U.S. Nuclear Regulatory Commission Operations Center Event Reports For 11/01/96 - 11/04/96 ** EVENT NUMBERS ** 31263 31264 31265 31266 31267 31268 31269 31270 31271 31272 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31263 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SALEM REGION: 1 |NOTIFICATION DATE: 11/01/96 | |UNIT: [ ] [2] [ ] STATE: NJ |NOTIFICATION TIME: 11:09 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 11/01/96 | +------------------------------------------------+EVENT TIME: 09:25[EST]| |NRC NOTIFIED BY: JOHN ROBERTSON |LAST UPDATE DATE: 11/01/96 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JAMES JOYNER 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | -COMPONENT COOLING WATER SYSTEM IN AN UNANALYZED CONDITION WHILE DEFUELED- | | | | DURING TESTING OF UNIT 2 WITH IT IN A DEFUELED CONDITION, THE LICENSEE | | DETERMINED THAT THE COMPONENT COOLING WATER SYSTEM IS IN AN UNANALYZED | | CONDITION. THIS CONDITION HAS A DIRECT IMPACT ON THE RESIDUAL HEAT REMOVAL | | (RHR) SYSTEM'S CAPABILITY TO REMOVE DECAY HEAT DURING AN ACCIDENT | | CONDITION. THIS CONDITION IS DUE TO ERRORS DISCOVERED IN THE INSTALLED RHR | | HEAT EXCHANGER COMPONENT COOLING FLOW METERS. BY USING ULTRASONIC FLOW | | METERS DURING THE TEST, THE LICENSEE DETERMINED THAT THE INSTALLED METERS | | ARE READING ABOUT 1,000 GPM HIGHER THAN NORMAL (NORMAL IS 3,000 TO 4,000 | | GPM) WHICH IS NON-CONSERVATIVE. THIS INSTRUMENTATION IS USED TO SET THE | | FLOW REQUIRED FOR RHR DURING ACCIDENT CONDITIONS AND TO PERFORM | | SURVEILLANCE TESTING OF THE COMPONENT COOLING WATER PUMPS. DUE TO ACTUAL | | FLOW BEING LOWER THAN INDICATED FLOW DURING COMPONENT COOLING WATER PUMP | | SURVEILLANCES, A DEGRADED PUMP CONDITION WITH PARAMETERS OUTSIDE THOSE THAT | | ARE ACCEPTABLE MAY HAVE GONE UNDETECTED. | | | | THE LICENSEE IS DETERMINING THE CAUSE AND CORRECTIVE ACTIONS AND PLANS TO | | DETERMINE IF THIS CONDITION ALSO EXISTS ON UNIT 1. | | | | THE LICENSEE NOTIFIED LOCAL OFFICIALS AND WILL NOTIFY THE NRC RESIDENT | | INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31264 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 11/01/96 | |UNIT: [2] [ ] [ ] STATE: NY |NOTIFICATION TIME: 16:30 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 11/01/96 | +------------------------------------------------+EVENT TIME: 14:58[EST]| |NRC NOTIFIED BY: PHIL SANTINI |LAST UPDATE DATE: 11/01/96 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MOHAMED SHANBAKY RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | PARTIAL TURBINE RUNBACK DURING THE REMOVAL OF A JUMPER FOR THE INDIVIDUAL | | ROD POSITION INDICATION (IRPI) FOR ROD L-3 RUNBACK ACTUATION DEFEAT | | | | AT 1458, A JUMPER FOR THE IRPI FOR ROD L-3 RUNBACK ACTUATION DEFEAT WAS | | REMOVED. (THIS JUMPER WAS PREVIOUSLY INSTALLED DUE TO A PROBLEM ON THE | | IRPI FOR ROD L-3, AND THE JUMPER WAS REMOVED BASED UPON SATISFACTORY | | PERFORMANCE OF THE IRPI AND SATISFACTORY TESTING PER THE NORMAL IRPI | | SURVEILLANCE TEST PROCEDURE, PMT-7.) DURING REMOVAL OF THE JUMPER, THE ROD | | BOTTOM/ROD STOP ALARM WAS RECEIVED, AND A PARTIAL RUNBACK OF 20 MWe (FROM | | 995 MWe) WAS EXPERIENCED POTENTIALLY DUE TO A SPIKE DURING THE JUMPER | | REMOVAL. THE UNIT DID NOT EXPERIENCE ANY AUTOMATIC ROD INSERTION, NO IRPIs | | INDICATED ANY CHANGE IN ROD POSITION, AND NO ROD BOTTOM LIGHTS ILLUMINATED. | | THE CONDITION CLEARED, THE RUNBACK TERMINATED, AND REACTOR POWER WAS ALMOST | | IMMEDIATELY RETURNED TO 100%. THE LICENSEE REFERENCED ABNORMAL OPERATING | | INSTRUCTION AOI-16.1.1 FOR A DROPPED ROD OR ERRONEOUS IRPI INDICATION, AND | | REACTOR ENGINEERING WAS INFORMED. THERE WERE NO OTHER ACTUATIONS THAT WERE | | UNUSUAL OR NOT UNDERSTOOD, AND ALL SYSTEMS FUNCTIONED AS REQUIRED. | | | | THE LICENSEE PLANS TO NOTIFY THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31265 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: NINE MILE POINT REGION: 1 |NOTIFICATION DATE: 11/01/96 | |UNIT: [1] [ ] [ ] STATE: NY |NOTIFICATION TIME: 16:39 [ET]| |RX TYPE: [1] GE-2,[2] GE-5 |EVENT DATE: 11/01/96 | +------------------------------------------------+EVENT TIME: 16:05[EST]| |NRC NOTIFIED BY: PETER FARSACI |LAST UPDATE DATE: 11/01/96 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MOHAMED SHANBAKY 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 | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DURING A HOT SHORT CONDITION PRIOR TO FEBRUARY 1995, TWO SHUTDOWN COOLING | | SYSTEM CONTAINMENT ISOLATION VALVES COULD HAVE DRIVEN CLOSED AND | | MECHANICALLY BOUND SUCH THAT THEY WOULD NOT HAVE BEEN CAPABLE OF BEING | | OPENED BY THEIR MOTOR OPERATORS TO ACHIEVE COLD SHUTDOWN WITHIN 72 HOURS. | | | | A RECENT RE-EVALUATION OF 10 CFR PART 50, APPENDIX 'R', HOT SHORTS | | IDENTIFIED A CONDITION IN WHICH UNIT 1 MAY HAVE OPERATED OUTSIDE OF ITS | | DESIGN BASIS FROM THE TIME THE NRC APPENDIX 'R' SAFETY EVALUATION REPORT | | WAS ISSUED THROUGH FEBRUARY 1995. SPECIFICALLY, TWO CONTAINMENT ISOLATION | | VALVES (38-01 AND 38-13) FOR THE SHUTDOWN COOLING SYSTEM COULD HAVE DRIVEN | | CLOSED DURING A HOT SHORT CONDITION. THIS IN TURN MAY HAVE MECHANICALLY | | BOUND THE VALVES CLOSED SUCH THAT THEY WOULD NOT HAVE BEEN CAPABLE OF BEING | | OPENED BY THEIR MOTOR OPERATORS TO ACHIEVE COLD SHUTDOWN WITHIN 72 HOURS. | | THE PLANT DESIGN WAS MODIFIED DURING THE 1995 REFUELING OUTAGE, SO THIS | | CONCERN DOES NOT AFFECT CURRENT PLANT OPERATIONS OR THE OPERABILITY OF THE | | VALVES BECAUSE THE BREAKERS/FUSES ARE NOT NORMALLY ENERGIZED. | | | | THE LICENSEE PREVIOUSLY ANALYZED THIS EVENT IN RESPONSE TO INFORMATION | | NOTICE 92-18, AND THE LICENSEE'S ASSESSMENT AT THE TIME TOOK CREDIT FOR THE | | THERMAL OVERLOADS IN THE CIRCUIT. RECENT LICENSEE ANALYSIS OF THE VALVES | | USING GENERIC LETTER 89-10 TECHNIQUES INDICATES THAT THE VALVES MAY NOT | | HAVE BEEN ABLE TO BE OPENED BY NORMAL MEANS AFTER THE HOT SHORT. THE | | LICENSEE PLANS TO ANALYZE THE ACTUAL CONDITIONS, AND THIS REPORT | | NOTIFICATION REPORT MAY BE RESCINDED BASED UPON THE LICENSEE FURTHER | | ENGINEERING EVALUATION. THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | | HOO NOTE: ISSUES REGARDING VALVE BINDING ARE DOCUMENTED IN AEOD REPORT | | S92-07, PRESSURE LOCKING AND THERMAL BINDING OF GATE VALVES (NUREG-1275, | | VOLUME 9). THERE WERE NO REPORTS ADDRESSING MECHANICAL VALVE BINDING. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31266 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HOPE CREEK REGION: 1 |NOTIFICATION DATE: 11/01/96 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 18:43 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 11/01/96 | +------------------------------------------------+EVENT TIME: 18:07[EST]| |NRC NOTIFIED BY: DEVON PRICE |LAST UPDATE DATE: 11/01/96 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MOHAMED SHANBAKY RDO | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 90 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DISCOVERY THAT RESTART OF THE SERVICE WATER PUMPS AFTER A LOSS OF POWER | | (LOP) AND LOSS OF COOLANT ACCIDENT (LOCA) MAY HAVE RESULTED IN THE FAILURE | | OF THE 'A' SERVICE WATER LOOP AND SUBSEQUENT LOSS OF TWO OUT OF FOUR | | ELECTRICAL DIVISIONS DUE TO TWO INOPERABLE VACUUM BREAKERS | | | | AT 0500 ON OCTOBER 29, 1996, THE TWO REDUNDANT VACUUM BREAKERS ON THE 'A' | | STATION SERVICE WATER LOOP WERE FOUND TO BE INOPERABLE DUE TO CORROSION. AS | | A RESULT, THE 'A' SERVICE WATER LOOP WAS DECLARED INOPERABLE, AND THE UNIT | | ENTERED A 72-HOUR SERVICE WATER LOOP TECHNICAL SPECIFICATION LIMITING | | CONDITION FOR OPERATION. ONE OF THE INOPERABLE VACUUM BREAKERS WAS | | SUBSEQUENTLY REPAIRED, SATISFACTORILY TESTED, AND RETURNED TO SERVICE AT | | 1830 ON OCTOBER 29, 1996. THE SECOND INOPERABLE VACUUM BREAKER WAS | | REPAIRED, SATISFACTORILY TESTED, AND RETURNED TO SERVICE ON OCTOBER 31, | | 1996. | | | | THE FUNCTION OF THE VACUUM BREAKERS IS TO REDUCE PRESSURE SURGES CAUSED BY | | THE RESTART OF ALL OF THE SERVICE WATER PUMPS FOLLOWING A LOSS OF POWER. ON | | NOVEMBER 1, 1996, THE LICENSEE'S FURTHER REVIEW DETERMINED THAT THE | | POST-LOP/LOCA RESTART OF THE SERVICE WATER PUMPS WITHOUT THE VACUUM | | BREAKERS MAY HAVE POTENTIALLY RESULTED IN THE FAILURE OF THE 'A' SERVICE | | WATER LOOP SUCH THE UNIT COULD HAVE POTENTIALLY LOST TWO OUT OF FOUR | | ELECTRICAL DIVISIONS (IN-HOUSE VITAL POWER). ONE OF THE POTENTIALLY LOST | | ELECTRICAL DIVISIONS WOULD HAVE BEEN REQUIRED DURING THE FIRST TEN MINUTES | | OF ACCIDENT RECOVERY BECAUSE THE LICENSEE TAKES CREDIT FOR THREE OF THE | | FOUR ELECTRICAL DIVISIONS. THIS SITUATION WAS DETERMINED TO BE APPLICABLE | | BETWEEN 0500 AND 1830 ON OCTOBER 29, 1996. | | | | THE LICENSEE IS CONSERVATIVELY REPORTING THIS CONDITION. LICENSEE | | ENGINEERING PERSONNEL ARE CONTINUING TO REVIEW THE CAPABILITY OF THE | | POST-LOP/LOCA RESTART WITHOUT THE VACUUM BREAKERS TO DETERMINE IF THIS | | REPORT WAS NECESSARY. IF THE LICENSEE CONCLUDES THAT THE SYSTEM IS CAPABLE | | OF WITHSTANDING A POST-LOP/LOCA RESTART WITHOUT THE VACUUM BREAKERS, THE | | LICENSEE PLANS TO WITHDRAW THIS NOTIFICATION. | | | | THE UNIT IS CURRENTLY AT 90% REACTOR POWER AND REDUCING LOAD FOR A PLANNED | | MAINTENANCE OUTAGE. THIS LOAD REDUCTION COMMENCED AT 1800 TODAY. | | | | THE LICENSEE PLANS TO NOTIFY THE NRC RESIDENT INSPECTOR AND THE LOWER | | ALLOWAYS CREEK TOWNSHIP. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31267 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CRYSTAL RIVER REGION: 2 |NOTIFICATION DATE: 11/01/96 | |UNIT: [3] [ ] [ ] STATE: FL |NOTIFICATION TIME: 23:13 [ET]| |RX TYPE: [3] B&W-L-LP |EVENT DATE: 11/01/96 | +------------------------------------------------+EVENT TIME: 22:20[EST]| |NRC NOTIFIED BY: W. K. BANDHAUER |LAST UPDATE DATE: 11/01/96 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MARK LESSER RDO | |DSAF 73.71(b)(1) SECURITY DEGRADATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 3 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | BREACH OF A PROTECTED AREA BARRIER | | | | A SECURITY OFFICER DISCOVERED A BREACH IN A PROTECTED AREA BARRIER AT 2220 | | TODAY. THIS BREACH OF THE PROTECTED AREA BARRIER HAD EXISTED FOR SEVERAL | | DAYS PRIOR TO DISCOVERY. IMMEDIATE COMPENSATORY ACTIONS WERE TAKEN UPON | | DISCOVERY, AND THE BREACH WAS PHYSICALLY CLOSED AT THE TIME OF THIS | | NOTIFICATION. THERE WAS NO INDICATION OF AN UNAUTHORIZED ACCESS ATTEMPT OR | | TAMPERING AS A RESULT OF THIS EVENT. (REFER TO THE HOO LOG FOR ADDITIONAL | | INFORMATION.) | | | | THE LICENSEE PLANS TO NOTIFY THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31268 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HOPE CREEK REGION: 1 |NOTIFICATION DATE: 11/02/96 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 07:32 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 11/02/96 | +------------------------------------------------+EVENT TIME: 04:41[EST]| |NRC NOTIFIED BY: MR. MOHNEY |LAST UPDATE DATE: 11/02/96 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MOHAMED SHANBAKY RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | M/R Y 29 POWER OPERATION | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | MANUAL REACTOR SCRAM DURING PLANT SHUTDOWN | | | | THE REACTOR WAS MANUALLY SCRAMMED FROM 29% POWER AT 0441 DURING A REACTOR | | SHUTDOWN. THE SHUTDOWN WAS PLANNED; HOWEVER, THE REACTOR WAS SCRAMMED AT A | | HIGHER POWER LEVEL THAN NORMAL. IT WAS NECESSARY TO INSERT A SCRAM AT A | | HIGHER POWER LEVEL BECAUSE THE ROD SEQUENCE CONTROL SYSTEM WAS INOPERABLE | | AND PREVENTED THE INSERTION OF THE CONTROL RODS FURTHER INTO THE CORE. | | | | ALL RODS FULLY INSERTED. THE PLANT IS BEING COOLED DOWN BY DUMPING STEAM | | TO THE MAIN CONDENSER TO ENTER A PLANNED MAINTENANCE OUTAGE. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31269 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: NINE MILE POINT REGION: 1 |NOTIFICATION DATE: 11/02/96 | |UNIT: [ ] [2] [ ] STATE: NY |NOTIFICATION TIME: 10:42 [ET]| |RX TYPE: [1] GE-2,[2] GE-5 |EVENT DATE: 11/02/96 | +------------------------------------------------+EVENT TIME: 08:13[EST]| |NRC NOTIFIED BY: TOM LYNCH |LAST UPDATE DATE: 11/02/96 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MOHAMED SHANBAKY RDO | |AINA 50.72(b)(2)(iii)(A) POT UNABLE TO SAFE SD | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 6 STARTUP | 6 STARTUP | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | HIGH PRESSURE CORE SPRAY (HPCS) INOPERABLE | | | | AT 0813, THE DIVISION III EMERGENCY SWITCHGEAR WAS DECLARED INOPERABLE | | BECAUSE ITS ASSOCIATED VENTILATION UNIT COOLER WAS INOPERABLE. THE | | VENTILATION COOLER WAS DECLARED INOPERABLE BECAUSE A MISSING INSPECTION | | COVER WOULD HAVE SHORT CYCLED THE COOL AIR AND PREVENTED THE PROPER COOLING | | OF THE SWITCHGEAR. | | | | THE DIVISION III SWITCHGEAR SUPPLIES POWER TO THE HPCS SYSTEM. THEREFORE, | | HPCS WAS ALSO DECLARED INOPERABLE. SINCE HPCS IS A SINGLE TRAIN HIGH | | PRESSURE INJECTION SYSTEM, THIS EVENT WAS REPORTED AS AFFECTING THE SAFE | | SHUTDOWN CAPABILITY OF THE PLANT. | | | | THE MISSING INSPECTION COVER WAS RE-INSTALLED AT 0825, AND HPCS IS AGAIN | | CONSIDERED OPERABLE. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31270 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: ARKANSAS NUCLEAR REGION: 4 |NOTIFICATION DATE: 11/02/96 | |UNIT: [ ] [2] [ ] STATE: AR |NOTIFICATION TIME: 18:53 [ET]| |RX TYPE: [1] B&W-L-LP,[2] CE |EVENT DATE: 11/02/96 | +------------------------------------------------+EVENT TIME: 14:50[CST]| |NRC NOTIFIED BY: REX KNIGHT |LAST UPDATE DATE: 11/02/96 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOESEPH TAPIA RDO | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 98 POWER OPERATION | 98 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | OFFSITE NOTIFICATION OF A CHEMICAL SPILL | | | | ON NOVEMBER 2, 1996, A CHEMIST WAS FILLING SERVICE WATER CHEMICAL INJECTION | | DAY TANKS FROM THE BULK STORAGE TANK. THE CHEMIST WAS DISTRACTED FROM HIS | | DUTIES AND ALLOWED THE DAY TANK TO OVERFLOW ONTO THE FLOOR IN A BERMED | | AREA. ALTHOUGH THE AREA WAS BERMED, IT CONTAINED AN EYEWASH STATION WITH A | | FLOOR DRAIN, AND THE PRODUCT WAS GOING INTO THE FLOOR DRAIN. THIS CAUSED | | THE CHEMICAL TO BE DISCHARGED TO THE IDLE SERVICE WATER BAY. THE LEAK WAS | | IDENTIFIED WITHIN THREE HOURS, AND THE FLOOR DRAINS WERE ISOLATED WITHIN | | THREE AND ONE HALF HOURS. THE LICENSEE ALSO CLOSED THE LAKE GATE ON THE | | IDLE SERVICE WATER BAY. THE LICENSEE CALCULATED THAT 814 GALLONS OF THE | | SOLUTION ENTERED THIS BAY AND CONSERVATIVELY ASSUMED THAT THE ENTIRE AMOUNT | | WAS DISCHARGED TO THE LAKE. THIS AMOUNT EQUATES TO APPROXIMATELY 9,233 | | POUNDS, AND THE REPORTABLE QUANTITY FOR THIS PRODUCT WAS 9,615 POUNDS. | | | | THE CHEMICAL SOLUTION INVOLVED IN THE SPILL CONTAINED 10% ZINC CHLORIDE AND | | 21% PHOSPHORIC ACID. THE TRADE NAME FOR THE CHEMICAL WAS C-27+, AND IT WAS | | USED AS A CORROSION INHIBITOR FOR SERVICE WATER TREATMENT. THE LICENSEE | | BELIEVES THAT THIS CHEMICAL SOLUTION DOES NOT CONTAIN ANY EXTREMELY | | HAZARDOUS SUBSTANCES, THAT THERE ARE NO HEALTH RISKS POSED BY THE RELEASE, | | AND THAT THERE ARE NO EXPECTED ENVIRONMENTAL CONSEQUENCES. | | | | THE LICENSEE REPORTED THIS CHEMICAL SPILL TO THE NRC RESIDENT INSPECTOR, | | THE ARKANSAS DEPARTMENT OF HEALTH, THE NATIONAL ENVIRONMENTAL RESPONSE | | CENTER, A STATE RESPONSE CENTER, AND A LOCAL COUNTY ENVIRONMENTAL RESPONSE | | CENTER. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31271 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CLINTON REGION: 3 |NOTIFICATION DATE: 11/03/96 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 01:34 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 11/02/96 | +------------------------------------------------+EVENT TIME: 22:00[CST]| |NRC NOTIFIED BY: DAVID HODEL |LAST UPDATE DATE: 11/03/96 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PATRICK HILAND 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 +------------------------------------------------------------------------------+ | THE HIGH PRESSURE CORE SPRAY DIESEL GENERATOR OUTPUT BREAKER FAILED ITS | | SURVEILLANCE TEST. | | | | THE DIESEL GENERATOR DIVISION-III OUTPUT BREAKER THAT CONNECTS THE DIESEL | | TO THE DIVISION-III 4.16-KV SAFETY-RELATED BUS FAILED TO CLOSE WITHIN 12 | | SECONDS AS REQUIRED BY TECHNICAL SPECIFICATION SURVEILLANCE 3.8.1.19.C.1. | | THIS BUS POWERS THE HIGH PRESSURE CORE SPRAY SYSTEM. THE BREAKER ACTUALLY | | CLOSED IN 20 SECONDS DURING THE SURVEILLANCE. THIS SURVEILLANCE SIMULATES | | A LOSS OF OFFSITE POWER WITH AN EMERGENCY CORE COOLING SYSTEM INITIATION | | SIGNAL. | | | | THE APPARENT CAUSE OF THE FAILURE WAS A MISCALIBRATION OF A TIME DELAY | | RELAY FOR THE BREAKER CLOSING CIRCUIT. THE RELAY FOR THE BREAKER SHOULD | | HAVE BEEN SET AT 0.5 SECONDS AND WAS ACTUALLY SET AT APPROXIMATELY 11 | | SECONDS. MAINTENANCE TO RECALIBRATE THE RELAY IS IN PROGRESS. THIS | | FAILURE DOES NOT AFFECT THE DIVISION I OR DIVISION II EMERGENCY DIESEL | | GENERATORS. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31272 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PALISADES REGION: 3 |NOTIFICATION DATE: 11/03/96 | |UNIT: [1] [ ] [ ] STATE: MI |NOTIFICATION TIME: 23:39 [ET]| |RX TYPE: [1] CE |EVENT DATE: 11/03/96 | +------------------------------------------------+EVENT TIME: 20:08[EST]| |NRC NOTIFIED BY: MICHEAL J KANE |LAST UPDATE DATE: 11/03/96 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PATRICK HILAND 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 +------------------------------------------------------------------------------+ | FAILURE OF THE SERVICE WATER OUTLET CONTROL VALVE TO OPEN FROM A CONTROL | | ROOM SIGNAL DURING COMPONENT COOLING WATER HEAT EXCHANGER PERFORMANCE | | TESTING | | | | DURING COMPONENT COOLING WATER HEAT EXCHANGER PERFORMANCE TESTING, THE | | SERVICE WATER OUTLET CONTROL VALVE FAILED TO OPEN FROM A CONTROL ROOM | | SIGNAL. THE VALVE WAS SUPPOSED TO OPEN WITHIN 45 SECONDS. THE VALVE WAS | | SUBSEQUENTLY DECLARED INOPERABLE, AND THIS CAUSED THE 'A' COMPONENT COOLING | | WATER HEAT EXCHANGER TO BE INOPERABLE. (BOTH COMPONENT COOLING WATER HEAT | | EXCHANGERS ARE REQUIRED TO BE OPERABLE DURING POWER OPERATION, BUT THE UNIT | | HAS RECENTLY ENTERED A REFUELING OUTAGE.) THE LICENSEE WAS ABLE TO OPEN | | THE VALVE LOCALLY. IT IS CURRENTLY OPEN, AND THE RESIDUAL HEAT REMOVAL | | SYSTEM AND PRIMARY COOLANT PUMPS ARE AVAILABLE FOR CORE COOLING. ALL | | SYSTEMS FUNCTIONED AS REQUIRED, AND THE UNIT IS NOT IN ANY TECHNICAL | | SPECIFICATION LIMITING CONDITIONS FOR OPERATION. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+