U.S. Nuclear Regulatory Commission Operations Center Event Reports For 12/05/97 - 12/08/97 ** EVENT NUMBERS ** 33350 33351 33352 33353 33354 33355 33356 33357 33358 33359 33360 33361 33362 33363 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33350 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SEABROOK REGION: 1 |NOTIFICATION DATE: 12/05/97 | |UNIT: [1] [ ] [ ] STATE: NH |NOTIFICATION TIME: 09:02 [ET]| |RX TYPE: [1] W-4-LP |EVENT DATE: 12/05/97 | +------------------------------------------------+EVENT TIME: 04:27[EST]| |NRC NOTIFIED BY: RON STRICKLAND |LAST UPDATE DATE: 12/05/97 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |KATHLEEN MODES RDO | |NLTR LICENSEE 24 HR REPORT | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | DEAD SEAL FOUND IN THE FOREBAY OF THE INTAKE STRUCTURE. | | | | THE LICENSEE WILL NOTIFY THE NATIONAL MARINE FISHERIES SERVICE OF THIS | | OCCURRENCE. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 33351 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: CALUMET TESTING SERVICES |NOTIFICATION DATE: 12/05/97 | | CITY: GRIFFITH REGION: 3 |NOTIFICATION TIME: 10:39 [ET]| | COUNTY: STATE: IN |EVENT DATE: 11/21/97 | |LICENSE#: 13-16347-01 AGREEMENT: N |EVENT TIME: 10:45[EST]| | DOCKET: |LAST UPDATE DATE: 12/05/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |MARK RING RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: TOM KEILMAN | | |HQ OPS OFFICER: DOUG WEAVER | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | RADIOGRAPHY SOURCE ASSEMBLY SEPARATED FROM CONTROL CABLE. | | | | A 70 Ci Ir-192 SOURCE ASSEMBLY MODEL #424-9 SEPARATED FROM THE CONTROL | | CABLE. THE SEPARATION WAS DISCOVERED BY A WORKER USING HIS SURVEY | | INSTRUMENT. ONE WORKER RECEIVED 25 mR DURING THE PROCESS OF RECOVERING | | THE SOURCE. | | | | THE LICENSEE HAD PREVIOUSLY NOTIFIED REGION 3 ABOUT THIS EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 33352 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 12/05/97 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 11:52 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 12/04/97 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 12:00[EST]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 12/05/97 | | 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 LAB. | | | | ON 12/04/97, AT 1200, IT WAS DISCOVERED THAT A NUCLEAR CRITICALITY SAFETY | | APPROVAL (NCSA) REQUIREMENT WAS NOT MET IN THE X-710 URANIUM SAMPLING | | LABORATORY ROOM 111. NCSA-710-006.AOO LISTS TWO NUCLEAR CRITICALITY SAFETY | | CONTROLS. THE FIRST CONTROL (ADMINISTRATIVE) REQUIRES THAT EACH SAMPLE | | CONTAINER FILLED WITH URANIUM-BEARING MATERIAL SHALL BE LABELED WITH ITS | | U-235 ENRICHMENT AND MASS: EXCEPTION BEING THAT P-10 TUBES AND HOKE TUBES | | SHALL HAVE PAPERWORK IDENTIFYING EACH IN LIEU OF LABELS. THE SECOND | | CONTROL (ADMINISTRATIVE) SPACING AND STORAGE WERE MAINTAINED THROUGH OUT | | THIS EVENT. SEVERAL U-TUBES WERE FOUND ON A PORTABLE CART UNLABELED, WHICH | | VIOLATES A REQUIREMENT OF THE FIRST CONTROL. THE LOSS OF ONE CONTROL | | (LABELING) MAKES THIS EVENT REPORTABLE TO THE NRC WITHIN 24 HOURS. THERE | | WAS NO RELEASE OF HAZARDOUS MATERIAL OR RADIOLOGICAL CONTAMINATION CONTROL | | EXPOSURE ASSOCIATED WITH THIS EVENT. | | | | THIS EVENT COULD HAVE RESULTED IN EXCEEDING THE 350 g U-235 LIMIT AND A | | CRITICAL MASS. ALSO, BY NOT LABELING THE U-TUBES, PERSONNEL WOULD NOT BE | | ABLE TO IDENTIFY THE CONTENTS OF THE U-TUBES OR THEIR STORAGE LIMITS. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |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: 12/05/97 | | 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. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33354 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SEABROOK REGION: 1 |NOTIFICATION DATE: 12/05/97 | |UNIT: [1] [ ] [ ] STATE: NH |NOTIFICATION TIME: 12:35 [ET]| |RX TYPE: [1] W-4-LP |EVENT DATE: 12/05/97 | +------------------------------------------------+EVENT TIME: 11:52[EST]| |NRC NOTIFIED BY: STRICKLAND |LAST UPDATE DATE: 12/05/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |KATHLEEN MODES 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 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | PLANT SHUTDOWN DUE TO THRU-WALL LEAK IN RHR SYSTEM PIPING. | | | | THE LICENSEE COMMENCED A PLANT SHUTDOWN IN ACCORDANCE WITH TECHNICAL | | SPECIFICATIONS DUE TO THE DISCOVERY OF A ONE DROP PER MINUTE UNISOLABLE | | LEAK FROM THE RHR PUMP 'A' SUCTION RELIEF LINE. THE LICENSEE ENTERED | | TECHNICAL SPECIFICATION 3.6.1.2 DUE TO THE LOSS OF THE CONTAINMENT BOUNDARY | | CAUSED BY THE LEAK. THE LICENSEE WILL MAKE A PRESS RELEASE REGARDING THIS | | EVENT. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |HOSPITAL | |EVENT NUMBER: 33355 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: CANCER TREATMENT CENTER |NOTIFICATION DATE: 12/05/97 | | CITY: WORCESTER REGION: 3 |NOTIFICATION TIME: 14:50 [ET]| | COUNTY: STATE: OH |EVENT DATE: 12/05/97 | |LICENSE#: 34-25978-01 AGREEMENT: N |EVENT TIME: 08:55[EST]| | DOCKET: |LAST UPDATE DATE: 12/05/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |MARK RING RDO | | |FRED COMBS, NMSS EO | +------------------------------------------------+ | |NRC NOTIFIED BY: M. MORRIS | | |HQ OPS OFFICER: BOB STRANSKY | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |IBBF 30.50(b)(2)(ii) EQUIP DISABLED/FAILS | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | OVEREXPOSURE DUE TO EQUIPMENT MALFUNCTION. | | | | A PATIENT RECEIVING TREATMENT USING A THERATRON MODEL 780 MACHINE WAS | | OVEREXPOSED WHEN THE Co-60 SOURCE FAILED TO RETRACT INTO ITS PROTECTIVE | | DRAWER AT THE CONCLUSION OF THE TREATMENT. THE PATIENT REMAINED IN | | THE RADIATION BEAM FOR APPROXIMATELY 30 SECONDS LONGER THAN EXPECTED | | BEFORE BEING DIRECTED TO MOVE OUT FROM UNDER THE HEAD OF THE MACHINE. | | THE LICENSEE ESTIMATES THAT THE PATIENT RECEIVED AN OVEREXPOSURE OF | | APPROXIMATELY 30 cGy (RADS) AS A RESULT OF THIS EVENT. A THERAPIST | | ENTERED THE ROOM TO ASSIST THE PATIENT IN HER EGRESS. THE LICENSEE | | HAS SECURED THE ROOM AND CONTACTED THE VENDOR. THE LICENSEE HAS ALREADY | | CONTACTED NRC REGION 3 REGARDING THIS EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33356 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HOPE CREEK REGION: 1 |NOTIFICATION DATE: 12/05/97 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 15:35 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 12/05/97 | +------------------------------------------------+EVENT TIME: 15:00[EST]| |NRC NOTIFIED BY: JESSE PIKE |LAST UPDATE DATE: 12/05/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |KATHLEEN MODES 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 20 POWER OPERATION | 20 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | PLANT SHUTDOWN DUE TO HPCI AND RCIC SYSTEMS DECLARED INOPERABLE. | | | | "AT 1403 ON 12/05/97, HOPE CREEK ENTERED TECH SPEC 3.0.3 DUE TO THE | | CONCURRENT INOPERABILITY OF THE HIGH PRESSURE COOLANT INJECTION (HPCI) | | SYSTEM AND THE REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM. THE HPCI | | SYSTEM WAS DECLARED INOPERABLE AT 1403 DUE TO HIGH VIBRATION ON THE HPCI | | TURBINE DURING THE PERFORMANCE OF AN INSERVICE SURVEILLANCE TEST. RCIC HAD | | PREVIOUSLY BEEN DECLARED INOPERABLE (AT 0529 ON 12/5/97) DUE TO A PROBLEM | | WITH THE GOVERNOR CONTROL SYSTEM THAT WAS DISCOVERED DURING THE RCIC | | INSERVICE SURVEILLANCE TEST. | | | | THERE IS NO LIMITING CONDITION OF OPERATION TO ADDRESS THE CONCURRENT | | INOPERABILITY OF HPCI AND RCIC; THEREFORE, TECH SPEC 3.0.3 WAS ENTERED. | | A PLANT SHUTDOWN WAS INITIATED AT 1500. | | | | NO OTHER MAJOR EQUIPMENT IS INOPERABLE AT THIS TIME." | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33357 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: LASALLE REGION: 3 |NOTIFICATION DATE: 12/05/97 | |UNIT: [1] [2] [ ] STATE: IL |NOTIFICATION TIME: 16:12 [ET]| |RX TYPE: [1] GE-5,[2] GE-5 |EVENT DATE: 12/05/97 | +------------------------------------------------+EVENT TIME: 13:30[CST]| |NRC NOTIFIED BY: JEFF WILLIAMS |LAST UPDATE DATE: 12/05/97 | |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 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DESIGN ISSUE REGARDING SIZING OF NITROGEN ACCUMULATORS FOR THE AUTOMATIC | | DEPRESSURIZATION SYSTEM. | | | | "THE SYSTEM FUNCTIONAL PERFORMANCE REVIEW (SFPR) CONDUCTED EARLIER THIS | | YEAR RAISED AN ISSUE THAT THE AUTOMATIC DEPRESSURIZATION SYSTEM (ADS) | | ACCUMULATORS IN THE DRYWELL MIGHT BE POTENTIALLY UNDERSIZED, OR THAT | | THEY WERE ADEQUATELY SIZED, AND THE UPDATED FINAL SAFETY ANALYSIS REPORT | | (UFSAR) MIGHT CONTAIN CONFLICTING INFORMATION THAT REQUIRED CLARIFICATION. | | THE SFPR DOCUMENTED THIS ISSUE IN VARIOUS CORRECTIVE ACTION ITEMS. UFSAR | | SECTION 5.2.2.4.1 SUGGESTS THE ACCUMULATORS NEED TO BE SIZED TO FULLY OPEN | | THE ADS VALVES ONCE, AT A POST LOSS OF COOLANT ACCIDENT (LOCA) CONTAINMENT | | DESIGN PRESSURE OF 45 PSIG, ON A LOSS OF PNEUMATIC SUPPLY TO THE | | ACCUMULATOR. UFSAR SECTION 7.3.1.2.2.1 SAYS THE ACCUMULATORS ARE DESIGNED | | SO THE VALVES CAN OPEN TWICE UNDER THE SAME CONDITIONS. ENGINEERING'S | | INVESTIGATION TO DATE HAS BEEN INCONCLUSIVE IN PROVING WHETHER THE SINGLE | | ADS ACTUATION IS THE ACTUAL SAFETY SYSTEM DESIGN LIMIT AND SIZING THE | | ACCUMULATORS FOR TWO ACTUATIONS WAS DONE FOR ADDITIONAL DESIGN MARGIN, | | OR IF THE TWO ACTUATION CASE IS THE DESIGN LIMITING CONDITION. THE | | ENGINEERING CALCULATIONS FOUND TO DATE PROVE THAT OUR ACCUMULATORS WILL | | MEET THE SINGLE ACTUATION, BUT INDICATE THAT ACCUMULATOR PRESSURE WILL BE | | 0.5 TO 1 PSIG TOO LOW TO FULLY OPEN THE ADS VALVES AS REQUIRED ON A SECOND | | ACTUATION. GE WAS ASKED TO SEARCH FOR ADDITIONAL DOCUMENTATION AND HELP | | RESOLVE THIS ISSUE THIS SUMMER, BUT THEIR EFFORTS WERE STOPPED BY A GE STOP | | WORK ORDER ON SAFETY RELATED WORK THIS FALL, AND HAVE ONLY RECENTLY BEEN | | RESTARTED. MORE WORK BY ENGINEERING AND GE MAY YET PROVE THIS TO BE A | | NON-ISSUE, BUT GIVEN THE SAFETY SIGNIFICANCE OF THE COMPONENTS INVOLVED, | | AND THE FACT THAT WE HAVE NOT BEEN ABLE TO RESOLVE THIS ISSUE AFTER A | | FAIRLY EXTENSIVE EFFORT TO DATE SUGGESTS THAT WE SHOULD REEVALUATE THIS | | CONCERN AS IF THE ACCUMULATORS ARE UNDERSIZED AT THIS TIME FOR OPERABILITY | | AND REPORTABILITY. THIS IS A CONSERVATIVE ENGINEERING DECISION PRIOR TO | | CONTINUING WITH THE ANALYSIS AND DISCOVERY EFFORT." | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33358 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BEAVER VALLEY REGION: 1 |NOTIFICATION DATE: 12/05/97 | |UNIT: [1] [ ] [ ] STATE: PA |NOTIFICATION TIME: 18:02 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 12/05/97 | +------------------------------------------------+EVENT TIME: 17:50[EST]| |NRC NOTIFIED BY: KONOPKA |LAST UPDATE DATE: 12/05/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |KATHLEEN MODES 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 +------------------------------------------------------------------------------+ | POTENTIAL TO RENDER AUXILIARY FEEDWATER PUMPS INOPERABLE DUE TO MISSING | | PENETRATION SEAL. | | | | THE FOLLOWING IS TEXT OF A FACSIMILE SUBMITTED BY THE LICENSEE: | | | | "THE UFSAR (APPENDIX D.5) STATES THE FOLLOWING WITH REGARD TO | | INVESTIGATIONS OF THE EFFECTS OF HIGH ENERGY PIPING BREAKS IN THE MAIN | | STEAM VALVE CUBICLE OUTSIDE CONTAINMENT: 'THE STEAM SUPPLY PIPING FROM THE | | MAIN STEAM LINES DOWN TO THE TURBINE DRIVEN MAIN FEEDWATER PUMP RUN JUST | | BELOW THE MAIN FEEDWATER PIPING, AND ARE SUBJECT TO DAMAGE FROM A MAIN | | FEEDWATER LINE BREAK. MAIN FEEDWATER LINE PIPE WHIP RESTRAINTS PROVIDE | | SOME PROTECTION FOR THESE LINES. LOSS OF THESE LINES IS CONSIDERED | | ACCEPTABLE SINCE THE ACCIDENT ANALYSIS CONSIDERED ONE OF THE TWO 50% | | CAPACITY ELECTRIC DRIVEN MAIN FEEDWATER PUMPS IS ADEQUATE...' | | | | THE UFSAR (APPENDIX D.5) STATES THE FOLLOWING REGARDING FLOOR PENETRATION | | SEALS IN THE MAIN STEAM VALVE CUBICLE: 'THE ENVIRONMENTAL EFFECT OF THE | | FEEDWATER LINE BREAK IS 2.1 PSI, 214øF, 100% HUMIDITY AND 1.66 FT OF | | FLOODING... THE FLOODING TAKES PLACE AS A RESULT OF THE BLOWDOWN OF THE | | AFFECTED STEAM GENERATOR AND TAKES PLACE OVER A LONG TIME. ATMOSPHERIC | | DUMP VALVES THUS PREVENT THE BLOWDOWN. IN ANY EVENT, THOSE FLOOR | | PENETRATIONS ABOVE THE AUXILIARY FEEDWATER PUMPS AND THE QUENCH SPRAY PUMPS | | HAVE BEEN FITTED WITH DAMS CAPABLE OF HANDLING THE MAXIMUM POSSIBLE LEVEL | | OF WATER. THESE DAMS WILL PREVENT WATER FROM POURING ONTO ELECTRIC MOTORS. | | FLOOR WATER WILL FLOW VIA THE PIPE TUNNEL ACCESS TO THE PIPE TUNNEL WHERE | | IT WILL BE PUMPED OUT BY THE SUMP PUMPS.' | | | | ON SEPTEMBER 9, 1997, THE NUCLEAR SHIFT SUPERVISOR WAS NOTIFIED OF A | | MISSING FLOOR PENETRATION SEAL. THE PENETRATION IS ASSOCIATED WITH A | | 3/4" DRAIN LINE LOCATED IN THE UNIT 1 MAIN STEAM VALVE CUBICLE FLOOR. | | ON DECEMBER 5, 1997, AN ENGINEERING EVALUATION CONCLUDED THAT IN THE EVENT | | OF A FEEDWATER LINE BREAK, WATER COULD DRAIN THROUGH THE MISSING FLOOR | | PENETRATION SEAL AND ENTER THE PUMP ROOM BELOW, CAUSING A TEMPERATURE RISE | | IN THE AREA THAT COULD DISABLE THE MOTOR DRIVEN AUXILIARY FEEDWATER PUMPS. | | AS NOTED IN THE UFSAR EXCERPT ABOVE, THE TURBINE DRIVEN AUXILIARY FEEDWATER | | PUMP MAY ALSO BE UNAVAILABLE IN THE EVENT OF A FEEDWATER LINE BREAK. THE | | POSTULATED EVENT, WITH THE MISSING FLOOR PENETRATION SEAL, COULD CAUSE | | THREE AUXILIARY FEEDWATER PUMPS TO BECOME INOPERABLE. THIS CONDITION IS | | OUTSIDE THE DESIGN BASIS OF THE PLANT. IT SHOULD BE NOTED THAT THE | | DEDICATED (APPENDIX R) AUXILIARY FEEDWATER PUMP WAS UNAFFECTED AND THIS | | SCENARIO HAS NEVER ACTUALLY OCCURRED AT THE PLANT. INSTALLATION OF A | | HYDROSTATIC AND FIRE RATED SEAL WAS COMPLETED ON OCTOBER 8, 1997." | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33359 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DRESDEN REGION: 3 |NOTIFICATION DATE: 12/06/97 | |UNIT: [ ] [ ] [3] STATE: IL |NOTIFICATION TIME: 05:03 [ET]| |RX TYPE: [1] GE-1,[2] GE-3,[3] GE-3 |EVENT DATE: 12/06/97 | +------------------------------------------------+EVENT TIME: 01:48[CST]| |NRC NOTIFIED BY: BRIAN SAMPSON |LAST UPDATE DATE: 12/06/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | | | | | 3 | N Y 99 POWER OPERATION | 99 POWER OPERATION | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | -PERIPHERAL CONTROL ROD INSERTED INTO THE CORE DURING A SURVEILLANCE TEST- | | | | DURING THE PERFORMANCE OF UNIT 3 TECH SPEC OPERATING SURVEILLANCE TEST | | #DOS-500-3, AVERAGE POWER RANGE MONITOR ROD BLOCK AND SCRAM FUNCTIONAL | | TEST, PERIPHERAL CONTROL ROD #22-03 RAPIDLY INSERTED TO THE FULL-IN | | POSITION (POSITION 00) FROM THE FULLY WITHDRAWN POSITION (POSITION #48). | | REACTOR PROTECTION SYSTEM, CHANNEL B, WAS DEENERGIZED AT THE TIME AS PART | | OF THE TEST. NO CORE THERMAL LIMITS WERE EXCEEDED OR CHALLENGED. | | | | CONTROL ROOM OPERATORS ELECTRICALLY ISOLATED CONTROL ROD #22-03 AND | | DECLARED IT INOPERABLE PENDING COMPLETION OF A ROOT CAUSE INVESTIGATION. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33360 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PILGRIM REGION: 1 |NOTIFICATION DATE: 12/06/97 | |UNIT: [1] [ ] [ ] STATE: MA |NOTIFICATION TIME: 10:18 [ET]| |RX TYPE: [1] GE-3 |EVENT DATE: 12/06/97 | +------------------------------------------------+EVENT TIME: 09:07[EST]| |NRC NOTIFIED BY: GORDON FIEDLER |LAST UPDATE DATE: 12/06/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MIKE MODES RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 75 POWER OPERATION | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - AUTO Rx SCRAM/MAIN TURBINE TRIP DUE TO FAILED MAIN FEED REG VALVE - | | | | WHILE STARTING UP THE PLANT, THE 'A' MAIN FEEDWATER REGULATING VALVE | | FAILED OPEN DUE TO A LOSS OF AIR FOR UNKNOWN REASONS. THE LICENSEE IS | | INVESTIGATING THE CAUSE. | | | | THE HIGH REACTOR VESSEL WATER LEVEL CAUSED THE MAIN TURBINE TO AUTO TRIP | | WHICH CAUSED THE REACTOR TO AUTO SCRAM FROM 75% POWER. ALL CONTROL RODS | | INSERTED COMPLETELY. PRIMARY CONTAINMENT ISOLATION SYSTEM GROUP 2 | | (REACTOR WATER CLEANUP SYSTEM) ISOLATED AND GROUP 6 (SECONDARY CONTAINMENT | | ISOLATION SYSTEM) ACTUATED, AS DESIGNED. | | | | THE PLANT IS STABLE IN CONDITION 3 (HOT SHUTDOWN). | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR AND PLANS TO ISSUE A PRESS | | RELEASE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 33361 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: WASTE MANAGEMENT |NOTIFICATION DATE: 12/06/97 | | CITY: LANCASTER REGION: 4 |NOTIFICATION TIME: 14:37 [ET]| | COUNTY: STATE: CA |EVENT DATE: 12/06/97 | |LICENSE#: AGREEMENT: Y |EVENT TIME: 08:30[PST]| | DOCKET: |LAST UPDATE DATE: 12/06/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |GARY SANBORN RDO | | |JOSE PICCONE, NMSS EO | +------------------------------------------------+ | |NRC NOTIFIED BY: DAVE EDWARDS | | |HQ OPS OFFICER: BOB STRANSKY | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | A TRUCK CONTAINING WASTE FROM THE LOS ANGELES TRANSFER STATION SET OFF A | | RADIATION MONITOR UPON ARRIVAL AT THE LANCASTER, CA LANDFILL. THE LOAD HAS | | BEEN CONTAINED, AND LOCAL GOVERNMENT AGENCIES HAVE BEEN CONTACTED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 33362 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 12/06/97 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 14:57 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 12/06/97 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 05:00[EST]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 12/06/97 | | CITY: PIKETON REGION: 3 +-----------------------------+ | COUNTY: PIKE STATE: OH |PERSON ORGANIZATION| |LICENSE#: GDP-2 AGREEMENT: N |MARK RING RDO | | DOCKET: 0707002 |JOSE PICCONE, NMSS EO | +------------------------------------------------+ | |NRC NOTIFIED BY: RON CRABTREE | | |HQ OPS OFFICER: BOB STRANSKY | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NBNL RESPONSE-BULLETIN | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | 24-HOUR NRC BULLETIN 91-01 REPORT. | | | | "AT 0500 HOURS, 12/06/97, LABORATORY PERSONNEL DISCOVERED A VIOLATION OF AN | | APPROVED NUCLEAR CRITICALITY SAFETY APPROVAL (NCSA) IN THE X-710 FACILITY. | | NCSA-0710-011.A00 DOUBLE CONTINGENCY CONTROL MATRIX, CONTROL B, REQUIREMENT | | 3.b FOR CONTINGENCY EVENT A/B.7.1.a WAS VIOLATED WHEN TWO CARTS WITH SAMPLE | | CONTAINERS ON EACH CART WERE DISCOVERED TO BE ADJACENT TO ONE ANOTHER IN | | ROOM 115, NOT SPACED 2 FEET EDGE-TO-EDGE AS REQUIRED. THIS CONSTITUTES THE | | LOSS OF ONE CONTROL AS DEFINED IN DOUBLE CONTINGENCY CONTROL MATRIX, PART B | | OF NCSA-0710-011.A00. ALTHOUGH ROOM 115 IS NOT SPECIFICALLY LISTED IN THE | | REQUIREMENT FOR CONTROL A (THE CONTROL WHICH LIMITS A 'BATCH' OF SAMPLE | | TUBES TO 350 GRAMS U-235 NET) IT SHOULD BE NOTED THAT THIS CONTROL WAS | | MAINTAINED THROUGHOUT THIS EVENT. ALTHOUGH THE NCSA ALLOWS A MAXIMUM OF | | 75 OF THESE TYPES OF SAMPLE CONTAINERS CONTAINING LESS THAN 20 WT% U-235 TO | | BE CONSIDERED A BATCH, IT IS IMPORTANT TO NOTE THAT IN THIS EVENT 1 CART | | CONTAINED A 'BATCH' OF APPROXIMATELY 30 SAMPLE CONTAINERS AND THE OTHER | | CART CONTAINED A 'BATCH' OF APPROXIMATELY 25 SAMPLE CONTAINERS WITH ALL | | SAMPLE MATERIAL LESS THAN 25 WT% U-235. THIS LOSS OF ONE CONTROL MAKES | | THIS EVENT REPORTABLE TO THE NRC PER UE2-RA-RE1030, APPENDIX D, CRITERIA A, | | SECTION 4(a). THERE WAS NO RELEASE OF HAZARDOUS MATERIALS OR RADIOLOGICAL | | CONTAMINATION EXPOSURE ASSOCIATED WITH THIS EVENT." | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33363 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PRAIRIE ISLAND REGION: 3 |NOTIFICATION DATE: 12/06/97 | |UNIT: [1] [ ] [ ] STATE: MN |NOTIFICATION TIME: 17:29 [ET]| |RX TYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 12/06/97 | +------------------------------------------------+EVENT TIME: 14:55[CST]| |NRC NOTIFIED BY: DUANE JOHNSON |LAST UPDATE DATE: 12/06/97 | |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 | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | APPENDIX R ISSUE - INSUFFICIENT SEPARATION OF PRESSURIZER LEVEL | | INSTRUMENTATION CHANNELS. | | | | THE LICENSEE'S 10CFR50, APPENDIX R ANALYSIS TAKES CREDIT FOR SEPARATION | | BETWEEN THE CHANNELS OF THE PRESSURIZER LEVEL INSTRUMENTATION BASED UPON | | INFORMATION CONTAINED IN PLANT DRAWINGS. THE LICENSEE DISCOVERED THAT | | THE INFORMATION IN THE DRAWINGS IS INCORRECT AND THE NECESSARY SEPARATION | | REQUIREMENTS ARE NOT MET; THEREFORE, THE APPENDIX R ANALYSIS IS INVALID. | | SPECIFICALLY, THE ISSUE INVOLVES INSUFFICIENT SEPARATION OF CABLES IN CABLE | | TRAYS. | | | | THE LICENSEE HAS TAKEN COMPENSATORY MEASURES INCLUDING (1) INSTRUCTING | | OPERATORS THAT THE USE OF THE REACTOR VESSEL LEVEL INSTRUMENTATION SYSTEM | | MAY BE NECESSARY IN THE EVENT OF A FIRE, AND (2) POSTING A CONTINUOUS FIRE | | WATCH IN THE AFFECTED AREA. THE LICENSEE IS ALSO MAKING MODIFICATIONS TO | | THE DESIGN TO PROTECT ONE CHANNEL OF PRESSURIZER LEVEL INSTRUMENTATION IN | | THE EVENT OF A FIRE IN THE AFFECTED AREA. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+