U.S. Nuclear Regulatory Commission Operations Center Event Reports For 07/26/95 - 07/27/95 ** EVENT NUMBERS ** 29007 29021 29111 29112 29113 29114 29115 29116 29117 29118 29119 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29007 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SOUTH TEXAS REGION: 4 |NOTIFICATION DATE: 06/30/95 | |UNIT: [1] [ ] [ ] STATE: TX |NOTIFICATION TIME: 13:33 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 06/29/95 | +------------------------------------------------+EVENT TIME: 17:11[CDT]| |NRC NOTIFIED BY: PETER |LAST UPDATE DATE: 07/26/95 | |HQ OPS OFFICER: TIM McGINTY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GARY SANBORN RDO | |NLTR LICENSEE 24 HR REPORT | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | TRAIN 'A' CONTROL ROOM ENVELOPE HVAC WAS INOPERABLE DUE TO A REG GUIDE 1.75 | | SEPARATION VIOLATION. | | | | THE TRAIN 'A' CONTROL ROOM ENVELOPE HVAC (HEATING VENTILATION AND AIR | | CONDITIONING) DAMPER 'A1HEFCV9584' WAS DETERMINED TO BE INOPERABLE ON | | 6/29/95 AT 1711 CDT DUE TO VIOLATION OF REGULATORY GUIDE (RG) 1.75 | | SEPARATION REQUIREMENTS. THE CONDITION EXISTED FOR A PERIOD GREATER THAN | | SEVEN DAYS, WHICH IS IN NONCOMPLIANCE WITH TECHNICAL SPECIFICATION 3.7.7, | | ACTION 'A'. THIS IS REPORTABLE PER STP UNIT 1 OPERATING LICENSE, ITEM 2.G. | | | | THE CONDITION WAS INITIALLY OBSERVED ON 6/28/95 AT 1530 CDT AND AN | | OPERABILITY/REPORTABILITY EVALUATION WAS REQUESTED IN ACCORDANCE WITH | | STATION PROCEDURES. THE RG 1.75 SEPARATION VIOLATION WAS CORRECTED ON | | 6/29/95 AT 1720 CDT. | | | | THE CONDITION INVOLVES THE WIRING FOR THE CONTROLLER FOR THE DAMPER, | | LOCATED BEHIND THE CONTROL BOARD. THE REQUIREMENT IS FOR 6 INCHES OF OPEN | | AIR GAP ON EXPOSED WIRING, AND THIS PARTICULAR WIRING ONLY HAD ABOUT 5 | | INCHES. THE LICENSEE IS INVESTIGATING THE POSSIBLE APPLICABILITY TO | | UNIT 2. | | | | THE LICENSEE INFORMED THE RESIDENT INSPECTOR. | | | | NOTE: SEE EVENT NUMBER 29021 FOR A RELATED EVENT ON UNIT 2. | | | | * * * UPDATE 1652 7/26/95 FROM TAPLETT TAKEN BY STRANSKY * * * | | | | THE LICENSEE IS RETRACTING THIS NOTIFICATION. THE LICENSEE HAS DETERMINED | | THAT THE STEADY-STATE SHORT CIRCUIT CURRENT IN THE NONSAFETY WIRING WOULD | | BE SUFFICIENTLY BELOW THE IGNITION TEMPERATURE OF IEEE 383 CABLE | | INSULATION. IN ADDITION, THE TEMPERATURE WOULD BE SUFFICIENTLY BELOW THE | | FUSION LEVEL OF THE COPPER IN THE CABLE SUCH THAT THE INITIAL FAULT WOULD | | NOT PROPAGATE AND CAUSE OTHER FAULTS. THE NRC RESIDENT INSPECTOR HAS BEEN | | INFORMED. NOTIFIED R4DO (HOWELL). | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29021 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SOUTH TEXAS REGION: 4 |NOTIFICATION DATE: 07/04/95 | |UNIT: [ ] [2] [ ] STATE: TX |NOTIFICATION TIME: 11:31 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 07/03/95 | +------------------------------------------------+EVENT TIME: 17:25[CDT]| |NRC NOTIFIED BY: TIM FRAWLEY |LAST UPDATE DATE: 07/26/95 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BLAIR SPITZBERG RDO | |NINF INFORMATION ONLY | | |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 +------------------------------------------------------------------------------+ | - TRAIN 'A' CONTROL ROOM ENVELOPE HVAC INOPERABLE DUE TO REGULATORY GUIDE | | 1.75 SEPARATION VIOLATION - | | | | TRAIN 'A' CONTROL ROOM ENVELOPE HVAC SYSTEM WAS DETERMINED TO BE INOPERABLE | | AT 1725 (CDT) ON 07/03/95 DUE TO VIOLATION OF REGULATORY GUIDE 1.75 | | SEPARATION REQUIREMENTS. THIS CONDITION EXISTED FOR A PERIOD OF GREATER | | THAN 7 DAYS WHICH IS IN NONCOMPLIANCE WITH TECHNICAL SPECIFICATION 3.7.7, | | ACTION STATEMENT 'A'. THIS IS REPORTABLE PER UNIT 2 OPERATING LICENSE, | | ITEM 2.G. | | | | THIS CONDITION WAS INITIALLY OBSERVED AT 0845 (CDT) ON 06/30/95, AND AN | | OPERABILITY/REPORTABILITY EVALUATION WAS REQUESTED IN ACCORDANCE WITH | | STATION PROCEDURES. THE OPERABILITY DETERMINATION WAS COMPLETED AT 1725 | | (CDT) ON 07/03/95. THE REGULATORY GUIDE 1.75 SEPARATION VIOLATION WAS | | CORRECTED AT 2219 (CDT) ON 07/03/95. | | | | THE CONDITION INVOLVES THE WIRING BEHIND THE CONTROL PANEL FOR THE FIRE | | PROTECTION DELUGE ACTUATION PUSH BUTTON. THE REQUIREMENT IS FOR 6 INCHES | | OF SEPARATION BETWEEN CLASS 1E WIRING AND NON-CLASS 1E WIRING, AND THE | | ACTUAL SEPARATION WAS LESS THAN 6 INCHES. THIS PROBLEM WAS RESOLVED BY | | WRAPPING THE CLASS 1E WIRING WITH HEAT RESISTANCE TAPE AND COATING. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | NOTE: SEE EVENT NUMBER 29007 FOR A RELATED EVENT ON UNIT 1. | | | | * * * UPDATE 1652 7/26/95 FROM TAPLETT TAKEN BY STRANSKY * * * | | | | THE LICENSEE IS RETRACTING THIS NOTIFICATION. THE LICENSEE DETERMINED THAT | | THE STEADY-STATE SHORT CIRCUIT CURRENT IN THE NONSAFETY WIRING WOULD BE | | SUFFICIENTLY BELOW THE IGNITION TEMPERATURE OF IEEE 383 CABLE INSULATION. | | IN ADDITION, THE TEMPERATURE WOULD BE SUFFICIENTLY BELOW THE FUSION LEVEL | | OF THE COPPER IN THE CABLE SUCH THAT THE INITIAL FAULT WOULD NOT PROPAGATE | | AND CAUSE OTHER FAULTS. THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED. | | NOTIFIED R4DO (HOWELL). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 29111 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: NUMEROUS REACTORS |NOTIFICATION DATE: 07/26/95 | | CITY: WELLSVILLE REGION: 1 |NOTIFICATION TIME: 11:20 [ET]| | COUNTY: STATE: NY |EVENT DATE: 07/26/95 | |LICENSE#: AGREEMENT: Y |EVENT TIME: 00:00[EDT]| | DOCKET: |LAST UPDATE DATE: 07/26/95 | | +-----------------------------+ | |PERSON ORGANIZATION| | | | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: ROBERT LOUGHLIN | | |HQ OPS OFFICER: RUDY KARSCH | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |CCCC 21.21 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DRESSER-RAND STEAM TURBINE DIVISION, WELLSVILLE, N.Y. | | | | TERRY TURBINES USED FOR AUX FEED AT NUMEROUS SITES COULD EXPERIENCE A | | PROBLEM WITH THE GOVERNOR LINKAGE UNDER SEVERE VIBRATION CONDITIONS OR A | | SEISMIC EVENT. SPECIFICALLY, A LOCK NUT WHICH SECURES THE GOVERNOR LINKAGE | | MAY NOT HAVE SUFFICIENT THREAD ENGAGEMENT TO GUARANTEE ADEQUATE LOCKING. | | DRESSER-RAND IS PREPARING A LIST OF AFFECTED PLANTS AND SPECIFIC | | RECOMMENDATIONS. A FINAL REPORT IS DUE NO LATER THAN 8/25/95. REPORT | | FORWARDED TO NRR (HODGE). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29112 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 07/26/95 | |UNIT: [2] [ ] [ ] STATE: NY |NOTIFICATION TIME: 11:39 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 07/26/95 | +------------------------------------------------+EVENT TIME: 10:57[EDT]| |NRC NOTIFIED BY: DEIRDRE MURPHY |LAST UPDATE DATE: 07/26/95 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RICHARD KEIMIG 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 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | CONTAINMENT VENTILATION ISOLATION DUE TO A HIGH RADIATION SIGNAL. | | | | "CONTAINMENT PRESSURE RELIEF" VALVES 1190, 1191, AND 1192 TRIPPED CLOSED ON | | HIGH RADIATION. A MOMENTARY SPIKE OF GREATER THAN 1 E -5 MICRO CURIES/CC | | CAUSED THE TRIP. VENTILATION WAS RESET AND THE SETPOINT WILL BE INCREASED | | PER PROCEDURE. THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29113 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 07/26/95 | |UNIT: [ ] [3] [ ] STATE: NY |NOTIFICATION TIME: 12:02 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 07/26/95 | +------------------------------------------------+EVENT TIME: 11:32[EDT]| |NRC NOTIFIED BY: VINCHKOSKI |LAST UPDATE DATE: 07/26/95 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: UNUSUAL EVENT +-----------------------------+ |10 CFR SECTION: |KEIMIG RDO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |DENNIG EO | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS |SULLIVAN FEMA | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 3 | N Y 100 POWER OPERATION | 80 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNUSUAL EVENT DECLARED DUE TO TECHNICAL SPECIFICATION REQUIRED SHUTDOWN. | | | | DURING PERFORMANCE OF THE SAFETY INJECTION TRAIN B LOGIC FUNCTIONAL TEST | | (3PT-14B), SEVERAL RELAYS ASSOCIATED WITH THE CONTAINMENT ISOLATION PHASE | | "A" ACTUATION LOGIC DID NOT ACTUATE AS EXPECTED. THE LICENSEE IS CURRENTLY | | INVESTIGATING THE CAUSE OF THE RELAY FAILURES. THE LICENSEE BEGAN A UNIT | | SHUTDOWN IN ACCORDANCE WITH TECHNICAL SPECIFICATION TABLE 3.5-4, NOTE 1. | | THE TECHNICAL SPECIFICATION REQUIRES THAT THE UNIT BE PLACED IN HOT | | SHUTDOWN WITHIN 4 HOURS. | | | | THE LICENSEE IS CURRENTLY REPLACING THE SUBJECT RELAYS, AND PLANS TO | | REPERFORM THE FUNCTIONAL TEST. ALL ECCS EQUIPMENT IS CURRENTLY OPERABLE, | | AND NO PROBLEMS ARE EXPECTED WITH THE UNIT SHUTDOWN. THE NRC RESIDENT | | INSPECTOR WILL BE INFORMED BY THE LICENSEE. THE LICENSEE INTENDS TO MAKE A | | PRESS RELEASE REGARDING THE UNIT SHUTDOWN. | | | | * * * UPDATE 1326 7/26/95 FROM VINCHKOSKI TAKEN BY STRANSKY * * * | | | | UNUSUAL EVENT WAS TERMINATED AT 1310 AFTER THE CONTAINMENT ISOLATION PHASE | | "A" LOGIC WAS REPAIRED AND TESTED SATISFACTORILY. THE UNIT SHUTDOWN WAS | | STOPPED WITH THE UNIT AT 65% POWER. THE LICENSEE STATED THAT A BAD CONTACT | | WAS FOUND ON ONE OF THE RELAYS, AND THAT A TEMPORARY MODIFICATION WAS | | INSTITUTED TO USE A SPARE CONTACT ON THAT RELAY. THE NRC RESIDENT | | INSPECTOR HAS BEEN INFORMED. NOTIFIED R1DO (KEIMIG), EO (DENNIG), FEMA | | (SULLIVAN). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29114 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DUANE ARNOLD REGION: 3 |NOTIFICATION DATE: 07/26/95 | |UNIT: [1] [ ] [ ] STATE: IA |NOTIFICATION TIME: 13:27 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 07/26/95 | +------------------------------------------------+EVENT TIME: 10:39[CDT]| |NRC NOTIFIED BY: FOWLER |LAST UPDATE DATE: 07/26/95 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BURDICK RDO | |AINC 50.72(b)(2)(iii)(C) POT UNCNTRL RAD REL | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | BOTH TRAINS OF STANDBY GAS TREATMENT SYSTEM (SGTS) INOPERABLE. | | | | FOLLOWING PLANNED MAINTENANCE AND TESTING OF THE "A" TRAIN OF SGTS, THE | | LICENSEE PERFORMED A MONTHLY SURVEILLANCE TEST OF THE "B" TRAIN. DURING | | THE TEST, THE FAN (1B-EF15B) TRIPPED DUE TO THERMAL OVERLOAD. THE LICENSEE | | DISCOVERED WATER IN THE CASING OF THE FAN. THE LICENSEE IS CURRENTLY | | INVESTIGATING THE SOURCE OF THE WATER IN THE FAN CASING. | | | | THE LICENSEE HAS DETERMINED THAT DURING THE PERIOD THAT MAINTENANCE WAS | | BEING PERFORMED ON THE "A" TRAIN (0400 UNTIL 1358 ON 7/25/95), BOTH TRAINS | | OF SGTS MAY HAVE BEEN INOPERABLE SIMULTANEOUSLY. THE NRC RESIDENT | | INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29115 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OYSTER CREEK REGION: 1 |NOTIFICATION DATE: 07/26/95 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 14:16 [ET]| |RX TYPE: [1] GE-2 |EVENT DATE: 07/26/95 | +------------------------------------------------+EVENT TIME: 14:00[EDT]| |NRC NOTIFIED BY: FULLER |LAST UPDATE DATE: 07/26/95 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |KEIMIG 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 | 90 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LICENSEE NOTIFIED STATE REGARDING EXCESSIVE DISCHARGE CANAL WATER | | TEMPERATURES. | | | | THE LICENSEE WILL NOTIFY THE NEW JERSEY BUREAU OF STANDARD PERMITTING, | | DIVISION OF WATER QUALITY, REGARDING A PLANT DISCHARGE CANAL TEMPERATURE IN | | EXCESS OF THE REPORTING LIMIT. (ALSO SEE RELATED EVENTS 29104 AND 29110.) | | THE LICENSEE STATED THAT THE TEMPERATURE IN THE PLANT DISCHARGE CANAL HAD | | EXCEEDED 97øF. THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE | | LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29116 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: POINT BEACH REGION: 3 |NOTIFICATION DATE: 07/26/95 | |UNIT: [1] [2] [ ] STATE: WI |NOTIFICATION TIME: 17:10 [ET]| |RX TYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 07/26/95 | +------------------------------------------------+EVENT TIME: 14:55[CDT]| |NRC NOTIFIED BY: ZEPPLIN |LAST UPDATE DATE: 07/26/95 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BURDICK 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 | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LICENSEE NOTIFIED STATE REGARDING FISH KILL NEAR COMMON INTAKE STRUCTURE. | | | | FOLLOWING CHLORINATION OF THE COMMON PLANT INTAKE STRUCTURE, THE LICENSEE | | NOTICED APPROXIMATELY 150 DEAD FISH ON THE TRAVELLING SCREENS. THE | | LICENSEE NOTIFIED THE WISCONSIN DEPARTMENT OF NATURAL RESOURCES. | | | | THE LICENSEE STATED THAT THE CHLORINATION OF THE INTAKE STRUCTURE WAS A NEW | | EVOLUTION. THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29117 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MAINE YANKEE REGION: 1 |NOTIFICATION DATE: 07/26/95 | |UNIT: [1] [ ] [ ] STATE: ME |NOTIFICATION TIME: 17:17 [ET]| |RX TYPE: [1] CE |EVENT DATE: 07/26/95 | +------------------------------------------------+EVENT TIME: 14:44[EDT]| |NRC NOTIFIED BY: EBERT |LAST UPDATE DATE: 07/26/95 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |KEIMIG 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 +------------------------------------------------------------------------------+ | POTENTIAL FOR PRESSURE LOCKING OF RECIRCULATION ACTUATION SYSTEM VALVES. | | | | THE FOLLOWING IS TEXT OF A FACSIMILE SUBMITTED BY THE LICENSEE: | | "IN RESPONSE TO NRC INFORMATION NOTICE 95-18, "POTENTIAL PRESSURE-LOCKING | | OF SAFETY-RELATED POWER-OPERATED GATE VALVES," AN ENGINEERING ANALYSIS OF | | POTENTIALLY SUSCEPTIBLE VALVES AT MAINE YANKEE WAS CONDUCTED. THE VALVES | | IDENTIFIED IN [EVENT #28749] WERE CONSIDERED TO BE SUSCEPTIBLE TO BONNET | | PRESSURE LOCK AND CORRECTIVE ACTIONS TO ALLEVIATE THE CONDITION HAVE BEEN | | TAKEN. THE INITIAL ENGINEERING REVIEW IDENTIFIED THE SUBJECT VALVES CS-M-1 | | AND CS-M-2 AS BEING POTENTIALLY SUSCEPTIBLE TO THE CONDITION BUT DUE TO | | THEIR LOCATION AND THE SYSTEM DESIGN, BONNET PRESSURE LOCK WAS NOT | | CONSIDERED CREDIBLE. THE FINAL ENGINEERING REVIEW DETERMINED THAT DURING | | ONE ACCIDENT, A SMALL BREAK LOCA, THE TIME BETWEEN SAFETY INJECTION AND | | SPRAY ACTUATION COULD BE SUFFICIENT TO ALLOW THE AMBIENT PRESSURE EXTERNAL | | TO THE VALVE TO RISE TO A POINT THAT BONNET PRESSURE LOCK COULD OCCUR." | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29118 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: QUAD CITIES REGION: 3 |NOTIFICATION DATE: 07/26/95 | |UNIT: [ ] [2] [ ] STATE: IL |NOTIFICATION TIME: 19:43 [ET]| |RX TYPE: [1] GE-3,[2] GE-3 |EVENT DATE: 07/26/95 | +------------------------------------------------+EVENT TIME: 17:40[CDT]| |NRC NOTIFIED BY: SCHARES |LAST UPDATE DATE: 07/26/95 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BURDICK RDO | |AINA 50.72(b)(2)(iii)(A) POT UNABLE TO SAFE SD | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | 4/4 MAIN CONDENSER VACUUM SWITCHES FOUND OUT OF TOLERANCE. | | | | THE LICENSEE DISCOVERED THAT 4/4 MAIN CONDENSER VACUUM SWITCHES WERE OUT OF | | TOLERANCE. THESE SWITCHES PROVIDE INPUT TO THE REACTOR PROTECTION SYSTEM | | TO SCRAM THE REACTOR IF CONDENSER VACUUM DECREASES. PLANT TECHNICAL | | SPECIFICATIONS REQUIRE THAT THE SWITCHES BE SET TO TRIP AT ò21" Hg. ALL | | FOUR SWITCHES TRIPPED AT 20 TO 21" Hg. THE LICENSEE IS CURRENTLY | | RECALIBRATING THE SWITCHES. | | | | THE LICENSEE STATED THAT THE SWITCHES HAD BEEN REPLACED EARLIER DURING THE | | PRESENT REFUELING OUTAGE, AND THAT DURING A CALIBRATION CHECK PERFORMED ON | | 4/27/95, 2/4 SWITCHES WERE FOUND OUT OF TOLERANCE. THE LICENSEE PLANS TO | | INVESTIGATE THE REASON FOR THE SETPOINT DRIFT, AND TO REPAIR THE PROBLEM | | BEFORE UNIT RESTART. THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29119 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HADDAM NECK REGION: 1 |NOTIFICATION DATE: 07/27/95 | |UNIT: [1] [ ] [ ] STATE: CT |NOTIFICATION TIME: 02:50 [ET]| |RX TYPE: [1] W-4-LP |EVENT DATE: 07/27/95 | +------------------------------------------------+EVENT TIME: 02:20[EDT]| |NRC NOTIFIED BY: TIM RYAN |LAST UPDATE DATE: 07/27/95 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RICHARD KEIMIG RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | M/R Y 100 POWER OPERATION | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | MANUAL REACTOR TRIP IN ANTICIPATION OF AUTOMATIC TRIP FROM LOW STEAM | | GENERATOR LEVEL. | | | | THE "B" FEED PUMP BREAKER FAILED CAUSING THE PUMP TO TRIP. THE REACTOR WAS | | MANUALLY TRIPPED PRIOR TO ACTUATION OF THE LOW STEAM GENERATOR WATER LEVEL | | TRIP. SAFETY INJECTION WAS MANUALLY INITIATED PER PROCEDURE WHEN | | PRESSURIZER LEVEL FELL TO 13%. THE LOWEST PRESSURIZER LEVEL REACHED WAS | | 12%. ALL CONTROL RODS INSERTED FULLY FOLLOWING THE TRIP, AND NO SAFETY | | VALVES OR PORVs OPENED. DECAY HEAT REMOVAL IS VIA STEAM DUMP TO THE MAIN | | CONDENSER. ELECTRICAL FEED IS FROM THE NORMAL STATION SERVICE TRANSFORMER. | | THE UNIT IS STABLE IN MODE 3. THE LICENSEE NOTIFIED THE CONNECTICUT | | DEPARTMENT OF ENVIRONMENTAL PROTECTION ABOUT THIS EVENT AND WILL INFORM THE | | NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+