U.S. Nuclear Regulatory Commission Operations Center Event Reports For 07/23/96 - 07/24/96 ** EVENT NUMBERS ** 30596 30775 30776 30777 30778 30779 30780 30781 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30596 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COMANCHE PEAK REGION: 4 |NOTIFICATION DATE: 06/07/96 | |UNIT: [1] [2] [ ] STATE: TX |NOTIFICATION TIME: 07:34 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 06/07/96 | +------------------------------------------------+EVENT TIME: 03:34[CDT]| |NRC NOTIFIED BY: CLOUSER |LAST UPDATE DATE: 07/23/96 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DALE POWERS RDO | |DDDD 73.71 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 76 POWER OPERATION | 76 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE REPORTED A SAFEGUARDS SYSTEM DEGRADATION RELATED TO PARAMETER | | ALARMS. IMMEDIATE COMPENSATORY MEASURES WERE TAKEN UPON DISCOVERY. (SEE | | THE HOO LOG FOR DETAILS.) | | | | THE NRC RESIDENT INSPECTOR WAS INFORMED. | | | | * * * 1444 JULY 23, 1996, UPDATE FROM HARRIS RECEIVED BY TROCINE * * * | | | | THE LICENSEE IS RETRACTING THIS EVENT AFTER DETERMINATION THAT THE FAILED | | COMPENSATORY MEASURE WAS NOT A REPORTABLE EVENT. INSTEAD, THIS EVENT WAS | | DETERMINED TO BE LOGGABLE PER 10 CFR PART 73, APPENDIX G, SECTION II(b). | | THE LICENSEE'S DETERMINATION WAS BASED UPON ITS REVIEW OF 10 CFR PART 73 | | AND OTHER DOCUMENTS SUCH AS GENERIC LETTER 91-03, REPORTING SAFEGUARDS | | EVENTS. | | | | THE LICENSEE PLANS TO NOTIFY THE NRC RESIDENT INSPECTOR. THE NRC | | OPERATIONS CENTER NOTIFIED THE R4DO (POWERS). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30775 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: NINE MILE POINT REGION: 1 |NOTIFICATION DATE: 07/23/96 | |UNIT: [ ] [2] [ ] STATE: NY |NOTIFICATION TIME: 09:00 [ET]| |RX TYPE: [1] GE-2,[2] GE-5 |EVENT DATE: 07/23/96 | +------------------------------------------------+EVENT TIME: 00:00[EDT]| |NRC NOTIFIED BY: CARL TERRY |LAST UPDATE DATE: 07/23/96 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: | | |CCCC 21.21 UNSPECIFIED PARAGRAPH | | | |VERN HODGE, NRR PCEB | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | DISCOVERY OF A CONDITION AFFECTING THE OPERABILITY OF CLOW (MANUFACTURER) | | VALVES INSTALLED IN THE UNIT 2 STANDBY GAS TREATMENT SYSTEM | | | | THE LICENSEE DETERMINED THAT CLOW (MANUFACTURER) VALVES IN THE STANDBY GAS | | TREATMENT SYSTEM HAVE A DOWEL PIN INSTALLED WHICH IS NOT PEENED IN PLACE. | | SHOULD THESE DOWELS COME LOOSE, IT COULD INTERFERE WITH THE VALVE LIMIT | | SWITCHES AND PREVENT THE MAKEUP OF CIRCUIT PERMISSIVES. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30776 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DRESDEN REGION: 3 |NOTIFICATION DATE: 07/23/96 | |UNIT: [ ] [2] [3] STATE: IL |NOTIFICATION TIME: 09:23 [ET]| |RX TYPE: [1] GE-1,[2] GE-3,[3] GE-3 |EVENT DATE: 07/23/96 | +------------------------------------------------+EVENT TIME: 07:50[CDT]| |NRC NOTIFIED BY: DAVE SLAGER |LAST UPDATE DATE: 07/23/96 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MONTE PHILLIPS RDO | |DDDD 73.71 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | 3 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | SAFEGUARDS SYSTEM DEGRADATION RELATED TO VITAL AREA ACCESS | | | | IMMEDIATE COMPENSATORY MEASURES TAKEN UPON DISCOVERY. THE LICENSEE WILL | | INFORM THE NRC RESIDENT INSPECTOR. (SEE THE HOO LOG FOR DETAILS.) | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30777 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: GINNA REGION: 1 |NOTIFICATION DATE: 07/23/96 | |UNIT: [1] [ ] [ ] STATE: NY |NOTIFICATION TIME: 09:51 [ET]| |RX TYPE: [1] W-2-LP |EVENT DATE: 07/23/96 | +------------------------------------------------+EVENT TIME: 08:57[EDT]| |NRC NOTIFIED BY: MACIUSKA |LAST UPDATE DATE: 07/23/96 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN MCFADDEN RDO | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 80 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TECHNICAL SPECIFICATION REQUIRED SHUTDOWN DUE TO INTEGRATED LEAKAGE OUTSIDE | | CONTAINMENT GREATER THAN LIMITS | | | | THE LICENSEE COMMENCED A PLANT SHUTDOWN TO MODE 4 PER TECHNICAL | | SPECIFICATION 3.0.3 BECAUSE THE INTEGRATED LEAKAGE OUTSIDE OF CONTAINMENT | | WAS GREATER THAN 2 GALLONS PER HOUR. THE SOURCE OF THE LEAK WAS A SMALL | | PIN HOLE IN A 90ø WELD SOCKET ON THE CONTAINMENT SPRAY TEST LINE. THIS WAS | | DISCOVERED BY AN AUXILIARY OPERATOR DURING PLANT ROUNDS. | | | | THE ACTUAL LEAKAGE MEASURED IS CURRENTLY 2.6 GALLONS PER HOUR, AND THE | | SYSTEM PRESSURE IS APPROXIMATELY 30 PSID FROM THE STATIC HEAD OF THE | | REFUELING WATER STORAGE TANK. THE OVERALL PLANT CONDITION IS CURRENTLY | | STABLE, AND ALL SYSTEMS ARE FUNCTIONING AS REQUIRED. THE LICENSEE INTENDS | | TO INSTALL A FREEZE SEAL AND REPAIR THE LEAK. THE LICENSEE IS ALSO | | REQUIRED TO PLACE THE UNIT IN A MODE 3 CONDITION BY 1457 AND IN A MODE 4 | | CONDITION BY 2057. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30778 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FITZPATRICK REGION: 1 |NOTIFICATION DATE: 07/23/96 | |UNIT: [1] [ ] [ ] STATE: NY |NOTIFICATION TIME: 16:47 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 07/23/96 | +------------------------------------------------+EVENT TIME: 16:33[EDT]| |NRC NOTIFIED BY: DAVE BURCH |LAST UPDATE DATE: 07/23/96 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN MCFADDEN RDO | |AINB 50.72(b)(2)(iii)(B) POT RHR INOP | | |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 | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DISCOVERY OF INCORRECT REVERSE POWER TRIP TIME DELAY DEVICES IN THE BREAKER | | CONTROL CIRCUIT FOR ONE OF FOUR EMERGENCY DIESEL GENERATORS | | | | THE 'B' EMERGENCY DIESEL GENERATOR (EDG) FAILED TO COMPLETE ITS STARTING | | SEQUENCE DUE TO A TRIP ON REVERSE POWER. DURING TROUBLESHOOTING, IT WAS | | DETERMINED THAT THE CAUSE WAS THE INSTALLATION OF INCORRECT TIME DELAY | | DEVICES IN THE BREAKER CONTROL CIRCUIT. A 0.8-SECOND TIME DELAY FOR THE | | REVERSE POWER TRIP WAS INSTALLED RATHER THAN THE REQUIRED 3.5-SECOND TIME | | DELAY. THIS CONDITION HAS EXISTED SINCE MAY 1990. | | | | A REVERSE POWER TRIP OF THE 'B' EDG (WHEN THE 'A' AND 'C' EDGs WERE | | INOPERABLE) ALONE COULD HAVE PREVENTED THE FULFILLMENT OF THE SAFETY | | FUNCTION OF SYSTEMS REQUIRED TO REMOVE RESIDUAL HEAT OR MITIGATE THE | | CONSEQUENCES OF AN ACCIDENT. THE TIME DELAY RELAYS FOR THE 'A', 'C', AND | | 'D' EDGs WERE DETERMINED TO BE PROPERLY INSTALLED. | | | | THE UNIT ENTERED A 7-DAY TECHNICAL SPECIFICATION LIMITING CONDITION FOR | | OPERATION ON JULY 22, 1996, AS A RESULT OF THIS DISCOVERY. THIS LIMITING | | CONDITION FOR OPERATION APPLIES TO TWO EDGs BEING OUT OF SERVICE. (THE 'D' | | EDG IS ALSO INOPERABLE AT THIS TIME DUE TO THE IDENTIFICATION OF AN | | UNRELATED PROBLEM WITH THE GOVERNOR BOOSTER PUMP.) THE 'B'EDG HAS BEEN | | REPAIRED. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30779 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SALEM REGION: 1 |NOTIFICATION DATE: 07/23/96 | |UNIT: [1] [2] [ ] STATE: NJ |NOTIFICATION TIME: 17:08 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 07/23/96 | +------------------------------------------------+EVENT TIME: 15:55[EDT]| |NRC NOTIFIED BY: JOHN ROBERTSON |LAST UPDATE DATE: 07/23/96 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN MCFADDEN RDO | |ADAS 50.72(b)(2)(i) DEG/UNANALYZED COND | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DISCOVERY THAT THE KEYS/KEYWAYS FOR THE ACTUATORS OF RESIDUAL HEAT REMOVAL | | FLOW CONTROL VALVES MADE BY FISHER CONTROLS INT'L ARE SUBJECT TO FAILURE | | | | DURING AN APPARENT CAUSE ANALYSIS OF THE RESIDUAL HEAT REMOVAL (RHR) FLOW | | CONTROL VALVES, LICENSEE ENGINEERING PERSONNEL DISCOVERED THAT THE | | KEYS/KEYWAYS ON THE ACTUATORS ARE SUBJECT TO FAILURE. THESE VALVES WERE | | MADE BY FISHER CONTROLS INT'L, MODEL TYPE 656/7600. THE FAILURE HAS BEEN | | DETERMINED TO BE CAUSED BY SIGNIFICANTLY EXCEEDING THE MATERIAL YIELD | | STRESS OF THE KEY/KEYWAY BASED ON NON-DESTRUCTIVE TESTING. THE ORIGINAL | | DESIGN FOR THE VALVE DID NOT ACCOUNT FOR THE NORMAL SHUTDOWN CONDITIONS | | WHERE THE DIFFERENTIAL PRESSURE WOULD BE HIGHER THAN THE ACCIDENT MODE | | VALVE DESIGN REQUIREMENTS. THE CONSEQUENCE OF THE KEY/KEYWAY FAILURE IS | | THAT THE VALVE COULD MOVE TO THE 'CLOSED' POSITION WITH NO CONTROL FROM THE | | CONTROL ROOM (THEREBY PARTIALLY BLOCKING RHR FLOW TO THE REACTOR CORE). | | | | CURRENTLY, BOTH SALEM UNITS ARE DEFUELED, AND THE RHR VALVES ARE NOT | | REQUIRED TO BE OPERABLE TO MITIGATE DESIGN BASIS ACCIDENTS. THERE IS NO | | SIGNIFICANT IMPACT TO THE HEALTH AND SAFETY OF THE PUBLIC DUE TO THIS | | PROBLEM WITH THE UNITS IN THIS MODE OF OPERATION. | | | | THE LICENSEE PLANS TO NOTIFY THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30780 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DRESDEN REGION: 3 |NOTIFICATION DATE: 07/23/96 | |UNIT: [ ] [2] [3] STATE: IL |NOTIFICATION TIME: 17:11 [ET]| |RX TYPE: [1] GE-1,[2] GE-3,[3] GE-3 |EVENT DATE: 07/23/96 | +------------------------------------------------+EVENT TIME: 15:15[CDT]| |NRC NOTIFIED BY: DAVE SLAGER |LAST UPDATE DATE: 07/23/96 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MONTE PHILLIPS RDO | |ADAS 50.72(b)(2)(i) DEG/UNANALYZED COND | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | 3 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | POTENTIAL INCREASE IN THE 10 CFR PART 100 DOSE RATES DUE TO THE DISCOVERY | | OF A POTENTIAL LEAK PATH FOR PRIMARY FLUID (POST ACCIDENT) TO BYPASS | | CONTAINMENT | | | | BASED ON A RE-EVALUATION OF IN NOTICE 90-78, IT WAS DETERMINED THAT THE | | CONTROL ROD DRIVE SYSTEM AND HYDRAULIC CONTROL UNITS ARE A POTENTIAL LEAK | | PATH FOR PRIMARY FLUID (POST ACCIDENT) TO BYPASS CONTAINMENT. PRELIMINARY | | DOSE ANALYSIS AND SYSTEM REVIEW INDICATES THAT 10 CFR PART 50, APPENDIX | | 'A', GENERAL DESIGN CRITERION 19, CONTROL ROOM DOSE LIMITS MAY BE EXCEEDED, | | AND THERE IS A POTENTIAL FOR AN INCREASE IN THE 10 CFR PART 100 DOSE RATES. | | | | PROCEDURES ARE BEING REVISED TO MODIFY RESPONSE TIME FROM 4 HOURS TO 1-1/2 | | HOURS IN ORDER TO BRING THE PLANT INTO COMPLIANCE WITH THE UPDATED FINAL | | SAFETY ANALYSIS REPORT. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30781 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SALEM REGION: 1 |NOTIFICATION DATE: 07/23/96 | |UNIT: [1] [2] [ ] STATE: NJ |NOTIFICATION TIME: 17:52 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 07/23/96 | +------------------------------------------------+EVENT TIME: 16:00[EDT]| |NRC NOTIFIED BY: JOHN ROBERTSON |LAST UPDATE DATE: 07/23/96 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN MCFADDEN RDO | |ADAS 50.72(b)(2)(i) DEG/UNANALYZED COND | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | 2 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | FAILURE TO PROPERLY EVALUATE THE AGGREGATE PERFORMANCE OF THE CONTAINMENT | | FAN COIL UNITS WITH THE FAILURES OF CERTAIN VITAL BUSES | | | | DURING A DESIGN REVIEW OF THE CONTAINMENT FAN COIL UNIT (CFCU) PERFORMANCE, | | LICENSEE ENGINEERING PERSONNEL DISCOVERED THAT FROM FEBRUARY TO MAY 1993, | | BOTH OF THE SALEM UNITS HAD OPERATED OUTSIDE THEIR DESIGN BASIS. THIS | | CONDITION RESULTED FROM FAILURE TO PROPERLY EVALUATE THE AGGREGATE | | PERFORMANCE OF THE CFCUs WITH THE FAILURES OF CERTAIN VITAL BUSES. | | SPECIFICALLY, THE ACCEPTANCE CRITERIA FOR THE CFCU PERFORMANCE TESTING DID | | NOT ENSURE THAT THE MINIMUM HEAT REMOVAL CAPABILITY FROM THE CFCUs WAS MET | | UNDER ALL CONDITIONS THAT CFCUs ARE ASSUMED IN THE ACCIDENT ANALYSES. | | | | CURRENTLY, BOTH SALEM UNITS ARE DEFUELED, AND THE CFCUs ARE NOT REQUIRED TO | | BE OPERABLE TO MITIGATE DESIGN BASIS ACCIDENTS. THERE IS NO SIGNIFICANT | | IMPACT TO THE HEALTH AND SAFETY OF THE PUBLIC DUE TO THIS PROBLEM WITH THE | | UNITS IN THIS MODE OF OPERATION. | | | | THE LICENSEE PLANS TO NOTIFY THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+