCIDENT (LOCA) OCCURRED. | | | | THE FOLLOWING TEXT IS TAKEN FROM FACSIMILE SENT IN BY THE LICENSEE: | | | | "QUESTIONS WERE RECENTLY POSED BY THE OPERATING SHIFTS CONCERNING THE | | OPERABILITY OF THE SAFETY INJECTION PUMPS DURING ACCUMULATOR LEVEL | | ADJUSTMENT. WESTINGHOUSE WAS SUBSEQUENTLY TASKED WITH EVALUATING THE | | EFFECT OF THIS EVOLUTION ON THE RUNOUT CALCULATIONS FOR THE SAFETY | | INJECTION PUMPS." | | | | "PRELIMINARY PUMP RUNOUT CALCULATION RESULTS HAVE BEEN RECEIVED FROM | | WESTINGHOUSE THAT INDICATE THAT THE SAFETY INJECTION PUMPS COULD | | POTENTIALLY GO TO 715 gpm (708 gpm USING RECENT PUMP TEST DATA) IF THE | | ACCUMULATOR FILL LINE IS OPEN DURING A LARGE BREAK LOCA DEMAND. THE COOK | | TECHNICAL SPECIFICATIONS STATE UNDER TECHNICAL SPECIFICATION 4.5.2.h THAT | | TOTAL SAFETY INJECTION FLOW SHALL NOT EXCEED 700 gpm WITH A SINGLE PUMP | | RUNNING AND THE MINIMUM FLOW VALVE OPEN. THE SAFETY INJECTION PUMPS MAY | | POTENTIALLY EXCEED THE 700 gpm RUNOUT LIMIT DURING THE INJECTION PHASE OF A | | LARGE BREAK LOCA, TOWARD THE END OF THE BLOWDOWN, IF THE ONLY SAFETY | | INJECTION PUMP IS PROVIDING FLOW TO ALL FOUR INJECTION LINES WHILE THE | | ACCUMULATOR FILL LINE IS FULLY OPEN AND THE MINIMUM FLOW LINE IS OPEN. THE | | SAFETY INJECTION PUMP HAS BEEN USED IN THE PAST TO RESTORE LEVEL IN THE | | ACCUMULATORS. THIS CONDITION IS BEING REPORTED UNDER 10CFR50.72(b)(1)(ii), | | AS A CONDITION OUTSIDE THE DESIGN BASIS." | | | | "DURING ACCUMULATOR LEVEL ADJUSTMENTS, THE OPERATING SAFETY INJECTION PUMP | | IS NOW DECLARED INOPERABLE AND THE SYSTEM CROSS-TIES CLOSED WHILE THE | | EVOLUTION IS UNDERWAY. THIS EFFECTIVELY PREVENTS THE POTENTIAL RUNOUT | | CONDITION." | | | | "THE EFFECT ON THE LOCA ANALYSIS IS STILL BEING ANALYZED. WHEN THE RESULTS | | BECOME AVAILABLE, ANY NECESSARY UPDATES TO THIS REPORT WILL BE MADE AT THAT | | TIME." | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31733 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SALEM REGION: 1 |NOTIFICATION DATE: 02/05/97 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 15:07 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 02/05/97 | +------------------------------------------------+EVENT TIME: 11:40[EST]| |NRC NOTIFIED BY: FRED PRIESTLEY |LAST UPDATE DATE: 02/05/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MICHAEL MODES 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 +------------------------------------------------------------------------------+ | AN OFFSITE NOTIFICATION WAS MADE TO THE NEW JERSEY DEPARTMENT OF | | ENVIRONMENTAL PROTECTION BECAUSE THE PERMIT TEMPERATURE LIMIT OF 27.5øF | | (DIFFERENTIAL) WAS EXCEEDED ON 02/02/97. | | | | DURING REVIEW OF DOWNLOADED COMPUTER INFORMATION, IT WAS DETERMINED THAT | | THE NEW JERSEY DEPARTMENT OF ENVIRONMENTAL PROTECTION PERMIT TEMPERATURE | | LIMIT OF 27.5øF WAS EXCEEDED ON 02/02/97. THE TEMPERATURE IS A | | DIFFERENTIAL BETWEEN THE INLET AND OUTLET OF THE CIRCULATING WATER SYSTEM, | | AND IT WAS DETERMINED TO BE 34.9øF. UPON RECEIPT OF THIS INFORMATION THE | | OPERATING SHIFT VERIFIED A CURRENT DIFFERENTIAL TEMPERATURE OF | | APPROXIMATELY 34øF. INCREASED FLOW HAS REDUCED THIS TO APPROXIMATELY 20øF. | | THE CIRCULATING WATER DIFFERENTIAL TEMPERATURE IS NOT NORMALLY MONITORED | | WHEN THE PLANT IS DEFUELED AND WHEN THE CIRCULATING WATER PUMPS ARE NOT | | OPERATING. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR AND PLANS TO NOTIFY THE | | LOWER ALLOWAYS CREEK TOWNSHIP AND THE STATE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31734 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SOUTH TEXAS REGION: 4 |NOTIFICATION DATE: 02/05/97 | |UNIT: [ ] [2] [ ] STATE: TX |NOTIFICATION TIME: 15:59 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 02/05/97 | +------------------------------------------------+EVENT TIME: 13:00[CST]| |NRC NOTIFIED BY: HESSLING |LAST UPDATE DATE: 02/05/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PHIL HARRELL RDO | |NLTR LICENSEE 24 HR REPORT | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 92 POWER OPERATION | 92 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | 5 OF 20 MAIN STEAM SAFETY VALVE SETPOINTS WERE FOUND TO BE HIGHER THAN THE | | 3% LIFT SETPOINT TOLERANCE. | | | | DURING TESTING OF MAIN STEAM SAFETY VALVES, 15 OF 20 MAIN STEAM SAFETY | | VALVE LIFT SETPOINTS WERE FOUND TO BE WITHIN THE 3% TOLERANCE SPECIFIED IN | | TECHNICAL SPECIFICATION 3.7.1.1. THE FOLLOWING MAIN STEAM SAFETY VALVES | | WERE FOUND TO BE OUTSIDE THE 3% LIFT SETPOINT TOLERANCE: | | | | VALVE NUMBER REQD SETPOINT AS-FOUND SETPOINT | | | | SG "A" MS-PV-7440D 1,325 psig 1,383 psig | | SG "A" MS-PV-7440 1,285 psig 1,381 psig | | SG "C" MS-PV-7430 1,285 psig 1,326 psig | | SG "B" MS-PV-7420B 1,305 psig 1,364 psig | | SG "B" MS-PV-7420D 1,325 psig 1,381 psig | | | | THE VALVES WERE RETESTED ONE AT A TIME, AND ALL THE VALVES HAVE BEEN | | ADJUSTED AND TESTED TO BE WITHIN THE ñ1% LIFT SETPOINT REQUIREMENTS AS | | SPECIFIED IN TECHNICAL SPECIFICATION 3.7.1.1. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31735 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PALISADES REGION: 3 |NOTIFICATION DATE: 02/05/97 | |UNIT: [1] [ ] [ ] STATE: MI |NOTIFICATION TIME: 16:12 [ET]| |RX TYPE: [1] CE |EVENT DATE: 02/05/97 | +------------------------------------------------+EVENT TIME: 13:50[EST]| |NRC NOTIFIED BY: C KOZUP |LAST UPDATE DATE: 02/05/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |TOM KOZAK RDO | |AMED 50.72(b)(2)(v) OFFSITE MEDICAL | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 HOT SHUTDOWN | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AN INJURED RADWASTE HANDLER WAS TRANSPORTED TO THE SOUTH HAVEN HOSPITAL | | AFTER FALLING 15 FEET FROM A LADDER. | | | | A RADWASTE HANDLER WAS WORKING ON A LADDER APPROXIMATELY 15 FEET OFF THE | | GROUND IN THE CASK WASH-DOWN AREA (DECONTAMINATION AREA ADJACENT TO THE | | SPENT FUEL POOL) WHEN HE FELL FROM THE LADDER. HE WAS WEARING SCRUBS | | (PAPER COVERALLS) ON THE OUTSIDE OF HIS CLOTHS AT THE TIME HE FELL FROM THE | | LADDER. HEALTH PHYSICISTS REMOVED ALL OF THE SCRUBS FROM THE INJURED | | INDIVIDUAL EXCEPT FROM HIS BACK. A HEALTH PHYSICIST ACCOMPANIED THE | | INJURED PERSON OFFSITE IN AN AMBULANCE. THE INJURED PERSON WAS TAKEN TO | | THE SOUTH HAVEN HOSPITAL, AND RADIOACTIVE CONTAMINATION WAS FOUND ON THE | | BACK OF THE SCRUBS THAT HE STILL HAD ON. THE RADIOACTIVELY CONTAMINATED | | SCRUBS WERE REMOVED FROM THE INJURED PERSON'S BACK AND DISPOSED OF AS | | RADIOACTIVELY CONTAMINATED MATERIAL. THE INJURED PERSON WAS NOT | | CONTAMINATED. | | | | THE PALISADES PUBLIC AFFAIRS OFFICER IS ANSWERING QUESTIONS FROM THE LOCAL | | NEWS MEDIA ABOUT THE ACCIDENT. THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF | | THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31736 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PALO VERDE REGION: 4 |NOTIFICATION DATE: 02/05/97 | |UNIT: [ ] [2] [ ] STATE: AZ |NOTIFICATION TIME: 16:42 [ET]| |RX TYPE: [1] CE,[2] CE,[3] CE |EVENT DATE: 02/05/97 | +------------------------------------------------+EVENT TIME: 14:55[MST]| |NRC NOTIFIED BY: BRAD EKLUND |LAST UPDATE DATE: 02/05/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PHIL HARRELL RDO | |HFIT 26.73 FITNESS FOR DUTY | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | A SMALL AMOUNT OF MATERIAL (POSSIBLY MARIJUANA) WAS FOUND THEN THROWN AWAY. | | | | A SMALL AMOUNT OF WHAT APPEARED TO BE MARIJUANA WAS FOUND IN NOVEMBER 1996. | | IT WAS WRAPPED IN AN AMERICAN FLAG THAT HAD BEEN IN STORAGE SINCE 1980. | | SPECIFICALLY, A SMALL PLASTIC BAG OF BROWNISH ORGANIC MATERIAL FELL TO THE | | FLOOR WHEN THE FLAG WAS BEING HUNG UP IN THE MAINTENANCE SHOP, AND THE | | MATERIAL WAS THROWN INTO THE TRASH. THE FOREMAN AND SUBSEQUENTLY THE | | SUPERVISOR WERE INFORMED OF THIS EVENT AND MADE A CURSORY SEARCH OF THE | | TRASH. HOWEVER, THEY WERE UNABLE TO RETRIEVE THE PLASTIC BAG AND DID NOT | | MAKE ANY ADDITIONAL NOTIFICATIONS AT THAT TIME. | | | | THE ONGOING INVESTIGATION IS ADDRESSING THE LACK OF NOTIFICATION TO | | SECURITY AND UPPER LEVEL MANAGEMENT WHEN THE CONDITION WAS FIRST IDENTIFIED | | AND THE FAILURE TO RETRIEVE THE MATERIAL. APPROPRIATE CORRECTIVE ACTIONS | | WILL BE TAKEN BASED UPON THE RESULTS OF THE INVESTIGATION. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31737 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: POINT BEACH REGION: 3 |NOTIFICATION DATE: 02/05/97 | |UNIT: [1] [2] [ ] STATE: WI |NOTIFICATION TIME: 17:02 [ET]| |RX TYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 02/05/97 | +------------------------------------------------+EVENT TIME: 15:15[CST]| |NRC NOTIFIED BY: HENNING |LAST UPDATE DATE: 02/05/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |TOM KOZAK RDO | |AUNA 50.72(b)(1)(ii)(A) UNANALYZED COND OP | | |ADAS 50.72(b)(2)(i) DEG/UNANALYZED COND | | |NLCO TECH SPEC LCO A/S | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 90 POWER OPERATION | 90 POWER OPERATION | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE OVERLOAD ALARM LIMIT SETPOINT FOR HIGH HEAD SAFETY INJECTION PUMP WAS | | EXCEEDED CAUSING THE HIGH HEAD SAFETY INJECTION PUMP BREAKER TO TRIP OPEN | | DURING PERFORMANCE OF OPERATION REFUELING TEST-3 (ORT-3), LARGE BREAK LOCA | | WITH A LOSS OF OFFSITE POWER. | | | | THE FOLLOWING TEXT WAS TAKEN FROM THE FACSIMILE SENT BY THE LICENSEE: | | | | "DURING ANALYSIS OF THE BREAKER TRIP OF THE UNIT 2 #2P15A HIGH HEAD SAFETY | | INJECTION PUMP, WHICH OCCURRED DURING PERFORMANCE OF THE ORT-3 TEST FOR | | SAFETY INJECTION WITH LOSS OF ENGINEERED SAFEGUARDS AC POWER ON 02/04/97, | | IT WAS DETERMINED THAT THE BREAKER TRIP POTENTIAL EXISTED FOR THE UNIT 1 | | #1P15A SAFETY INJECTION PUMP. THIS POTENTIAL EXISTS DUE TO THE OVERCURRENT | | RELAY PROTECTION SCHEME WHICH EXISTS ON THE TRAIN "A" SAFETY INJECTION | | MOTOR BREAKER CUBICLE. THE #1P15A SAFETY INJECTION PUMP HAS BEEN DECLARED | | INOPERABLE, AND A LIMITING CONDITION FOR OPERATION HAS BEEN ENTERED PER | | TECHNICAL SPECIFICATION 15.3.3.A.2.b (72 HOURS). THE SAME POTENTIAL DOES | | NOT EXIST ON TRAIN "B" DUE TO A DIFFERENT PROTECTIVE RELAY SCHEME. THE | | SETPOINTS OF THE TRAIN "A" PROTECTIVE SCHEME WILL BE ADJUSTED TO CORRECT | | THE TRIPPING POTENTIAL AND ALLOW RETURN TO OPERABILITY OF THE TRAIN "A" | | PUMPS. THIS CONDITION AFFECTS #1P15A (AT POWER UNIT) AND #2P15A (DEFUELED | | UNIT)". | | | | THE PERFORMANCE OF ORT-3 (OPERATION REFUELING TEST FOR A DESIGN BASIS | | ACCIDENT WITH A LOSS OF OFFSITE POWER) IS PERFORMED EVERY REFUELING OUTAGE. | | DURING THE PERFORMANCE OF THIS TEST, THE HIGH HEAD SAFETY INJECTION PUMP | | #2P15A BREAKER TRIPPED BECAUSE THE PUMP CURRENT EXCEEDED THE PUMP'S | | OVERLOAD ALARM SETPOINT, WHICH WAS SET AT 90 AMPS WITH A DELAY TIME OF | | APPROXIMATELY 7.5 SECONDS. DURING NORMAL OPERATION, THE SAFETY INJECTION | | PUMPS DRAW 85 AMPS. DURING PERFORMANCE OF ORT-3, A SAFETY INJECTION PUMP | | DRAWS APPROXIMATELY 90 AMPS. THEREFORE, THE SAFETY INJECTION PUMP BREAKER | | TRIPPED OPEN BECAUSE IT WAS DRAWING 90 AMPS FOR OVER 7.5 SECONDS. THIS | | CONDITION DOES NOT PLACE UNIT 2 IN ANY TECHNICAL SPECIFICATION ACTION | | STATEMENT SINCE THE UNIT IS DEFUELED, BUT IT PLACES UNIT 1 (WHICH IS AT 90% | | POWER) IN A 72-HOUR LIMITING CONDITION FOR OPERATION PER TECHNICAL | | SPECIFICATION 15.3.3.A.2.b. | | | | THE LICENSEE PLANS TO CHANGE THE OVERLOAD SETPOINT FROM 90 AMPS WITH A TIME | | DELAY OF APPROXIMATELY 7.5 SECONDS TO A SETPOINT OF 105 AMPS WITH A SHORTER | | TIME DELAY OF APPROXIMATELY 6.3 SECONDS. THE HIGH HEAD SAFETY INJECTION | | PUMP MOTOR WILL STILL BE WITHIN ITS CAPABILITY CURVE WITH THE NEW OVERLOAD | | SETPOINT CHANGES. THE NEW OVERLOAD SETPOINT CHANGES WILL BE COMPLETED BY | | THE END OF 02/06/97. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31738 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: POINT BEACH REGION: 3 |NOTIFICATION DATE: 02/05/97 | |UNIT: [1] [2] [ ] STATE: WI |NOTIFICATION TIME: 17:52 [ET]| |RX TYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 02/05/97 | +------------------------------------------------+EVENT TIME: 15:20[CST]| |NRC NOTIFIED BY: HENNIG |LAST UPDATE DATE: 02/05/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |TOM KOZAK 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 90 POWER OPERATION | 90 POWER OPERATION | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE MADE A NOTIFICATION TO THE WISCONSIN STATE DEPARTMENT OF | | NATURAL RESOURCES REGARDING AN UNMONITORED RELEASE OF THE FACILITY SUMPS TO | | THE ENVIRONMENT. | | | | DUE TO THE RELEASE OF FACILITY SUMPS (WHICH BYPASSED THE NORMAL RELEASE | | POINT MONITORS) TO THE ENVIRONMENT, A FORMAL NOTIFICATION WAS MADE TO THE | | WISCONSIN STATE DEPARTMENT OF NATURAL RESOURCES. THE CAUSE OF THE RELEASE | | IS CURRENTLY BELIEVED TO BE AN UNDERGROUND LEAK OF THE PIPING FROM THE | | EFFLUENT SUMP TO THE RETENTION POND. ACTUAL RADIOLOGICAL RELEASES HAVE NOT | | TAKEN PLACE. | | | | TWELVE-HOUR GRAB SAMPLES ARE BEING PERFORMED FOR RADIOLOGICAL MONITORING, | | AND A CONTRACTOR HAS BEEN SCHEDULED TO PERFORM PIPING REPAIRS ON 02/06/97. | | THE CAUSE OF THE PIPE BREAK IS STILL UNDER INVESTIGATION. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+