U.S. Nuclear Regulatory Commission Operations Center Event Reports For 04/07/98 - 04/08/98 ** EVENT NUMBERS ** 33914 33945 34029 34030 34031 34032 34033 34034 34035 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33914 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MCGUIRE REGION: 2 |NOTIFICATION DATE: 03/18/98 | |UNIT: [1] [2] [ ] STATE: NC |NOTIFICATION TIME: 12:58 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 03/18/98 | +------------------------------------------------+EVENT TIME: 12:38[EST]| |NRC NOTIFIED BY: JOEL HOWARD |LAST UPDATE DATE: 04/07/98 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |THOMAS JOHNSON RDO | |AUNA 50.72(b)(1)(ii)(A) UNANALYZED COND OP | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | FAILURE TO PERFORM TECHNICAL SPECIFICATION LOGGING OF OPPOSITE UNIT | | AFFECTED SYSTEMS. | | | | THE FOLLOWING TEXT IS A PORTION OF A FACSIMILE RECEIVED FROM THE LICENSEE: | | | | "MCGUIRE NUCLEAR STATION HAS DETERMINED THAT PAST ELECTRICAL ALIGNMENT AND | | TECHNICAL SPECIFICATION LOGGING PRACTICES MAY HAVE CAUSED OPERATION IN AN | | UNANALYZED CONDITION. MCGUIRE NUCLEAR STATION HAS SHARED 600-VOLT BUSES | | THAT PROVIDE POWER TO SAFETY-RELATED COMPONENTS ASSOCIATED WITH SERVICE | | WATER, AUXILIARY BUILDING VENTILATION, AND CONTROL ROOM VENTILATION. TWO | | SHARED BUSES (1EMXH [AND] 1EMXG) ARE ALIGNED TO THE ESSENTIAL [4,160-VOLT] | | BUS (1ETA) POWERED BY THE 1A EMERGENCY DIESEL GENERATOR. THESE TWO BUSES | | SUPPLY UNIT 1 AND UNIT 2 'A' TRAIN COMPONENTS ASSOCIATED WITH THESE | | SYSTEMS. TWO SHARED BUSES (2EMXH [AND] 2EMXG) ARE ALIGNED TO THE ESSENTIAL | | [4,160-VOLT] BUS (2ETB) POWERED BY THE 2B EMERGENCY DIESEL GENERATOR. THESE | | TWO BUSES SUPPLY UNIT 1 AND UNIT 2 'B' TRAIN SAFETY-RELATED COMPONENTS | | ASSOCIATED WITH THESE SYSTEMS." | | | | "WHEN THE 1A EMERGENCY DIESEL GENERATOR HAD BEEN REMOVED FROM SERVICE, THE | | EMERGENCY AC POWER HAS BEEN LOGGED INOPERABLE FOR UNIT 1. HOWEVER, NO | | TECHNICAL SPECIFICATION LOGGING ENTRIES HAVE BEEN MADE FOR THE UNIT 2 | | SAFETY-RELATED COMPONENTS POWERED FROM [BUS] 1ETA. THESE COMPONENTS NO | | LONGER HAVE AN ALIGNED EMERGENCY AC POWER SOURCE. THEREFORE, CERTAIN 'B' | | TRAIN REDUNDANT COMPONENTS ON SAFETY-RELATED SYSTEMS COULD HAVE BEEN | | INOPERABLE. IN A SIMILAR MANNER, WHEN THE 2B EMERGENCY DIESEL GENERATOR | | HAS BEEN REMOVED FROM SERVICE, NO TECHNICAL SPECIFICATION LOGGING ENTRIES | | HAVE BEEN MADE TO TRACK UNIT 1 SAFETY-RELATED COMPONENTS WITHOUT ALIGNED | | EMERGENCY AC POWER." | | | | "THE STATION HAS ADMINISTRATIVE GUIDANCE IN PLACE TO REQUIRE TECHNICAL | | SPECIFICATION LOGGING OF OPPOSITE UNIT AFFECTED SYSTEMS AS DESCRIBED ABOVE. | | THIS PREVENTS ENTRY INTO THIS CONDITION IN THE FUTURE. SITE TECHNICAL | | STAFF WILL REVIEW THE AFFECT ON SAFETY SYSTEM OPERATION TO DETERMINE IF | | THE PLANT ACTUALLY OPERATED IN AN UNANALYZED CONDITION." | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | | | | * * * RETRACTION 1449 4/7/1998 FROM J. DIAL TAKEN BY STRANSKY * * * | | | | THE LICENSEE IS RETRACTING THIS NOTIFICATION. AFTER FURTHER RESEARCH AND A | | REVIEW OF EDG INOPERABILITY VERSUS INOPERABLE EQUIPMENT ON THE OTHER UNIT, | | THE LICENSEE HAS DETERMINED THAT THE PLANT WAS NOT OPERATED IN AN | | UNANALYZED CONDITION. THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED. | | NOTIFIED R2DO (SKINNER). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33945 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SAN ONOFRE REGION: 4 |NOTIFICATION DATE: 03/23/98 | |UNIT: [ ] [2] [3] STATE: CA |NOTIFICATION TIME: 17:37 [ET]| |RX TYPE: [1] W-3-LP,[2] CE,[3] CE |EVENT DATE: 03/23/98 | +------------------------------------------------+EVENT TIME: 13:45[PST]| |NRC NOTIFIED BY: G. L. PLUMLEE |LAST UPDATE DATE: 04/07/98 | |HQ OPS OFFICER: FANGIE JONES +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BILL JONES RDO | |DDDD 73.71 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | 3 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | PLANT SECURITY REPORT | | | | DISCOVERY OF A COMPROMISE OF CLASSIFIED SAFEGUARDS INFORMATION. IMMEDIATE | | COMPENSATORY MEASURES WERE TAKEN UPON DISCOVERY. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | | | | ***UPDATE ON 04/07/98 AT 1410 ET BY G.L. PLUMLEE TAKEN BY MACKINNON*** | | | | A TEAM WAS APPOINTED TO REVIEW THE DRAWINGS THAT WERE DECONTROLLED IN JULY | | 1995. A REVIEW OF THESE DRAWINGS DISCOVERED THAT APPROXIMATELY 32% OF THE | | DRAWINGS CONTAINED SOME SAFEGUARDS INFORMATION, ALBEIT OF LOW SAFEGUARDS | | VALUE. A SECOND INDEPENDENT TEAM WILL RE-REVIEW THOSE DECONTROLLED DRAWINGS | | THAT WERE NOT IDENTIFIED AS HAVING SAFEGUARDS INFORMATION BY THE FIRST | | REVIEW TEAM. THE LICENSEE INFORMED NRC REGION 4 BLAINE MURRAY AND BRUCE | | EARNEST OF THIS EVENT UPDATE. R4DO (CHUCK CAIN) NOTIFIED. | | | | THE NRC RESIDENT INSPECTOR WILL BE NOTIFIED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 34029 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 04/07/98 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 09:20 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 04/06/98 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 09:45[EDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 04/07/98 | | CITY: PIKETON REGION: 3 +-----------------------------+ | COUNTY: PIKE STATE: OH |PERSON ORGANIZATION| |LICENSE#: GDP-2 AGREEMENT: N |MARK RING RDO | | DOCKET: 0707002 |DON COOL, NMSS EO | +------------------------------------------------+ | |NRC NOTIFIED BY: ERIC SPAETH | | |HQ OPS OFFICER: JOHN MacKINNON | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NBNL RESPONSE-BULLETIN | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | NRC BULLETIN 91-01 RESPONSE (24- HOUR REPORT) | | | | OPERATIONS PERSONNEL DISCOVERED THAT A NUCLEAR CRITICALITY SAFETY APPROVAL | | (NCSA) REQUIREMENT WAS NOT BEING MAINTAINED WITHIN THE X-326 PROCESS | | BUILDING. EIGHT (8) CONTAMINATED ITEMS, EACH WRAPPED IN A PLASTIC BAG, WERE | | FOUND ON A CART WITH LESS THAN THE REQUIRED TWO FOOT EDGE-TO-EDGE SPACING | | SPECIFIED IN REQUIREMENT #6 OF NCSA PLANT062.A000. THIS CONSTITUTES A LOSS | | OF CONTROL "A" (INTERACTION/SPACING) IN THE DOUBLE CONTINGENCY MATRIX FOR | | CONTINGENCY EVENT B.17.1. CONTROL "B" (GEOMETRY) WAS MAINTAINED THROUGHOUT | | THIS EVENT. CONTROL "A" WAS RE-ESTABLISHED AT 1130 HOURS UNDER THE | | DIRECTION OF NUCLEAR CRITICALITY SAFETY (NCS) PERSONNEL. | | | | THERE WAS NO LOSS OF HAZARDOUS/RADIOACTIVE MATERIAL OR | | RADIOACTIVE/RADIOLOGICAL CONTAMINATION EXPOSURE AS A RESULT OF THIS EVENT. | | | | SAFETY SIGNIFICANCE OF EVENT: | | | | PIGTAILS ARE EVACUATED PRIOR TO REMOVING, THUS MASS OF U-235 IS EXPECTED TO | | BE MINIMAL. EIGHT CONTAMINATED LEGACY PIGTAILS MADE OF TYGON TUBING WERE | | FOUND. THE PIGTAILS WERE WRAPPED IN PLASTIC BAGS. BASED ON THE SMALL | | DIAMETER (< 6 INCHES) THE PIGTAILS WERE IN SAFE GEOMETRY. IN ADDITION, THE | | PLASTIC BAGS PREVENT ADDITION OF MODERATION TO THE PIGTAILS. THUS, THE | | SAFETY SIGNIFICANCE IS LOW. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY PORTSMOUTH PERSONNEL. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34030 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOK REGION: 3 |NOTIFICATION DATE: 04/07/98 | |UNIT: [1] [2] [ ] STATE: MI |NOTIFICATION TIME: 12:06 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 04/07/98 | +------------------------------------------------+EVENT TIME: 08:30[EDT]| |NRC NOTIFIED BY: RANDY PTACEK |LAST UPDATE DATE: 04/07/98 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MARK RING 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 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | HYDROGEN RECOMBINERS DECLARED INOPERABLE DUE TO INCORRECTLY CALIBRATED | | TEMPERATURE INDICATION. | | | | DURING RESEARCH INTO INSTRUMENTATION UNCERTAINTY CALCULATIONS, THE LICENSEE | | DISCOVERED THAT THE TECHNICAL SPECIFICATION CHANNEL CALIBRATION | | SURVEILLANCE PROCEDURE FOR THE HYDROGEN RECOMBINER TEMPERATURE MEASUREMENT | | CIRCUITRY WAS INADEQUATE. THE PROCEDURE DIRECTS THE TECHNICIAN TO CALIBRATE | | THE CONTROL ROOM INDICATION; HOWEVER, IT SHOULD DIRECT THE TECHNICIAN TO | | CALIBRATE THE ENTIRE INSTRUMENT LOOP FROM THE SENSING DEVICE TO THE CONTROL | | ROOM INDICATION. THE LICENSEE REPORTED THAT THIS CONDITION HAS EXISTED | | SINCE THE UNITS BEGAN COMMERCIAL OPERATION. | | | | THE LICENSEE HAS DECLARED ALL HYDROGEN RECOMBINERS INOPERABLE BECAUSE | | RECOMBINER TEMPERATURE IS USED TO DETERMINE THE OPERABILITY OF THE | | RECOMBINERS IN ACCORDANCE WITH TECHNICAL SPECIFICATIONS. THE ENGINEERING | | AND MAINTENANCE DEPARTMENTS ARE EVALUATING THIS CONDITION TO DETERMINE | | APPROPRIATE ACTIONS TO RESTORE THE RECOMBINERS. THE NRC RESIDENT INSPECTOR | | HAS BEEN INFORMED. | | | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34031 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BROWNS FERRY REGION: 2 |NOTIFICATION DATE: 04/07/98 | |UNIT: [ ] [ ] [3] STATE: AL |NOTIFICATION TIME: 13:12 [ET]| |RX TYPE: [1] GE-4,[2] GE-4,[3] GE-4 |EVENT DATE: 04/07/98 | +------------------------------------------------+EVENT TIME: 11:16[CDT]| |NRC NOTIFIED BY: R SWAFFORD |LAST UPDATE DATE: 04/07/98 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PIERCE SKINNER RDO | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | | |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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | | | | | 3 | M/R Y 100 POWER OPERATION | 0 HOT SHUTDOWN | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | MANUAL SCRAM DUE TO ENTERING INSTABILITY REGION 1 OF THE POWER TO FLOW MAP. | | | | ENGINEERS WERE IN PANEL 9-18 (LOGIC PANEL FOR RECIRCULATION PUMPS A & B) | | WHEN A METAL RULER THAT THEY WERE USING APPARENTLY TOUCHED SOME CONTACTS | | INSIDE THE PANEL, CAUSING THE RECIRCULATION PUMPS TO RUNBACK. OPERATORS | | MANUALLY SCRAMMED THE PLANT PER TECHNICAL SPECIFICATION 3.5.M.2 AFTER THEY | | VERIFIED THAT THE UNIT HAD ENTERED INSTABILITY REGION 1 OF THE POWER TO | | FLOW MAP. ALL CONTROL RODS FULLY INSERTED INTO THE CORE. REACTOR VESSEL | | WATER LEVEL DECREASED FROM +33 INCHES TO JUST BELOW +11.2", CAUSING A | | PRIMARY CONTAINMENT ISOLATION SIGNAL. THE PRIMARY CONTAINMENT ISOLATION | | SIGNAL CAUSED THE FOLLOWING ISOLATIONS: GROUP 2 (RAD WASTE), GROUP 3 | | (REACTOR WATER CLEANUP), GROUP 6 (REACTOR BUILDING VENTILATION) AND GROUP 8 | | (TRANSVERSING INCORE PROBE). | | | | ALL EMERGENCY CORE COOLING SYSTEMS AND THE EMERGENCY DIESEL GENERATORS ARE | | FULLY OPERABLE IF NEEDED. THE LICENSEE STATED THAT THEIR ELECTRICAL GRID | | IS STABLE. THE LICENSEE SAID THAT THEY ARE PLANNING TO GO TO A COLD | | SHUTDOWN CONDITION TO DO SOME PLANNED MAINTENANCE. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34032 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DAVIS BESSE REGION: 3 |NOTIFICATION DATE: 04/07/98 | |UNIT: [1] [ ] [ ] STATE: OH |NOTIFICATION TIME: 18:55 [ET]| |RX TYPE: [1] B&W-R-LP |EVENT DATE: 04/07/98 | +------------------------------------------------+EVENT TIME: 14:14[EDT]| |NRC NOTIFIED BY: CRAIG GILLIG |LAST UPDATE DATE: 04/07/98 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MARK RING RDO | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 74 POWER OPERATION | 74 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ENTERED/EXITED TECHNICAL SPECIFICATION REQUIRED SHUTDOWN ACTION STATEMENT | | DUE TO INOPERABLE MAIN STEAM SAFETY VALVE. | | | | WHILE PERFORMING SETPOINT TESTING OF MAIN STEAM SAFETY VALVES, THE SETPOINT | | FOR VALVE SP17B3 WAS FOUND TO BE OUT OF TOLERANCE AND THE VALVE WAS | | DECLARED INOPERABLE. THE VALVE WAS SUBSEQUENTLY ADJUSTED AND DECLARED | | OPERABLE. HOWEVER, POST-TEST CALIBRATION OF THE PRESSURE GAUGE USED FOR THE | | TEST WAS UNSATISFACTORY, AND THE VALVE WAS AGAIN DECLARED INOPERABLE. | | | | TECHNICAL SPECIFICATION 3.7.1.1 REQUIRES THAT THE VALVE BE RESTORED OR THE | | HIGH NEUTRON FLUX TRIP SETPOINTS BE REDUCED WITHIN FOUR HOURS. DUE TO THE | | PROBLEM WITH THE PRESSURE GAUGE, THE LICENSEE ASSUMED THAT THE VALVE WAS | | INOPERABLE AS OF 1414 (THE TIME OF INITIAL INOPERABILITY); THEREFORE THE | | FOUR HOUR REQUIREMENTS WERE NOT MET. IN THIS CASE, TECHNICAL SPECIFICATIONS | | REQUIRE THAT THE UNIT BE PLACED IN HOT STANDBY WITHIN THE FOLLOWING SIX | | HOURS. THE LICENSEE REPORTED THAT THE HIGH NEUTRON FLUX TRIP SETPOINTS WERE | | READJUSTED APPROXIMATELY 14 MINUTES AFTER EXPIRATION OF THE INITIAL FOUR | | HOUR TIME LIMIT, PERMITTING THE UNIT TO EXIT THE SHUTDOWN REQUIREMENT. | | | | THE NRC RESIDENT INSPECTOR WILL BE INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34033 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: ARKANSAS NUCLEAR REGION: 4 |NOTIFICATION DATE: 04/07/98 | |UNIT: [1] [ ] [ ] STATE: AR |NOTIFICATION TIME: 19:42 [ET]| |RX TYPE: [1] B&W-L-LP,[2] CE |EVENT DATE: 04/07/98 | +------------------------------------------------+EVENT TIME: 17:50[CDT]| |NRC NOTIFIED BY: HAROLD WILLIAMS |LAST UPDATE DATE: 04/07/98 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CHARLES CAIN RDO | |DDDD 73.71 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | SECURITY EVENT INVOLVING POTENTIAL TAMPERING WITH NONSAFETY EQUIPMENT. | | IMMEDIATE COMPENSATORY MEASURES TAKEN UPON DISCOVERY. REFER TO THE HOO LOG | | FOR ADDITIONAL DETAILS. THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 34034 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 04/08/98 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 00:52 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 04/07/98 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 01:00[CDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 04/08/98 | | CITY: PADUCAH REGION: 3 +-----------------------------+ | COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION| |LICENSE#: GDP-1 AGREEMENT: Y |MARK RING RDO | | DOCKET: 0707001 |LARRY CAMPER EO | +------------------------------------------------+JOSEPH GIITTER IRD | |NRC NOTIFIED BY: HALICKS | | |HQ OPS OFFICER: CHAUNCEY GOULD | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |OCBA 76.120(c)(2)(i) ACCID MT EQUIP FAILS | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | CRITICALITY ACCIDENT ALARM SYSTEM(CAAS) IN THE "C-720" FACILITY INOPERABLE | | | | IT WAS DISCOVERED THAT THE CAAS IN THE "C-720" FACILITY WAS NOT ABLE TO | | PROVIDE THE REQUIRED ALARMS IN THE "C-300" CENTRAL CONTROL FACILITY(CCF). | | DURING PERFORMANCE OF THE QUARTERLY TSR-REQUIRED SURVEILLANCE, THE CAAS | | CLUSTER BEING TESTED FAILED TO GIVE THE 10mR LIGHT ON THE ALARM CONSOLE IN | | THE CCF WHICH SHOWS ACTIVATION OF THE CLUSTER. THE ALARM HORNS AND LIGHTS | | IN THE CAAS-ALARMED AREA FUNCTIONED AS REQUIRED. | | | | UNDER THE PLAN WHICH WAS DEVELOPED TO BRING THE PLANT INTO COMPLIANCE WITH | | NRC REGULATIONS, ISSUE NO.50 ADDRESSES UNALARMED BUILDINGS WITHIN THE | | EVACUATION AREA OF CAAS-ALARMED FACILITIES. PERSONNEL ENTERING THOSE | | FACILITIES ARE REQUIRED TO CARRY A RADIO CAPABLE OF RECEIVING EMERGENCY | | ANNOUNCEMENTS. IN THE EVENT OF A CAAS ACTIVATION, THE OPERATOR IN THE CCF | | USES THE 10mR LIGHT AS VERIFICATION OF THE POSSIBLE OCCURRENCE OF A | | CRITICALITY AND MAKES AN ANNOUNCEMENT REGARDING THE ALARM OVER THE PLANT | | "ALL CALL" PUBLIC ADDRESS SYSTEM. THIS ALERTS PERSONNEL IN UNALARMED | | BUILDINGS WITHIN THE EVACUATION ZONE OF THE FACILITY IN ALARM TO EVACUATE | | TO THEIR ASSEMBLY POINT. DURING TROUBLESHOOTING OF THE PROBLEM WITH THE | | 10mR LIGHT, IT WAS DETERMINED THAT THIS CONDITION EXISTED PRIOR TO THE | | PERFORMANCE OF THE TEST AND WHILE THE CAAS WAS CONSIDERED OPERABLE. | | | | THE RESIDENT INSPECTOR WAS NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34035 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DUANE ARNOLD REGION: 3 |NOTIFICATION DATE: 04/08/98 | |UNIT: [1] [ ] [ ] STATE: IA |NOTIFICATION TIME: 05:23 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 04/08/98 | +------------------------------------------------+EVENT TIME: 02:06[CDT]| |NRC NOTIFIED BY: STEIMER |LAST UPDATE DATE: 04/08/98 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MARK RING RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | A PRESSURE DISCHARGE TO THE SUPPRESSION POOL OCCURRED WHILE TWO | | SURVEILLANCES WERE BEING PERFORMED CONCURRENTLY. | | | | WHILE THE PLANT WAS IN DAY 4 OF REFUEL OUTAGE 15 WITH CORE ALTERATIONS IN | | PROGRESS, LOCAL LEAK RATE TESTING(LLRT) WAS IN PROGRESS ON THE "A" INBOARD | | MAIN STEAM ISOLATION VALVE(MSIV) WITH APPROXIMATELY 40 PSIG OF AIR PRESSURE | | BETWEEN THE "A" INBOARD MSIV AND THE "A" MAIN STREAM LINE PLUG AT THE | | REACTOR VESSEL. SURVEILLANCE TESTING OF THE AUTOMATIC DEPRESSURIZATION | | SYSTEM(ADS) TIMER CALIBRATION AND LOGIC SYSTEM FUNCTIONAL WAS BEING | | PERFORMED CONCURRENTLY WITH THE LLRT. THE SURVEILLANCE TEST ACTUATES THE | | PILOT SOLENOIDS TO THE 4 ADS SAFETY RELIEF VALVES(SRVs) WHICH PROVIDES THE | | PNEUMATIC PRESSURE TO OPEN THEM. WHEN THIS OCCURRED, THE PRESSURE THAT WAS | | ESTABLISHED IN THE "A" MAIN STEAM LINE DISCHARGED TO THE SUPPRESSION POOL. | | THE DEPRESSURIZATION WAS CONFIRMED BY PERSONNEL PERFORMING THE LLRT AND THE | | SUPPRESSION POOL LEVEL RECORDERS. THE ADS LOGIC TEST WAS SUSPENDED UNTIL | | THE "A" MAIN STEAM LINE WAS COMPLETELY DEPRESSURIZED. | | | | THE RESIDENT INSPECTOR WAS NOTIFIED. | +------------------------------------------------------------------------------+