U.S. Nuclear Regulatory Commission Operations Center Event Reports For 06/04/98 - 06/05/98 ** EVENT NUMBERS ** 34331 34333 34335 34337 34340 34341 34342 34343 34344 34345 34346 34347 34348 34349 34350 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34331 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MCGUIRE REGION: 2 |NOTIFICATION DATE: 06/03/98 | |UNIT: [1] [ ] [ ] STATE: NC |NOTIFICATION TIME: 11:09 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 06/03/98 | +------------------------------------------------+EVENT TIME: 10:00[EDT]| |NRC NOTIFIED BY: DAVID MILLER |LAST UPDATE DATE: 06/04/98 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CHRIS CHRISTENSEN 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 | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | A MAIN FEEDWATER ISOLATION VALVE FAILED ITS STROKE TIME TEST REQUIREMENT. | | | | THE FOLLOWING TEXT IS A PORTION OF A FACSIMILE RECEIVED FROM THE LICENSEE: | | | | "DURING THE UNIT SHUTDOWN PROCESS FOR A SCHEDULED REFUELING OUTAGE, MCGUIRE | | TESTED MAIN FEEDWATER ISOLATION VALVES 'AS FOUND.' ONE OF THE FOUR (4) | | VALVES (1CF-30) FAILED ITS VALVE STROKE TIME REQUIREMENTS. MCGUIRE | | IMMEDIATELY INITIATED FURTHER TESTING AND ANALYSIS TO DETERMINE WHETHER THE | | VALVE WOULD HAVE PERFORMED ITS FUNCTION DURING UNIT OPERATION. DURING | | VALVE DISASSEMBLY, THE ACTUATOR INTERNALS WERE FOUND TO HAVE BEEN INSTALLED | | INCORRECTLY. UPON REVIEW OF THE AVAILABLE TEST INFORMATION, MCGUIRE HAS | | DETERMINED THAT THERE MAY HAVE BEEN PERIODS OF TIME WHEN [VALVE] 1CF-30 MAY | | NOT HAVE STROKED CLOSED WITHIN THE REQUIRED TIME. THE REMAINING VALVES ON | | UNIT 1 HAVE BEEN CONFIRMED TO BE PROPERLY ASSEMBLED AND WERE STROKE TESTED | | WITHIN THE REQUIRED TIME FRAME. MCGUIRE IS CONTINUING TO INVESTIGATE | | WHETHER [VALVE] 1CF-30 WOULD ACTUALLY HAVE SUCCESSFULLY PERFORMED ITS | | REQUIRED FUNCTION DURING UNIT OPERATION AND WHETHER UNIT 2 IS AFFECTED. | | FURTHER INFORMATION WILL BE PROVIDED WHEN AVAILABLE." | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE AT 1625 EDT ON 06/04/98 FROM JIMMY DIAL TO S.SANDIN * * * | | | | THE FOLLOWING INFORMATION WAS PROVIDED VIA FACSIMILE AS AN UPDATE: | | | | "FURTHER INVESTIGATION HAS REVEALED THAT [VALVE] '1CF-30AB' ('B' [STEAM | | GENERATOR] CF CONTAINMENT OUTSIDE ISOLATION) MAY HAVE BEEN INOPERABLE | | DURING THE ENTIRE UNIT 1 CYCLE 12. UNTIL FURTHER CALCULATIONS HAVE BEEN | | PERFORMED WHICH MAY PROVE OTHERWISE, IT IS FELT THAT WITH THE IMPROPERLY | | INSTALLED ACTUATOR, [VALVE] '1CF-30' MAY NOT HAVE PERFORMED ITS DESIGN | | FUNCTION DURING A DESIGN BASIS ACCIDENT." | | | | "DURING UNIT 1 CYCLE 12, TWO FEEDWATER ISOLATIONS OCCURRED. DATA COLLECTED | | FROM THESE FEEDWATER ISOLATIONS SHOWED THAT [VALVE] '1CF-30' DID PASS THE | | REQUIRED TECHNICAL SPECIFICATIONS STROKE TIME." | | | | "ALL FOUR UNIT 1 CONTAINMENT ISOLATION VALVE ACTUATORS ARE CURRENTLY BEING | | REPLACED WITH PNEUMATIC ACTUATORS." | | | | "UPDATE ON THE STATUS OF UNIT 2 CF CONTAINMENT ISOLATION VALVES[:]" | | | | "MCGUIRE IS CURRENTLY PERFORMING PARTIAL RADIOGRAPH INSPECTION OF THE UNIT | | 2 VALVES TO VERIFY PROPER ACTUATOR ORIENTATION. THE MAIN EMPHASIS WILL BE | | ON [VALVE] '2CF-28,' WHICH IS THE ONLY VALVE WITH MAJOR MAINTENANCE | | PERFORMED ON IT DURING THE PREVIOUS OUTAGE." | | | | THE R2DO (CHRISTENSEN) WAS INFORMED OF THIS UPDATE BY THE NRC OPERATIONS | | OFFICER. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34333 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: LIMERICK REGION: 1 |NOTIFICATION DATE: 06/03/98 | |UNIT: [ ] [2] [ ] STATE: PA |NOTIFICATION TIME: 11:59 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 06/03/98 | +------------------------------------------------+EVENT TIME: 09:14[EDT]| |NRC NOTIFIED BY: PEAKS |LAST UPDATE DATE: 06/05/98 | |HQ OPS OFFICER: HENRY BAILEY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LAURIE PELUSO 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 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | REACTOR WATER CLEANUP ISOLATION DUE TO INADVERTENT STANDBY LIQUID CONTROL | | PUMP INITIATION AND INJECTION INTO THE REACTOR VESSEL | | | | AT 0914, THE UNIT 2 REACTOR WATER CLEANUP SYSTEM ISOLATED DUE TO THE | | INADVERTENT INITIATION OF THE '2C' STANDBY LIQUID CONTROL PUMP AND | | INJECTION INTO THE REACTOR PRESSURE VESSEL. AT 0920, THE '2C' STANDBY | | LIQUID CONTROL PUMP (A POSITIVE DISPLACEMENT PUMP) WAS SECURED. THE | | APPROXIMATE AMOUNT OF WATER INJECTED WAS BETWEEN 300 AND 350 GALLONS, AND | | THE FINAL VESSEL WATER LEVEL WAS 91 INCHES. | | | | THE CAUSE FOR THE STANDBY LIQUID CONTROL SYSTEM INITIATION IS UNKNOWN AND | | IS CURRENTLY UNDER INVESTIGATION. PRIOR TO THE INCIDENT, UNIT 2 WAS SHUT | | DOWN IN OPERATIONAL CONDITION 4 (COLD SHUTDOWN) WITH THE UNIT DEPRESSURIZED | | AND REACTOR VESSEL LEVEL AT 88 INCHES. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED BY THE LICENSEE. | | | | * * * UPDATE AT 1814 ON 06/03/98 FROM SCHIENDELMAN RECEIVED BY GOULD * * * | | | | THE LICENSEE HAS FORMED AN INVESTIGATION TEAM TO REVIEW THE INADVERTENT | | INITIATION OF THE '2C' STANDBY LIQUID CONTROL PUMP AND TO ACCOMPLISH THE | | FOLLOWING ACTIVITIES: | | | | 1. DETERMINE THE CAUSE OF THE INADVERTENT INJECTION AND CORRECTIVE | | ACTIONS TO PREVENT RECURRENCE, | | | | 2. DEVELOP THE PLAN FOR CLEANUP OF THE REACTOR WATER, AND | | | | 3. PERFORM AN ASSESSMENT OF THE IMPACT ON SYSTEMS AND COMPONENTS | | INCLUDING THE REACTOR VESSEL AND INTERNALS, CARBON-STEEL COMPONENTS, | | AND FUEL. | | | | THE LICENSEE STATED THAT THE REACTOR WATER CHEMISTRY PARAMETERS AT 1435 ON | | 06/03/98 WERE THE FOLLOWING: | | | | CONDUCTIVITY - 75 æMHO/CM | | | | pH READINGS - 8.49 | | | | BORON CONCENTRATION - 54.7 PPM | | | | CLEANUP OF THE REACTOR WATER HAS COMMENCED. | | | | THE NRC RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE. THE R1DO (PELUSO) | | WAS NOTIFIED BY THE NRC OPERATIONS OFFICER. | | | | * * * UPDATE AT 0814 ON 06/04/98 FROM CARL RICH RECEIVED BY TROCINE * * * | | | | THE LICENSEE REPORTED THAT THE UNIT 2 REACTOR WATER CHEMISTRY IS STEADILY | | IMPROVING AS THE CLEANUP PROCESS CONTINUES. AS OF 0547 ON 06/04/98, | | REACTOR WATER CONDUCTIVITY WAS 40.15 æMHO/CM, AND REACTOR WATER pH WAS | | 7.97. | | | | THE CLEANUP PROCESS INVOLVES CHANGING OUT THE WATER IN THE REACTOR VESSEL | | (BASICALLY FEEDING AND BLEEDING). THE LICENSEE IS UTILIZING THE REACTOR | | WATER CLEANUP SYSTEM TO CONTINUOUSLY DILUTE 130-135 GALLONS PER MINUTE, AND | | IT IS ESTIMATED THAT IT WILL TAKE ANOTHER 48 HOURS FOR THIS CLEANUP PROCESS | | TO BE COMPLETED. | | | | THE EVENT INVESTIGATION TEAM IS CONTINUING TO INVESTIGATE THE CAUSE OF THE | | INADVERTENT STANDBY LIQUID INITIATION AND TO DEVELOP CORRECTIVE ACTIONS TO | | PREVENT RECURRENCE. THE TEAM IS ALSO ASSESSING THE IMPACT ON SYSTEMS AND | | COMPONENTS INCLUDING THE REACTOR VESSEL AND INTERNALS, CARBON-STEEL | | COMPONENTS, AND FUEL. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR OF THIS UPDATE. THE NRC | | OPERATIONS OFFICES NOTIFIED THE R1DO (PELUSO). | | | | * * * UPDATE AT 0910 ON 06/04/98 FROM CARL RICH RECEIVED BY TROCINE * * * | | | | AS OF 0845 ON 06/04/98, REACTOR WATER CONDUCTIVITY WAS 33.6 æMHO/CM, pH WAS | | 7.97, AND BORON CONCENTRATION WAS 24 PPM. | | | | THE NRC OPERATIONS OFFICER NOTIFIED THE R1DO (PELUSO). | | | | * * * UPDATE AT 1820 ON 06/04/98 FROM CARL RICH TO S.SANDIN * * * | | | | UNIT 2 REACTOR WATER CHEMISTRY IS STEADILY IMPROVING AS CLEANUP CONTINUES. | | AS OF 1540 ON 06/04/98, REACTOR WATER CONDUCTIVITY WAS 20.4 æMHO/CM, | | REACTOR WATER pH WAS 7.96, AND BORON CONCENTRATION WAS 12.8 PPM. | | | | THE EVENT INVESTIGATION TEAM IS CONTINUING TO INVESTIGATE THE CAUSE OF THE | | INADVERTENT STANDBY LIQUID INITIATION. GENERAL ELECTRIC AND SYSTEM EXPERTS | | WILL BE ONSITE ON 06/05/98 TO SUPPORT THIS EFFORT. THE TEAM IS ALSO | | ASSESSING THE IMPACT ON SYSTEMS AND COMPONENTS. | | | | THE LICENSEE PLANS TO INFORM THE NRC RESIDENT INSPECTOR. THE NRC | | OPERATIONS OFFICER NOTIFIED THE R1DO (PELUSO). | | | | * * * UPDATE AT 0631 ON 06/05/98 FROM JEFF KLENK RECEIVED BY TROCINE * * * | | | | UNIT 2 REACTOR WATER CHEMISTRY CONTINUES TO IMPROVE, AND CLEANUP IS | | CONTINUING. AS OF 0500 HOURS ON 06/05/98, REACTOR WATER CONDUCTIVITY WAS | | 9.6 æMHOS/CM, REACTOR WATER pH WAS 7.93, AND BORON LEVEL WAS 5.25 PPM. | | | | THE EVENT INVESTIGATION TEAM CONTINUES TO INVESTIGATE THE CAUSE OF THE '2C' | | STANDBY LIQUID CONTROL PUMP INITIATION AND TO DEVELOP CORRECTIVE ACTIONS TO | | PREVENT RECURRENCE. THE INITIATION RELAYS ASSOCIATED WITH THE '2C' STANDBY | | LIQUID CONTROL PUMP HAVE BEEN REMOVED FOR ANALYSIS. AN ELECTRONICS EXPERT | | FROM GENERAL ELECTRIC IS SCHEDULED TO BE ON SITE THIS MORNING TO AID IN THE | | INVESTIGATION. THE IMPACT ON SYSTEMS AND COMPONENTS IS STILL BEING | | ASSESSED. | | | | THE LICENSEE PLANS TO NOTIFY THE NRC RESIDENT INSPECTOR. THE NRC | | OPERATIONS OFFICER NOTIFIED THE R1DO (PELUSO). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 34335 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: U.S. NAVY RAD. SAFETY COMMITTEE |NOTIFICATION DATE: 06/03/98 | | CITY: ARLINGTON REGION: 2 |NOTIFICATION TIME: 16:24 [ET]| | COUNTY: STATE: VA |EVENT DATE: 06/02/98 | |LICENSE#: 4523645-01NA AGREEMENT: N |EVENT TIME: 15:00[EDT]| | DOCKET: |LAST UPDATE DATE: 06/04/98 | | +-----------------------------+ | |PERSON ORGANIZATION| | |BRUCE JORGENSEN/REG3 RDO | | |FRED COMBS/NMSS EO | +------------------------------------------------+JARVELA EPA | |NRC NOTIFIED BY: FARRAND |CHUCK HOSEY REG2 | |HQ OPS OFFICER: CHAUNCEY GOULD | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | A NAVY ACTIVITY IN VIRGINIA HAD RECEIVED A SHIPMENT OF 38 NEW COOKING POTS | | FROM ATLANTIC EQUIPMENT COMPANY (A KITCHEN EQUIPMENT SUPPLIER) THAT APPEAR | | TO BE CONTAMINATED. | | | | THE CONTAMINATED POTS WERE FROM LOT #M43 WHICH WAS FABRICATED DURING | | OCTOBER 1997. THE NAME OF THE POT MANUFACTURER WHO SUPPLIED ATLANTIC | | EQUIPMENT COMPANY IS BOLIATH (LOCATED IN WISCONSIN). THE ISOTOPE IN THE | | POT MATERIAL, DETERMINED FROM A SURVEY, WAS COBALT-60 ON THE ORDER OF 0.002 | | MICROCURIES/POT. WITH EACH POT WEIGHING ABOUT 10 POUNDS, THAT COMES OUT TO | | BE ABOUT 1 PICOCURIE/GRAM. ONLY THE POTS WITH THE #M43 LOT NUMBER HAD | | INDICATIONS OF COBALT-60. BOLIATH OBTAINED THE STEEL FOR THESE POTS FROM | | ALLEGHENY STEEL COMPANY. THE POTS WERE MADE WITH THREE LAYERS OF MATERIAL; | | WITH THE OUTSIDE AND INSIDE SURFACES MADE FROM STAINLESS STEEL AND THE | | INNER LAYER MADE FROM CARBON STEEL. IT HAS BEEN DETERMINED THAT THE CARBON | | STEEL MAY BE THE SOURCE OF THE CONTAMINATION. BOLIATH HAS REQUESTED THE | | ASSISTANCE OF A METALLURGIST FROM ALLEGHENY STEEL COMPANY. THE NAVY HAS | | THE POTS IN STORAGE AND PLANS TO RETURN THEM TO BOLIATH. | | | | * * * UPDATE AT 2359 ON 06/04/98 BY TROCINE * * * | | | | A COMMISSIONERS' ASSISTANTS BRIEFING WAS CONDUCTED AT 1430 ON 06/04/98, AND | | THE FOLLOWING NOTIFICATIONS WERE MADE (* OFFICE DID NOT PARTICIPATE): AEOD | | (*CONGEL AND *MARTIN), IRD (HOGAN AND MOHSENI), JACKSON (SMITH), DICUS | | (LUBENAU), DIAZ (CASTLEMAN), McGAFFIGAN (SCHLUETER), EDO (*THOMA AND | | *TRACY), DEDE (MITCHELL), NMSS EO (*COMBS), NMSS (KNAPP AND SMITH), R2DO | | (*CHRISTENSEN), REGION 1 (PANGBURN), REGION 2 (KUZO), REGION 3 (PETERSON), | | PAO (GAGNER AND HAYDEN), CAO (COMBS), SECY (*HART), SP (SOLLENBERGER), IP | | (*), BRIEFER (HOSEY), AND EPA (STUDEVILLE). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34337 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MCGUIRE REGION: 2 |NOTIFICATION DATE: 06/03/98 | |UNIT: [ ] [2] [ ] STATE: NC |NOTIFICATION TIME: 16:44 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 06/03/98 | +------------------------------------------------+EVENT TIME: 16:00[EDT]| |NRC NOTIFIED BY: DENNIS McCORKLE |LAST UPDATE DATE: 06/04/98 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CHRIS CHRISTENSEN RDO | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS |JOHN ZWOLINSKI, NRR EO | |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 +------------------------------------------------------------------------------+ | DISCOVERY THAT THE VALVE SEAT ON ONE CYLINDER OF THE #2A EMERGENCY DIESEL | | GENERATOR (EDG) HAD DROPPED OUT OF ITS NORMAL POSITION | | | | UNIT 2 WAS AT 100% POWER WITH ONE OF TWO EDGs (THE #2A) INOPERABLE FOR | | MAINTENANCE ACTIVITIES. WHILE REMOVING THE HEAD FROM #2A EDG, THE LICENSEE | | DISCOVERED THAT THE VALVE SEAT ON ONE CYLINDER HAD DROPPED OUT OF ITS | | NORMAL POSITION. | | | | UNIT 2 ENTERED A 72-HOUR TECHNICAL SPECIFICATION LIMITING CONDITION FOR | | OPERATION ACTION STATEMENT AT 1732 ON 06/02/98. THE #2A EDG WAS LAST RUN | | SUCCESSFULLY ON 05/12/98. | | | | THE LICENSEE IS INVESTIGATING THIS CONDITION TO DETERMINE WHETHER THE #2A | | EDG WOULD HAVE PERFORMED ITS REQUIRED SAFETY FUNCTION AND TO DETERMINE | | CORRECTIVE ACTION. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE AT 1625 EDT ON 06/04/98 FROM JIMMY DIAL TO S.SANDIN * * * | | | | THE FOLLOWING INFORMATION WAS PROVIDED VIA FACSIMILE AS AN UPDATE: | | | | "A RUN FOR PREPARATION TO RETURN TO SERVICE WAS COMPLETED ON [THE] #2A | | [EDG] AT APPROXIMATELY 0930 ON 06/04/98. [THE] #2A EDG SUCCESSFULLY RAN AT | | LOAD FOR THE TEST, BUT [IT] HAD UNACCEPTABLE ENGINE DIAGNOSTICS DATA. | | TROUBLESHOOTING REVEALED AN INTAKE VALVE SPRING ON CYLINDER '4L' HAD | | FAILED. THIS INFORMATION IS BEING INCORPORATED INTO THE ROOT CAUSE | | INVESTIGATION." | | | | "THE #2A EDG REMAINS IN THE 72-HOUR TECHNICAL SPECIFICATION LIMITED | | CONDITION FOR OPERATION ACTION STATEMENT DECLARED AT 1732 ON 06/02/98." | | | | "THE #2B EDG IS CONSIDERED OPERABLE WITH A SUCCESSFUL SURVEILLANCE RUN AND | | DIAGNOSTICS." | | | | THE R2D0 (CHRISTENSEN) WAS INFORMED OF THIS UPDATE BY THE NRC OPERATIONS | | OFFICER. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 34340 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 06/04/98 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 03:13 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 06/04/98 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 02:20[EDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 06/04/98 | | CITY: PIKETON REGION: 3 +-----------------------------+ | COUNTY: PIKE STATE: OH |PERSON ORGANIZATION| |LICENSE#: GDP-2 AGREEMENT: N |BRUCE JORGENSEN RDO | | DOCKET: 0707002 |JOHN HICKEY, NMSS EO | +------------------------------------------------+FRANK CONGEL, AEOD IRD | |NRC NOTIFIED BY: GREG BARCH | | |HQ OPS OFFICER: LEIGH TROCINE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |PAAA 95.57(b) LOSS OF CLASSIFIED INFO | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | POTENTIAL COMPROMISE OF CLASSIFIED INFORMATION DUE TO AN UNSECURED | | CLASSIFIED REPOSITORY (1-HOUR REPORT) | | | | THE FOLLOWING TEXT IS A PORTION OF A FACSIMILE RECEIVED FROM PORTSMOUTH: | | | | "WHILE CONDUCTING ROUTINE SECURITY CHECKS IN THE X-100 FACILITY, PROTECTIVE | | FORCES PERSONNEL DISCOVERED AN UNSECURED CLASSIFIED REPOSITORY IN THE | | OFFICE AREA. THIS DISCOVERY WAS MADE AT 0220 HOURS ON THURSDAY, JUNE 4, | | 1998, AND [THE DISCOVERY] WAS IMMEDIATELY REPORTED TO THE PROTECTIVE FORCES | | SHIFT COMMANDER WHO THEN REPORTED THE INCIDENT TO THE ON-DUTY PLANT SHIFT | | SUPERINTENDENT. THE CUSTODIAN OF THE CLASSIFIED REPOSITORY WAS NOTIFIED, | | AND THE CONTENTS OF THE REPOSITORY WILL BE INVENTORIED. LEAVING A | | CLASSIFIED REPOSITORY UNSECURED CONSTITUTES A SECURITY INFRACTION AT THE | | PORTSMOUTH GASEOUS DIFFUSION PLANT." IT WAS ALSO REPORTED THAT THE | | CUSTODIAN IS CURRENTLY EN ROUTE TO THE SITE TO INVENTORY THE CONTENTS OF | | THE REPOSITORY. | | | | PORTSMOUTH PERSONNEL NOTIFIED THE NRC RESIDENT INSPECTOR AND PLAN TO NOTIFY | | THE DEPARTMENT OF ENERGY SITE REPRESENTATIVE. | | | | * * * UPDATE AT 1200 ON 06/04/97 BY TROCINE * * * | | | | THE NRC OPERATIONS OFFICE CALLED THE SITE (DICK BRINK) TO CLARIFY THE | | INITIAL REPORTING REQUIREMENT OF 'OTHER NON-CFR REQUIREMENT.' THIS REPORT | | WAS ACTUALLY MADE IN ACCORDANCE WITH PROCEDURE UE2-RA-RE1030, APPENDIX 'D,' | | SECTION 'L,' ITEM 2, WHICH REQUIRES PORTSMOUTH PERSONNEL TO REPORT ACTIONS | | TAKEN WHEN AN UNATTENDED SECURITY CONTAINER HAVING CLASSIFIED MATTER IS | | FOUND UNLOCKED {10 CFR 95.25} AND IN ACCORDANCE WITH ITEM 4 WHICH REQUIRES | | PORTSMOUTH PERSONNEL TO REPORT ANY INFRACTIONS, LOSSES, COMPROMISES, OR | | POSSIBLE COMPROMISES OF CLASSIFIED INFORMATION OR CLASSIFIED DOCUMENTS NOT | | FALLING WITHIN PARAGRAPH 'A' OF THIS SECTION {10 CFR 95.57(b)}. | | | | THE NRC OPERATIONS CENTER NOTIFIED THE R3DO (JORGENSEN), NMSS EO (COMBS), | | AND AEOD IRD (CONGEL). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 34341 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 06/04/98 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 03:16 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 06/03/98 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 19:54[EDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 06/04/98 | | CITY: PIKETON REGION: 3 +-----------------------------+ | COUNTY: PIKE STATE: OH |PERSON ORGANIZATION| |LICENSE#: GDP-2 AGREEMENT: N |BRUCE JORGENSEN RDO | | DOCKET: 0707002 |JOHN HICKEY, NMSS EO | +------------------------------------------------+ | |NRC NOTIFIED BY: DALE NOEL | | |HQ OPS OFFICER: LEIGH TROCINE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NBNL RESPONSE-BULLETIN | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | NRC BULLETIN 90-01 RESPONSE (24-HOUR REPORT) | | | | AT 1954 HOURS ON 06/03/98, OPERATIONS PERSONNEL DISCOVERED THAT A NUCLEAR | | CRITICALITY SAFETY APPROVAL (NCSA) REQUIREMENT WAS NOT BEING MAINTAINED IN | | THE X-330 PROCESS BUILDING. A LAUNDRY CART OF ANTI-CONTAMINATION CLOTHING | | WAS FOUND WITHOUT THE REQUIRED COVER IN PLACE FOR MODERATION CONTROL; THUS | | VIOLATING REQUIREMENT #2 OF NSCA-PLANT-055. THIS CONSTITUTES THE LOSS OF | | CONTROL 'A' (MODERATION) IN THE DOUBLE CONTINGENCY MATRIX FOR CONTINGENCY | | EVENT A/B.1. CONTROL 'B' (MASS) WAS MAINTAINED THROUGHOUT THIS EVENT. | | CONTROL 'A' WAS RE-ESTABLISHED AT 2200 HOURS ON 06/03/98 UNDER THE | | DIRECTION OF NUCLEAR CRITICALITY SAFETY FIELD PERSONNEL. | | | | THERE WAS NO LOSS OF HAZARDOUS/RADIOACTIVE MATERIAL, AND THERE WERE NO | | RADIOACTIVE/RADIOLOGICAL CONTAMINATION EXPOSURES AS A RESULT OF THIS EVENT. | | | | THE LICENSEE STATED THAT THERE WAS A LACK OF ATTENTION TO DETAIL REGARDING | | NUCLEAR CRITICALITY CONTROLS. THERE WAS NO MODERATOR FOUND IN THE LAUNDRY | | CART, AND THERE WAS NO KNOWN OR SUSPECTED AMOUNT OF URANIUM-235 INVOLVED IN | | ANY FORM. | | | | PORTSMOUTH PERSONNEL NOTIFIED THE NRC RESIDENT INSPECTOR AND PLAN TO NOTIFY | | THE DEPARTMENT OF ENERGY SITE REPRESENTATIVE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34342 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FITZPATRICK REGION: 1 |NOTIFICATION DATE: 06/04/98 | |UNIT: [1] [ ] [ ] STATE: NY |NOTIFICATION TIME: 04:01 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 06/04/98 | +------------------------------------------------+EVENT TIME: 03:15[EDT]| |NRC NOTIFIED BY: K. SHAWN ALLEN |LAST UPDATE DATE: 06/04/98 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LAURIE PELUSO RDO | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 98 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TECHNICAL SPECIFICATION REQUIRED SHUTDOWN DUE TO THE FAILURE OF A SCRAM | | DISCHARGE VOLUME DRAIN VALVE TO MEET THE CLOSING TIME REQUIRED BY THE | | INSERVICE TEST PROCEDURE | | | | DURING THE PERFORMANCE OF A PLANNED QUARTERLY SURVEILLANCE, SCRAM DISCHARGE | | VOLUME DRAIN VALVE 03-AOV-37 STROKED IN 20.9 SECONDS IN LIEU OF 20.8 | | SECONDS AS REQUIRED BY THE INSERVICE TEST PROCEDURE. (TECHNICAL | | SPECIFICATIONS REQUIRE THE VALVE TO STROKE IN LESS THAN 30 SECONDS.) | | BECAUSE THE VALVE FAILED TO MEET THE STROKE TIME REQUIRED BY THE PROCEDURE, | | THE LICENSEE DECLARED THE VALVE INOPERABLE. ACCORDINGLY, THE UNIT ENTERED | | A 24-HOUR TO COLD SHUTDOWN TECHNICAL SPECIFICATION LIMITING CONDITION FOR | | OPERATION. | | | | INSERVICE TESTING ENGINEERS ARE CURRENTLY EN ROUTE TO THE SITE TO EVALUATE | | THE OPERABILITY OF THE VALVE. | | | | THE LICENSEE PLANS TO NOTIFY THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34343 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 06/04/98 | |UNIT: [ ] [ ] [3] STATE: CT |NOTIFICATION TIME: 10:16 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 04/19/98 | +------------------------------------------------+EVENT TIME: : [EDT]| |NRC NOTIFIED BY: DALE BRODSKY |LAST UPDATE DATE: 06/04/98 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LAURIE PELUSO RDO | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | | | |FEMA, DOE, USDA, HHS FAX | | |EPA, DOT (VIA EPA) FAX | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | | | | | 3 | N N 0 HOT SHUTDOWN | 0 HOT SHUTDOWN | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | OFFSITE NOTIFICATION OF A HISTORICAL PROBLEM WITH DISCHARGES FROM A | | NON-RADIOACTIVE WASTE COLLECTION SUMP TO THE LONG ISLAND SOUND | | | | THIS EVENT INVOLVES HISTORICAL DISCHARGES FROM A NON-RADIOACTIVE COLLECTION | | SUMP WHICH IS PART OF THE WATER PURIFICATION SYSTEM. DURING THE NORMAL | | DISCHARGE PROCESS, THE LICENSEE CONTINUES TO ADD WATER TO THE TANK AFTER | | THE WATER HAS BEEN SAMPLED FOR DISCHARGE. THEREFORE, SOME OF THE DISCHARGE | | WATER IS NOT SAMPLED. THIS IS A VIOLATION OF THE LICENSEE'S STATE EFFLUENT | | DISCHARGE PERMIT. THE LICENSEE STATED THAT WATER WAS LAST DISCHARGED FROM | | THE WASTE COLLECTION SUMP (TANK) ON THE EVENING OF 04/19/98. DISCHARGED | | WATER GOES TO THE LONG ISLAND SOUND. | | | | THE LICENSEE IS CURRENTLY IN THE PROCESS OF NOTIFYING THE STATE AND LOCAL | | OFFICIALS AND THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34344 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOK REGION: 3 |NOTIFICATION DATE: 06/04/98 | |UNIT: [1] [ ] [ ] STATE: MI |NOTIFICATION TIME: 10:36 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 06/04/98 | +------------------------------------------------+EVENT TIME: 08:50[EDT]| |NRC NOTIFIED BY: MARY BETH DEPUYDT |LAST UPDATE DATE: 06/04/98 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ 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 | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DISCOVERY THAT A CONTAINMENT SPRAY HEAT EXCHANGER WAS INSTALLED 180 DEGREES | | FROM THE DESIGN SINCE ORIGINAL CONSTRUCTION | | | | THE FOLLOWING TEXT IS A PORTION OF A FACSIMILE RECEIVED FROM THE LICENSEE: | | | | "DURING A GENERIC LETTER 89-13 ('SERVICE WATER SYSTEM PROBLEMS AFFECTING | | SAFETY-RELATED SYSTEMS') INSPECTION OF THE CONTAINMENT SPRAY (CTS) HEAT | | EXCHANGERS, IT WAS DETERMINED THAT THE UNIT 1 WEST CTS HEAT EXCHANGER HAD | | BEEN INSTALLED 180 DEGREES FROM THE DESIGN, i.e., THE SERVICE WATER INLET | | PIPING HAD BEEN ALIGNED TO THE SERVICE WATER OUTLET SIDE OF THE HEAT | | EXCHANGER DURING ORIGINAL CONSTRUCTION. THIS RESULTED IN THE IMPINGEMENT | | PLATE BEING LOCATED ON THE SERVICE WATER OUTLET SIDE INSTEAD OF THE INLET | | SIDE. THE IMPINGEMENT PLATE IS DESIGNED TO BE LOCATED ON THE INLET SIDE TO | | PREVENT SAND AND SILT FROM IMPINGING ON THE HEAT EXCHANGER TUBES IN THE | | LOCALIZED AREA OF THE SHELL SIDE INLET NOZZLE. WITH THE IMPINGEMENT PLATE | | LOCATED ON THE OUTLET SIDE OF THE HEAT EXCHANGER, ACCELERATED EROSION OF | | THE TUBE MATERIAL AT THE INLET SIDE NOZZLE COULD OCCUR." | | | | "ALTHOUGH THIS POTENTIAL DEGRADATION WOULD NOT AFFECT THE HEAT TRANSFER | | CAPABILITIES OF THE HEAT EXCHANGER, TUBE FAILURE COULD RESULT IN LEAKAGE OF | | CTS WATER INTO THE SERVICE WATER SYSTEM." | | | | "THE ANALYZED ACCIDENT WHICH IS BOUNDING FOR CTS HEAT EXCHANGER OPERATION | | IS THE [REACTOR COOLANT PUMP] SUCTION LINE LARGE BREAK [LOSS OF COOLANT | | ACCIDENT]. THIS ACCIDENT WOULD REQUIRE THAT THE CTS HEAT EXCHANGER BE IN | | SERVICE FOR AT LEAST 28 HOURS AFTER THE ACCIDENT TO LOWER CONTAINMENT | | PRESSURE." | | | | "WITH THE INFORMATION AVAILABLE, IT CANNOT BE DETERMINED IF THE [UNIT] 1 | | WEST CTS HEAT EXCHANGER WOULD OPERATE FOR THE MINIMUM REQUIRED PERIOD OF | | TIME. TO DETERMINE IF THE [HEAT EXCHANGER] TUBES HAVE EXPERIENCED | | DEGRADATION - AND IF THEY HAVE, TO WHAT DEGREE - IT WILL BE NECESSARY TO | | PERFORM EDDY CURRENT TESTING ON THE TUBES. ONCE THIS IS COMPLETED, A MORE | | ACCURATE PICTURE OF THE CONDITION OF THE [HEAT EXCHANGER] TUBES WILL BE | | AVAILABLE, AND A FINAL DETERMINATION OF THE IMPACT OF THIS CONDITION WILL | | BE MADE." | | | | "REVIEW OF PREVIOUS INSPECTION RECORDS INDICATE THAT THE REMAINING CTS HEAT | | EXCHANGERS, UNIT 1 EAST AND UNIT 2 EAST AND WEST, ARE CORRECTLY INSTALLED. | | THIS WILL [BE] CONFIRMED DURING FUTURE [GENERIC LETTER] 89-13 INSPECTIONS, | | WHICH WILL BE COMPLETED PRIOR TO UNIT STARTUP." | | | | "PLANS ARE UNDERWAY TO SCHEDULE THE EDDY CURRENT TESTING, BUT IT IS NOT | | CURRENTLY KNOWN WHEN IT WILL TAKE PLACE. THIS CONDITION WILL BE RESOLVED | | PRIOR TO STARTUP OF THE UNIT." | | | | THE LICENSEE PLANS TO INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34345 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HARRIS REGION: 2 |NOTIFICATION DATE: 06/04/98 | |UNIT: [1] [ ] [ ] STATE: NC |NOTIFICATION TIME: 12:18 [ET]| |RX TYPE: [1] W-3-LP |EVENT DATE: 06/04/98 | +------------------------------------------------+EVENT TIME: 12:15[EDT]| |NRC NOTIFIED BY: MIKE VERRILLI |LAST UPDATE DATE: 06/04/98 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CHRIS CHRISTENSEN RDO | |AESS 50.72(b)(1)(v) EMERGENCY SIREN 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 SIRENS IN LEE COUNTY DUE TO THUNDERSTORMS ON MAY 23, | | 1998. | | | | ON JUNE 4, 1998, AT 1215 EDT, CP&L DETERMINED THAT A REPORTABLE CONDITION | | EXISTED IN THAT ALL SIX EMERGENCY SIRENS IN LEE COUNTY HAD BEEN LOST ON | | MAY 23, 1998. THIS CONDITION CONSTITUTED A LOSS OF OFF-SITE COMMUNICATIONS | | PER 10 CFR 50.72(b)(1)(v). EMERGENCY SIREN (#39) IS THE ONLY SIREN IN LEE | | COUNTY POWERED BY CP&L. THE POWER TO THE REMAINING 5 SIRENS (#42, #45, | | #46, #48, AND #58) IN LEE COUNTY ARE POWERED BY THE CENTRAL ELECTRIC | | MEMBERSHIP CORPORATION. CP&L DOES NOT HAVE AN IMMEDIATE METHOD TO | | DETERMINE THE AVAILABILITY OF THESE REMAINING FIVE SIRENS. ON MAY 23, | | 1998, THE CP&L CUSTOMER SERVICE CENTER REPORTED THAT POWER TO SIREN #39 WAS | | LOST FROM 1215 EDT TO 1515 EDT DUE TO A THUNDERSTORM. AN IMMEDIATE | | NOTIFICATION WAS NOT MADE ON MAY 23, 1998, PENDING CONFIRMATION OF THE | | AVAILABILITY OF THE REMAINING LEE COUNTY SIRENS. HOWEVER, THE CENTRAL | | ELECTRIC MEMBERSHIP CORPORATION DID NOT CONFIRM THAT POWER TO SIRENS #42, | | #45, #46, #48, AND #58 HAD ALSO BEEN LOST FROM 1145 EDT TO 1400 EDT ON | | MAY 23, 1998, UNTIL JUNE 4, 1998. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34346 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CALVERT CLIFFS REGION: 1 |NOTIFICATION DATE: 06/04/98 | |UNIT: [1] [2] [ ] STATE: MD |NOTIFICATION TIME: 13:49 [ET]| |RX TYPE: [1] CE,[2] CE |EVENT DATE: 06/04/98 | +------------------------------------------------+EVENT TIME: 13:45[EDT]| |NRC NOTIFIED BY: MARK GECKLE |LAST UPDATE DATE: 06/04/98 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LAURIE PELUSO 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 N 0 HOT STANDBY | 0 HOT STANDBY | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ACCESS TO OWNER CONTROLLED PROPERTY GRANTED FOR TRANSPORTATION OF VICTIMS | | ON OFFSHORE BARGE TO HOSPITAL. | | | | THE U.S. COAST GUARD AND STATE POLICE REQUESTED AND WERE GRANTED ACCESS TO | | OWNER CONTROLLED PROPERTY IN A RESCUE EFFORT FOR VICTIMS OVERCOME BY | | AMMONIA VAPORS ON A BARGE IN THE CHESAPEAKE BAY. THERE ARE ONE OR MORE | | APPARENT FATALITIES INVOLVED. | | | | THE LICENSEE PLANS TO ISSUE A PRESS RELEASE AND HAS INFORMED THE NRC | | RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34347 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: LIMERICK REGION: 1 |NOTIFICATION DATE: 06/04/98 | |UNIT: [1] [2] [ ] STATE: PA |NOTIFICATION TIME: 15:00 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 06/04/98 | +------------------------------------------------+EVENT TIME: 10:45[EDT]| |NRC NOTIFIED BY: PETER A. GARDNER |LAST UPDATE DATE: 06/04/98 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LAURIE PELUSO RDO | |NLTR LICENSEE 24 HR REPORT | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 90 POWER OPERATION | 90 POWER OPERATION | | 2 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LICENSEE IDENTIFIED THAT THE FIRE EXTINGUISHER DISTRIBUTION WAS NOT IN | | ACCORDANCE WITH THE NATIONAL FIRE PROTECTION ASSOCIATION (NFPA) CODE | | REFERENCED IN THE UPDATED FINAL SAFETY ANALYSIS REPORT (UFSAR). | | | | THE FOLLOWING TEXT IS A PORTION OF A FACSIMILE RECEIVED FROM THE LICENSEE: | | | | "ON 06/03/98 AT APPROXIMATELY 1515 EDT, ENGINEERING IDENTIFIED THAT FIRE | | EXTINGUISHER DISTRIBUTION WAS NOT IN COMPLIANCE WITH THE UFSAR (APPENDIX 9A | | FPER, SECTION 9A.3.1.1). LIMERICK USES NFPA 10-1975 AS THE OFFICIAL CODE | | OF RECORD WHICH STATES THAT CLASS 'A' EXTINGUISHING CAPABILITY RATED FOR | | '2A' MUST BE PROVIDED SUCH THAT THE MAXIMUM TRAVEL DISTANCE IS NO MORE THAN | | 75 FEET AND [THAT] CLASS 'B' EXTINGUISHING CAPABILITY RATED FOR '2B' BE | | PROVIDED SUCH THAT THE MAXIMUM TRAVEL DISTANCE IS NO LONGER THAN 50 FEET. | | THERE ARE SEVERAL INSTANCES WHERE THERE ARE CLASS 'A' MATERIAL AREAS WITH | | NO CLASS 'A' EXTINGUISHERS, AND SEVERAL CLASS 'B' EXTINGUISHERS EXCEED THE | | 50-FOOT REQUIREMENT." | | | | "THIS VIOLATION WAS FOUND DURING THE CURRENT UFSAR REVIEW THAT LIMERICK IS | | PERFORMING. ENGINEERING IS CURRENTLY REVIEWING CORRECTIVE ACTION | | REQUIREMENTS. NOTE [THAT] THERE ARE NO SPECIFIC TECHNICAL REQUIREMENTS | | MANUAL (TRM) OR TECH SPEC REQUIREMENTS FOR FIRE EXTINGUISHERS. AT THIS | | TIME, ALL REQUIRED TRM FIRE DETECTION AND SUPPRESSION EQUIPMENT IS | | OPERABLE." | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34348 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: NINE MILE POINT REGION: 1 |NOTIFICATION DATE: 06/04/98 | |UNIT: [1] [ ] [ ] STATE: NY |NOTIFICATION TIME: 17:32 [ET]| |RX TYPE: [1] GE-2,[2] GE-5 |EVENT DATE: 06/04/98 | +------------------------------------------------+EVENT TIME: 16:40[EDT]| |NRC NOTIFIED BY: JIM KRONENBITTER |LAST UPDATE DATE: 06/04/98 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LAURIE PELUSO RDO | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LICENSEE IDENTIFIED A VALVE ALIGNMENT OF THE CORE SPRAY SYSTEM IN RESPONSE | | TO GENERIC LETTER 96-06 WHICH WAS CONTRARY TO THE APPENDIX 'R' SAFE | | SHUTDOWN ANALYSIS. | | | | THE FOLLOWING TEXT IS A PORTION OF A FACSIMILE RECEIVED FROM THE LICENSEE: | | | | "WHILE REVIEWING A FIRE PROTECTION ENGINEERING ANALYSIS, ENGINEERING | | PERSONNEL DISCOVERED THAT REQUIREMENTS FOR THE NINE MILE POINT 1, APPENDIX | | 'R,' SAFE SHUTDOWN ANALYSIS WERE NOT SATISFIED. SPECIFICALLY, MANUAL | | VALVES DOWNSTREAM OF THE TWO CORE SPRAY SYSTEM HIGH POINT VENT LINES WHICH | | HAD BEEN OPENED TO PRECLUDE GENERIC LETTER 96-06 POST-[LOSS OF COOLANT | | ACCIDENT] THERMAL OVERPRESSURIZATION CONCERNS, ARE REQUIRED TO BE CLOSED TO | | SATISFY APPENDIX 'R' [HIGH/LOW] PRESSURE INTERFACE/INVENTORY LOSS PATH | | CONCERNS." | | | | "THIS CONDITION CONSTITUTES OPERATION IN A CONDITION OUTSIDE [THE] DESIGN | | BASIS. IMMEDIATE CORRECTIVE ACTION HAS BEEN TAKEN TO OPEN BREAKERS FOR | | MOTOR-OPERATED VALVES IN THE VENT LINES. THIS ACTION ELIMINATED THE | | APPENDIX 'R' BOUNDARY INTERFACE CONCERNS." | | | | THE LICENSEE PLANS TO INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 34349 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 06/04/98 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 18:25 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 06/04/98 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 11:48[EDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 06/04/98 | | CITY: PIKETON REGION: 3 +-----------------------------+ | COUNTY: PIKE STATE: OH |PERSON ORGANIZATION| |LICENSE#: GDP-2 AGREEMENT: N |BRUCE JORGENSEN RDO | | DOCKET: 0707002 |JOHN HICKEY, NMSS EO | +------------------------------------------------+ | |NRC NOTIFIED BY: RICK LARSON | | |HQ OPS OFFICER: STEVE SANDIN | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NBNL RESPONSE-BULLETIN | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | 24-HOUR NRC BULLETIN 91-01 REPORT INVOLVING LOSS OF THE DOUBLE CONTINGENCY | | MATRIX | | | | THE FOLLOWING TEXT IS A PORTION OF A FACSIMILE RECEIVED FROM PORTSMOUTH: | | | | "ON JUNE 4, 1998, AT 1148 HOURS, CHEMICAL OPERATIONS PERSONNEL DISCOVERED | | THAT A NUCLEAR CRITICALITY SAFETY APPROVAL (NCSA) REQUIREMENT WAS NOT BEING | | MAINTAINED IN THE X-705 DECON BUILDING. A CONTAINER FOR CONTAMINATED | | ANTI-Cs AT A BOUNDARY CONTROL STATION WAS FOUND WITHOUT THE REQUIRED COVER | | IN PLACE FOR SPLASH/VOLUME CONTROL, THUS VIOLATING REQUIREMENT #4 OF | | NCSA-0705_076, CONTROL 'A' (VOLUME), IN THE DOUBLE CONTINGENCY MATRIX FOR | | EVENT A/B 3.3. CONTROL 'B' (GEOMETRY) WAS MAINTAINED THROUGH THIS EVENT. | | CONTROL 'A' WAS RE-ESTABLISHED AT APPROXIMATELY 1200 HOURS UNDER THE | | DIRECTION OF [THE] NUCLEAR CRITICALITY SAFETY ENGINEER." | | | | "THERE WAS NO LOSS OF HAZARDOUS/RADIOACTIVE MATERIAL OR | | RADIOACTIVE/RADIOLOGICAL CONTAMINATION EXPOSURE AS A RESULT OF THIS EVENT." | | | | PORTSMOUTH PERSONNEL INFORMED THE NRC RESIDENT INSPECTOR AND THE DEPARTMENT | | OF ENERGY SITE REPRESENTATIVE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34350 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BEAVER VALLEY REGION: 1 |NOTIFICATION DATE: 06/04/98 | |UNIT: [1] [2] [ ] STATE: PA |NOTIFICATION TIME: 20:02 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 06/04/98 | +------------------------------------------------+EVENT TIME: 18:25[EDT]| |NRC NOTIFIED BY: GEORGE E. STOROLIS |LAST UPDATE DATE: 06/04/98 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LAURIE PELUSO RDO | |AINB 50.72(b)(2)(iii)(B) POT RHR INOP | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | LICENSEE DISCOVERED A DISCREPANCY BETWEEN THE UPDATED FINAL SAFETY ANALYSIS | | (UFSAR) DESCRIPTION AND PRACTICE INVOLVING INTAKE STRUCTURE CUBICLE DOORS. | | | | THE FOLLOWING TEXT IS A PORTION OF A FACSIMILE RECEIVED FROM THE LICENSEE: | | | | "DURING THE PREPARATION FOR A QUALITY SERVICES UNIT AUDIT, A UFSAR | | DISCREPANCY WAS IDENTIFIED. THE UNIT 1 UFSAR (SECTION 9.7) STATES: 'RIVER | | WATER PUMPS AND ENGINE-DRIVEN FIRE PUMP - INTAKE STRUCTURE - THERE ARE NO | | EQUIPMENT OR FLOOR DRAINS LOCATED IN THE INTAKE STRUCTURE. THERE ARE NO | | PRECAUTIONS NECESSARY TO PREVENT FLOODING IN THE EVENT OF A MAJOR PIPE | | RUPTURE IN ANY OF THE PRESSURE WATER LINES IN THE PUMP CUBICLES BECAUSE | | OPEN CUBICLE ACCESS DOORS WILL PERMIT THE EXCESS WATER TO FLOW OUT OF THE | | CUBICLES.' THESE STATEMENTS IN THE UFSAR IMPLY THAT EACH OF THE | | ENTRANCE/EXIT FIRE DOORS ON THE FOUR RIVER WATER PUMP CUBICLES IN THE | | INTAKE STRUCTURE ARE MAINTAINED OPEN. THESE FOUR FIRE/SECURITY DOORS ARE | | NORMALLY MAINTAINED CLOSED." | | | | "AN ENGINEERING REVIEW OF THE INTERNAL FLOODING CALCULATIONS WAS PERFORMED | | IN EFFORTS TO DETERMINE WHETHER THE UFSAR COULD BE REVISED TO REFLECT THE | | NORMAL INTAKE STRUCTURE PUMP CUBICLE DOOR CONFIGURATION TO BE CLOSED. THE | | REVIEW DETERMINED A NEW FAILURE MODE OF EQUIPMENT IN THE PUMP CUBICLES THAT | | HAD NOT PREVIOUSLY BEEN CONSIDERED WHICH COULD INTRODUCE INTERNAL FLOODING. | | THIS REVIEW NOTED THAT WITH A PUMP CUBICLE ENTRANCE/EXIT DOOR CLOSED, | | INTERNAL FLOODING COULD BE POSTULATED WHICH COULD CAUSE A SECOND DOOR | | LEADING TO AN ADJACENT PUMP CUBICLE TO OPEN. THIS RESULTANT IMPACT COULD | | POTENTIALLY LEAD TO THE LOSS OF THE REDUNDANT TRAINS OF RIVER WATER PUMPS | | AT UNIT 1 OR TO THE LOSS OF THE REDUNDANT TRAINS OF SERVICE WATER PUMPS AT | | UNIT 2." | | | | "THIS CONDITION IS BEING REPORTED IN ACCORDANCE WITH THE PROVISIONS OF | | 10CFR50.72(b)(2)(iii) SINCE THE LOSS OF BOTH RIVER/SERVICE WATER PUMPS | | WOULD REMOVE THE NORMAL SAFETY-RELATED METHODS OF COOLING EQUIPMENT | | NECESSARY TO REMOVE DECAY HEAT, AND THUS, THE UNITS WERE IN AN UNANALYZED | | CONDITION THAT SIGNIFICANTLY COMPROMISES PLANT SAFETY." | | | | "FLOOD DOORS (IMMEDIATE TO THE FIRE/SECURITY DOORS) ON EACH OF THE TWO | | DOORS CONNECTING THE TWO ADJACENT PUMP CUBICLES HAVE BEEN CLOSED. THIS | | WILL PROVIDE ADEQUATE PROTECTION TO PREVENT A POSTULATED INTERNAL FLOOD | | EVENT IN ONE CUBICLE FROM ADVERSELY AFFECTING THE ADJACENT CUBICLE. | | [BEAVER VALLEY] UNIT 1 AND UNIT 2 HAVE AN ALTERNATE INTAKE STRUCTURE WHICH | | COULD BE USED IN THE EVENT OF A LOSS OF THE SAFETY-RELATED FUNCTIONS IN THE | | MAIN INTAKE STRUCTURE." | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+