U.S. Nuclear Regulatory Commission Operations Center Event Reports For 03/21/96 - 03/22/96 ** EVENT NUMBERS ** 30147 30148 30149 30150 30151 30152 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30147 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HOPE CREEK REGION: 1 |NOTIFICATION DATE: 03/21/96 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 01:19 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 03/21/96 | +------------------------------------------------+EVENT TIME: 00:32[EST]| |NRC NOTIFIED BY: JOHN DeDOMENICO |LAST UPDATE DATE: 03/21/96 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LARRY NICHOLSON RDO | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 7 STARTUP | 7 STARTUP | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - TECH SPEC REQUIRED PLANT SHUTDOWN DUE TO HPCI AND AD SYSTEMS INOPERABLE - | | | | AT 2255 ON 03/20/96, THE LICENSEE DECLARED THE HIGH PRESSURE COOLANT | | INJECTION (HPCI) SYSTEM INOPERABLE DUE TO A FAILED TECH SPEC SURVEILLANCE | | TEST. TECH SPEC LCO A/S 3.5.1.c REQUIRES THE LICENSEE TO RESTORE THE HPCI | | SYSTEM TO OPERABLE STATUS WITHIN 14 DAYS OR TO PLACE THE PLANT IN AT LEAST | | A HOT SHUTDOWN CONDITION WITHIN THE NEXT 12 HOURS PROVIDED THE OTHER | | EMERGENCY CORE COOLING SYSTEMS ARE OPERABLE. | | | | AT 0032 ON 03/21/96, THE LICENSEE DECLARED THE AUTOMATIC DEPRESSURIZATION | | (AD) SYSTEM INOPERABLE SINCE THE AD SYSTEM COULD NOT BE TESTED BECAUSE THE | | INITIAL TEST CONDITIONS COULD NOT BE MET WITH THE PLANT IN OPERATIONAL | | CONDITION 2. TECH SPEC LCO A/S 3.5.1.d REQUIRES THE LICENSEE TO PLACE THE | | PLANT IN AT LEAST A HOT SHUTDOWN CONDITION WITHIN THE NEXT 12 HOURS WITH | | THE AD SYSTEM INOPERABLE. | | | | THE LICENSEE ENTERED TECH SPEC LCO A/S 3.0.3 WHICH REQUIRES THE LICENSEE TO | | PLACE THE PLANT IN AT LEAST A HOT SHUTDOWN CONDITION WITHIN 6 HOURS WITH | | BOTH THE HPCI AND AD SYSTEMS INOPERABLE. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30148 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PALISADES REGION: 3 |NOTIFICATION DATE: 03/21/96 | |UNIT: [1] [ ] [ ] STATE: MI |NOTIFICATION TIME: 09:04 [ET]| |RX TYPE: [1] CE |EVENT DATE: 03/21/96 | +------------------------------------------------+EVENT TIME: 08:41[EST]| |NRC NOTIFIED BY: VINCENT |LAST UPDATE DATE: 03/21/96 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JACOBSON 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 +------------------------------------------------------------------------------+ | LICENSEE DISCOVERED TWO APPENDIX R DEFICIENCIES | | | | DURING A REVIEW OF THE LICENSEE'S 10 CFR PART 50, APPENDIX R, COMPLIANCE | | STRATEGIES, THE LICENSEE IDENTIFIED TWO DEFICIENCIES WHICH PLACE THE PLANT | | OUTSIDE OF ITS DESIGN BASIS. THE DEFICIENCIES ARE AS FOLLOWS: (1) THE | | LICENSEE'S SAFE SHUTDOWN PROCEDURES DO NOT ADDRESS THE USE OF PORTABLE | | VENTILATION EQUIPMENT FOR CONTROL ROOM AND CABLE SPREADING ROOM COOLING | | WHICH WOULD BE NEEDED APPROXIMATELY 6 HOURS AFTER CERTAIN TYPES OF FIRES, | | AND (2) SEVERAL PLANT AREAS DO NOT HAVE ADEQUATE EMERGENCY LIGHTING | | AVAILABLE. THE LICENSEE HAS TAKEN COMPENSATORY ACTIONS TO ADDRESS THESE | | DEFICIENCIES. THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE | | LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30149 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FITZPATRICK REGION: 1 |NOTIFICATION DATE: 03/21/96 | |UNIT: [1] [ ] [ ] STATE: NY |NOTIFICATION TIME: 15:43 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 03/21/96 | +------------------------------------------------+EVENT TIME: 14:00[EST]| |NRC NOTIFIED BY: ZAREMBA |LAST UPDATE DATE: 03/21/96 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN ROGGE RDO | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | | |VERN HODGE NRR | | |HENRY BAILEY AEOD | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | POTENTIAL FOR CIRCUIT BREAKER SPRING CHARGING MOTOR LIMIT SWITCH FAILURES | | TO AFFECT 4 KV CIRCUIT BREAKERS IN BOTH SAFETY DIVISIONS | | | | ON FEBRUARY 12, 1996, FAILURES OF CIRCUIT BREAKER SPRING CHARGING MOTOR | | LIMIT SWITCHES CAUSED THE CIRCUIT BREAKERS FOR RESIDUAL HEAT REMOVAL | | SERVICE WATER PUMPS 'A' AND 'C' TO FAIL TO CLOSE. UPON EVALUATION OF THESE | | FAILURES FOR POTENTIAL 10 CFR PART 21 REPORTABILITY, THE LICENSEE CONCLUDED | | (AT 1400 ON MARCH 21, 1996) THAT THE FAILURE OF THESE LIMIT SWITCHES HAD | | THE POTENTIAL TO AFFECT 4 KV CIRCUIT BREAKERS IN BOTH SAFETY DIVISIONS. | | | | THE FAILED LIMIT SWITCHES WERE DAMAGED DUE TO INTERRUPTION OF A DIRECT | | CURRENT INDUCTIVE LOAD CIRCUIT WITH APPROXIMATELY 6 AMPS CURRENT COMPARED | | TO A GENERAL ELECTRIC SALES CATALOG LISTING OF 2.2 AMPS. GENERAL ELECTRIC | | HAS REPORTED ADEQUATE LIFE TESTING FOR THESE SWITCHES. HOWEVER, THE FAILED | | LIMIT SWITCH CONTACTS HAD BEEN OPERATED ONLY 2,163 AND 3,233 TIMES IN LIEU | | OF THE 10,000 TIMES THAT GENERAL ELECTRIC WAS CERTIFYING. | | | | SHORTLY AFTER THESE FAILURES OCCURRED, THE LICENSEE TESTED THE PUMPS ON THE | | OPPOSITE TRAIN WITH SATISFACTORY RESULTS. BECAUSE ONLY ONE TRAIN WAS | | INOPERABLE, THE UNIT ENTERED A 7 DAY TECHNICAL SPECIFICATION LIMITING | | CONDITION FOR OPERATION. THE LICENSEE SUBSEQUENTLY DETERMINED THAT 4 KV | | CIRCUIT BREAKERS THAT WERE USED IN OTHER SAFETY RELATED APPLICATIONS WERE | | POTENTIALLY AFFECTED. AS A RESULT, THE LICENSEE REPLACED THE LIMIT SWITCH | | CONTACTS IN THE FAILED CIRCUIT BREAKERS AND IN 6 OTHERS WHICH HAD MORE THAN | | 1,500 CYCLES. (THIS 1,500 CYCLE THRESHOLD WAS DETERMINED BY AN ENGINEERING | | EVALUATION.) PREVIOUS FAILURES HAD NOT BEEN OBSERVED. THERE ARE NO | | CURRENT TECHNICAL SPECIFICATION LIMITING CONDITIONS FOR OPERATION | | ASSOCIATED WITH THIS ISSUE. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR AND PLANS TO SUBMIT A | | LICENSEE EVENT REPORT IN ACCORDANCE WITH 10 CFR 50.73. THE LICENSEE | | BELIEVES THAT THIS WILL ALSO FULFILL THE REPORTING REQUIREMENTS OF 10 CFR | | PART 21. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30150 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SOUTH TEXAS REGION: 4 |NOTIFICATION DATE: 03/21/96 | |UNIT: [ ] [2] [ ] STATE: TX |NOTIFICATION TIME: 20:35 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 03/21/96 | +------------------------------------------------+EVENT TIME: 08:25[CST]| |NRC NOTIFIED BY: JOHN F. MILLIFF |LAST UPDATE DATE: 03/21/96 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LINDA HOWELL RDO | |NLTR LICENSEE 24 HR REPORT | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | 24 HOUR REPORT PER FACILITY OPERATING LICENSE, PARAGRAPH '2G', BECAUSE A | | FUEL HANDLING BUILDING HEATING, VENTILATION AND AIR CONDITIONING (HVAC) | | SYSTEM TECHNICAL SPECIFICATION LIMITING CONDITION FOR OPERATION (LCO) | | TIME CLOCK FOR REPORTABILITY PURPOSES BEGAN AND EXPIRED PRIOR TO THE | | ACTUAL LCO TIME CLOCK. | | | | AT 2110 (CST) ON MARCH 16, 1996, THE FUEL HANDLING BUILDING HVAC SYSTEM | | TRAIN 'B' WAS FOUND TO BE INOPERABLE DUE TO THE FAILURE OF FLOW TRANSMITTER | | #HF-FT-9507A WHICH PREVENTS FLOW CONTROL DAMPER #HF-HV-9507A FROM OPERATING | | IN AUTOMATIC MODE. TECHNICAL SPECIFICATION 3.7.8 REQUIRES OPERABILITY | | OF TWO INDEPENDENT EXHAUST FILTER TRAINS AND THEIR ASSOCIATED DAMPERS. THE | | LCO ACTION STATEMENT REQUIRES THAT AN INOPERABLE FILTER TRAIN BE RETURNED | | TO OPERABLE STATUS WITHIN 7 DAYS OR THAT THE UNIT BE PLACED IN | | HOT STANDBY MODE WITHIN THE NEXT 6 HOURS AND COLD SHUTDOWN MODE WITHIN | | THE FOLLOWING 30 HOURS. THE REQUIRED LCO SHUTDOWN IS AT 2110 (CST) ON | | MARCH 23, 1996. THE FLOW TRANSMITTER AND DAMPER REPAIRS ARE CURRENTLY | | IN PROGRESS AND SHOULD SUPPORT THE ACTUAL LCO TIME CLOCK. | | | | A REVIEW OF COMPUTER ALARM HISTORY DATA INDICATED THAT FLOW TRANSMITTER | | #HF-FT-9507A FAILED AND DAMPER #HF-HV-9507A BECAME INOPERABLE AT 0825 (CST) | | ON MARCH 14, 1996. FOR REPORTABILITY PURPOSES, THE 7 DAY LCO TIME CLOCK | | WOULD HAVE EXPIRED AT 0825 (CST) ON MARCH 21, 1996. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30151 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FT CALHOUN REGION: 4 |NOTIFICATION DATE: 03/22/96 | |UNIT: [1] [ ] [ ] STATE: NE |NOTIFICATION TIME: 02:34 [ET]| |RX TYPE: [1] CE |EVENT DATE: 03/21/96 | +------------------------------------------------+EVENT TIME: 23:00[CST]| |NRC NOTIFIED BY: MATT POHL |LAST UPDATE DATE: 03/22/96 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LINDA HOWELL 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 HOT SHUTDOWN | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - HYDRAZINE DISCHARGE TO MISSOURI RIVER EXCEEDED NPDES PERMIT LIMIT - | | | | LICENSEE WILL NOTIFY THE NEBRASKA DEPARTMENT OF ENVIRONMENTAL QUALITY THAT | | AT 2300 (CST) ON 03/21/96, THE HYDRAZINE LEVEL (143 PPB) IN A SAMPLE OF | | THE PLANT CIRCULATING WATER DISCHARGED TO THE MISSOURI RIVER EXCEEDED THE | | NATIONAL POLLUTION DISCHARGE ELIMINATION SYSTEM (NPDES) PERMIT LIMIT OF | | 100 PPB. | | | | LICENSEE TERMINATED THE CONDENSATE SYSTEM FLUSH WHICH WAS THE SOURCE OF THE | | HYDRAZINE RELEASE. HYDRAZINE IS USED TO SCAVENGE OXYGEN IN THE CONDENSATE | | AND FEEDWATER SYSTEMS. | | | | THE HYDRAZINE LEVEL IN A CIRCULATING WATER SAMPLE TAKEN AT 0015 (CST) ON | | 03\22\96 WAS 3 PPB. | | | | LICENSEE IS DETERMINING THE REASON FOR THE HIGH HYDRAZINE LEVEL IN THE | | CONDENSATE SYSTEM. | | | | LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30152 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CRYSTAL RIVER REGION: 2 |NOTIFICATION DATE: 03/22/96 | |UNIT: [3] [ ] [ ] STATE: FL |NOTIFICATION TIME: 04:22 [ET]| |RX TYPE: [3] B&W-L-LP |EVENT DATE: 03/22/96 | +------------------------------------------------+EVENT TIME: 04:00[EST]| |NRC NOTIFIED BY: BILL BANDHAUER |LAST UPDATE DATE: 03/22/96 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MILTON SHYMLOCK RDO | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 3 | N N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - CREV SYSTEM DESIGN FLOW RATE CALCULATIONS MAY BE NONCONSERVATIVE - | | | | LICENSEE DETERMINED THAT THE CONTROL ROOM EMERGENCY VENTILATION (CREV) | | SYSTEM DESIGN CALCULATIONS ASSUMED NOMINAL AIR FLOW VALUES. THE CREV FANS | | HAVE AN ALLOWABLE ADJUSTMENT TOLERANCE OF +/- 10% OF NOMINAL FLOW RATE. | | THE CURRENTLY MEASURED ACTUAL FLOW RATES ARE WITHIN THE ALLOWABLE DESIGN | | FLOW RATE TOLERANCE. THE DESIGN CALCULATIONS DO NOT PROVIDE ASSURANCE THAT | | ADJUSTMENT WITHIN THIS TOLERANCE WILL PROVIDE ADEQUATE CHARCOAL FILTRATION | | EFFICIENCY AT THE HIGHER TOLERANCE NOR ADEQUATE DILUTION OF AIR INLEAKAGE | | (DOSE) AT THE LOWER TOLERANCE. THE CALCULATION IS CURRENTLY BEING | | REPERFORMED USING THE TOLERANCE VALUES. LICENSEE WILL RESOLVE THIS ISSUE | | PRIOR TO THE PLANT ENTERING MODE 4 WHEN THE CREV SYSTEM WILL BE REQUIRED. | | THE CASE FOR FUEL MOVEMENT (FUEL ACCIDENT) HAS ALREADY BEEN ANALYZED AND | | IS WELL WITHIN THE DESIGN LIMITS. | | | | LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+