U.S. Nuclear Regulatory Commission Operations Center Event Reports For 12/08/97 - 12/09/97 ** EVENT NUMBERS ** 32482 32842 33218 33252 33278 33353 33364 33365 33366 33367 33368 33369 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32482 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VERMONT YANKEE REGION: 1 |NOTIFICATION DATE: 06/13/97 | |UNIT: [1] [ ] [ ] STATE: VT |NOTIFICATION TIME: 17:24 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 06/13/97 | +------------------------------------------------+EVENT TIME: 17:15[EDT]| |NRC NOTIFIED BY: M. F. EMPEY |LAST UPDATE DATE: 12/08/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RICHARD KEIMIG 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 +------------------------------------------------------------------------------+ | DISCOVERY THAT THE ORIGINAL PRIMARY CONTAINMENT PAINT WAS NOT DESIGN BASIS | | ACCIDENT QUALIFIED OR TESTED IN ACCORDANCE WITH THE FINAL SAFETY ANALYSIS | | REPORT (FSAR) AND THAT IT COULD EXPERIENCE PREMATURE BLISTERING. | | | | DURING A REVIEW OF AN INDUSTRY EVENT REGARDING CONTAINMENT MATERIALS | | (SPECIFICALLY COATINGS), IT WAS DETERMINED THE VERMONT YANKEE'S ORIGINAL | | PRIMARY CONTAINMENT PAINT WAS NOT DESIGN BASIS ACCIDENT QUALIFIED AT THE | | TIME OF LICENSING. FURTHERMORE, WHAT TESTING HAS BEEN COMPLETED ON THE | | EXISTING PAINT DOES NOT MEET THE REQUIREMENTS OF FSAR SECTION 14.9.1.6. | | THIS SECTION OF THE FSAR REGARDS RADIATION RESISTANCE. THE LICENSEE | | BELIEVES THAT THIS ISSUE IS ALREADY BOUNDED WITHIN AN INDUSTRY NOTICE | | (NRC BULLETIN 96-03), AND THE LICENSEE DOES NOT BELIEVE THAT THIS IS | | AN OPERABILITY ISSUE. THE UNIT IS NOT CURRENTLY IN ANY TECHNICAL | | SPECIFICATION LIMITING CONDITIONS FOR OPERATION AS A RESULT OF THIS ISSUE. | | | | THE LICENSEE PLANS TO NOTIFY THE NRC RESIDENT INSPECTOR TOMORROW MORNING. | | | | * * * UPDATE ON 12/08/97 AT 1535 BY BROOKS TAKEN BY GOULD * * * | | | | THE LICENSEE IS RETRACTING THIS EVENT SINCE A RAD DOSE OF 4.00E8 WAS | | REQUIRED TO BLISTER THE COATING AND THEY HAVE DETERMINED THAT THE SUBMERGED | | COATING ACCIDENT DOSE WILL NOT EXCEED 3.00E8. SINCE THE DOSE RATE WHICH | | THE COATING WILL BE SUBJECT TO IS LESS THAN THE DOSE RATE UNDER WHICH THE | | COATING HAS BEEN DEMONSTRATED TO PERFORM SUCCESSFULLY, THIS EVENT IS NOT | | REPORTABLE TO THE NRC. THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | THE OPERATIONS OFFICER NOTIFIED THE R1DO JIM TRAPP. | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32842 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VERMONT YANKEE REGION: 1 |NOTIFICATION DATE: 08/29/97 | |UNIT: [1] [ ] [ ] STATE: VT |NOTIFICATION TIME: 13:17 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 08/29/97 | +------------------------------------------------+EVENT TIME: 13:15[EDT]| |NRC NOTIFIED BY: BRYAN CROKE |LAST UPDATE DATE: 12/08/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JAMES LINVILLE 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 +------------------------------------------------------------------------------+ | - CRACKS DISCOVERED IN RAD WASTE EXHAUST DUCT LEADING TO THE PLANT STACK - | | | | A LICENSEE MAINTENANCE TECHNICIAN DISCOVERED 4 TO 6 CRACKS IN THE RAD | | WASTE EXHAUST DUCT LEADING TO THE PLANT STACK. THE CRACKS ARE LOCATED | | OUTSIDE THE RAD WASTE BUILDING APPROXIMATELY 25 FEET ABOVE GROUND LEVEL. | | THE LARGEST CRACK IS APPROXIMATELY 1/16 INCH WIDE X 2 INCHES LONG. | | SWIPES AND AIR SAMPLES TAKEN NEAR THE OUTSIDE OF THE CRACKS INDICATE NO | | DETECTABLE ACTIVITY. | | | | THE LICENSEE PLANS TO COVER THE CRACKS WITH TEMPORARY BANDS, INSPECT OTHER | | PLANT DUCTWORK FOR CRACKS, AND DETERMINE PERMANENT CORRECTIVE ACTIONS. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE ON 12/08/97 AT 1535 BY BROOKS TAKEN BY GOULD * * * | | | | THE LICENSEE IS RETRACTING THIS EVENT. FOLLOW-UP ASSESSMENTS REVEALED THAT | | SURVEYS AND SAMPLES TAKEN AT OR NEAR THE AFFECTED AREA, COMBINED WITH A | | REVIEW OF SURVEY RECORDS FOR THE AFFECTED AREAS, SHOWS THAT THE AS-FOUND | | CONDITION FULLY SUPPORTED THE APPLICABLE SYSTEMS SAFETY DESIGN BASES. IT | | WAS FURTHER DETERMINED THAT THE LEVEL OF RADIOACTIVE MATERIAL POTENTIALLY | | RELEASED VIA THE CRACK(S) WAS WELL WITHIN THE LIMITS. THIS EVENT, | | THEREFORE, SHOULD NOT HAVE BEEN REPORTED. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | | | | THE OPERATIONS OFFICER NOTIFIED THE R1DO JIM TRAPP. | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33218 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VERMONT YANKEE REGION: 1 |NOTIFICATION DATE: 11/05/97 | |UNIT: [1] [ ] [ ] STATE: VT |NOTIFICATION TIME: 17:32 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 11/05/97 | +------------------------------------------------+EVENT TIME: 17:05[EST]| |NRC NOTIFIED BY: MICHAEL EMPEY |LAST UPDATE DATE: 12/08/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LEANNE HARRISON 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 DISCREPANCIES IN AS-BUILT CONFIGURATION OF THE | | DOWNCOMER AFFECTING EXPECTED LOADING OF THE MARK I CONTAINMENT FOLLOWING A | | LOCA. | | | | "DURING THE DEVELOPMENT OF SPECIFICATIONS FOR AN UPCOMING ECCS STRAINER | | REPLACEMENT, DISCREPANCIES WERE FOUND BETWEEN THE PLANT AS-BUILT DATA AND | | THE DATA USED IN THE DEVELOPMENT OF GE MARK I CONTAINMENT LOAD CALCULATIONS | | FOR VY. VY CURRENTLY MAINTAINS CONTAINMENT TORUS LEVELS IN ORDER TO ASSURE | | TORUS VOLUME AND TORUS DIFFERENTIAL PRESSURE ARE 68,000 TO 70,000 CUBIC | | FEET AND > 1.7 PSID, RESPECTIVELY. BASED ON VY CALCULATIONS, DOWNCOMER | | SUBMERGENCE COULD BE .4 FEET GREATER THAN EXPECTED BY TECHNICAL | | SPECIFICATIONS. PLANS ARE BEING FORMULATED TO REVIEW ALL CALCULATIONS | | INVOLVED." | | | | AN OPERABILITY DETERMINATION PERFORMED BY ENGINEERING CONCLUDED THAT THE | | ADDITIONAL LOADING WOULD BE SMALL IN RELATION TO THE CONSERVATISM | | INCORPORATED IN THE MARK I DESIGN MARGIN. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE ON 12/08/97 AT 1535 BY BROOKS TAKEN BY GOULD * * * | | | | THE LICENSEE IS RETRACTING THIS EVENT. FOLLOW-UP EVALUATIONS WERE | | PERFORMED AND IT WAS DETERMINED THAT THE PREVIOUS ANALYSIS WHICH QUALIFIED | | THE HYDRODYNAMIC EFFECTS OF BLOWDOWNS INTO THE TORUS WITH 0 PSID BETWEEN | | THE DRYWELL AND THE TORUS BOUNDED THE CONDITIONS ASSESSED IN THE PLANT | | UNIQUE LOAD DESCRIPTION (PULD). THIS CONDITION WAS IN FACT CONSISTENT WITH | | THE PLANT'S DESIGN BASES, DESPITE THE NON-CONSERVATIVE ERROR INTRODUCED | | THROUGH THE SELECTION OF THE WRONG INITIAL TORUS LEVEL (IN THE PULD). | | BASED ON THIS UNDERSTANDING, THE LICENSEE DETERMINED THAT THIS EVENT IS | | NOT REPORTABLE TO THE NRC. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | THE OPERATIONS OFFICER NOTIFIED R1DO JIM TRAPP. | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33252 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SURRY REGION: 2 |NOTIFICATION DATE: 11/12/97 | |UNIT: [1] [2] [ ] STATE: VA |NOTIFICATION TIME: 10:48 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 11/12/97 | +------------------------------------------------+EVENT TIME: 10:30[EDT]| |NRC NOTIFIED BY: BILL WEBSTER |LAST UPDATE DATE: 12/08/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CHARLES OGLE 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 | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ATWS BLOCKING SETPOINT SET NONCONSERVATIVELY. | | | | "THE INTERLOCK SETPOINT FOR ATWS MITIGATING SYSTEM ACTUATION CIRCUITRY | | (AMSAC) IS SET FOR 37 PERCENT TURBINE FIRST STAGE IMPULSE PRESSURE. | | IT HAS BEEN DETERMINED THAT THIS SETPOINT CORRESPONDS TO GREATER THAN 40% | | REACTOR THERMAL POWER WHICH IS OUTSIDE THE DESIGN BASIS. BOTH UNITS ARE | | CURRENTLY OPERATING AT FULL POWER, THEREFORE AMSAC IS FULLY OPERABLE. | | CORRECTIVE ACTIONS ARE BEING REVIEWED TO ENSURE AMSAC IS OPERABLE AT | | 40 PERCENT THERMAL REACTOR POWER IN ACCORDANCE WITH THE DESIGN BASIS. | | THIS EVENT IS BEING REPORTED IN ACCORDANCE WITH 10 CFR 50.72(b)(1)(ii)B." | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | HOO NOTE: SEE RELATED EVENTS #33132, 33205, 33217, 33225 AND 33235. | | | | * * * UPDATE AT 1116 ON 12/08/97 BY JIM HELM ENTERED BY JOLLIFFE * * * | | | | WESTINGHOUSE ANALYSES HAVE ESTABLISHED THAT THE PEAK RCS PRESSURE FOLLOWING | | THE LIMITING ATWS EVENT WOULD NOT EXCEED THE VALUE OF 3200 PSIG (AND BE | | WITHIN THE ASME SERVICE LEVEL 'C' STRESS LIMIT CRITERION) FOR INITIAL POWER | | LEVELS BELOW 70% OF NOMINAL THERMAL POWER ASSUMING NO AMSAC ACTUATION. | | HENCE, THE PEAK RCS PRESSURE AT LESS THAN 42% NOMINAL THERMAL POWER WITHOUT | | AMSAC IS BOUNDED BY THE WESTINGHOUSE ANALYSIS AT 70% NOMINAL THERMAL POWER. | | THEREFORE, THIS EVENT DOES NOT REPRESENT A CONDITION WHERE THE PLANT | | OPERATED OUTSIDE THE DESIGN BASIS OF AMSAC AND THAT THE FUNCTIONAL | | PERFORMANCE REQUIREMENTS OF AMSAC WERE MET AND THUS, THIS EVENT IS NOT | | REPORTABLE TO THE NRC. THEREFORE, THE LICENSEE DESIRES TO RETRACT THIS | | EVENT. THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. THE OPERATIONS | | OFFICER NOTIFIED THE R2DO BOB HAAG. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 33278 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 11/18/97 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 12:35 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 11/15/97 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 10:30[EST]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 12/08/97 | | CITY: PIKETON REGION: 3 +-----------------------------+ | COUNTY: PIKE STATE: OH |PERSON ORGANIZATION| |LICENSE#: GDP-2 AGREEMENT: N |JOHN MADERA RDO | | DOCKET: 0707002 |FRED COMBS, NMSS EO | +------------------------------------------------+ | |NRC NOTIFIED BY: KIETH VANDERPOOL | | |HQ OPS OFFICER: BOB STRANSKY | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NBNL RESPONSE-BULLETIN | | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | 24-HOUR NRC BULLETIN 91-01 REPORT. | | | | "ON 11/15/97, AT 1030, IT WAS DISCOVERED THAT A NUCLEAR CRITICALITY SAFETY | | APPROVAL (NCSA) REQUIREMENT WAS NOT BEING MET IN THE X-326 HIGH ASSAY | | SAMPLING AREA (HASA) VAULT. NCSA-PLANT 048.A.00 LISTS TWO NUCLEAR | | CRITICALITY SAFETY CONTROLS. THE FIRST CONTROL, WHICH IS ADMINISTRATIVE, | | REQUIRES SPACING BETWEEN THE ITEMS IF THERE IS A HIDDEN CAVITY WITH A | | POTENTIAL VOLUME, AND THE SECOND CONTROL, WHICH IS ADMINISTRATIVE, INVOLVES | | MODERATION. THE FIRST CONTROL WAS VIOLATED WHEN THE ITEMS WERE STORED | | TOGETHER UNDER THE MINIMUM REQUIREMENT OF TWO FEET. THE SECOND CONTROL, | | MODERATION, WAS MAINTAINED THROUGHOUT THIS EVENT. THE LOSS OF ONE CONTROL, | | SPACING, MAKES THIS EVENT REPORTABLE TO THE NRC VIA 24-HOUR EVENT | | NOTIFICATION PER NUCLEAR REGULATORY EVENT REPORTING PROCEDURE UE2.RA.RE1030 | | APPENDIX D, CRITERIA A, PARAGRAPH 4A. THERE WAS NO RELEASE OF RADIOACTIVE | | MATERIALS OR RADIOLOGICAL CONTAMINATION EXPOSURE ASSOCIATED WITH THIS | | EVENT. AS A SPECIAL NOTE, AT THE TIME THIS EVENT OCCURRED, IT WAS | | DETERMINED THAT THIS CONDITION WAS NOT REPORTABLE BECAUSE CRITICALITY COULD | | NOT OCCUR. HOWEVER, ON 11/17/97, AFTER FURTHER EVALUATION, IT WAS | | DETERMINED THAT THIS EVENT WAS REPORTABLE BECAUSE A LOSS OF ONE OF TWO | | CONTROLS EXISTED. THE NRC RESIDENT INSPECTOR HAS BEEN NOTIFIED OF THIS | | EVENT." | | | | * * * UPDATE ON 12/08/97 AT 1638 BY MAY TAKEN BY GOULD * * * | | | | THIS REPORT WAS INCORRECTLY REPORTED TO THE NRC. THE CORRECT REPORTING | | REQUIREMENT FOR THIS EVENT TO THE NRC WAS DUE TO THE NOTIFICATION OF | | ANOTHER GOVERNMENT AGENCY, DOE. THE OPERATIONS OFFICER NOTIFIED THE R1DO | | JACOBSON AND NMSS EO PICCONE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 33353 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 12/05/97 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 11:55 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 12/04/97 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 18:00[EST]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 12/08/97 | | CITY: PIKETON REGION: 3 +-----------------------------+ | COUNTY: PIKE STATE: OH |PERSON ORGANIZATION| |LICENSE#: GDP-2 AGREEMENT: N |MARK RING RDO | | DOCKET: 0707002 |FRED COMBS, NMSS EO | +------------------------------------------------+ | |NRC NOTIFIED BY: LARSON | | |HQ OPS OFFICER: CHAUNCEY GOULD | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NBNL RESPONSE-BULLETIN | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE PLANT DISCOVERED THAT A NUCLEAR CRITICALITY SAFETY APPROVAL (NCSA) | | REQUIREMENT WAS NOT MET IN THE X-710 URANIUM SAMPLING LABORATORY. | | | | ON 12/04/97, AT 1800, IT WAS DISCOVERED THAT A NCSA REQUIREMENT WAS NOT | | MET IN THE X-710 URANIUM SAMPLING LABORATORY ROOM 111. NCSA-710-006.A00 | | LISTS TWO NUCLEAR CRITICALITY SAFETY CONTROLS. THE FIRST CONTROL | | (ADMINISTRATIVE) REQUIRES THAT NO MORE THAN ONE ROW OF CONTAINERS SHALL | | BE STORED ON LAB SHELVES, BENCHES OR COUNTER TOPS. ROWS SHALL BE SPACED | | AT LEAST 18" APART. NO URANIUM-BEARING MATERIAL SHALL BE STORED ON TOP OF | | THE STORAGE CABINETS. THE FIRST CONTROL WAS MAINTAINED THROUGHOUT THIS | | EVENT. THE SECOND CONTROL (ADMINISTRATIVE) IS THAT THE MASS LIMIT OF 350 | | gm U-235 SHALL NOT BE EXCEEDED ON A PER DRAWER, ARRAY OR SHELF BASIS. A | | MINIMUM OF 24" SEPARATION FROM OTHER URANIUM-BEARING MATERIAL SHALL | | BE MAINTAINED FOR ALL CONTAINERS OF URANIUM-BEARING MATERIAL IN MOTION. | | SAMPLE CONTAINERS FILLED WITH URANIUM-BEARING MATERIAL SHALL NOT BE | | STACKED. A GROUP OF APPROXIMATELY 60 SAMPLE CONTAINERS CONTAINING | | URANIUM-BEARING MATERIAL WERE FOUND PLACED ON A PORTABLE STORAGE CART | | WHICH VIOLATES A REQUIREMENT OF THE SECOND CONTROL. THE LOSS OF ONE | | CONTROL (STACKING) MAKES THIS A REPORTABLE EVENT. THERE WAS NO RELEASE | | OF HAZARDOUS MATERIALS OR RADIOLOGICAL CONTAMINATION EXPOSURES ASSOCIATED | | WITH THE EVENT. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE ON 12/08/97 AT 1638 BY BROOKS TAKEN BY GOULD * * * | | | | THE DEPARTMENT DETERMINED THAT THIS EVENT SHOULD HAVE BEEN REPORTED AS A | | LOSS OF TWO CONTROLS DUE TO A NCSA NON-COMPLIANCE INSTEAD OF LOSS OF ONE | | CONTROL. THE STACKING OF SAMPLE CONTAINERS CONSTITUTES A LOSS OF TWO | | CONTROLS PER NCSA-0710-006.A00 DOUBLE CONTINGENCY CONTROL MATRIX. THERE | | WAS NO RELEASE OF HAZARDOUS MATERIALS OR RADIOLOGICAL CONTAMINATION | | EXPOSURES ASSOCIATED WITH THIS EVENT. | | | | THE LICENSEE NOTIFIED DOE AND THE NRC RESIDENT INSPECTOR. | | | | THE OPERATIONS OFFICER NOTIFIED THE R3DO JOHN JACOBSON AND THE NMSS EO JOSE | | PICCONE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33364 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: NINE MILE POINT REGION: 1 |NOTIFICATION DATE: 12/08/97 | |UNIT: [ ] [2] [ ] STATE: NY |NOTIFICATION TIME: 14:14 [ET]| |RX TYPE: [1] GE-2,[2] GE-5 |EVENT DATE: 12/08/97 | +------------------------------------------------+EVENT TIME: 10:53[EST]| |NRC NOTIFIED BY: CONWAY |LAST UPDATE DATE: 12/08/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JIM TRAPP RDO | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | POTENTIAL PRIMARY CONTAINMENT PRESSURE SUPPRESSION FUNCTION BYPASS PATHWAY. | | | | "A GENERAL ELECTRIC PART 21.21(b) NOTIFICATION (SC07-04) WAS MADE FOR | | POTENTIAL PRIMARY CONTAINMENT PRESSURE SUPPRESSION FUNCTION BYPASS | | PATHWAYS. A POSTULATED SINGLE FAILURE OF A CABLE RACEWAY/WIREWAY WHICH | | CONTAINS THE ISOLATION VALVE CONTROL WIRING FOR THE INBOARD CONTAINMENT | | PURGE SYSTEM VALVES COULD LEAD TO EXCESSIVE PRIMARY CONTAINMENT PRESSURE | | POST ACCIDENT. IN-DEPTH CALCULATIONS AND ANALYSIS STILL NEED TO BE | | PERFORMED TO DETERMINE THE MAXIMUM PRESSURE RISE. ADDITIONAL QUESTIONS | | WERE RAISED CONCERNING WHETHER THE CREATION OF BYPASS PATHWAYS ALSO OCCUR | | DURING NORMAL OPERATION OR SURVEILLANCE TESTING. | | | | A REVIEW OF NINE MILE POINT UNIT 2 PROCEDURES FOUND THAT DURING PRIMARY | | CONTAINMENT PURGE FOLLOWING FORCED AND PLANNED UNIT OUTAGES, A BYPASS | | PATHWAY IS CREATED DURING THE HIGH-FLOW INERTING PROCEDURE WHEN BOTH THE | | SUPPRESSION CHAMBER AND THE DRYWELL AIR SPACES ARE PURGED IN ORDER TO | | REDUCE CONTAINMENT OXYGEN LEVELS. THE SAME BYPASS PATHWAY LINEUP IS | | UTILIZED FOR THE DEINERTING PROCESS WHICH PROCEEDS OUTAGES WHICH REQUIRE | | PRIMARY CONTAINMENT ACCESS. THE LAST TIME A BYPASS FLOWPATH EXISTED WAS ON | | 11/12/97, FOLLOWING PLANT STARTUP FROM FORCED OUTAGE 97-03. | | | | ALL CONTAINMENT PURGE VALVES ARE CLOSED. ADMINISTRATIVE CONTROLS WILL BE | | IMPLEMENTED TO PRECLUDE CREATION OF A BYPASS FLOWPATH UNTIL PROCEDURE | | CHANGES CAN BE COMPLETED." | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33365 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SEABROOK REGION: 1 |NOTIFICATION DATE: 12/08/97 | |UNIT: [1] [ ] [ ] STATE: NH |NOTIFICATION TIME: 15:36 [ET]| |RX TYPE: [1] W-4-LP |EVENT DATE: 12/08/97 | +------------------------------------------------+EVENT TIME: 09:51[EST]| |NRC NOTIFIED BY: MESSINA |LAST UPDATE DATE: 12/08/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JIM TRAPP 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 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LICENSEE SUPERVISOR TESTED POSITIVE FOR ALCOHOL. | | | | DURING AN EAP FOLLOWUP CHECK PERFORMED AT 0951 ON 12/08/97, A LICENSEE | | SUPERVISOR TESTED AT .022 BAC LEVEL. EXTRAPOLATED BACK TO THE TIME THE | | EMPLOYEE ENTERED THE SITE (0730) IS .057 BAC LEVEL WHICH IS IN VIOLATION | | OF THE LICENSEE POLICY OF BEING AT OR ABOVE .04 BAC FOR SCHEDULED WORK. | | THE LICENSEE SUSPENDED THE EMPLOYEE'S PROTECTED AREA ACCESS, GAVE THE | | EMPLOYEE A MINIMUM 14 DAY SUSPENSION WITHOUT PAY, AND WILL CONDUCT A | | WORK REVIEW FROM 12/04/97, TO THE CURRENT DATE. THE EMPLOYEE HAD NO VITAL | | AREA ACCESS DURING THIS PERIOD. 12/04/97 IS THE LAST DATE THE SUBJECT | | SUCCESSFULLY COMPLETED A FITNESS FOR DUTY TEST. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33366 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BEAVER VALLEY REGION: 1 |NOTIFICATION DATE: 12/08/97 | |UNIT: [1] [2] [ ] STATE: PA |NOTIFICATION TIME: 16:12 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 12/08/97 | +------------------------------------------------+EVENT TIME: 16:00[EST]| |NRC NOTIFIED BY: COTTER |LAST UPDATE DATE: 12/08/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JIM TRAPP RDO | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNITS 1 AND 2 MAY HAVE OPERATED OUTSIDE THEIR DESIGN BASIS BECAUSE THEY DID | | NOT HAVE AVAILABLE A MINIMUM OF ONE HHSI/CHARGING PUMP. | | | | "UNIT 1 UFSAR SECTION 6.3.2, EMERGENCY CORE COOLING SYSTEM SYSTEM DESIGN | | AND OPERATION, STATES THE FOLLOWING: 'ADEQUATE EMERGENCY CORE COOLING | | FOLLOWING A LOCA IS PROVIDED BY ECCS...' AND 'THE PRINCIPLE COMPONENTS OF | | THE ECCS WHICH PROVIDE EMERGENCY CORE COOLING IMMEDIATELY FOLLOWING A LOSS | | OF COOLANT ARE THE THREE ACCUMULATORS (ONE FOR EACH LOOP), TWO OF THE THREE | | SAFETY INJECTION CHARGING PUMPS (WHICH PERFORM THE CHARGING FUNCTIONS | | DURING NORMAL OPERATIONS) AND THE TWO LOW HEAD SAFETY INJECTION PUMPS.' | | UFSAR SECTION 1.3.1, SINGLE FAILURE CRITERION, STATES THAT THE EMERGENCY | | CORE COOLING SYSTEM, AND OTHER LISTED SAFETY RELATED FLUID SYSTEMS, ARE | | DESIGNED TO ACCEPT ONLY A SINGLE ACTIVE FAILURE IN THE SHORT TERM, OR TO | | ACCEPT A SINGLE ACTIVE OR PASSIVE FAILURE IN THE LONG TERM FOLLOWING ANY | | ACCIDENT CONDITION. THEREFORE, ADEQUATE CORE COOLING IN THE EVENT OF A | | DESIGN BASIS LOCA IS PROVIDED BY A MINIMUM OF ONE HHSI/CHARGING PUMP AT | | UNIT 1. | | | | UNIT 2 UFSAR SECTION 6.3.2, EMERGENCY CORE COOLING SYSTEM DESIGN, STATES | | THE FOLLOWING: 'THE ECCS COMPONENTS ARE DESIGNED SUCH THAT ADEQUATE CORE | | COOLING IN THE EVENT OF A DESIGN BASIS LOCA IS PROVIDED; 1) IN THE | | INJECTION PHASE BY A MINIMUM OF TWO ACCUMULATORS, ONE HHSI/CHARGING PUMP | | AND ONE LHSI PUMP, AND 2) IN THE RECIRCULATION PHASE BY A MINIMUM OF ONE | | CHARGING PUMP AND ONE RECIRCULATION SPRAY PUMP WITH THEIR ASSOCIATED | | VALVES AND PIPING...' | | | | ON DECEMBER 8, 1997, IT WAS DETERMINED THAT UNIT 1 AND UNIT 2 MAY HAVE | | OPERATED IN A CONDITION THAT IS OUTSIDE THE DESIGN BASIS OF THE PLANT. | | A MINIMUM OF ONE HHSI/CHARGING PUMP MAY NOT HAVE BEEN AVAILABLE TO | | PROVIDE EMERGENCY CORE COOLING AS DESCRIBED IN THE UFSAR DUE TO INTRUSION | | OF GAS INTO THE SUCTION OF THE PUMPS, AND SUBSEQUENT GAS BINDING. THIS | | DETERMINATION IS BASED ON ENGINEERING EVALUATION OF THE RESULTS OF SCOPING | | EXPERIMENTS CONDUCTED TO ASSESS FLUID FLOW PATTERNS ENTERING THE UNIT 1 | | AND UNIT 2 CHARGING PUMPS. | | | | INCREASED MONITORING AND VENT SYSTEM IMPROVEMENTS ARE PLANNED. IN | | ADDITION, FLOW ORIFICES ARE BEING REPLACED AT UNIT 1 AND WILL BE REPLACED | | AT UNIT 2 DURING THE NEXT REFUELING OUTAGE, TO REDUCE THE GENERATION OF | | GAS BUBBLES. PRESENTLY, UNIT 2 GAS MONITORING AND VENTING PRACTICES | | ENSURE OPERABILITY OF THE HHSI/CHARGING PUMPS." | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 33367 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 12/08/97 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 16:38 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 12/07/97 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 22:00[EST]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 12/08/97 | | CITY: PIKETON REGION: 3 +-----------------------------+ | COUNTY: PIKE STATE: OH |PERSON ORGANIZATION| |LICENSE#: GDP-2 AGREEMENT: N |JACOBSON RDO | | DOCKET: 0707002 |JOSE PICCONE, NMSS EO | +------------------------------------------------+ | |NRC NOTIFIED BY: MAY | | |HQ OPS OFFICER: CHAUNCEY GOULD | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NBNL RESPONSE-BULLETIN | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | VIOLATION OF AN APPROVED NUCLEAR SAFETY APPROVAL (NCSA) IN BUILDING X-710. | | | | NCSA-PLANT 018.A01 DOUBLE CONTINGENCY CONTROL MATRIX B.4.1, CONTROL A, | | REQUIREMENT 5 AND NCSA-0710-011.A00A/B.7.1, CONTROL B, REQUIREMENT 3.B WERE | | VIOLATED WHEN A CART OF SAMPLE TUBES WAS DISCOVERED IN BUILDING X-710, ROOM | | 126, NOT SPACED TWO FEET FROM A BAG OF DRY ACTIVE WASTE (DAW), AS REQUIRED. | | THIS CONDITION CONSTITUTES A LOSS OF ONE CONTROL. MASS AND MODERATION | | CONTROLS WERE MAINTAINED THROUGHOUT THIS EVENT. THE CART WAS IMMEDIATELY | | MOVED AND COMPLIANCE RESTORED. THERE WAS NO RELEASE OF HAZARDOUS MATERIALS | | OR RADIOLOGICAL CONTAMINATION EXPOSURES. | | | | THE LICENSEE NOTIFIED DOE AND THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 33368 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: MQS INSPECTION COMPANY, IL |NOTIFICATION DATE: 12/08/97 | | CITY: TRAINER REGION: 1 |NOTIFICATION TIME: 22:06 [ET]| | COUNTY: STATE: PA |EVENT DATE: 12/08/97 | |LICENSE#: 12-00622-07 AGREEMENT: N |EVENT TIME: 08:55[EST]| | DOCKET: |LAST UPDATE DATE: 12/08/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |JIM TRAPP, R1 RDO | | | | +------------------------------------------------+JOHN JACOBSON, R3 RDO | |NRC NOTIFIED BY: BANFIELD | | |HQ OPS OFFICER: CHAUNCEY GOULD | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |IBBF 30.50(b)(2)(ii) EQUIP DISABLED/FAILS | | |NINF INFORMATION ONLY | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AMERSHAM SENTINEL RADIOGRAPHY CAMERA SOURCE DRIVE CABLE FAILURE. | | | | THE NRC LICENSEE, MSQ INSPECTION COMPANY, ELK GROVE VILLAGE, IL, REPORTED | | A PROBLEM WITH AN AMERSHAM SENTINEL RADIOGRAPHY CAMERA, MODEL 660B, LOCATED | | AT THE TOSCO REFINERY IN TRAINER, PA, TO AMERSHAM PERSONNEL. | | | | THE IRIDIUM-192 (62 CURIES) CAMERA SOURCE DRIVE CABLE FAILED AND THE | | ISOTOPE WOULD NOT RETRACT INTO THE CAMERA SHIELDED CONTAINER. THERE WERE | | ONLY MINOR EXPOSURES TO MQS INSPECTION PERSONNEL. AMERSHAM PERSONNEL | | RESPONDED TO THE REFINERY AND RETRACTED THE SOURCE INTO THE SHIELDED | | CONTAINER AT 2143 EST AND THEN TOOK THE CAMERA BACK TO THE THEIR FACTORY. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33369 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SAN ONOFRE REGION: 4 |NOTIFICATION DATE: 12/09/97 | |UNIT: [ ] [2] [3] STATE: CA |NOTIFICATION TIME: 01:32 [ET]| |RX TYPE: [1] W-3-LP,[2] CE,[3] CE |EVENT DATE: 12/08/97 | +------------------------------------------------+EVENT TIME: 19:10[PST]| |NRC NOTIFIED BY: TODD COOK |LAST UPDATE DATE: 12/09/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: | | |DDDD 73.71 UNSPECIFIED PARAGRAPH | | | |BLAINE MURRAY, R4 IAT | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 Y 100 POWER OPERATION | 100 POWER OPERATION | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | PLANT SECURITY EVENT - | | | | PHYSICAL ASSAULT ON A CONTRACTOR INSIDE THE UNIT 2 AUXILIARY FEEDWATER | | BUILDING. COMPENSATORY MEASURES FULLY IMPLEMENTED WITHIN LICENSEE | | SPECIFIED TIME LIMITS. THE LICENSEE WILL INFORM THE NRC RESIDENT | | INSPECTOR. REFER TO THE HOO LOG FOR ADDITIONAL DETAILS. | +------------------------------------------------------------------------------+