U.S. Nuclear Regulatory Commission Operations Center Event Reports For 04/23/97 - 04/24/97 ** EVENT NUMBERS ** 32184 32187 32200 32202 32203 32204 32205 32206 32207 32208 32209 32210 32211 32212 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32184 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BRAIDWOOD REGION: 3 |NOTIFICATION DATE: 04/21/97 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 09:32 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 04/21/97 | +------------------------------------------------+EVENT TIME: 07:15[CDT]| |NRC NOTIFIED BY: R YURKOVIH |LAST UPDATE DATE: 04/23/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | GREATER THAN 1% OF UNIT 1 STEAM GENERATOR #1B TUBES ARE DEFECTIVE. | | | | ON 04/01/97, THE LICENSEE INITIATED AN INSERVICE INSPECTION OF 100% OF THE | | TUBES OF UNIT 1 STEAM GENERATOR #1B. | | | | TECHNICAL SPECIFICATION SURVEILLANCE REQUIREMENT 4.4.5.2.C REQUIRES THAT | | THE RESULTS OF EACH SAMPLE INSPECTION BE CLASSIFIED INTO 1 OF 3 CATEGORIES. | | A STEAM GENERATOR WILL BE CLASSIFIED AS CATEGORY C-3 IF MORE THAN 10% OF | | THE TOTAL TUBES INSPECTED ARE DEGRADED OR MORE THAN 1% OF THE INSPECTED | | TUBES ARE DEFECTIVE. A STEAM GENERATOR TUBE IS CONSIDERED DEGRADED IF IT | | HAS AN IMPERFECTION OF GREATER THAN OR EQUAL TO 20% NOMINAL TUBE WALL | | THICKNESS. A STEAM GENERATOR TUBE IS CONSIDERED DEFECTIVE IF IT HAS AN | | IMPERFECTION GREATER THAN OR EQUAL TO 40% NOMINAL TUBE WALL OR EXCEEDS THE | | 3.0 VOLT INTERIM PLUGGING CRITERIA. | | | | ON 04/21/97, THE RESULTS OF THE SAMPLE INSPECTION CAUSED STEAM GENERATOR 1B | | TO BE CLASSIFIED AS CATEGORY C-3 BASED ON GREATER THAN 1% OF THE INSERVICE | | TUBES BEING DEFECTIVE. THE NUMBER OF INSERVICE TUBES IS 4154. THE ACTUAL | | NUMBER OF DEFECTIVE TUBES IS 62. THESE TUBES ARE CONSIDERED DEFECTIVE | | MAINLY DUE TO CIRCUMFERENTIAL CRACK-LIKE INDICATIONS AT THE HOT LEG | | TOP-OF-TUBESHEET ROLL TRANSITION REGION AND AXIAL CRACK-LIKE INDICATIONS | | WITHIN THE HOT LEG TUBE SUPPORT PLATES GREATER THAN 3.0 VOLTS. STEAM | | GENERATORS #1A, #1C, AND #1D DATA HAS NOT BEEN ANALYZED AT THIS TIME. | | | | ALL FOUR UNIT 1 STEAM GENERATORS ARE SCHEDULED TO BE REPLACED IN 1998. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE AT 0953 ON 04/23/97 FROM ALEXANDER TAKEN BY JOLLIFFE * * * | | | | IN ADDITION TO THE ABOVE, GREATER THAN 1% OF UNIT 1 STEAM GENERATOR #1A | | TUBES ARE DEFECTIVE. | | | | ON 04/01/97, A STEAM GENERATOR TUBE INSERVICE INSPECTION WAS INITIATED ON | | BRAIDWOOD UNIT 1 IN ACCORDANCE WITH TECHNICAL SPECIFICATION REQUIREMENT | | 4.4.5.0, AND 100% OF THE INSERVICE TUBES WERE SELECTED FOR INSPECTION. | | THE ABOVE DESCRIPTION OF CATEGORY C-3 WAS CORRECTED TO STATE THAT STEAM | | GENERATOR #1A WILL BE CLASSIFIED AS CATEGORY C-3 IF MORE THAN 10% OF THE | | TOTAL TUBES INSPECTED ARE DEGRADED OR MORE THAN 1% OF THE INSPECTED TUBES | | ARE DEFECTIVE. | | | | AT 0730 CDT ON 04/23/97, THE RESULTS OF THE SAMPLE INSPECTION CAUSED STEAM | | GENERATOR #1A TO BE CLASSIFIED AS CATEGORY C-3 BASED ON GREATER THAN 1% OF | | THE TUBES BEING DEFECTIVE. THE NUMBER OF INSERVICE TUBES IS 3986. THE | | ACTUAL NUMBER OF DEFECTIVE TUBES IS 124. THESE TUBES ARE CONSIDERED | | DEFECTIVE MAINLY DUE TO CIRCUMFERENTIAL CRACK-LIKE INDICATIONS AT THE HOT | | LEG TOP-OF-TUBESHEET ROLL TRANSITION REGION AND CRACK-LIKE INDICATIONS | | WITHIN THE HOT LEG TUBE SUPPORT PLATES GREATER THAN THE 3.0 VOLT INTERIM | | PLUGGING CRITERIA. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. THE R3DO (PHILLIPS) WAS | | NOTIFIED BY THE NRC OPERATIONS CENTER. | | | | * * * UPDATE AT 2308 EDT ON 04/23/97, FROM ALEXANDER TO GOULD * * * | | | | AT 2100 CDT ON 04/23/97, THE RESULTS OF THE SAMPLE INSPECTION CAUSED STEAM | | GENERATOR #1D TO BE CLASSIFIED AS CATEGORY C-3 BASED ON GREATER THAN 1% OF | | THE INSERVICE TUBES BEING DEFECTIVE. THE NUMBER OF INSERVICE TUBES IS 4153 | | WITH THE ACTUAL NUMBER OF DEFECTIVE TUBES BEING 179. THESE TUBES ARE | | CONSIDERED DEFECTIVE MAINLY DUE TO CIRCUMFERENTIAL CRACK-LIKE INDICATIONS | | AT THE HOT LEG TOP-OF-TUBESHEET ROLL TRANSITION REGION AND AXIAL CRACK-LIKE | | INDICATIONS WITHIN THE HOT LEG TUBE SUPPORT PLATES GREATER THAN THE 3.0 | | VOLT INTERIM PLUGGING CRITERIA. | | | | THE NRC RESIDENT INSPECTOR WAS INFORMED. THE R3DO (PHILLIPS) WAS NOTIFIED | | BY THE NRC OPERATIONS CENTER. | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32187 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OCONEE REGION: 2 |NOTIFICATION DATE: 04/21/97 | |UNIT: [1] [2] [3] STATE: SC |NOTIFICATION TIME: 11:17 [ET]| |RX TYPE: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-LP |EVENT DATE: 04/16/97 | +------------------------------------------------+EVENT TIME: 15:30[EDT]| |NRC NOTIFIED BY: DAN DURHAM |LAST UPDATE DATE: 04/23/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |KENNETH BARR, REG 2 RDO | |DDDD 73.71 UNSPECIFIED PARAGRAPH |AL CHAFFEE, NRR EO | | |GENE McPEEK, NRR IAT | | |JOHN DAVIDSON, NMSS IAT | | |STUART RUBIN, AEOD IRD | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 | | 3 | N Y 100 POWER OPERATION | 100 POWER OPERATION | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - SECURITY EVENT: POTENTIAL TAMPERING EVENT OF A SUSPICIOUS NATURE - | | | | THE LICENSEE SUSPECTS TAMPERING OF RADIATION PROTECTION SAMPLING VALVES. | | IMMEDIATE COMPENSATORY MEASURES WERE TAKEN UPON DISCOVERY. OUTSIDE LAW | | ENFORCEMENT AGENCIES HAVE NOT BEEN NOTIFIED. (REFER TO THE HOO LOG FOR | | DETAILS.) | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | NOTE: REFER TO EVENT #31367 ON 11/21/96, FOR A RELATED EVENT. | | | | * * * UPDATE AT 1014 ON 04/23/97, FROM DAN DURHAM TAKEN BY JOLLIFFE * * * | | | | AT 1530 ON 04/16/97, THE LICENSEE DISCOVERED THE ORIGINAL CONDITION | | DESCRIBED ABOVE. AT THAT TIME, THE LICENSEE DETERMINED THAT THIS EVENT | | WAS A LOGGABLE SECURITY EVENT AND NOT A 1-HOUR SECURITY EVENT REPORTABLE | | TO THE NRC. | | | | AT 1600 ON 04/17/97, THE LICENSEE NOTIFIED THE LOCAL FBI REPRESENTATIVE AS | | A COURTESY. | | | | AT 1040 ON 04/21/97, AFTER THE LICENSEE COMPLETED A PRELIMINARY | | INVESTIGATION OF THE EVENT AND COULD NOT REACH A PLAUSIBLE EXPLANATION OF | | THE CAUSE OF THE EVENT AND COULD NOT DISCOUNT THE POTENTIAL FOR TAMPERING, | | THE LICENSEE DECIDED TO NOTIFY THE NRC OPERATIONS CENTER AS A CONSERVATIVE | | MEASURE. | | | | AT 1014 ON 04/23/97, AFTER FURTHER REVIEW, THE LICENSEE DESIRES TO RETRACT | | THIS EVENT NOTIFICATION SINCE IT IS A LOGGABLE SECURITY EVENT AND NOT A | | REPORTABLE EVENT. THE SUBJECT VALVES ARE NOT SAFETY OR SECURITY-RELATED | | EQUIPMENT AND ARE NOT CONTAINMENT ISOLATION VALVES. | | | | THE LICENSEE IS CONTINUING TO INVESTIGATE THIS EVENT. | | | | THE LICENSEE NOTIFIED AN ONSITE NRC REGION 2 INSPECTOR BILL STANSBERRY AND | | THE NRC RESIDENT INSPECTOR. THE HOO NOTIFIED R2DO AL BELISLE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 32200 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: ACALA, ROCK ISLAND, ILLINOIS |NOTIFICATION DATE: 04/22/97 | | CITY: ROCK ISLAND REGION: 3 |NOTIFICATION TIME: 17:41 [ET]| | COUNTY: STATE: IL |EVENT DATE: 04/22/97 | |LICENSE#: 1200722-13&14 AGREEMENT: Y |EVENT TIME: 15:13[CDT]| | DOCKET: |LAST UPDATE DATE: 04/23/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |MONTE PHILLIPS RDO | | |CHARLEY HAUGHNEY EO | +------------------------------------------------+STUART RUBIN, AEOD FEMA | |NRC NOTIFIED BY: MOHS |RON HAUBER IP | |HQ OPS OFFICER: CHAUNCEY GOULD | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |BAB1 20.2201(a)(1)(i) LOST/STOLEN LNM>1000X | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE U.S. ARMY EUROPE (USAREUR), ROCK ISLAND, ILLINOIS, REPORTED THAT | | SEVERAL THOUSAND (2,184) M43A1 CHEMICAL AGENT DETECTORS (CAD) AND 319 | | CHEMICAL AGENT MONITORS (CAM) ARE MISSING IN EUROPE. EACH CAD CONTAINED | | 250 MICROCURIES OF AMERICIUM-241, AND EACH CAM CONTAINED 10 MILLICURIES OF | | NICKEL-63. | | | | A MISSING M43A1 CAD CONTAINING 250 MICROCURIES OF AMERICIUM-241 IS GREATER | | THAN THE LIMITS FOR REPORTING (1,000 TIMES APPENDIX C WHICH IS EQUIVALENT | | TO 1 MICROCURIE). THE MISSING 365 CAMs EACH CONTAINING 10 MILLICURIES OF | | NICKEL-63 ARE GREATER THAN THE LIMITS FOR REPORTING (1,000 TIMES APPENDIX C | | WHICH IS EQUIVALENT TO 0.1 CURIE). THESE ARE APPARENT LOSSES (SINCE 1989) | | BECAUSE THE LICENSEE IS STILL WORKING ON IMPROVEMENTS OF THE ACCOUNTABILITY | | FOR THESE ITEMS. | | | | (REFER TO THE HOO LOG FOR A CONTACT TELEPHONE NUMBER.) | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32202 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SUMMER REGION: 2 |NOTIFICATION DATE: 04/22/97 | |UNIT: [1] [ ] [ ] STATE: SC |NOTIFICATION TIME: 20:22 [ET]| |RX TYPE: [1] W-3-LP |EVENT DATE: 04/22/97 | +------------------------------------------------+EVENT TIME: 16:54[EDT]| |NRC NOTIFIED BY: PROPER |LAST UPDATE DATE: 04/23/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |AL BELISLE RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 FROM 100% POWER IN ANTICIPATION OF A MAIN TURBINE TRIP | | DUE TO AN ELECTROHYDRAULIC CONTROL (EHC) SYSTEM OIL LEAK | | | | THE MANUAL REACTOR TRIP WAS INITIATED IN ANTICIPATION OF A MAIN TURBINE | | TRIP DUE TO AN EHC SYSTEM OIL LEAK. THE OIL LEAK APPEARED TO BE COMING | | FROM A BLOWN O-RING ON THE SHUTDOWN SERVO MECHANISM TO THE MAIN TURBINE | | INTERCEPT VALVES. ALL CONTROL RODS FULLY INSERTED, NO POWER-OPERATED | | RELIEF VALVES OR CODE SAFETY VALVES LIFTED, AND NO EMERGENCY CORE COOLING | | SYSTEM INJECTIONS OCCURRED. THERE WAS, HOWEVER, A PROBLEM WITH TWO OF | | THREE MAIN FEEDWATER REGULATING VALVES NOT FULLY CLOSING AND WITH THE 'B' | | AND 'C' MAIN FEEDWATER PUMPS NOT TRIPPING. THE PUMPS WERE MANUALLY | | TRIPPED. THE LICENSEE PLANS TO INVESTIGATE THE CAUSE OF THESE | | MALFUNCTIONS. | | | | THE LICENSEE NOTIFIED STATE OFFICIALS AND THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE AT 1314 ON 04/23/97, FROM PROPER TO GOULD * * * | | | | THE FOLLOWING TEXT IS FROM A FACSIMILE SUBMITTED BY THE LICENSEE: | | | | "THE FOLLOWING PROVIDES ADDITIONAL INFORMATION AND CLARIFICATION FOR THE | | MANUAL REACTOR TRIP REPORTED ON 04/22/97, FOR THE STATION. IN ADDITION TO | | THE MANUAL REACTOR TRIP, AN [ENGINEERED SAFETY FEATURE] ACTUATION OCCURRED | | FOR THE START OF THE EMERGENCY FEEDWATER SYSTEM FOR THE 'A' STEAM GENERATOR | | ON A LOW-LOW LEVEL ACTUATION SIGNAL. THE STEAM GENERATOR LEVEL DECREASED | | TO 26% NARROW RANGE DUE TO 'SHRINK' FOLLOWING THE REACTOR TRIP. THE | | EMERGENCY FEEDWATER ACTUATION FUNCTIONED PROPERLY AND RESTORED STEAM | | GENERATOR LEVELS TO WITHIN THE PROPER BANDS." | | | | "THE INITIAL REPORT IDENTIFIED THE FAILURE OF TWO FEEDWATER FLOW REGULATING | | VALVES TO FULLY CLOSE FOLLOWING THE INITIATION OF A FEEDWATER ISOLATION | | SIGNAL. FURTHER REVIEW AND EVALUATION IDENTIFIED THAT ONLY ONE FEEDWATER | | FLOW REGULATING VALVE FAILED TO FULLY CLOSE. HOWEVER, THE FEEDWATER | | ISOLATION FUNCTION WAS SATISFACTORILY ACCOMPLISHED BY THE FEEDWATER | | ISOLATION VALVES. THERE WAS NO UNCONTROLLED COOLDOWN, AND THE STEAM DUMP | | SYSTEM FUNCTIONED PROPERLY ALLOWING THE PLANT TO BE PROMPTLY STABILIZED IN | | HOT STANDBY AT NORMAL OPERATING TEMPERATURE AND PRESSURE. THE FAILURE OF | | THE TWO MAIN FEEDWATER PUMPS TO IMMEDIATELY TRIP HAD NO IMPACT ON THE | | ACCOMPLISHMENT OF THE FEEDWATER ISOLATION AND IS NOT PART OF THE AUTOMATIC | | FEEDWATER ISOLATION FUNCTION ASSOCIATED WITH LOW REACTOR COOLANT SYSTEM | | AVERAGE TEMPERATURE." | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED BY THE LICENSEE. THE R2DO | | (BELISLE) WAS NOTIFIED BY THE NRC OPERATIONS CENTER. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32203 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 04/23/97 | |UNIT: [1] [ ] [ ] STATE: CT |NOTIFICATION TIME: 11:36 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 04/23/97 | +------------------------------------------------+EVENT TIME: 09:45[EDT]| |NRC NOTIFIED BY: R. G. DeLOUREIRO |LAST UPDATE DATE: 04/23/97 | |HQ OPS OFFICER: HENRY BAILEY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN MCFADDEN 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 N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | MOLDED CASE CIRCUIT BREAKERS HAVE INADEQUATE AMPERAGE INTERRUPT RATINGS. | | | | SHORT CIRCUIT ANALYSES HAVE DETERMINED THAT MOLDED CASE CIRCUIT BREAKERS | | (MCCB) IN THE FOLLOWING MOTOR CONTROL CENTERS (MCC) HAVE INADEQUATE | | AMPERAGE INTERRUPT RATINGS: C2, C7, C8, CD4, CD4A, D1, D3, E2, E5, E6A, | | F1, F2, F3, F4, F5, AND FE3. CONSEQUENTLY, THE CIRCUIT BREAKERS WOULD NOT | | BE ABLE TO CLEAR A FAULT RESULTING IN THE POTENTIAL DE-ENERGIZATION OF THE | | ENTIRE MCC. THESE MCCBs ARE ALL IN THE 480 VAC ELECTRICAL DISTRIBUTION | | SYSTEM. A TOTAL OF 41 MCCBs WITH INADEQUATE INTERRUPT RATINGS HAVE BEEN | | IDENTIFIED. THE CAUSE(S) AND CORRECTIVE ACTION(S) FOR THESE DEFECTIVE | | MCCBs ARE NOT KNOWN AT THIS TIME. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR AND APPLICABLE STATE AND | | LOCAL AUTHORITIES. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32204 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: TURKEY POINT REGION: 2 |NOTIFICATION DATE: 04/23/97 | |UNIT: [ ] [4] [ ] STATE: FL |NOTIFICATION TIME: 11:37 [ET]| |RX TYPE: [3] W-3-LP,[4] W-3-LP |EVENT DATE: 04/23/97 | +------------------------------------------------+EVENT TIME: 10:54[EDT]| |NRC NOTIFIED BY: SPENCE |LAST UPDATE DATE: 04/23/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |AL BELISLE RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION |AL CHAFFEE, NRR EO | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 4 | A/R Y 100 POWER OPERATION | 0 HOT STANDBY | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AUTOMATIC REACTOR TRIP ON AN OVER-TEMPERATURE-DELTA-TEMPERATURE SIGNAL | | | | UNIT 4 WAS AT 100% POWER AND RECEIVED A TURBINE OVERSPEED PROTECTION | | ACTUATION CAUSING THE REACTOR TO TRIP ON OVER-TEMPERATURE-DELTA-TEMPERATURE | | SIGNAL. ALL CONTROL RODS FULLY INSERTED. INJECTION WAS NOT INITIATED, BUT | | THE STEAM GENERATOR CODE SAFETY VALVES LIFTED AND RESEATED. THERE WERE NO | | ENGINEERED SAFETY FEATURES ACTUATIONS. (THE AUXILIARY FEEDWATER SYSTEM WAS | | NOT REQUIRED.) | | | | THE LICENSEE IS FORMING AN EVENT RESPONSE TEAM TO INVESTIGATE THE CAUSE OF | | THE EVENT. THE HEAT SINK IS THE STEAM DUMPS TO THE ATMOSPHERE. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR AND PLANS TO NOTIFY LOCAL | | AGENCIES. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32205 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: ZION REGION: 3 |NOTIFICATION DATE: 04/23/97 | |UNIT: [1] [2] [ ] STATE: IL |NOTIFICATION TIME: 13:16 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 04/23/97 | +------------------------------------------------+EVENT TIME: 10:40[CDT]| |NRC NOTIFIED BY: DON NOLDIN |LAST UPDATE DATE: 04/23/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MONTE PHILLIPS RDO | |ADAS 50.72(b)(2)(i) DEG/UNANALYZED COND | | |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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | 2 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - EIGHT STEAM GENERATOR PRESSURE TRANSMITTERS DECLARED INOPERABLE - | | | | THE LICENSEE DETERMINED THROUGH PRELIMINARY CALCULATIONS THAT STEAM | | GENERATOR PRESSURE TRANSMITTERS #1(2)PT-514, 524, 534, AND 544 AND | | #1(2)PT-515, 525, 535, AND 545 WOULD NOT OPERATE PROPERLY DURING A STEAM | | LINE BREAK OUTSIDE-OF-CONTAINMENT ACCIDENT. THIS IS DUE TO UNACCEPTABLY | | LOW INSTRUMENTATION CABLE INSULATION RESISTANCE CAUSED BY ELEVATED | | TEMPERATURES IN THE VALVE ROOMS AND STEAM TUNNELS. THE RESULTING CURRENT | | LEAKAGE IN THE INSTRUMENT CABLES WOULD RESULT IN AN UPSCALE BIAS IN THE | | INDICATED STEAM GENERATOR PRESSURE. THE MAGNITUDE OF THIS BIAS WOULD | | EXCEED THE RANGE OF THE INSTRUMENT EFFECTIVELY CAUSING THE INDICATION TO | | READ 1200 PSI REGARDLESS OF ACTUAL PRESSURE. THEREFORE, IN THE EVENT OF | | A STEAM LINE BREAK OUTSIDE CONTAINMENT, THESE INSTRUMENTS WOULD NOT BE | | AVAILABLE TO AID IN IDENTIFICATION OF THE FAULTED STEAM GENERATOR AS | | ASSUMED IN THE PLANT EMERGENCY OPERATING PROCEDURES. THIS ALSO RENDERS | | THE SAFETY INJECTION ACTUATION SIGNAL FOR THE HIGH DIFFERENTIAL PRESSURE | | BETWEEN TWO STEAM LINES INOPERABLE. | | | | THE LICENSEE ALSO DETERMINED THAT FISCHER & PORTER MODEL #50EP10413CXA | | TRANSMITTERS #1(2)PT-514, 524, 534, AND 544 HAVE NOT BEEN QUALIFIED FOR | | HARSH ENVIRONMENTS GREATER THAN 320øF, AND THEREFORE, THEIR FUNCTION IS | | NOT ASSURED DURING PEAK TEMPERATURES OF 480øF REACHED DURING MAIN STEAM | | LINE BREAK OUTSIDE-OF-CONTAINMENT ACCIDENTS. THIS CONDITION HAS EXISTED | | SINCE ORIGINAL INSTALLATION IN 1973. THE LICENSEE DECLARED THESE EIGHT | | INSTRUMENTS INOPERABLE; THEY ARE NOT REQUIRED TO BE OPERABLE IN MODES 5 | | OR 6. THE LICENSEE IS DETERMINING CORRECTIVE ACTIONS WHICH WILL BE | | COMPLETED PRIOR TO STARTUP OF EITHER UNIT. THE LICENSEE INFORMED THE | | NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32206 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: WATERFORD REGION: 4 |NOTIFICATION DATE: 04/23/97 | |UNIT: [3] [ ] [ ] STATE: LA |NOTIFICATION TIME: 14:43 [ET]| |RX TYPE: [3] CE |EVENT DATE: 04/23/97 | +------------------------------------------------+EVENT TIME: 09:45[CDT]| |NRC NOTIFIED BY: SCOTT |LAST UPDATE DATE: 04/23/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |ELMO COLLINS RDO | |DDDD 73.71 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 3 | N N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE REPORTED THAT AN INDIVIDUAL'S FITNESS-FOR-DUTY WAS QUESTIONED | | DUE TO INATTENTIVENESS WHILE ON WATCH. IMMEDIATE COMPENSATORY MEASURES | | WERE TAKEN UPON DISCOVERY. (REFER TO THE HOO LOG FOR DETAILS.) | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32207 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SEABROOK REGION: 1 |NOTIFICATION DATE: 04/23/97 | |UNIT: [1] [ ] [ ] STATE: NH |NOTIFICATION TIME: 16:47 [ET]| |RX TYPE: [1] W-4-LP |EVENT DATE: 04/23/97 | +------------------------------------------------+EVENT TIME: 15:15[EDT]| |NRC NOTIFIED BY: STRICKLAND |LAST UPDATE DATE: 04/23/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN MCFADDEN RDO | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | | | |WILLIAM BEECHER OPA | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 ISSUED A MEDIA ADVISORY ON A PUBLIC DEMONSTRATION PLANNED FOR | | 04/26/97. | | | | THE MEDIA ADVISORY REPORTED THAT ON SATURDAY, APRIL 26, 1997, ANTI-NUCLEAR | | ACTIVISTS AND ENVIRONMENTALISTS ARE PLANNING TO CONDUCT A RALLY AND CIVIL | | DISOBEDIENCE DEMONSTRATION AT SEABROOK STATION TO COMMEMORATE THE CHERNOBYL | | ACCIDENT AND THE 20TH ANNIVERSARY OF A PREVIOUS SEABROOK RALLY. THE | | LICENSEE PLANS TO IMPLEMENT ADDITIONAL SECURITY MEASURES DURING THE RALLY | | AND HAS COORDINATED WITH LOCAL LAW ENFORCEMENT OFFICIALS. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 32208 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: WESTERN ATLAS LOGGING SERVICES |NOTIFICATION DATE: 04/23/97 | | CITY: BATON ROUGE REGION: 4 |NOTIFICATION TIME: 17:18 [ET]| | COUNTY: STATE: LA |EVENT DATE: 04/23/97 | |LICENSE#: LA-2187-LO1 AGREEMENT: Y |EVENT TIME: 16:45[CDT]| | DOCKET: |LAST UPDATE DATE: 04/23/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |ELMO COLLINS RDO | | |JOHN HICKEY, NMSS EO | +------------------------------------------------+FRANK CONGEL, AEOD IRD | |NRC NOTIFIED BY: LARKIN-NRC STATE PROGRAMS | | |HQ OPS OFFICER: CHAUNCEY GOULD | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NAGR AGREEMENT STATE | | |NINF INFORMATION ONLY | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | A POTENTIAL OCCUPATIONAL EXPOSURE TO AN INDIVIDUAL AT THE WESTERN ATLAS | | LOGGING SERVICES FACILITY IN BROUSSARD, LOUISIANA. | | | | THE POTENTIAL EXPOSURE OCCURRED ON 04/17/97, WHEN A TEMPORARY CONTRACT | | EMPLOYEE SERVICED A SOURCE CONTAINER THAT CONTAINED A 5 CURIE | | AMERICIUM/BERYLLIUM NEUTRON SOURCE. THERE WAS NO RADIOACTIVE MATERIAL | | RELEASE, BUT THE EMPLOYEE HANDLED THE SOURCE AND PUT IT IN HIS POCKET. | | THE DOSE TO THE INDIVIDUAL IS CALCULATED TO BE 4 AND 6 REM ACCORDING TO | | AN OAK RIDGE NATIONAL LABORATORY CONSULTANT. BLOOD WORK HAS BEEN PERFORMED | | LOCALLY AND THE RESULTS WERE SENT TO THE OAK RIDGE NATIONAL LABORATORY | | CONSULTANT. THE LICENSEE IS STILL INVESTIGATING THIS INCIDENT AND PLANS TO | | PREPARE A MORE DETAILED REPORT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32209 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: POINT BEACH REGION: 3 |NOTIFICATION DATE: 04/23/97 | |UNIT: [ ] [2] [ ] STATE: WI |NOTIFICATION TIME: 17:09 [ET]| |RX TYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 04/23/97 | +------------------------------------------------+EVENT TIME: 15:15[CDT]| |NRC NOTIFIED BY: SCHROEDER |LAST UPDATE DATE: 04/23/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ 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 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNIT 2 REPORTED AN UNAUTHORIZED ENTRY INTO THE VITAL AREA. COMPENSATORY | | MEASURES WERE NOT NECESSARY. (REFER TO THE HOO LOG FOR ADDITIONAL | | DETAILS.) | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32210 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SAINT LUCIE REGION: 2 |NOTIFICATION DATE: 04/23/97 | |UNIT: [ ] [2] [ ] STATE: FL |NOTIFICATION TIME: 18:29 [ET]| |RX TYPE: [1] CE,[2] CE |EVENT DATE: 04/23/97 | +------------------------------------------------+EVENT TIME: 17:58[EDT]| |NRC NOTIFIED BY: WILLIAMS |LAST UPDATE DATE: 04/23/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |AL BELISLE 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 N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AN ANTICIPATED CONTAINMENT ISOLATION ACTUATION SIGNAL (CIAS) WAS GENERATED | | ON UNIT 2 WHEN TWO OUT OF FOUR CONTAINMENT RADIATION MONITORS WENT INTO | | HIGH ALARM. | | | | THE RADIATION MONITORS WENT INTO HIGH RADIATION ALARM DURING THE REMOVAL | | OF THE UPPER GUIDE STRUCTURE (UGS) FROM THE REACTOR VESSEL. AN EARLIER | | ATTEMPT TO LIFT THE UGS WAS MADE AT 1145 THAT RESULTED IN ONE CONTAINMENT | | RADIATION MONITOR GOING INTO ALARM WITH INCREASING TRENDS NOTED ON THE | | OTHER THREE RAD MONITORS. THE CONTAINMENT EVACUATION ALARM SOUNDED, THE | | CONTAINMENT BUILDING WAS EVACUATED, AND THE UGS WAS LOWERED BACK INTO THE | | REACTOR VESSEL PRIOR TO THE CIAS TWO-OUT-OF-FOUR HIGH RADIATION LOGIC | | SIGNAL BEING MADE UP. RADIATION LEVELS RETURNED TO NORMAL VALUES ON ALL | | FOUR CHANNELS WHEN THE UGS WAS IN ITS FULLY LOWERED POSITION. | | | | IT IS POSTULATED THAT A PIECE OF AN INCORE DETECTOR WAS BROKEN OFF DURING | | EARLIER REMOVAL OF THE DETECTOR AND THAT IT IS LODGED NEAR THE TOP OF ITS | | INSTRUMENTATION TUBE WHICH IS LOCATED NEAR THE TOP OF THE UGS. THE HIGH | | RADIATION LEVELS OCCURRED WHEN THE INSTRUMENT TUBES NEARED OR BROKE THE | | SURFACE OF THE WATER IN THE REACTOR CAVITY. IT WAS DECIDED TO REMOVE THE | | UGS FROM THE REACTOR VESSEL AND PLACE IT IN ITS NORMAL UNDERWATER STORAGE | | LOCATION IN THE LOWER REACTOR CAVITY PRIOR TO RETRIEVAL OF THE INCORE | | DETECTOR TO PREVENT DEBRIS FROM FALLING INTO THE CORE. | | | | SINCE A VALID CIAS ON HIGH RADIATION LEVEL WAS EXPECTED DURING LIFT OF | | THE UGS, PRECAUTIONS WERE TAKEN PRIOR TO THE ACTUAL LIFT TO REDUCE THE | | POTENTIAL CONSEQUENCES. ONCE THE UGS WAS PLACED IN THE LOWER CAVITY, | | RADIATION LEVELS DECREASED TO NORMAL LEVELS, AND THE CIAS WAS RESET | | (AT 1815) AFTER VERIFYING THAT ALL COMPONENTS CORRECTLY ACTUATED. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR AND THERE HAS BEEN MEDIA | | INTEREST IN THE INITIAL EVACUATION ALARM. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32211 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FARLEY REGION: 2 |NOTIFICATION DATE: 04/23/97 | |UNIT: [1] [ ] [ ] STATE: AL |NOTIFICATION TIME: 19:41 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 04/23/97 | +------------------------------------------------+EVENT TIME: 17:00[CDT]| |NRC NOTIFIED BY: LERO |LAST UPDATE DATE: 04/23/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |AL BELISLE RDO | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 OVERSTRESSED CONDITION ON UNIT 1 REACTOR COOLANT SYSTEM PIPING | | AND SUPPORTS. | | | | THE LICENSEE PERFORMED A WALKDOWN TO DETERMINE IF THERE WERE ANY STRUCTURAL | | REASONS FOR THE EXCESSIVE VIBRATION WHICH WAS NOTED ON THE '1C' REACTOR | | COOLANT PUMP. DURING THIS WALKDOWN (WITH UNIT 1 IN A HOT STANDBY MODE), | | THE LICENSEE OBSERVED THAT THE HOT GAPS ASSOCIATED WITH THE STEAM GENERATOR | | SUPPORT BUMPERS APPEARED TO BE TOO LARGE ON SEVERAL OF THE BUMPERS AND | | INSUFFICIENT ON SEVERAL OTHERS. DURING AN ADDITIONAL WALKDOWN, WITH UNIT 1 | | IN COLD SHUTDOWN MODE, THE LICENSEE TOOK MEASUREMENTS ON THE SIX STEAM | | GENERATORS. THE LICENSEE INITIATED A DESIGN REVIEW AND STRUCTURAL ANALYSIS | | TO DETERMINE THE SIGNIFICANCE OF THE CLOSE BUMPER CONDITION. | | | | WESTINGHOUSE HAS COMPLETED A PRELIMINARY ANALYSIS, AND THE RESULTS INDICATE | | THAT THE ELBOW IN THE '1C' STEAM GENERATOR HOT LEG INLET AND ONE STEAM | | GENERATOR LOWER LATERAL SUPPORT ARE EXHIBITING STRESSES POTENTIALLY HIGHER | | THAN THE ASME CODE ALLOWABLE LIMIT. | | | | DURING THIS OUTAGE, THE LICENSEE PERFORMED 10 YEAR INSERVICE INSPECTIONS ON | | A NUMBER OF WELDS IN REACTOR COOLANT SYSTEM (RCS) LOOP 'C.' THE LICENSEE | | IS PERFORMING ADDITIONAL VISUAL INSPECTIONS ON THE LOOP 'C' COMPONENT | | SUPPORTS. TO DATE, NO DEFECTS IN THE RCS LOOP 'C' WELDS HAVE BEEN | | IDENTIFIED, AND THE VISUAL INSPECTIONS HAVE NOT IDENTIFIED ANY GROSS | | STRUCTURAL DEFORMATION. | | | | THE RESULTS OF THIS ANALYSIS ARE PRELIMINARY AND MAY CHANGE PENDING | | COMPLETION OF THE FINAL CALCULATIONS. | | | | IN ORDER TO RETURN THE '1C' STEAM GENERATOR SUPPORT BUMPERS TO THEIR | | ORIGINAL DESIGN CONFIGURATION, DESIGN MODIFICATIONS FOR ALL SIX OF THE | | '1C' STEAM GENERATOR LOWER LATERAL SUPPORT SUPPORT BUMPER LOCATIONS HAVE | | BEEN DEVELOPED AND ARE IN THE PROCESS OF IMPLEMENTATION. | | | | THE LICENSEE PLANS TO NOTIFY THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 32212 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 04/24/97 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 00:05 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 04/23/97 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 15:42[CDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 04/24/97 | | CITY: PADUCAH REGION: 3 +-----------------------------+ | COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION| |LICENSE#: GDP-1 AGREEMENT: Y |MONTE PHILLIPS RDO | | DOCKET: 0707001 |JOHN HICKEY, NMSS EO | +------------------------------------------------+FRANK CONGEL, AEOD IRD | |NRC NOTIFIED BY: MATT C. MAURER | | |HQ OPS OFFICER: LEIGH TROCINE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NLTR LICENSEE 24 HR REPORT | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ACTUATION OF A 'Q' SAFETY SYSTEM DUE TO A VALID SIGNAL (OTHER NON-CFR | | REQUIREMENT REPORTED WITHIN 24 HOURS PER PLANT PROCEDURES.) | | | | AT 1542 (CDT) ON APRIL 23, 1997, THE WATER INVENTORY CONTROL SAFETY SYSTEM | | ACTUATED ON THE POSITION #1 AUTOCLAVE IN THE C-360 TOLL AND TRANSFER | | FACILITY. THE AUTOCLAVE HAD BEEN PLACED IN MODE 5 (HEATING) AT | | APPROXIMATELY 1445 (CDT) ON APRIL 23, 1997. THE ACTUATION OF THE WATER | | INVENTORY CONTROL SAFETY SYSTEM AUTOMATICALLY CLOSES STEAM SUPPLY VALVES | | XV-153 AND FV-105 AND THERMOSTATIC VENT VALVE XV-134 THUS LIMITING THE | | AMOUNT OF WATER IN THE AUTOCLAVE. THE ACTUATION WAS DETERMINED TO BE A | | VALID RESPONSE TO EXCESS WATER IN THE AUTOCLAVE. | | | | ALL SYSTEMS FUNCTIONED AS REQUIRED. THE AUTOCLAVE WAS DECLARED INOPERABLE | | AT 1648 (CDT). AN ENGINEERING INVESTIGATION OF THE ACTUATION WAS | | INITIATED. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+