U.S. Nuclear Regulatory Commission Operations Center Event Reports For 02/21/96 - 02/22/96 ** EVENT NUMBERS ** 30003 30004 30005 30006 30007 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30003 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VOGTLE REGION: 2 |NOTIFICATION DATE: 02/21/96 | |UNIT: [1] [ ] [ ] STATE: GA |NOTIFICATION TIME: 00:57 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 02/20/96 | +------------------------------------------------+EVENT TIME: 22:25[EST]| |NRC NOTIFIED BY: W. L. BARGERON |LAST UPDATE DATE: 02/21/96 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MARK LESSER 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 92 POWER OPERATION | 92 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TECHNICAL SPECIFICATION 3.0.3 ENTRY - INOPERABILITY OF UNIT 1 NUCLEAR | | SERVICE COOLING WATER (NSCW) DUE TO THE DISCOVERY OF CRACK INDICATIONS IN | | THE PUMP DISCHARGE LINES NEAR A WELDED CONNECTION (A CONDITION WHICH COULD | | HAVE RESULTED IN THE FAILURE OF BOTH TRAINS OF NSCW DURING A POSTULATED | | SEISMIC EVENT) | | | | AT 1810 ON FEBRUARY 20, 1996, THE LICENSEE DECLARED UNIT 1 NSCW TRAIN 'B' | | INOPERABLE AND ENTERED A 72-HOUR TECHNICAL SPECIFICATION LIMITING CONDITION | | FOR OPERATION (LCO) FOLLOWING THE DISCOVERY OF CRACK INDICATIONS IN THE | | PUMP DISCHARGE LINES NEAR A WELDED CONNECTION AND FOLLOWING THE SUBSEQUENT | | ENGINEERING EVALUATION. INSPECTION OF UNIT 1 NSCW TRAIN 'B' WAS INITIATED | | AFTER THE DISCOVERY OF SIMILAR CRACK INDICATIONS IN THE UNIT 1 NSCW TRAIN | | 'A' DISCHARGE LINES ON FEBRUARY 19, 1996. (WHEN SMALL LINEAR CRACK | | INDICATIONS WHICH WERE NOT LEAKING WERE DISCOVERED ON TRAIN 'A' ON FEBRUARY | | 19, 1996, AN INTERIM OPERABILITY DETERMINATION WAS MADE UNTIL FURTHER | | ENGINEERING EVALUATION COULD EITHER PROVE OR DISPROVE OPERABILITY, AND | | REPAIRS WERE COMMENCED.) | | | | THERE ARE 3 PUMPS PER TRAIN IN THE NSCW DESIGN, AND THE UNIT 1 DESIGN IS | | CONDUCIVE TO FATIGUE CRACKING AS EVIDENCED ON ALL 6 PUMPS. BASED ON | | ENGINEERING EVALUATION BEING UNABLE TO CONCLUDE THAT TRAIN 'A' NSCW WOULD | | PERFORM ITS SAFETY FUNCTION AFTER A SEISMIC EVENT, THE LICENSEE ENTERED | | TECHNICAL SPECIFICATION 3.0.3 AT 2225 ON FEBRUARY 20, 1996. THIS TECHNICAL | | SPECIFICATION WAS EXITED AT 2242, WHEN SUFFICIENT REPAIRS WERE COMPLETED ON | | TRAIN 'A' NSCW TO RESTORE THE SYSTEM TO OPERABLE STATUS. THE 72-HOUR LCO | | FOR TRAIN 'B' IS STILL IN EFFECT, AND REPAIRS ARE UNDERWAY. THIS TECHNICAL | | SPECIFICATION LCO IS NOT CASCADED TO THE EMERGENCY DIESEL GENERATORS. ONLY | | TWO PUMPS ARE REQUIRED TO MEET MINIMUM FLOW REQUIREMENTS, AND THE EMERGENCY | | DIESEL GENERATOR ASSOCIATED WITH THE INOPERABLE NSCW TRAIN CURRENTLY HAS | | FLOW THROUGH IT AND IS CONSIDERED TO BE OPERABLE. IN ADDITION, THE | | LICENSEE IS DEVELOPING A PLAN TO EVALUATE THE NSCW PIPING ON UNIT 2. THE | | UNIT 2 PIPING IS NEWER, AND THE UNIT 2 NSCW SYSTEM HAS A DIFFERENT | | GEOMETRY. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30004 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 02/21/96 | |UNIT: [ ] [3] [ ] STATE: NY |NOTIFICATION TIME: 03:34 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 02/21/96 | +------------------------------------------------+EVENT TIME: 01:40[EST]| |NRC NOTIFIED BY: STEPHEN DAVIS |LAST UPDATE DATE: 02/21/96 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |WILLIAM RULAND 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 3 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | POTENTIAL SINGLE FAILURE CONCERNS WHICH COULD IMPACT TRAIN 'A' AND 'B' | | ENGINEERED SAFEGUARDS FEATURES (ESF) ACTUATION CIRCUITRY WHILE THE UNIT IS | | IN COLD SHUTDOWN DUE TO A LACK OF SEPARATION BETWEEN TRAIN 'A' AND TRAIN | | 'B' COMPONENTS | | | | DURING REVIEW OF AN EXTENT OF CONDITION EVALUATION, ENGINEERING IDENTIFIED | | THAT THE TWO CONTAINMENT ISOLATION PHASE 'B' ACTUATION PUSH BUTTONS LOCATED | | IN THE CONTROL ROOM ARE NOT SEPARATED OR MODULARIZED AS REQUIRED. EACH | | PUSH BUTTON ACTUATES THE CONTAINMENT ISOLATION PHASE 'B' RELAYS IN BOTH | | TRAINS 'A' AND 'B'. WIRES FROM BOTH TRAINS 'A' AND 'B' ARE TERMINATED ON | | THE CONTACT BLOCKS OF BOTH PUSH BUTTONS AND COME INTO CONTACT BEFORE THEY | | EXIT THE PANEL. THE TWO PUSH BUTTONS ARE LOCATED APPROXIMATELY ONE INCH | | APART. POWER SUPPLIES TO THE PHASE 'B' ISOLATION RELAYS ARE COMMON WITH | | ALL OTHER ESF RELAYS. DUE TO A LACK OF SEPARATION BETWEEN TRAIN 'A' AND | | TRAIN 'B' COMPONENTS, THERE ARE POTENTIAL SINGLE FAILURE CONCERNS WHICH | | COULD IMPACT TRAIN 'A' AND TRAIN 'B' ESF ACTUATION CIRCUITRY. THIS IS | | STILL UNDER EVALUATION BY ENGINEERING. | | | | THE UNIT IS NOT IN ANY TECHNICAL SPECIFICATION LIMITING CONDITIONS FOR | | OPERATION AT THIS TIME BECAUSE IT IS IN A COLD SHUTDOWN CONDITION. ONE | | RESIDUAL HEAT REMOVAL PUMP AND ONE REACTOR COOLANT PUMP ARE CURRENTLY IN | | SERVICE. THE EMERGENCY DIESEL GENERATORS ARE ALSO AVAILABLE. | | | | THE LICENSEE WILL NOTIFY THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30005 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VERMONT YANKEE REGION: 1 |NOTIFICATION DATE: 02/21/96 | |UNIT: [1] [ ] [ ] STATE: VT |NOTIFICATION TIME: 14:34 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 02/21/96 | +------------------------------------------------+EVENT TIME: 14:23[EST]| |NRC NOTIFIED BY: WOOKEY |LAST UPDATE DATE: 02/21/96 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BILL RULAND 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 +------------------------------------------------------------------------------+ | OUTSIDE OF DESIGN BASES IMMEDIATELY PRIOR TO ENTERING REFUELING OUTAGES IN | | 1990 AND 1992 BECAUSE ALL THREE LAYERS OF CONCRETE SHIELDING WERE REMOVED | | FROM ABOVE THE REACTOR VESSEL WITH REACTOR POWER >0% | | | | WHILE PERFORMING AN EVENT REPORT INVESTIGATION OF THE SHIELDING OF THE | | REFUELING FLOOR REACTOR CAVITY, THE LICENSEE DISCOVERED THAT ON TWO | | OCCASIONS, ALL THREE LAYERS OF THE CONCRETE SHIELDING WERE REMOVED FROM | | ABOVE THE REACTOR VESSEL WITH REACTOR POWER >0%. THESE TWO OCCASIONS | | OCCURRED IMMEDIATELY PRIOR TO ENTERING REFUELING OUTAGES IN 1990 AND 1992. | | AN EVALUATION SHOWED THAT 30 DAYS OF EXPOSURE IN THE TECHNICAL SUPPORT | | CENTER COULD HAVE EXCEEDED THE DESIGN BASIS OF THE 5 REM TOTAL (NUREG 0737) | | IF A DESIGN BASES ACCIDENT OCCURRED AT THE TIME THE BLOCKS WERE REMOVED. | | CURRENT PROCEDURES (EFFECTIVE SINCE 03/16/95) REQUIRE THAT TWO SHIELDING | | LAYERS REMAIN INTACT UNTIL THE MODE SWITCH IS IN THE SHUTDOWN OR REFUEL | | POSITION. | | | | THE NRC RESIDENT INSPECTOR WILL BE INFORMED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30006 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: QUAD CITIES REGION: 3 |NOTIFICATION DATE: 02/22/96 | |UNIT: [1] [2] [ ] STATE: IL |NOTIFICATION TIME: 00:36 [ET]| |RX TYPE: [1] GE-3,[2] GE-3 |EVENT DATE: 02/21/96 | +------------------------------------------------+EVENT TIME: 21:05[CST]| |NRC NOTIFIED BY: BRAD WILLIAMS |LAST UPDATE DATE: 02/22/96 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |B. J. HOLT 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 N 0 REFUELING | 0 REFUELING | | 2 | N Y 97 POWER OPERATION | 97 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | POSTULATED FAILURE OF THE CONTROL ROOM EMERGENCY FILTRATION UNIT BOOSTER | | FANS DURING A POSTULATED LOSS OF OFFSITE POWER ON UNIT 1 | | | | AN ENGINEERING WALKDOWN WAS PERFORMED ON THE TOXIC GAS ANALYZER AND THE | | CONTROL ROOM EMERGENCY FILTRATION UNIT. THE TOXIC GAS ANALYZER IS FED FROM | | A NON-SAFETY-RELATED POWER SUPPLY ON UNIT 1. IN THE EVENT OF A LOSS OF | | OFFSITE POWER ON UNIT 1, A TOXIC GAS ANALYZER RELAY WOULD DE-ENERGIZE, AND | | THIS WOULD PREVENT THE CONTROL ROOM EMERGENCY FILTRATION UNIT BOOSTER FANS | | FROM STARTING OR RUNNING. (THE CONTROL ROOMS FOR UNITS 1 AND 2 ARE LOCATED | | IN A COMMON AREA.) AS A RESULT, THE LICENSEE ENTERED A 14-DAY LIMITING | | CONDITION FOR OPERATION PER TECHNICAL SPECIFICATION 3.8.H.1.a AT 2105 CST | | ON FEBRUARY 21, 1996. THE LICENSEE IS CURRENTLY PERFORMING AN | | INVESTIGATION TO DETERMINE THE APPROPRIATE CORRECTIVE ACTIONS. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30007 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FITZPATRICK REGION: 1 |NOTIFICATION DATE: 02/22/96 | |UNIT: [1] [ ] [ ] STATE: NY |NOTIFICATION TIME: 03:40 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 02/22/96 | +------------------------------------------------+EVENT TIME: 03:33[EST]| |NRC NOTIFIED BY: ROGER LOCY |LAST UPDATE DATE: 02/22/96 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |WILLIAM RULAND 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 60 POWER OPERATION | 60 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TECHNICAL SPECIFICATION REQUIRED SHUTDOWN AND FORCED OUTAGE AS A RESULT OF | | SLOW CONTROL ROD SCRAM TIMES DUE TO STICKING OF THE VITON DIAPHRAGMS IN THE | | SCRAM PILOTS | | | | THE LICENSEE SCRAM-TIME TESTED 20 OF 137 CONTROL RODS, AND THE AVERAGE | | SCRAM TIME (TO NOTCH 46) OF THESE 20 RODS EXCEEDED THE TECHNICAL | | SPECIFICATION 3.3.C LIMIT OF 0.338 SECONDS FOR THE CORE AVERAGE. THE | | AVERAGE TIME FOR THIS SAMPLE WAS 0.373 SECONDS. AVERAGING THESE 20 ROD | | TIMES IN WITH THE PREVIOUSLY MEASURED TIMES (TO NOTCH 46) FOR THE REMAINING | | RODS DOES NOT INCREASE THE CORE AVERAGE SCRAM TIME ABOVE THE TECHNICAL | | SPECIFICATION LIMIT. HOWEVER, THE LICENSEE IS ASSUMING THAT ALL ROD TIMES | | WOULD HAVE INCREASED IF ALL OF THE RODS WERE TESTED. BASED ON THIS | | ASSUMPTION, THE LICENSEE ENTERED TECHNICAL SPECIFICATION ACTION STATEMENT | | 3.3.E WHICH REQUIRES THAT AN ORDERLY SHUTDOWN BE INITIATED AND THAT THE | | REACTOR BE PLACED IN A COLD CONDITION WITHIN 24 HOURS. THE CURRENT | | PROJECTION FOR UNIT RESTART IS FEBRUARY 27, 1996. | | | | THE LICENSEE HAS ATTRIBUTED THE ROOT CAUSE OF THE INCREASE IN SCRAM TIMES | | TO STICKING OF THE VITON DIAPHRAGMS IN THE SCRAM PILOTS. ALL OF THE | | CONTROL ROD SCRAM PILOTS HAVE VITON DIAPHRAGMS, AND THESE DIAPHRAGMS WERE | | INSTALLED DURING THE DECEMBER 1994 REFUELING OUTAGE. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR AND MAY ISSUE A PRESS | | RELEASE. | +------------------------------------------------------------------------------+