U.S. Nuclear Regulatory Commission Operations Center Event Reports For 03/14/97 - 03/17/97 ** EVENT NUMBERS ** 31778 31931 31934 31950 31951 31952 31953 31954 31955 31956 31957 31958 31959 31960 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31778 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BRUNSWICK REGION: 2 |NOTIFICATION DATE: 02/13/97 | |UNIT: [1] [ ] [ ] STATE: NC |NOTIFICATION TIME: 01:44 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 02/12/97 | +------------------------------------------------+EVENT TIME: 22:05[EST]| |NRC NOTIFIED BY: MIKE WILLIAMS |LAST UPDATE DATE: 03/14/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN POTTER 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 95 POWER OPERATION | 95 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | FAILURE OF A HIGH PRESSURE COOLANT INJECTION SYSTEM MINIMUM FLOW BYPASS | | VALVE TO MEET ITS REQUIRED STROKE TIME DURING TESTING | | | | WHILE PERFORMING A HIGH PRESSURE COOLANT INJECTION SYSTEM OPERABILITY TEST, | | THE MINIMUM FLOW BYPASS VALVE TO THE SUPPRESSION POOL EXCEEDED ITS REQUIRED | | OPENING STROKE TIME OF 10 SECONDS. THE ACTUAL STROKE TIME WAS 10.04 | | SECONDS. AS A RESULT, THE HIGH PRESSURE COOLANT INJECTION SYSTEM WAS | | DECLARED TO BE INOPERABLE, AND A 7-DAY TECHNICAL SPECIFICATION LIMITING | | CONDITION FOR OPERATION WAS ENTERED AT 2205 ON FEBRUARY 12, 1997. | | | | THE LICENSEE DETERMINED THAT THE INITIAL SAFETY SIGNIFICANCE WAS MINIMAL | | BECAUSE THE AUTOMATIC DEPRESSURIZATION, LOW PRESSURE COOLANT INJECTION, | | CORE SPRAY, AND REACTOR CORE ISOLATION COOLING SYSTEMS WERE ALL OPERABLE. | | THE LICENSEE PLANS TO INSPECT AND REPAIR THE MINIMUM FLOW VALVE TO OBTAIN | | THE REQUIRED STROKE TIME. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE AT 1130 EST ON 03/14/97, FROM STEVE TABOR TO S. SANDIN * * * | | | | THE LICENSEE IS RETRACTING THIS EVENT NOTIFICATION BASED UPON COMPLETION OF | | AN ENGINEERING EVALUATION THAT DETERMINED AN OPENING STROKE TIME UP TO 16.6 | | SECONDS WAS ACCEPTABLE FOR THE SUBJECT VALVE. CONSEQUENTLY, THE HIGH | | PRESSURE COOLANT INJECTION SYSTEM WAS CAPABLE OF PERFORMING ITS DESIGN | | FUNCTION. THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. THE NRC | | OPERATIONS CENTER NOTIFIED THE R2DO (AL BELISLE). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31931 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: ZION REGION: 3 |NOTIFICATION DATE: 03/11/97 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 17:45 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 03/11/97 | +------------------------------------------------+EVENT TIME: 15:54[CST]| |NRC NOTIFIED BY: WINTERS |LAST UPDATE DATE: 03/15/97 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: UNUSUAL EVENT +-----------------------------+ |10 CFR SECTION: |WAYNE KROPP RDO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |STUART RICHARDS, NRR EO | |AESF 50.72(b)(2)(ii) ESF ACTUATION |BOB CALDWELL FEMA | | |STU RUBIN, IRD AEOD | | |AL CHAFFEE NRR | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | DECLARATION OF AN UNUSUAL EVENT DUE TO THE LOSS OF OFFSITE POWER TO UNIT 1, | | i.e., LOSS OF THE SYSTEM AUXILIARY TRANSFORMER AND THE SUBSEQUENT STARTING | | AND LOADING OF THE EMERGENCY DIESEL GENERATORS (EDG) | | | | THE SYSTEM AUXILIARY TRANSFORMER [WHICH SUPPLIES POWER TO THE ENGINEERED | | SAFETY FEATURE (ESF) BUSES] TRIPPED, AND THE DELUGE SYSTEM ACTUATED FOR | | UNKNOWN REASONS. BOTH UNIT 1 EDGs ('1A' AND '1B') AND THE SHARED EDG ('0') | | STARTED AND SUPPLIED POWER TO THE UNIT 1 ESF BUSES. SHUTDOWN COOLING WAS | | LOST FOR 8 MINUTES DUE TO THE INTERRUPTION IN POWER, AND AN INCREASE IN | | REACTOR COOLANT TEMPERATURE FROM 92øF TO 112øF WAS OBSERVED. THE EDGs ARE | | STILL RUNNING AND SUPPLYING POWER FOR THE RESIDUAL HEAT REMOVAL (RHR) | | SYSTEM. AS A RESULT OF THIS EVENT, AN UNUSUAL EVENT WAS DECLARED AT 1617 | | CST ON MARCH 11, 1997. | | | | OFFSITE POWER IS CURRENTLY AVAILABLE FROM UNIT 2; HOWEVER, THE LICENSEE HAS | | CHOSEN TO CONTINUE RUNNING THE EDGs WHILE TROUBLESHOOTING THE SYSTEM | | AUXILIARY TRANSFORMER PROBLEM. THE CRITERION FOR TERMINATING THE UNUSUAL | | EVENT IS THE RESTORATION OF RELIABLE OFFSITE POWER TO THE ESF BUSES. | | | | THE LICENSEE PLANS TO INFORM THE NRC RESIDENT INSPECTOR. | | | | *** 1950 EST MARCH 11, 1997, UPDATE FROM WINTERS TAKEN BY KARSCH *** | | | | THE LICENSEE HAS RESTORED OFFSITE POWER TO UNIT 1 BUS '147' VIA THE UNIT 2 | | SYSTEM AUXILIARY TRANSFORMER. BOTH UNIT 1 TRAINS OF RHR ARE CURRENTLY | | BEING POWERED BY UNIT 1 BUSES '148' AND '149' WHICH ARE IN TURN BEING | | POWERED BY THE '1A' AND '1B' EDGs, RESPECTIVELY. | | | | THE OPERATIONS CENTER NOTIFIED THE NRR EO (RICHARDSON) AND R3DO (KROPP). | | | | *** 0536 EST MARCH 12, 1997, UPDATE FROM RENDALL RECEIVED BY TROCINE *** | | | | THE LICENSEE PROVIDED AN UPDATE REGARDING THE STATUS OF UNIT 1. THE UNIT 1 | | SYSTEM AUXILIARY TRANSFORMER IS STILL DE-ENERGIZED. IN ADDITION, THE TWO | | ESSENTIAL BUSES ('148' AND '149') WHICH ARE SUPPLYING POWER TO RHR ARE | | STILL BEING SUPPLIED BY THE '1A' AND '1B' EDGs, AND THE REMAINING ESSENTIAL | | UNIT 1 BUS ('147') IS BEING SUPPLIED BY THE UNIT 2 SYSTEM AUXILIARY | | TRANSFORMER. THE RING BUS WAS ALSO CLOSED AT 0426 CST ON MARCH 12, 1997. | | | | THE LICENSEE REPORTED THE FOLLOWING PRIORITIES: | | | | 1. INITIATE A RESERVE FEED FROM THE UNIT 2 SYSTEM AUXILIARY TRANSFORMER TO | | BUSES '148' AND '149,' | | 2. PROVIDE ALTERNATE POWER TO THE STATION FIRE PROTECTION CARDOX (CO2) | | TANK COMPRESSOR, | | 3. CLEAR THE UNIT 2 MAIN GENERATOR (OUT OF SERVICE TO OBTAIN ADDITIONAL | | GROUND BREAKERS), | | 4. RECOVER THE UNIT 1 SYSTEM AUXILIARY TRANSFORMER, | | 5. DEVELOP RADWASTE CONTINGENCIES, | | 6. DEPRESSURIZE THE UNIT 1 GENERATOR, | | 7. IMPLEMENT ALTERNATE HEATING TO BUILDINGS, AND | | 8. DEVELOP AN ALTERNATE POWER SOURCE TO THE '1A' INSTRUMENT AIR | | COMPRESSOR. | | | | THE LICENSEE PLANS TO PROVIDE ADDITIONAL INFORMATION IF THE STATUS OF THE | | PLANT OR EMERGENCY CLASSIFICATION CHANGES. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR, AND THE APPLICABLE STATE | | AND LOCAL AGENCIES. THE NRC OPERATIONS CENTER NOTIFIED THE R3DO (KROPP), | | NRR EO (RICHARDSON), AND AEOD IRD (RUBIN). | | | | HOO NOTES: THE LICENSEE'S TECHNICAL SUPPORT CENTER WAS ACTIVATED DURING | | THIS EVENT. BOTH UNITS ARE IN COLD SHUTDOWN WITH FUEL LOADED IN THE | | REACTOR VESSELS. THE UNIT 1 REACTOR COOLANT SYSTEM IS CURRENTLY SOLID AND | | DEPRESSURIZED. THE UNIT 2 EDGs ('2A' AND '2B') WERE NOT AFFECTED BY THIS | | EVENT. HOWEVER, THE '2B' EDG HAS BEEN OUT OF SERVICE DUE TO A PREVIOUS | | PROBLEM INVOLVING A CYLINDER LINER FAILURE. | | | | * * * 0133 EST MARCH 15, 1997 UPDATE FROM ROWE RECEIVED BY TROCINE * * * | | | | ON MARCH 14, 1997, THE LICENSEE RE-ENERGIZED THE UNIT 1 SYSTEM AUXILIARY | | TRANSFORMER AT 0740 CST; AND THIS TRANSFORMER BECAME THE POWER SUPPLY FOR | | UNIT 1 ESSENTIAL BUSES '147,' '148,' AND '149' AT 1718 CST, 1832 CST, AND | | 2350 CST, RESPECTIVELY. AS A RESULT, THE LICENSEE TERMINATED THE UNUSUAL | | EVENT AT 0021 CST ON MARCH 15, 1997, BECAUSE A RELIABLE POWER SUPPLY FROM | | OFFSITE POWER TO THE ESSENTIAL SERVICE BUSES WAS RE-ESTABLISHED. | | | | THE LICENSEE PLANS TO LEAVE COMMAND AND CONTROL IN THE TECHNICAL SUPPORT | | CENTER UNTIL ALL EVOLUTIONS (SUCH AS EDG RELIABILITY) HAVE BEEN COMPLETED. | | AT THIS TIME, THE LICENSEE'S FIRST PRIORITY IS TO PROVE EDG OPERABILITY. | | THE '1A' AND '1B' EDGs ARE CURRENTLY RUNNING, AND THEY HAVE BEEN LOADED TO | | 4 MW EACH. THE OPERABILITY ASSESSMENT ON THE UNIT 1 EDGs HAS ALSO BEEN | | WRITTEN, BUT IT STILL NEEDS TO BE SIGNED. IN ADDITION, THE LICENSEE PLANS | | TO COOL DOWN THE '1A' AND '1B' EDGs, DO A PERFORMANCE TEST OF '1A' EDG, | | PERFORM A ROLL-OVER OF THE '0' EDG TO PROVE THAT THERE IS NO WATER IN THE | | CYLINDERS, AND PERFORM A ROLL-OVER OF THE '1A' EDG 24 HOURS AFTER | | PERFORMANCE OF THE OPERABILITY TEST HAS BEEN PERFORMED. THE LICENSEE PLANS | | TO TEST THE '1B' EDG AFTER OPERABILITY OF THE '1A' EDG HAS BEEN VERIFIED. | | | | THE LICENSEE HAS NOTIFIED THE NRC RESIDENT INSPECTOR AND THE APPLICABLE | | STATE AND LOCAL AGENCIES. THE NRC OPERATIONS CENTER NOTIFIED THE R3DO | | (KROPP), AEOD IRD (CONGEL AND RUBIN), NRR EO (RICHARDS), NRR (CAPRA AND | | ZIMMERMAN), AND FEMA (CIBOCH). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31934 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: LASALLE REGION: 3 |NOTIFICATION DATE: 03/11/97 | |UNIT: [1] [2] [ ] STATE: IL |NOTIFICATION TIME: 21:38 [ET]| |RX TYPE: [1] GE-5,[2] GE-5 |EVENT DATE: 03/11/97 | +------------------------------------------------+EVENT TIME: 19:45[CST]| |NRC NOTIFIED BY: JAY HOUSTON |LAST UPDATE DATE: 03/15/97 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: UNUSUAL EVENT +-----------------------------+ |10 CFR SECTION: |WAYNE KROPP RDO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |STUART RICHARDS, NRR EO | | |KNUPP FEMA | | |STU RUBIN, IRD AEOD | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | THE LICENSEE DECLARED AN UNUSUAL EVENT AT 1945 CST WHEN LAKE LEVEL ROSE | | ABOVE THE MAXIMUM ALLOWED FINAL SAFETY ANALYSIS REPORT (FSAR) VALUE. | | | | THE MAXIMUM LAKE LEVEL ALLOWED BY THE LICENSEE'S FSAR IS 701 FEET, AND THE | | LAKE LEVEL IS NOW AT 701.8 FEET. THE LAKE LEVEL BLOWDOWN VALVE IS BROKEN, | | AND RAIN IS FORECAST. THE LICENSEE, THEREFORE, EXPECTS THAT LAKE LEVEL | | MIGHT INCREASE IN THE NEAR FUTURE. THE LICENSEE IS ATTEMPTING TO HAVE | | DIVERS REPAIR THE BLOWDOWN VALVE. IN ADDITION, PERSONNEL ARE MONITORING | | THE LOWER ELEVATIONS IN THE PLANT, AND THE ENGINEERING DEPARTMENT IS | | RE-EVALUATING THE 701-FOOT LEVEL LIMIT. | | | | THE LICENSEE IS ACTIVATING ITS TECHNICAL SUPPORT CENTER AND HAS NOTIFIED | | STATE GOVERNMENT AGENCIES AND THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE AT 2159 ON MARCH 15, 1997, FROM ARGUBRIGHT TO S. SANDIN * * * | | | | THE STATION REMAINS IN AN UNUSUAL EVENT (EAL HU2) DUE TO A HIGH LAKE LEVEL | | (>701 FEET) THAT IS OUTSIDE OF THE PLANT'S DESIGN BASIS. LAKE LEVEL IS | | CURRENTLY 701.5 FEET AND HAS BEEN TRENDING DOWNWARD SINCE BLOWDOWN FLOW WAS | | REESTABLISHED ON THURSDAY, MARCH 13, 1997. | | | | THE STATION ANTICIPATES TERMINATING THE UNUSUAL EVENT NEXT WEEK WHEN LAKE | | LEVEL HAS BEEN RESTORED TO LESS THAN 700.75 FEET (CONFIRMED BY SURVEYOR), | | PROVIDED NO SIGNIFICANT PRECIPITATION IS FORECASTED IN THE SUBSEQUENT 3 | | DAYS. | | | | COMPENSATORY AND CONTINGENCY ACTIONS (FLOOD WATCHES, EMERGENCY BACKUP | | PUMPING EQUIPMENT, SANDBAGS, ETC.) ESTABLISHED AT THE ONSET OF THE UNUSUAL | | EVENT WILL REMAIN IN EFFECT UNTIL THE UNUSUAL EVENT IS TERMINATED. | | | | BASED ON THE CORRECTIVE, MITIGATING, AND COMPENSATORY ACTIONS TAKEN AND THE | | CURRENT DOWNWARD TREND IN LAKE LEVEL, THE TECHNICAL SUPPORT CENTER MANNING | | ESTABLISHED AT THE ONSET OF THE EVENT HAS BEEN SECURED. THE UNIT 1 SHIFT | | MANAGER WILL CONTINUE FULFILLING THE POSITION OF ACTING STATION DIRECTOR. | | THE UNIT 1 PLANT MANAGER HAS BEEN ASSIGNED AS THE ISSUES MANAGER FOR ANY | | NEW AND REMAINING ISSUES. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. THE HOO NOTIFIED THE | | R3DO (KROPP) AND NRR EO (RICHARDS). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31950 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: NINE MILE POINT REGION: 1 |NOTIFICATION DATE: 03/14/97 | |UNIT: [1] [ ] [ ] STATE: NY |NOTIFICATION TIME: 07:48 [ET]| |RX TYPE: [1] GE-2,[2] GE-5 |EVENT DATE: 03/14/97 | +------------------------------------------------+EVENT TIME: 07:30[EST]| |NRC NOTIFIED BY: DOUG LACUYER |LAST UPDATE DATE: 03/14/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JENNY JOHANSEN 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 +------------------------------------------------------------------------------+ | IDENTIFICATION OF CRACKS IN VERTICAL SHROUD WELD HEAT AFFECTED ZONES | | | | AS A RESULT OF AUGMENTED IN-SERVICE INSPECTION OF THE REACTOR CORE SHROUD | | IN ACCORDANCE WITH THE BOILING WATER REACTOR VESSEL INTERNAL PROJECT | | (BWRVIP07) GUIDELINES, WELD INDICATIONS (CRACKS) WERE FOUND IN THE HEAT | | AFFECTED ZONES ON THE OUTSIDE DIAMETER ONLY. A SIGNIFICANT PORTION OF THE | | EQUIVALENT LENGTH OF WELDS V9 AND V10 EXHIBITED INDICATIONS. INSPECTION IS | | CONTINUING, AND OTHER VERTICAL WELDS MAY BE CRACKED. THIS EXCEEDS THE | | INITIAL FLAW EVALUATION ACCEPTANCE CRITERIA OF A MINIMUM REQUIRED UNCRACKED | | LENGTH OF 27 INCHES. EXPANDED SAMPLE INSPECTIONS ARE UNDER WAY TO | | DETERMINE THE EXTENT OF CRACKING OF OTHER SHROUD VERTICAL WELDS IN | | ACCORDANCE WITH THE BWRVIP07 CRITERIA, WHICH WAS RECENTLY REVIEWED AND | | ACCEPTED BY THE NRC STAFF FOR UNIT 1. AS A RESULT OF THE EXPANDED | | EXAMINATIONS, ENGINEERING PLANS TO ASSESS THE ACCEPTABILITY OF THE CRACKING | | AND OVERALL SAFETY IMPLICATIONS. ALL OF THE REACTOR FUEL IS IN THE SPENT | | FUEL POOL AT THIS TIME. BASED UPON THIS DETAILED ANALYSIS, THIS | | NOTIFICATION MAY BE RESCINDED. | | | | THE LICENSEE PLANS TO NOTIFY THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31951 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MCGUIRE REGION: 2 |NOTIFICATION DATE: 03/14/97 | |UNIT: [ ] [2] [ ] STATE: NC |NOTIFICATION TIME: 09:25 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 03/14/97 | +------------------------------------------------+EVENT TIME: 08:35[EST]| |NRC NOTIFIED BY: LARRY ABERNATHY |LAST UPDATE DATE: 03/14/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |AL BELISLE RDO | |ADEG 50.72(b)(1)(ii) DEGRAD COND DURING OP | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 23 POWER OPERATION | 23 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | SLOW CLOSURE TIME FOR UNIT 2 FEEDWATER ISOLATION VALVE DURING TESTING AS A | | RESULT OF VALVE FAILURES ON UNIT 1 (REFER TO EVENT #31946 FOR INFORMATION | | REGARDING UNIT 1 AND EVENT #31952 FOR INFORMATION REGARDING ANOTHER SLOW | | VALVE CLOSURE ON UNIT 2.) | | | | AS A RESULT OF TWO UNIT 1 FEEDWATER ISOLATION VALVES FAILING TO ACTUATE | | DURING TESTING, THE LICENSEE REDUCED UNIT 2 REACTOR POWER FROM 100% TO 23% | | FOR TESTING OF THE UNIT 2 FEEDWATER ISOLATION VALVES. DURING THIS TESTING, | | FEEDWATER ISOLATION VALVE 2CF-28 FAILED TO CLOSE IN THE REQUIRED 10 | | SECONDS. ACTUAL CLOSURE TIME WAS 25.4 SECONDS. VALVE 2CF-28 IS THE | | ISOLATION VALVE FOR THE '2C' STEAM GENERATOR. | | | | THIS WAS THE FIRST OF FOUR UNIT 2 FEEDWATER ISOLATION VALVES TO BE TESTED, | | AND THIS FAILURE PLACES UNIT 2 IN A FOUR-HOUR TECHNICAL SPECIFICATION | | LIMITING CONDITION FOR OPERATION WHICH REQUIRES THE VALVE TO BE SECURED IN | | THE CLOSED POSITION UNTIL IT IS REPAIRED. WITH THE UNIT AT REDUCED POWER, | | THE LICENSEE ALSO UTILIZES THE LOWER FEEDWATER NOZZLES AS A REDUNDANT MEANS | | OF SUPPLYING FEEDWATER TO THE STEAM GENERATORS. | | | | THE LICENSEE PLANS TO NOTIFY THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31952 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MCGUIRE REGION: 2 |NOTIFICATION DATE: 03/14/97 | |UNIT: [ ] [2] [ ] STATE: NC |NOTIFICATION TIME: 10:49 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 03/14/97 | +------------------------------------------------+EVENT TIME: 10:35[EST]| |NRC NOTIFIED BY: LARRY ABERNATHY |LAST UPDATE DATE: 03/14/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |AL BELISLE RDO | |ADEG 50.72(b)(1)(ii) DEGRAD COND DURING OP | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 23 POWER OPERATION | 23 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | SLOW CLOSURE TIME FOR A UNIT 2 FEEDWATER ISOLATION VALVE DURING TESTING AS | | A RESULT OF VALVE FAILURES ON UNIT 1 (REFER TO EVENT #31946 FOR INFORMATION | | REGARDING UNIT 1 AND EVENT #31951 FOR INFORMATION REGARDING ANOTHER SLOW | | UNIT 2 VALVE CLOSURE.) | | | | AS A RESULT OF TWO UNIT 2 FEEDWATER ISOLATION VALVES FAILING TO ACTUATE | | DURING TESTING, THE LICENSEE REDUCED UNIT 2 REACTOR POWER FROM 100% TO 23% | | FOR TESTING OF THE UNIT 2 FEEDWATER ISOLATION VALVES. DURING THIS TESTING, | | FEEDWATER ISOLATION VALVE 2CF-30 FAILED TO CLOSE IN THE REQUIRED 10 | | SECONDS. ACTUAL CLOSURE TIME WAS 14.8 SECONDS. VALVE 2CF-30 IS THE | | ISOLATION VALVE FOR THE '2B' STEAM GENERATOR. | | | | THIS WAS THE THIRD OF FOUR UNIT 2 FEEDWATER ISOLATION VALVES TO BE TESTED, | | AND THIS FAILURE PLACES UNIT 2 IN ANOTHER FOUR-HOUR TECHNICAL SPECIFICATION | | LIMITING CONDITION FOR OPERATION WHICH REQUIRES THE VALVE TO BE SECURED IN | | THE CLOSED POSITION UNTIL IT IS REPAIRED. WITH THE UNIT AT REDUCED POWER, | | THE LICENSEE ALSO UTILIZES THE LOWER FEEDWATER NOZZLES AS A REDUNDANT MEANS | | OF SUPPLYING FEEDWATER TO THE STEAM GENERATORS. | | | | VALVE 2CF-26 WAS THE SECOND OF FOUR UNIT 2 FEEDWATER ISOLATION VALVES TO BE | | TESTED. THIS VALVE SUCCESSFULLY CLOSED WITHIN THE REQUIRED 10 SECONDS, AND | | IT IS THE ISOLATION VALVE FOR THE '2A' STEAM GENERATOR. THE LICENSEE ALSO | | PLANS TO TEST THE ISOLATION VALVE FOR THE '2D' STEAM GENERATOR. | | | | THE LICENSEE PLANS TO NOTIFY THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31953 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: NINE MILE POINT REGION: 1 |NOTIFICATION DATE: 03/14/97 | |UNIT: [1] [ ] [ ] STATE: NY |NOTIFICATION TIME: 13:05 [ET]| |RX TYPE: [1] GE-2,[2] GE-5 |EVENT DATE: 03/13/97 | +------------------------------------------------+EVENT TIME: 18:00[EST]| |NRC NOTIFIED BY: B. BOIMENU |LAST UPDATE DATE: 03/14/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JENNY JOHANSEN RDO | |HFIT 26.73 FITNESS FOR DUTY | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | FITNESS-FOR-DUTY REPORT | | | | A CONTRACT SUPERVISOR TESTED POSITIVE DURING A CONFIRMATORY TEST FOR | | ILLEGAL DRUG USE. THE DRUG TESTING LABORATORY REPORTED THAT THE FIRST | | CONFIRMATORY SAMPLE, WHICH TESTED POSITIVE, HAD BEEN DILUTED. A SECOND | | CONFIRMATORY SAMPLE WAS TAKEN UNDER DIRECT OBSERVATION, AND THE RESULTS | | WERE ALSO POSITIVE. THE INDIVIDUAL'S SITE ACCESS HAS BEEN TERMINATED, AND | | THE LICENSEE IS REVIEWING THE INDIVIDUAL'S WORK FOR SAFETY IMPACT. THE | | INDIVIDUAL HAD BEEN INVOLVED WITH THE CLEANING OF THE MAIN CONDENSER. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 31954 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 03/14/97 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 13:30 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 03/14/97 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 00:00[CST]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 03/14/97 | | CITY: PADUCAH REGION: 3 +-----------------------------+ | COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION| |LICENSE#: GDP-1 AGREEMENT: Y |WAYNE KROPP RDO | | DOCKET: 0707001 |JOSEPHINE PICCONE EO | +------------------------------------------------+KEVIN RAMSEY (FAX) NMSS | |NRC NOTIFIED BY: MARK LOMBARD | | |HQ OPS OFFICER: STEVE SANDIN | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |CDEG 21.21(c)(3)(i) DEFECTS/NONCOMPLIANCE | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | 10 CFR PART 21 NOTIFICATION REGARDING STRESS CORROSION CRACKING OF CYLINDER | | VALVE PACKING NUTS | | | | IT HAS BEEN DETERMINED THAT STRESS CORROSION CRACKING OF THE 1-INCH | | CYLINDER VALVE PACKING NUTS USED IN VARIOUS STAGES OF THE ENRICHMENT | | PROCESS HAS, IN ONE CASE, RESULTED IN A REPORTABLE RELEASE OF UF6. THIS | | PROBLEM HAS ONLY BEEN OBSERVED IN THE 636-ALLOY NUTS ON VALVES SUPPLIED BY | | HUNT VALVE CO., INC. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31955 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HARRIS REGION: 2 |NOTIFICATION DATE: 03/14/97 | |UNIT: [1] [ ] [ ] STATE: NC |NOTIFICATION TIME: 17:42 [ET]| |RX TYPE: [1] W-3-LP |EVENT DATE: 03/14/97 | +------------------------------------------------+EVENT TIME: 16:22[EST]| |NRC NOTIFIED BY: RICH WELLS |LAST UPDATE DATE: 03/14/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |AL BELISLE RDO | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE CONTACTED A STATE AGENCY REGARDING AN AUTOMOBILE TRANSMISSION | | FLUID LEAK IN THE EMPLOYEE PARKING LOT. | | | | THE FOLLOWING IS TEXT OF A FACSIMILE RECEIVED FROM THE LICENSEE: | | | | "ON MARCH 14, 1997 AT 1622 HOURS, THE WATER QUALITY SUPERVISOR WITH THE | | NORTH CAROLINA DIVISION OF WATER QUALITY - RALEIGH REGIONAL OFFICE WAS | | NOTIFIED THAT A VEHICLE PARKED IN THE HARRIS PLANT PARKING LOT HAD LEAKED | | SUBSTANTIAL AMOUNTS OF TRANSMISSION FLUID ON THE PAVEMENT. FACILITY | | PERSONNEL OBSERVED THE LEAK AND PLACED ABSORBENT MATERIAL ON THE FLUID AND | | ABSORBENT BOOMS AROUND THE AREA. THE PARKING LOT STORM DRAIN WAS | | INSPECTED, AND NO OIL SHEEN WAS OBSERVED. SINCE IT WAS RAINING AT THE TIME | | OF THE LEAK, IT CANNOT BE DETERMINED IF THE LEAK WAS CONTAINED." | | | | THE LICENSEE INFORMED THE STATE AGENCY AND THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31956 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DIABLO CANYON REGION: 4 |NOTIFICATION DATE: 03/14/97 | |UNIT: [1] [2] [ ] STATE: CA |NOTIFICATION TIME: 19:48 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 03/14/97 | +------------------------------------------------+EVENT TIME: 16:01[PST]| |NRC NOTIFIED BY: BOB MACGRUDER |LAST UPDATE DATE: 03/14/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN PELLET 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 Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE DISCOVERED A CONDITION INVOLVING EACH UNIT'S REFUELING WATER | | STORAGE TANK LEVEL CHANNELS WHICH WOULD PLACE EACH UNIT OUTSIDE ITS DESIGN | | BASIS FOLLOWING AN ACCIDENT ASSUMING ONE LEVEL CHANNEL OUT-OF-SERVICE AND | | AN ACTIVE FAILURE ON A SECOND LEVEL CHANNEL. | | | | THE FOLLOWING IS TEXT OF A FACSIMILE RECEIVED FROM THE LICENSEE: | | | | "TECHNICAL SPECIFICATION (TS) 3.3.3.6 REGARDING POST-ACCIDENT MONITORING | | INSTRUMENTATION REQUIRES THE OPERABILITY OF TWO REFUELING WATER STORAGE | | TANK (RWST) CHANNELS. | | | | ON MARCH 6, 1997, PG&E DETERMINED THAT THE TS 3.3.3.6 INSTRUMENT #8 DOES | | NOT ADEQUATELY ENSURE AVAILABILITY OF THE RESIDUAL HEAT REMOVAL (RHR) PUMP | | TRIP LOGIC WHICH USES THREE RWST LEVEL CHANNELS TO GET TWO LOW LEVEL | | READINGS AND SUBSEQUENT RHR PUMP TRIP. WITH ONE OF THE THREE LEVEL | | CHANNELS OUT-OF-SERVICE (OOS) AND A SINGLE MODE FAILURE IN ANOTHER LEVEL | | CHANNEL, THE RHR PUMP TRIP CIRCUIT WOULD BE DISABLED AND COULD ALLOW THE | | RWST LEVEL TO FALL BELOW DESIGN BASIS LOW LEVEL PRIOR TO COMPLETION OF COLD | | LEG RECIRCULATION SWITCHOVER. | | | | ON MARCH 14, 1997, PG&E DISCOVERED THAT ON SEVERAL PREVIOUS OCCASIONS, A | | RWST LEVEL CHANNEL WAS PLACED IN AN OOS CONDITION. WITHOUT AN AUTOMATIC | | RHR TRIP FUNCTION, THE OPERATOR RESPONSE MAY BE INSUFFICIENT TO PREVENT | | RWST LEVEL FROM DROPPING BELOW THE DESIGN BASIS LEVEL. THE PLANT IS | | CURRENTLY OPERATING WITHIN DESIGN BASIS WITH ALL THREE RWST LEVEL CHANNELS | | IN SERVICE. | | | | PG&E HAS COMPLETED AN INTERPRETATION OF TS 3.3.3.6 INSTRUMENT #8 REGARDING | | ACTION WHEN A RWST LEVEL CHANNEL IS DECLARED INOPERABLE. THE TS | | INTERPRETATION EXPLICITLY DIRECTS OPERATORS TO PLACE THE INOPERABLE RWST | | LEVEL CHANNEL IN "CUTOUT" WITHIN 6 HOURS OF DECLARING THE LEVEL CHANNEL OOS | | AND IF, AFTER 72 HOURS THE CHANNEL IS NOT RETURNED TO SERVICE, THE | | OPERATORS MUST PLACE THE PLANT IN MODE 3 (HOT STANDBY) WITHIN 6 HOURS. THE | | PLANT MUST BE PLACED IN MODE 5 (COLD SHUTDOWN) WITHIN THE NEXT 30 HOURS. | | | | PG&E IS CONSERVATIVELY REPORTING THIS EVENT IN ACCORDANCE WITH 10 CFR | | 50.72(b)(1)(ii)(B) AS A CONDITION OUTSIDE THE DESIGN BASIS OF THE PLANT | | SINCE BASED ON PRELIMINARY EVALUATIONS, THE OPERATOR RESPONSE MAY BE | | INSUFFICIENT TO PREVENT RWST LEVEL FROM DROPPING BELOW THE DESIGN BASIS | | LEVEL. | | | | PG&E WILL BE SUBMITTING A REVISION TO TSs TO MORE APPROPRIATELY CONTROL | | OPERATION OF RWST LEVEL CHANNELS." | | | | THE LICENSEE PLANS TO INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31957 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SUSQUEHANNA REGION: 1 |NOTIFICATION DATE: 03/15/97 | |UNIT: [ ] [2] [ ] STATE: PA |NOTIFICATION TIME: 03:07 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 03/15/97 | +------------------------------------------------+EVENT TIME: 02:24[EST]| |NRC NOTIFIED BY: DAVE WALSH |LAST UPDATE DATE: 03/15/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JENNY JOHANSEN RDO | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 HOT SHUTDOWN | 0 HOT SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | COURTESY NOTIFICATION REGARDING COMMENCEMENT OF THE EIGHTH REFUELING OUTAGE | | FOR UNIT 2 | | | | UNIT 2 WAS TAKEN OFF LINE AT 0224 ON MARCH 15, 1997, IN ORDER TO COMMENCE A | | PLANNED REFUELING OUTAGE. THE UNIT IS CURRENTLY STABLE IN HOT SHUTDOWN, | | AND THE LICENSEE PLANS TO CONTINUE COOLING THE UNIT DOWN TO PLACE IT IN A | | COLD SHUTDOWN CONDITION. THIS REFUELING OUTAGE IS CURRENTLY SCHEDULED FOR | | COMPLETION WITHIN FOUR WEEKS. | | | | THE LICENSEE PLANS TO NOTIFY THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31958 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PRAIRIE ISLAND REGION: 3 |NOTIFICATION DATE: 03/15/97 | |UNIT: [ ] [2] [ ] STATE: MN |NOTIFICATION TIME: 04:07 [ET]| |RX TYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 03/15/97 | +------------------------------------------------+EVENT TIME: 00:40[CST]| |NRC NOTIFIED BY: BILL MATHER |LAST UPDATE DATE: 03/15/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |WAYNE KROPP 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 N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | PLANNED OFFSITE NOTIFICATION REGARDING THE RELEASE OF WATER CONTAINING | | CONCENTRATIONS OF MONOETHANOLAMINE (ETA) IN EXCESS OF THE NATIONAL | | POLLUTION DISCHARGE ELIMINATION SYSTEM (NPDES) PERMIT LIMIT | | | | AT 0040 CST ON MARCH 15, 1997, ETA IN THE UNIT 2 STEAM GENERATORS WAS | | GREATER THAN THE NPDES PERMIT LIMIT OF 6 PPM ETA WHILE THE STEAM GENERATORS | | WERE BEING DRAINED TO THE RIVER IN PREPARATION FOR CREVICE FLUSHING. THE | | '21' STEAM GENERATOR WATER RELEASE WAS 12,608 GALLONS WITH 13 PPM ETA, AND | | THE '22' STEAM GENERATOR WATER RELEASE WAS 11,040 GALLONS WITH 7.9 PPM ETA. | | THE RELEASE WAS STOPPED, AND THE LICENSEE'S ENVIRONMENTAL REGULATORY | | AFFAIRS DEPARTMENT WAS NOTIFIED. PERSONNEL IN THIS DEPARTMENT PLAN TO | | NOTIFY THE STATE DUTY OFFICER FOR THE POLLUTION CONTROL AGENCY OF | | MINNESOTA. | | | | ETA IS NOT ADDED WHILE THE UNIT IS SHUT DOWN. IT IS USED FOR pH CONTROL | | WHILE THE UNIT IS OPERATING. THE LICENSEE BELIEVES THAT THE CONCENTRATION | | OF ETA RELEASED WAS DUE TO HIDE OUT RETURN IN THE STEAM GENERATORS LEACHING | | INTO THE WATER. | | | | THE LICENSEE HAS SUBMITTED AN APPLICATION TO PERMIT RELEASES AT LEVELS LESS | | THAN 25 PPM ETA. PREVIOUS APPROVAL HAS BEEN GIVEN BY THE MINNESOTA | | POLLUTION CONTROL AGENCY FOR RELEASES AT LEVELS LESS THAN 25 PPM ETA. | | | | THE LICENSEE PLANS TO NOTIFY THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE 1536EST FROM LESS ANDERSON TO S. SANDIN * * * | | | | THE LICENSEE DETERMINED THAT THE SOURCE OF THE ETA IS FROM THE CHEMICAL | | DECOMPOSITION OF MORPHOLINE USED FOR CHEMISTRY CONTROL RATHER THAN STEAM | | GENERATOR HIDEOUT. MORPHOLINE IS ADDED TO THE STEAM GENERATORS WHILE THE | | UNIT IS SHUTDOWN. THE LICENSEE INFORMED THE STATE OF MINNESOTA. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31959 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOPER REGION: 4 |NOTIFICATION DATE: 03/15/97 | |UNIT: [1] [ ] [ ] STATE: NE |NOTIFICATION TIME: 18:32 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 03/15/97 | +------------------------------------------------+EVENT TIME: 12:00[CST]| |NRC NOTIFIED BY: DOUG HITZELL |LAST UPDATE DATE: 03/15/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN PELLET RDO | |NLTR LICENSEE 24 HR REPORT | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 92 POWER OPERATION | 92 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LICENSEE 24 HOUR REPORT RELATED TO INOPERABLE FIRE PUMPS. | | | | THE FOLLOWING IS TEXT OF A FACSIMILE RECEIVED FROM THE LICENSEE: | | | | "ON MARCH 1, 1997, AT 1900 HOURS, THE ELECTRIC FIRE PUMP (FP-P-E) WAS MADE | | INOPERABLE DUE TO A BEARING FAILURE. INITIALLY, IT WAS BELIEVED THAT THE | | BEARING FAILED DUE TO OVERHEATING OF THE PUMP DURING LOW FLOW OPERATION. | | THE BEARING FAILED DUE TO WATER INTRUSION FROM EXCESSIVE PACKAGE LEAKAGE. | | THE OVERHEATING OF THE PUMP OCCURRED DUE TO THE SETPOINT FOR THE MINIMUM | | FLOW RELIEF VALVE BEING TOO HIGH. THIS REQUIRED ENTRY INTO TECHNICAL | | SPECIFICATION 3.15.B. ON MARCH 15, 1997, AT 1200 HOURS, THE DIESEL FIRE | | PUMP WAS MADE INOPERABLE DUE TO LOSS OF VOLTAGE IN BOTH BANKS OF STARTING | | BATTERIES. THIS REQUIRED ENTRY INTO TECHNICAL SPECIFICATION 3.15.C WHICH | | REQUIRES THAT BACKUP FIRE SUPPRESSION BE PROVIDED AND A SPECIAL REPORT TO | | THE NRC BE SUBMITTED BY TELEPHONE WITHIN 24 HOURS AND IN WRITING NO LATER | | THAN ONE WORKING DAY FOLLOWING THE EVENT OUTLINING THE ACTION TAKEN, THE | | CAUSE OF THE INOPERABILITY, AND THE PLANS AND SCHEDULE FOR RESTORING THE | | SYSTEM TO OPERABLE STATUS. THE BACKUP FIRE PUMP FP-P-C WAS IN SERVICE | | DURING THIS TIME. THE CAUSE OF THE INOPERABILITY IS DESCRIBED ABOVE. THE | | ELECTRIC FIRE PUMP HAS BEEN RESTORED TO AVAILABLE STATUS AS OF 1538 HOURS | | ON MARCH 15, 1997, BUT REQUIRES THE RELIEF VALVE TO BE RESET PRIOR TO BEING | | DECLARED OPERABLE. THIS IS ESTIMATED TO BE COMPLETED BY MARCH 19, 1997. | | THE DIESEL FIRE PUMP REQUIRES REPLACEMENT OF BOTH BANKS OF STARTING | | BATTERIES AND REPLACEMENT OF THE BATTERY CHARGER CONTROL CARD. THE | | BATTERIES WILL BE REPLACED BY THE EVENING OF MARCH 15, 1997. IT IS | | ESTIMATED THAT THE REPLACEMENT BATTERY CHARGER CONTROL CARD WILL BE | | REPLACED BY MARCH 19, 1997, AND THE PUMP RETURNED TO OPERABLE STATUS AT | | THAT TIME. | | | | THIS NOTIFICATION IS IN ACCORDANCE WITH TECHNICAL SPECIFICATION 3.15.C.2.a | | SUBMITTAL OF SPECIAL REPORT BY TELEPHONE WITHIN 24 HOURS. THIS WILL BE | | FOLLOWED BY A WRITTEN REPORT PER TECHNICAL SPECIFICATION 3.15.C.2.b ON THE | | FIRST WORKING DAY FOLLOWING THE EVENT." | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31960 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 03/16/97 | |UNIT: [2] [ ] [ ] STATE: NY |NOTIFICATION TIME: 20:18 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 03/16/97 | +------------------------------------------------+EVENT TIME: 17:00[EST]| |NRC NOTIFIED BY: MICHELE SAVINO |LAST UPDATE DATE: 03/16/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JENNY JOHANSEN RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 2 | N Y 76 POWER OPERATION | 76 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNIT 2 EXPERIENCED A STEAM GENERATOR BLOWDOWN (SGBD) ACTUATION DUE TO A | | VALID RADIATION MONITOR ALARM. | | | | RADIATION MONITOR 'R49' ALARMED (SETPOINT 1E-5 MR/HR) CAUSING SGBD FOR ALL | | FOUR STEAM GENERATORS (SG) TO ISOLATE. OPERATORS ENTERED THE ABNORMAL | | OPERATING PROCEDURE FOR SG TUBE LEAKAGE AND SUBSEQUENTLY IDENTIFIED THAT SG | | '23' HAD DEVELOPED < 1.78 GALLONS PER DAY (GPD) PRIMARY-TO-SECONDARY | | LEAKAGE. THIS LEAKAGE IS WELL BELOW THE TECHNICAL SPECIFICATION | | 3.1.F.2.a.1 LIMIT OF 0.3 GALLONS PER MINUTE (GPM) TOTAL WHICH CORRESPONDS | | TO 432 GPD THAT WOULD REQUIRE THE UNIT TO BE PLACED IN COLD SHUTDOWN WITHIN | | 24 HOURS. THERE IS NO OTHER KNOWN LEAKAGE IN THE REMAINING THREE SGs. SG | | '23' HAS BEEN PLUGGED IN THE PAST. UNIT 2 IS SCHEDULED TO ENTER A | | REFUELING OUTAGE AT THE BEGINNING OF MAY 1997. SGBD FOR THE UNAFFECTED SGs | | HAS BEEN UNISOLATED AND RETURNED TO SERVICE AT THIS TIME. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+