U.S. Nuclear Regulatory Commission Operations Center Event Reports For 12/19/97 - 12/22/97 ** EVENT NUMBERS ** 33141 33430 33431 33432 33433 33434 33435 33436 33437 33438 33439 33440 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33141 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: WOLF CREEK REGION: 4 |NOTIFICATION DATE: 10/24/97 | |UNIT: [1] [ ] [ ] STATE: KS |NOTIFICATION TIME: 10:24 [ET]| |RX TYPE: [1] W-4-LP |EVENT DATE: 10/24/97 | +------------------------------------------------+EVENT TIME: 05:30[CDT]| |NRC NOTIFIED BY: DAVE DEES |LAST UPDATE DATE: 12/20/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DALE POWERS 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 +------------------------------------------------------------------------------+ | LOCAL LEAK RATE TEST OF CONTAINMENT PENETRATION EXCEEDED ALLOWABLE LIMIT. | | | | RESULTS OF A LOCAL LEAK RATE TEST PERFORMED ON CONTAINMENT PENETRATION #28 | | (VALVES #EFHV-32 AND #EFHV-34) EXCEEDED THE ALLOWABLE LEAKAGE RATE. THIS | | CONDITION RESULTED IN TOTAL CONTAINMENT INTEGRATED LEAKAGE EXCEEDING THE | | USAR LIMIT OF 0.6 La. THE LICENSEE PLANS TO CONDUCT FURTHER TESTING TO | | DETERMINE THE LEAKAGE RATES OF THE TWO VALVES INDIVIDUALLY. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | | | | ***UPDATE ON 12/20/97 @ 0215 BY FERGUSON TO GOULD*** THE LICENSEE IS | | RETRACTING THIS EVENT, SINCE THE TEST METHOD USED RESULTED IN A HIGHER | | LEAKAGE RATE THAN ACTUAL. THE TEST METHOD WAS MODIFIED TO ISOLATE THE TWO | | SERIES VALVES AND PROVIDE A MORE ACCURATE LEAKAGE INDICATION. THE ACTUAL | | LEAKAGE DID NOT EXCEED THE USAR LIMIT. | | | | THE RESIDENT INSPECTOR WILL BE INFORMED. REG 4 RDO(SANBORN) WAS NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33430 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: QUAD CITIES REGION: 3 |NOTIFICATION DATE: 12/19/97 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 00:25 [ET]| |RX TYPE: [1] GE-3,[2] GE-3 |EVENT DATE: 12/18/97 | +------------------------------------------------+EVENT TIME: 21:25[CST]| |NRC NOTIFIED BY: LECHMAIER |LAST UPDATE DATE: 12/19/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PATRICK HILAND 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 Y 99 POWER OPERATION | 99 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | BOTH UNIT 1 AND UNIT 1/2 EMERGENCY DIESEL GENERATORS DECLARED INOPERABLE. | | | | WHILE PERFORMING PREVENTATIVE MAINTENANCE ON THE UNIT 1 EMERGENCY DIESEL | | GENERATOR (EDG), THE TIME DELAY RELAY FOR START FAILURE WAS FOUND TO BE OUT | | OF TOLERANCE. THIS WAS DISCOVERED AT 1400 CST ON 12/18/97 AND THE UNIT 1 | | EDG WAS DECLARED INOPERABLE AT THAT TIME. THE UNIT 1/2 EDG WAS THEN TESTED | | TO DETERMINE IF ITS TIME DELAY RELAY WAS WITHIN APPROPRIATE SPECIFICATIONS. | | THE TEST WAS COMPLETED AND THE RELAY WAS ALSO DETERMINED TO BE OUT OF | | TOLERANCE AT 2125 CST ON 12/18/97. THIS MEANS THAT BOTH THE UNIT 1 AND | | UNIT 1/2 EDGs WERE INOPERABLE AT THE SAME TIME. RELAY REPLACEMENT AND | | TESTING WAS IN PROGRESS AT THE TIME. THE CAUSE OF THE RELAY PROBLEM IS | | BEING INVESTIGATED. UNIT 1 IS IN AN LCO ACTION STATEMENT WHICH GIVES | | THEM TWO HOURS TO CORRECT THE PROBLEM OR BE IN HOT SHUTDOWN CONDITION | | IN 12 HOURS. | | | | THE NRC RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33431 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 12/19/97 | |UNIT: [ ] [ ] [3] STATE: CT |NOTIFICATION TIME: 09:11 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 12/19/97 | +------------------------------------------------+EVENT TIME: 09:05[EST]| |NRC NOTIFIED BY: SMITH |LAST UPDATE DATE: 12/19/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JAMES NOGGLE RDO | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | UNIT 3 NOTIFIED THE STATE OF CONNECTICUT THAT TRACE AMOUNTS OF | | CONTAMINATION WAS FOUND AT A DUMP USED FOR SILT DISPOSAL. | | | | THE LICENSEE REPORTED THAT TRACE AMOUNTS OF COBALT-60, IN THE ORDER OF | | 0.06 PICOCURIES, WERE FOUND AT THE WATERFORD CITY DUMP. THEY HAD | | PREVIOUSLY DEPOSITED SILT FROM THEIR INTAKE INTO THE DUMP. THEY WILL | | RECOVER ALL OF THE SILT AND BRING IT BACK TO THE PLANT. THERE MAY BE | | NEWS MEDIA INTEREST. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33432 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: GRAND GULF REGION: 4 |NOTIFICATION DATE: 12/19/97 | |UNIT: [1] [ ] [ ] STATE: MS |NOTIFICATION TIME: 09:30 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 12/19/97 | +------------------------------------------------+EVENT TIME: 08:30[CST]| |NRC NOTIFIED BY: SPARKS |LAST UPDATE DATE: 12/19/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GARY SANBORN RDO | |AARC 50.72(b)(1)(v) OTHER ASMT/COMM INOP | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | LOSS OF EMERGENCY ASSESSMENT CAPABILITY DUE TO PLANNED MAINTENANCE. | | | | THE PRIMARY EMERGENCY OPERATIONS FACILITY (EOF) WAS DECLARED OUT OF SERVICE | | FOR PLANNED MAINTENANCE ACTIVITIES FOR 6 HOURS. HOWEVER, THE BACKUP EOF | | WAS AVAILABLE. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33433 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PERRY REGION: 3 |NOTIFICATION DATE: 12/19/97 | |UNIT: [1] [ ] [ ] STATE: OH |NOTIFICATION TIME: 10:44 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 12/19/97 | +------------------------------------------------+EVENT TIME: 09:39[EST]| |NRC NOTIFIED BY: ARTHUR |LAST UPDATE DATE: 12/19/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PATRICK HILAND RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | A/R Y 100 POWER OPERATION | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | PLANT HAD A REACTOR SCRAM FROM 100% POWER DUE TO A TURBINE TRIP. | | | | THE REACTOR SCRAM OCCURRED AFTER THE CONTROL ROOM RECEIVED A LOW EHC | | PRESSURE ALARM. WHEN THE SECOND EHC PUMP STARTED APPROXIMATELY | | 16 SECONDS LATER, A TURBINE TRIP WAS RECEIVED FOLLOWED BY AN AUTOMATIC | | REACTOR SCRAM. ALL RODS FULLY INSERTED, NO ECCS INJECTION OCCURRED AND | | NO SRVs LIFTED. THE HEAT SINK IS THE MAIN CONDENSER. THE CAUSE OF THE | | EHC LOW PRESSURE ALARM IS A BROKEN AIR LINE GOING TO THE #3 EHC CONTROL | | VALVE (#1N-11F250A). THE PLANT IS STABLE IN CONDITION 3 (HOT SHUTDOWN). | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33434 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: LASALLE REGION: 3 |NOTIFICATION DATE: 12/19/97 | |UNIT: [1] [2] [ ] STATE: IL |NOTIFICATION TIME: 13:40 [ET]| |RX TYPE: [1] GE-5,[2] GE-5 |EVENT DATE: 12/19/97 | +------------------------------------------------+EVENT TIME: 10:08[CST]| |NRC NOTIFIED BY: DAN COVEYOU |LAST UPDATE DATE: 12/19/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRUCE JORGENSEN RDO | |ADAS 50.72(b)(2)(i) DEG/UNANALYZED COND | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | -INADEQUATE TURB BLDG VENT SYS EXHAUST TUNNEL/HPCS SYS SWITCHGEAR ROOM WALL | | | | AS PART OF LICENSEE ENGINEERING EVALUATIONS, A DETAILED TRANSIENT ANALYSIS | | WAS PERFORMED TO PREDICT PRESSURES IN THE TURBINE BUILDING VENTILATION | | (TBV) SYSTEM EXHAUST TUNNEL DOWNSTREAM OF THE HIGH ENERGY LINE BREAK (HELB) | | CHECK DAMPERS (#1/2VT79YA/B/C) ASSOCIATED WITH THE LATCH SETPOINT AND | | SINGLE FAILURE CONCERNS RAISED BY THE EVALUATIONS. THE PRELIMINARY RESULTS | | OF THE ANALYSIS PERFORMED TO ESTABLISH THE BASELINE CASE ASSUMING NORMAL | | DAMPER CLOSURE IN RESPONSE TO THE MAIN STEAM HELB, DETERMINED THAT THE | | PRESSURE DOWNSTREAM OF THE DAMPERS COULD EXCEED THE PRESSURE CAPABILITY OF | | THE BLOCK WALL THAT SEPARATES THE TBV SYSTEM EXHAUST TUNNEL FROM THE HIGH | | PRESSURE CORE SPRAY (HPCS) SYSTEM SWITCHGEAR ROOM. THIS COULD POTENTIALLY | | RESULT IN DAMAGE TO THE HPCS SYSTEM EQUIPMENT IN THE HPCS SYSTEM SWITCHGEAR | | ROOM AND CONSEQUENT LOSS OF HPCS SYSTEM FUNCTION. THE ORIGINAL ANALYSIS | | ASSUMED THAT THE HELB CHECK DAMPERS CLOSED FAST ENOUGH TO PREVENT DAMAGE | | DOWNSTREAM OF THE DAMPERS. CONSIDERING THE NEW ANALYSIS, THIS MAY NOT BE | | TRUE. | | | | CURRENTLY, BOTH UNIT 1 (COLD SHUTDOWN IN A MAINTENANCE OUTAGE) AND UNIT 2 | | (DEFUELED IN A REFUELING OUTAGE) ARE NOT IN A CONDITION WHERE STEAM COULD | | CREATE ENOUGH ENERGY TO RESULT IN AN IMMEDIATE CONCERN. | | | | THE LICENSEE IS DETERMINING CORRECTIVE ACTIONS. THIS CONDITION WILL BE | | RESOLVED PRIOR TO RESTART OF EACH UNIT. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33435 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BEAVER VALLEY REGION: 1 |NOTIFICATION DATE: 12/19/97 | |UNIT: [ ] [2] [ ] STATE: PA |NOTIFICATION TIME: 14:41 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 12/19/97 | +------------------------------------------------+EVENT TIME: 13:33[EST]| |NRC NOTIFIED BY: GEORGE STOROLIS |LAST UPDATE DATE: 12/19/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JAMES NOGGLE RDO | |ADAS 50.72(b)(2)(i) DEG/UNANALYZED COND | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | - 2 OF 2 UNIT 2 EDGs INOPERABLE DUE TO MISSING ISOLATOR COMPUTER CARD - | | | | UNIT 2 IS IN MODE 5 (COLD SHUTDOWN) IN A MAINTENANCE OUTAGE. | | | | ON 12/19/97, THE LICENSEE DISCOVERED A NONCONFORMING CONDITION IN THE | | CONTROL CIRCUITRY FOR THE UNIT 2 EMERGENCY DIESEL GENERATOR (EDG) | | VENTILATION SYSTEM. TWO EDG TEMPERATURE CONTROL CIRCUITS DO NOT HAVE | | AN ISOLATOR COMPUTER CARD (ICC) INSTALLED BETWEEN THE QA CATEGORY 2 | | TEMPERATURE INDICATORS LOCATED IN THE BUILDING SERVICES PANEL AND THE | | QA CATEGORY 1 TEMPERATURE CONTROLLERS WHICH MODULATE THE OUTDOOR AIR | | DAMPERS AND RETURN AIR DAMPERS FOR THE EDG ROOM. THE EFFECT OF THE | | IDENTIFIED NONCONFORMANCE IS THAT THE CIRCUIT CANNOT BE CREDITED WITH | | OPENING THE OUTSIDE AIR DAMPERS AS REQUIRED UPON START OF THE EDGs, | | SINCE IT IS NOT QA CATEGORY 1. THIS WOULD NOT PREVENT THE EDGs FROM | | STARTING BUT, WITHOUT VENTILATION, THE EDG ROOM WOULD CONTINUE TO HEAT UP | | AND DEGRADE THE PERFORMANCE OF THE EDG(s) UNTIL THE EDG(s) WOULD NO | | LONGER BE ABLE TO PERFORM THEIR INTENDED FUNCTION. | | | | AT 1333 ON 12/19/97, THE LICENSEE DECLARED BOTH EDGs INOPERABLE, EVEN | | THOUGH THEY ARE FUNCTIONAL, AND INVOKED THE APPROPRIATE TECH SPEC LCO | | ACTION STATEMENT(S). A LICENSEE REVIEW OF HISTORICAL REVISIONS OF DESIGN | | DRAWINGS OF THE EDG VENTILATION SYSTEM CONTROL CIRCUITRY INDICATES THAT | | AN ICC WAS INCLUDED IN THE ORIGINAL DESIGN. THE LICENSEE VERIFIED THAT | | AN ICC IS NOT INSTALLED IN UNIT 2 AND THE CURRENT UNIT 2 DRAWINGS ARE | | CORRECT AND THIS PROBLEM DOES NOT EXIST ON UNIT 1. | | | | THE LICENSEE IS DETERMINING CORRECTIVE ACTIONS AND INFORMED THE NRC | | RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33436 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SAN ONOFRE REGION: 4 |NOTIFICATION DATE: 12/19/97 | |UNIT: [ ] [2] [3] STATE: CA |NOTIFICATION TIME: 16:28 [ET]| |RX TYPE: [1] W-3-LP,[2] CE,[3] CE |EVENT DATE: 12/19/97 | +------------------------------------------------+EVENT TIME: 12:30[PST]| |NRC NOTIFIED BY: MARTIN SPEER |LAST UPDATE DATE: 12/19/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: | | |DDDD 73.71 UNSPECIFIED PARAGRAPH | | | |KEN BROCKMAN, R4 IAT | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 75 POWER OPERATION | 75 POWER OPERATION | | 3 | N Y 100 POWER OPERATION | 100 POWER OPERATION | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | PLANT SECURITY EVENT - | | | | PLANT SAFEGUARDS DEGRADATION RELATED TO COMPUTER FAILURE. COMPENSATORY | | MEASURES WERE TAKEN WITHIN PRESCRIBED TIME LIMITS. THE LICENSEE WILL | | INFORM THE NRC RESIDENT INSPECTOR. REFER TO THE HOO LOG FOR ADDITIONAL | | DETAILS. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 33437 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 12/19/97 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 16:39 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 12/19/97 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 02:23[EST]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 12/19/97 | | CITY: PIKETON REGION: 3 +-----------------------------+ | COUNTY: PIKE STATE: OH |PERSON ORGANIZATION| |LICENSE#: GDP-2 AGREEMENT: N |BRUCE JORGENSEN RDO | | DOCKET: 0707002 |SUSAN SHANKMAN, NMSS EO | +------------------------------------------------+ | |NRC NOTIFIED BY: ERIC SPAETH | | |HQ OPS OFFICER: DICK JOLLIFFE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NLTR LICENSEE 24 HR REPORT | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - X-343 AUTOCLAVE S/D DUE TO STEAM S/D ALARM ON A HI CONDENSATE CONDITION - | | | | AT 0223 ON 12/19/97, PLANT OPERATORS RECEIVED A STEAM SHUTDOWN ALARM ON THE | | #1 AUTOCLAVE IN THE X-343 BUILDING WHILE THE AUTOCLAVE WAS IN OPERATIONAL | | MODE II (HEATING). THE STEAM SHUTDOWN ALARM WAS ACTUATED BY THE 'A' AND | | 'B' HIGH CONDENSATE ALARM PROBES. LICENSEE INVESTIGATION REVEALED THAT | | THE SAFETY-RELATED #1 AUTOCLAVE HIGH CONDENSATE ALARM WAS CAUSED BY AN | | ACTUAL HIGH CONDENSATE CONDITION IN THE X-343 BUILDING. PLANT OPERATORS | | IMMEDIATELY SHUT #1 AUTOCLAVE DOWN (MODE VII) AND DECLARED IT INOPERABLE. | | THERE WAS NO RELEASE OF HAZARDOUS MATERIALS OR RADIOLOGICAL CONTAMINATION | | EXPOSURES ASSOCIATED WITH THIS HIGH CONDENSATE ALARM ACTUATION. | | | | PLANT PERSONNEL SUSPECT THAT THE HIGH CONDENSATE CONDITION WAS CAUSED BY A | | PARTIALLY PLUGGED STRAINER. | | | | THE LICENSEE IS DETERMINING THE CAUSE AND CORRECTIVE ACTIONS. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR AND THE ONSITE DOE | | REPRESENTATIVE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33438 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PERRY REGION: 3 |NOTIFICATION DATE: 12/20/97 | |UNIT: [1] [ ] [ ] STATE: OH |NOTIFICATION TIME: 00:06 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 12/19/97 | +------------------------------------------------+EVENT TIME: 19:48[EST]| |NRC NOTIFIED BY: FERRELL |LAST UPDATE DATE: 12/20/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRUCE JORGENSEN RDO | |HFIT 26.73 FITNESS FOR DUTY | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | AN OPERATIONS SECTION SRO EXCEEDED THE LICENSEE'S LIMITS FOR | | FITNESS-FOR-DUTY FOR ALCOHOL. | | | | THE INDIVIDUAL DID NOT PERFORM LICENSED DUTIES AND WAS ASSIGNED TO A WORK | | RELEASE GROUP. TESTING WAS PERFORMED FOLLOWING A SHIFT TURNOVER MEETING. | | THE INDIVIDUAL EXCEEDED THE LIMITS WHEN HE TESTED AT .08% ALCOHOL. THE | | INDIVIDUAL WAS ESCORTED OFF SITE AND HIS ACCESS HAS BEEN REVOKED TO THE | | PROTECTED AREA. THE INDIVIDUAL WAS DRIVEN HOME BY HIS SUPERVISOR. NO | | PLANT SYSTEMS WERE AFFECTED. THE RESIDENT INSPECTOR WAS NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33439 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: NINE MILE POINT REGION: 1 |NOTIFICATION DATE: 12/21/97 | |UNIT: [ ] [2] [ ] STATE: NY |NOTIFICATION TIME: 16:27 [ET]| |RX TYPE: [1] GE-2,[2] GE-5 |EVENT DATE: 12/21/97 | +------------------------------------------------+EVENT TIME: 13:08[EST]| |NRC NOTIFIED BY: TOM RESTUCCIO |LAST UPDATE DATE: 12/21/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JAMES NOGGLE RDO | |AINB 50.72(b)(2)(iii)(B) POT RHR INOP | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 95 POWER OPERATION | 95 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - RCIC SYSTEM INOPERABLE DUE TO FAILING ITS IN-SERVICE TEST - | | | | DURING A TECH SPEC SURVEILLANCE TEST OF THE REACTOR CORE ISOLATION COOLING | | (RCIC) SYSTEM, THE RCIC PUMP FAILED TO MEET THE ESTABLISHED IN-SERVICE | | TEST DIFFERENTIAL PRESSURE ACCEPTANCE CRITERIA. BECAUSE OF THIS, THE | | LICENSEE DECLARED THE RCIC SYSTEM INOPERABLE, EVEN THOUGH IT IS FUNCTIONAL. | | THE HIGH PRESSURE CORE SPRAY SYSTEM IS OPERABLE. TECH SPEC LCO ACTION | | STATEMENT 3.7.4 REQUIRES THE LICENSEE TO RESTORE THE RCIC SYSTEM TO | | OPERABLE STATUS WITHIN 14 DAYS TO SHUT UNIT 2 DOWN. THE LICENSEE IS | | REVIEWING THE TEST DATA AND DETERMINING CORRECTIVE ACTIONS. | | | | THIS EVENT HAS NO EFFECT ON THE OPERATION OF UNIT 2 (95%) OR UNIT 1 (100%). | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33440 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DRESDEN REGION: 3 |NOTIFICATION DATE: 12/22/97 | |UNIT: [ ] [2] [ ] STATE: IL |NOTIFICATION TIME: 05:20 [ET]| |RX TYPE: [1] GE-1,[2] GE-3,[3] GE-3 |EVENT DATE: 12/22/97 | +------------------------------------------------+EVENT TIME: 03:03[CST]| |NRC NOTIFIED BY: KEITH POLSON |LAST UPDATE DATE: 12/22/97 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRUCE JORGENSEN RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 99 POWER OPERATION | 99 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ESF ACTUATION - HPCI ISOLATION DURING A ROUTINE SURVEILLANCE | | | | HPCI ISOLATED FOR UNKNOWN REASONS DURING THE PERFORMANCE OF THE HPCI LOW | | PRESSURE ISOLATION CHANNEL FUNCTIONAL TEST. INSTEAD OF RECEIVING THE | | EXPECTED HALF ISOLATION SIGNAL, A FULL ISOLATION SIGNAL WAS RECEIVED. THE | | HPCI SYSTEM HAS BEEN DECLARED INOPERABLE. A ROOT CAUSE INVESTIGATION HAS | | BEEN INITIATED. ALL OTHER SAFETY RELATED EQUIPMENT IS OPERABLE. | | | | THE NRC RESIDENT INSPECTOR WILL BE NOTIFIED. | +------------------------------------------------------------------------------+