U.S. Nuclear Regulatory Commission Operations Center Event Reports For 11/07/97 - 11/10/97 ** EVENT NUMBERS ** 33229 33230 33231 33232 33233 33234 33235 33236 33237 33238 33239 33240 33241 33242 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33229 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SAINT LUCIE REGION: 2 |NOTIFICATION DATE: 11/07/97 | |UNIT: [ ] [2] [ ] STATE: FL |NOTIFICATION TIME: 08:46 [ET]| |RX TYPE: [1] CE,[2] CE |EVENT DATE: 11/07/97 | +------------------------------------------------+EVENT TIME: 04:50[EST]| |NRC NOTIFIED BY: SWIATEK |LAST UPDATE DATE: 11/07/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CHUCK OGLE RDO | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | DOT NATIONAL RESPONSE CENTER AND FLORIDA NOTIFIED OF HYDRAZINE RELEASE. | | | | AT 0145 ON 11/07/97, A LICENSEE CHEMISTRY TECHNICIAN NOTICED A REDUCTION | | IN THE AMOUNT OF HYDRAZINE THAT WAS INJECTED INTO THE FEEDWATER SYSTEM. | | A LICENSEE INVESTIGATION REVEALED THAT HYDRAZINE WAS LEAKING TO A DRAIN | | LINE TO A FLOOR DRAIN AND TO A SETTLING POND ONSITE. THE DRAIN LINE WAS | | OPEN AS PART OF A CLEARANCE ON A PARALLEL PUMP AND THE ASSOCIATED ISOLATION | | VALVE WAS NOT FULLY CLOSED. THE AMOUNT OF HYDRAZINE RELEASED TO THE POND | | WAS APPROXIMATELY 10 POUNDS. ANY RELEASE OF HYDRAZINE IN EXCESS OF 1 POUND | | IS REPORTABLE. | | | | THE LICENSEE DETERMINED THIS EVENT TO BE REPORTABLE AT 0450 AND NOTIFIED | | THE DOT NATIONAL RESPONSE CENTER AND THE FLORIDA EMERGENCY RESPONSE | | COMMISSION OF THE RELEASE WITHIN ONE HOUR. | | | | THE LICENSEE STOPPED THE HYDRAZINE RELEASE BY CLOSING THE ISOLATION VALVE. | | THE RELEASE IS CONTAINED IN THE SETTLING POND ONSITE. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33230 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: NORTH ANNA REGION: 2 |NOTIFICATION DATE: 11/07/97 | |UNIT: [1] [2] [ ] STATE: VA |NOTIFICATION TIME: 10:13 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 11/07/97 | +------------------------------------------------+EVENT TIME: 08:45[EST]| |NRC NOTIFIED BY: JAY LEBERSTIEN |LAST UPDATE DATE: 11/07/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CHUCK OGLE 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 Y 100 POWER OPERATION | 100 POWER OPERATION | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | VIRGINIA NOTIFIED OF ONE CUBIC FOOT OF CONCRETE GOING INTO LAKE ANNA. | | | | WHILE PERFORMING AN ENVIRONMENTAL AUDIT OF STATION ACTIVITIES, THE LICENSEE | | DETERMINED THAT A SMALL QUANTITY OF CONCRETE MAY HAVE ENTERED LAKE ANNA | | DURING AN ONGOING EROSION ABATEMENT PROJECT. STATION PERSONNEL HAVE BEEN | | USING WASTE CONCRETE TO STABILIZE AN AREA OF EROSION ON A SMALL SECTION OF | | THE BANK OF THE LAKE. EXAMINATION OF THE LAKE SEDIMENT AT THE BOTTOM OF | | THE BANK REVEALED THE PRESENCE OF LESS THAN ONE CUBIC FOOT OF CONCRETE. | | | | THE LICENSEE NOTIFIED THE VIRGINIA DEPARTMENT OF ENVIRONMENTAL QUALITY. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33231 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HATCH REGION: 2 |NOTIFICATION DATE: 11/07/97 | |UNIT: [1] [2] [ ] STATE: GA |NOTIFICATION TIME: 10:29 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 11/07/97 | +------------------------------------------------+EVENT TIME: 09:33[EST]| |NRC NOTIFIED BY: FRANK GORLEY |LAST UPDATE DATE: 11/07/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CHUCK OGLE 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 REFUELING | 0 REFUELING | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | NON-LICENSED LICENSEE SUPERVISOR TESTED POSITIVE FOR ALCOHOL. | | | | A NON-LICENSED SOUTHERN NUCLEAR EMPLOYEE (SUPERVISOR) WAS GIVEN A FOR-CAUSE | | TEST FOR ALCOHOL. THE INDIVIDUAL TESTED POSITIVE FOR ALCOHOL. THE | | INDIVIDUAL WAS ESCORTED OFFSITE BY SECURITY DEPARTMENT PERSONNEL AND HIS | | PLANT ACCESS BADGE WAS SUSPENDED. THE INDIVIDUAL WILL BE PLACED IN | | SOUTHERN NUCLEAR MANDATORY EMPLOYEE ASSISTANCE PROGRAM FOR EVALUATION. | | | | THE LICENSEE WILL REVIEW THE INDIVIDUAL'S RECENT WORK ACTIVITIES. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33232 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FT CALHOUN REGION: 4 |NOTIFICATION DATE: 11/07/97 | |UNIT: [1] [ ] [ ] STATE: NE |NOTIFICATION TIME: 12:04 [ET]| |RX TYPE: [1] CE |EVENT DATE: 11/07/97 | +------------------------------------------------+EVENT TIME: 10:40[CST]| |NRC NOTIFIED BY: ERICK MATZKE |LAST UPDATE DATE: 11/07/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PHIL HARRELL RDO | |AUNA 50.72(b)(1)(ii)(A) UNANALYZED COND OP | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - LOW PRESSURE SI SYSTEM MAY BE SUSCEPTIBLE TO WATER HAMMER LOADS - | | | | A DRAFT CALCULATION PERFORMED BY THE LICENSEE'S CONTRACTOR, DUKE | | ENGINEERING COMPANY, INDICATES THAT THE LOW PRESSURE SAFETY INJECTION | | (LPSI) SYSTEM MAY BE SUSCEPTIBLE TO WATER HAMMER LOADS IN EXCESS OF PIPING | | SUPPORT ALLOWABLES. THIS CONDITION IS POSSIBLE IF NITROGEN VOIDS OF | | CERTAIN CRITICAL SIZES ARE PRESENT IN THE SAFETY INJECTION (SI) SYSTEM | | PIPING DURING A SI ACTUATION SYSTEM SCENARIO. THIS CALCULATION WAS | | PERFORMED AS A RESULT OF SIGNIFICANT LEAKAGE FROM SI TANKS #SI-6A AND | | #SI-6C IDENTIFIED IN CONDITION REPORT #199700570 DATED 05/13/97. | | | | A PREVIOUS OPERABILITY EVALUATION PERFORMED AS A RESULT OF THIS CONDITION | | REPORT AND THE SUBSEQUENT OPERATIONS MEMO ENSURE THE OPERABILITY OF THE | | LPSI SYSTEM BY IMPLEMENTING CONTINGENCY MEASURES TO MAINTAIN THE LPSI | | HEADER AT A PRESSURE ABOVE 210 PSIG. | | | | BASED ON PREVIOUS SI TANK LEAKAGE AND POTENTIAL LOW HEADER PRESSURE, | | THE LPSI SYSTEM MAY HAVE BEEN IN AN UNANALYZED CONDITION IN THE PAST. | | THE LICENSEE IS PERFORMING A REVIEW TO DETERMINE THE EXTENT OF THE | | PREVIOUS SI TANK LEAKAGE. | | | | THE HIGH PRESSURE SAFETY INJECTION (HPSI) SYSTEM IS NOT CURRENTLY | | SUSCEPTIBLE TO WATER HAMMER LOADS SINCE SI TANK LEAKAGE HAS NOT OCCURRED | | INTO THE HPSI SYSTEM. | | | | THIS REPORT IS BEING MADE TO DOCUMENT THIS HISTORICAL EVENT. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33233 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOK REGION: 3 |NOTIFICATION DATE: 11/07/97 | |UNIT: [1] [2] [ ] STATE: MI |NOTIFICATION TIME: 17:27 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 11/07/97 | +------------------------------------------------+EVENT TIME: 14:30[EST]| |NRC NOTIFIED BY: MARY BETH DEPUYDT |LAST UPDATE DATE: 11/07/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MIKE JORDAN RDO | |AUNA 50.72(b)(1)(ii)(A) UNANALYZED COND OP | | |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 N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | -SEVERAL AUXILIARY BUILDING CABLE TRAYS IN VIOLATION OF 10CFR50, APPENDIX R | | | | 10CFR50, APPENDIX R, SECTION III.G.2.(b) REQUIRES A SEPARATION SPACE OF | | 20 FEET BETWEEN TRAINS WITH NO INTERVENING COMBUSTIBLE MATERIALS WITH FIRE | | DETECTION AND SUPPRESSION INSTALLED. COOK UNITS 1 AND 2 DEVIATE FROM THIS | | REQUIREMENT BECAUSE AT TWO LOCATIONS IN THE AUXILIARY BUILDING (ELEVATIONS | | 587 FEET AND 609 FEET) CABLE TRAYS ARE INSTALLED WITH INTERVENING | | COMBUSTIBLE MATERIALS (THERMOLAG) INSIDE THE 20 FOOT SEPARATION SPACE. | | THUS, COOK IS NOT IN COMPLIANCE WITH 10CFR50, APPENDIX R. | | | | AT 1430 CST ON 11/07/97, THE LICENSEE DETERMINED THAT THIS CONDITION | | CONSTITUTED AN UNANALYZED CONDITION, OUTSIDE THE PLANT DESIGN BASIS AND | | WAS THEREFORE REPORTABLE TO THE NRC. | | | | COOK'S CONFIGURATION HAD BEEN DESCRIBED TO THE NRC IN SUBMITTALS DATING | | BACK TO 1983. HOWEVER, THE DEVIATION FROM 10CFR50, APPENDIX R DESCRIBED | | ABOVE WAS NOT SPECIFICALLY NOTED IN APPLICABLE APPENDIX R SAFETY EVALUATION | | REPORTS. IN MAY, 1997, THE LICENSEE SUBMITTED A LETTER TO THE NRC WHICH | | RESPONDED TO NRC QUESTIONS DATED 03/26/97 REGARDING THIS CONFIGURATION, | | AND PROVIDED THE BASIS FOR WHY THE LICENSEE DID NOT BELIEVE AN EXEMPTION TO | | APPENDIX R WAS NECESSARY. DURING A LICENSEE CONVERSATION WITH NRR STAFF ON | | 11/06/97, THE LICENSEE WAS INFORMED THAT A SPECIFIC EXCEPTION TO APPENDIX R | | IS REQUIRED FOR THIS DEVIATION, OR THE INTERVENING COMBUSTIBLES WOULD HAVE | | TO BE ELIMINATED. | | | | THE FIRE WATCHES FOR INOPERABLE THERMOLAG WERE ESTABLISHED IN JUNE, 1992, | | AND WERE RELEASED ON 12/30/96. ROVING FIRE WATCHES WERE REESTABLISHED ON | | 01/24/97 FOLLOWING NRC QUESTIONS REGARDING THIS DEVIATION. THESE FIRE | | WATCHES WERE UPGRADED TO CONTINUOUS ON 11/06/97 AND WILL REMAIN IN PLACE | | UNTIL THIS ISSUE IS RESOLVED. THUS, ADEQUATE COMPENSATORY ACTIONS HAVE | | BEEN TAKEN. | | | | THE LICENSEE IS CONTINUING TO INVESTIGATE THIS ISSUE. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33234 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CLINTON REGION: 3 |NOTIFICATION DATE: 11/07/97 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 17:42 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 11/07/97 | +------------------------------------------------+EVENT TIME: 13:30[CST]| |NRC NOTIFIED BY: TIM HOLLAND |LAST UPDATE DATE: 11/07/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MIKE JORDAN 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 +------------------------------------------------------------------------------+ | - ALL SAFETY RELATED 480 VOLT MOTORS INOPERABLE DUE TO INADEQUATE PM - | | | | CLINTON IS IN CONDITION 4 (COLD SHUTDOWN) IN A REFUELING OUTAGE. | | | | CLINTON CONDITION REPORT #1-97-09-232 STATES THAT DURING A PLANT WALKDOWN | | ON 09/17/97, THE INTEGRATED SAFETY ASSESSMENT TEAM DISCOVERED THAT | | UNDERNEATH THE #1SX01PC SX PUMP MOTOR THERE WAS AN EXCESSIVE AMOUNT OF | | GREASE AND IT HAD SPRAYED ONTO THE PUMP COUPLING GUARD. | | | | THE BEARINGS OF THIS PUMP MOTOR ARE BEING LUBRICATED ONCE EVERY 18 MONTHS | | PER PREVENTATIVE MAINTENANCE (PM) ITEM #PEMSXMOO3. VENDOR MANUAL | | #K2828B-0003 REQUIRES THAT THE DRAIN PLUG ON THE MOTOR BE REMOVED WHEN | | APPLYING GREASE TO THE MOTOR BEARINGS SO THAT THE NEW GREASE PUSHES THE | | OLD GREASE OUT OF THE DRAIN PLUG HOLE. ELECTRICAL MAINTENANCE TECHNICIANS | | HAVE NOT BEEN REMOVING THE DRAIN PLUG WHEN APPLYING NEW GREASE SINCE THE | | PM ITEM DOES NOT INCLUDE THIS PROCEDURAL STEP. | | | | THE LICENSEE IDENTIFIED THAT THIS IS A GLOBAL CONCERN AT CLINTON FOR SAFETY | | RELATED 480 VOLT MOTORS IN ALL THREE SAFETY DIVISIONS. THUS, UNTIL FURTHER | | AND MORE RIGOROUS INSPECTIONS CAN BE COMPLETED, THE LICENSEE HAS DECLARED | | ALL SAFETY RELATED 480 VOLT MOTORS INOPERABLE. | | | | THE LICENSEE IS DETERMINING CORRECTIVE ACTIONS AND WILL RESOLVE THIS ISSUE | | PRIOR TO PLANT RESTART. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33235 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 11/07/97 | |UNIT: [ ] [3] [ ] STATE: NY |NOTIFICATION TIME: 19:37 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 11/07/97 | +------------------------------------------------+EVENT TIME: 19:32[EST]| |NRC NOTIFIED BY: RUSSELL LONG |LAST UPDATE DATE: 11/07/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 3 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - ATWS BLOCKING SETPOINT SET NONCONSERVATIVELY - | | | | AS A RESULT OF A CONDITION PREVIOUSLY REPORTED BY OTHER UTILITIES, | | THE LICENSEE PERFORMED A REVIEW OF THE ATWS MITIGATION SYSTEM ACTUATION | | CIRCUITRY (AMSAC) DESIGN DOCUMENTS. DURING THIS REVIEW, THE LICENSEE | | DETERMINED THAT THERE IS A DISCREPANCY BETWEEN THE INDIAN POINT UNIT 3 | | AMSAC SETPOINT AND THE NRC AMSAC SAFETY EVALUATION REPORT (SER). | | SPECIFICALLY, THE AMSAC C-20 INTERLOCK IS SET TO ENABLE AMSAC AT | | 40% TURBINE IMPULSE PRESSURE RATHER THAN AT 40% REACTOR POWER AS STATED | | IN THE NRC SER. THE EXISTING C-20 SETPOINT FOR AUTOMATICALLY BLOCKING | | AND ENABLING AMSAC IS NONCONSERVATIVE SINCE IT HAS THE EFFECT OF NOT | | PERMITTING AMSAC ACTUATION UNTIL POWER IS RAISED ABOVE APPROXIMATELY | | 45% POWER. THIS CONDITION HAS EXISTED SINCE INITIAL AMSAC INSTALLATION | | IN 1988. | | | | THE LICENSEE DECLARED THE AMSAC SYSTEM INOPERABLE AND ADMINISTRATIVE | | CONTROLS PERMIT SEVEN DAYS TO RESTORE OPERABILITY. THE LICENSEE IS | | REVISING THE AMSAC SETPOINT TO ASSURE THAT AMSAC IS ARMED AT AND ABOVE | | 40% REACTOR POWER OR EVALUATING THE CONDITION TO DETERMINE IF IT IS | | ACCEPTABLE AS IS. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | | | | NOTE: SEE RELATED EVENTS 33132, 33205, 33217, 33225. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33236 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HOPE CREEK REGION: 1 |NOTIFICATION DATE: 11/07/97 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 20:29 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 11/07/97 | +------------------------------------------------+EVENT TIME: 07:39[EST]| |NRC NOTIFIED BY: DEVON PRICE |LAST UPDATE DATE: 11/07/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LEANNE HARRISON RDO | |AARC 50.72(b)(1)(v) OTHER ASMT/COMM INOP | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | -SAFETY PARAMETER DISPLAY SYSTEM INOP FOR 12 HOURS DURING REFUELING OUTAGE- | | | | THE PLANT IS IN OPERATIONAL CONDITION 5 IN A REFUELING OUTAGE WITH CORE | | RELOAD ACTIVITIES IN PROGRESS. | | | | THE PLANT SAFETY PARAMETER DISPLAY (SPD) SYSTEM WAS INOPERABLE FROM 0739 | | UNTIL THE SPD SYSTEM COMPUTER WAS REBOOTED AT 1938 WHICH REINITIALIZED THE | | COMPUTER AND RETURNED THE SYSTEM TO OPERABLE STATUS. | | | | ALL SAFETY SYSTEMS REQUIRED FOR THIS OPERATIONAL CONDITION ARE OPERABLE. | | THE 'B' RHR LOOP IS IN SERVICE PROVIDING SHUTDOWN COOLING. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 33237 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 11/07/97 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 22:22 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 11/07/97 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 02:45[EST]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 11/07/97 | | CITY: PIKETON REGION: 3 +-----------------------------+ | COUNTY: PIKE STATE: OH |PERSON ORGANIZATION| |LICENSE#: GDP-2 AGREEMENT: N |MIKE JORDAN RDO | | DOCKET: 0707002 |CHARLEY HAUGHNEY EO | +------------------------------------------------+RICHARD BARRETT IRD | |NRC NOTIFIED BY: GREG BARCH | | |HQ OPS OFFICER: DICK JOLLIFFE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NBNL RESPONSE-BULLETIN | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - CELL RCW DRAIN VALVE PLUGGED WITH SEDIMENT - 24 HOUR NRCB 91-01 REPORT - | | | | WHILE VERIFYING VALVE CLARITY ON THE RECIRCULATING COOLING WATER (RCW) | | CONDENSER DRAIN VALVES, THE ODD SIDE RCW DRAIN VALVE ON CELL #33-5-7 | | WAS OPENED AS REQUIRED BY NUCLEAR CRITICALITY SAFETY APPROVAL | | #NCSA-0333-015.AO1, BUT THE DRAIN LINE WAS PLUGGED WITH SEDIMENT. | | WHEN THE SEDIMENT WAS REMOVED, RCW FLOWED FROM THE DRAIN LINE. THIS | | PLUGGING OF THE RCW CONDENSER DRAIN LINE HAS BEEN DEEMED A VIOLATION | | OF ONE OF THE TWO NUCLEAR CRITICALITY SAFETY CONTROLS (CONTROL 'B') | | IN PLACE IN NCSA-033_015.AO1. THERE WAS NO LOSS OF CONTROL 'A' | | (THE SECOND NCS CONTROL) DURING THIS EVENT. | | | | THERE WAS NO RELEASE OF HAZARDOUS MATERIALS OR RADIOLOGICAL CONTAMINATION | | EXPOSURES ASSOCIATED WITH THIS EVENT. | | | | THIS EVENT IS BEING REPORTED TO THE NRC AS AN NRC BULLETIN 91-01, 24 HOUR | | REPORT. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | NOTE: REFER TO RELATED EVENTS 33206, 33207, 33210, 33219, 33222, 33228. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |IRRETRIEVABLE WELL LOGGING SOURCE | |EVENT NUMBER: 33238 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: WESTERN ATLAS LOGGING SERVICES |NOTIFICATION DATE: 11/08/97 | | CITY: REGION: 3 |NOTIFICATION TIME: 12:18 [ET]| | COUNTY: CRAWFORD STATE: MI |EVENT DATE: 11/08/97 | |LICENSE#: AGREEMENT: N |EVENT TIME: 11:10[EST]| | DOCKET: |LAST UPDATE DATE: 11/08/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |MIKE JORDAN, R3 RDO | | |CHARLEY HAUGHNEY EO | +------------------------------------------------+PHIL HARRELL, R4 RDO | |NRC NOTIFIED BY: PHIL STORE, WALS RSO |JOE GIITTER IRD | |HQ OPS OFFICER: DICK JOLLIFFE |JIM CAMERON, R3 REG | +------------------------------------------------+FRED COMBS NMSS | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |EIRR 39.77(c) WELL LOGGING SOURCE | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - POSSIBLE EXTERNAL EXPOSURE OF FOUR OIL/GAS WELL RIG WORKERS - | | | | A PARTIALLY ENERGIZED ELECTRICALLY DRIVEN PULSED NEUTRON GENERATOR WAS | | REMOVED FROM AN OIL/GAS WELL IN CRAWFORD COUNTY, MICHIGAN, ON FRIDAY | | EVENING 11/07/97. THE GENERATOR WAS ENERGIZED AT 10% OR LESS OF ITS NORMAL | | LOGGING VOLTAGE OUTPUT FOR AS MUCH AS TEN MINUTES AFTER IT HAD BEEN REMOVED | | FROM THE WELL. THREE RIG OPERATION PERSONNEL AND ONE WALS EMPLOYEE MAY | | HAVE BEEN EXTERNALLY EXPOSED TO THE NEUTRON GENERATOR. THEIR NEUTRON FILM | | BADGES WILL BE READ TO DETERMINE THE AMOUNT OF EXTERNAL EXPOSURE, IF ANY. | | A BASELINE WHITE BLOOD CELL COUNT WILL ALSO BE TAKEN FOR EACH OF THE FOUR | | INDIVIDUALS. RESULTS ARE EXPECTED BY 11/11/97. | | | | THE GENERATOR IS A PARTICLE ACCELERATOR THAT BOMBARDS A TRITIUM NITRIDE | | TARGET WITH ELECTRONS AND THE TARGET EMITS NEUTRONS THAT ARE USED TO | | ANALYZE UNDERGROUND ROCK FORMATIONS THAT MAY CONTAIN OIL OR GAS. | | | | THE WELL NAME AND NUMBER IS STATES LOVELLE #1-26A LOCATED IN THE CONNERS | | MARSH FIELD IN CRAWFORD COUNTY, MICHIGAN. | | | | THE WELL LOGGING COMPANY IS WESTERN ATLAS LOGGING SERVICES (WALS) AND THE | | WELL OPERATING COMPANY IS MERCURY EXPLORATION COMPANY. | | | | JIM CAMERON, REG 3, WILL CONTACT THE STATE OF MICHIGAN REPRESENTATIVE. | | | | PHIL STORES, WALS RADIATION SAFETY OFFICER (RSO), PLANS TO SUBMIT A WRITTEN | | REPORT OF THIS EVENT TO NRC REGION 4. | | | | REFER TO THE HOO LOG FOR WALS CONTACT NAME AND TELEPHONE NUMBERS. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33239 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CRYSTAL RIVER REGION: 2 |NOTIFICATION DATE: 11/08/97 | |UNIT: [3] [ ] [ ] STATE: FL |NOTIFICATION TIME: 14:54 [ET]| |RX TYPE: [3] B&W-L-LP |EVENT DATE: 11/08/97 | +------------------------------------------------+EVENT TIME: 13:52[EST]| |NRC NOTIFIED BY: DICK SWEENEY |LAST UPDATE DATE: 11/08/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CHARLES OGLE 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 3 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - EXTRANEOUS MATERIAL FOUND IN REACTOR BUILDING WHILE PLANT IS SHUTDOWN - | | | | THE PLANT IS IN MODE 5 (COLD SHUTDOWN) IN A MAINTENANCE OUTAGE. | | | | DURING AN EXTENT OF CONDITION EVALUATION (PLANT WALKDOWN), THE LICENSEE | | DISCOVERED PIECES OF STYROFOAM-LIKE SUBSTANCES IN THREE LOCATIONS IN | | THE REACTOR BUILDING. THE LICENSEE HAS NOT BEEN ABLE TO DETERMINE IF | | THIS MATERIAL HAD BEEN CONSIDERED IN CALCULATIONS FOR POST-LOCA COOLDOWN. | | THIS MATERIAL HAS APPARENTLY BEEN IN THE REACTOR BUILDING SINCE INITIAL | | CONSTRUCTION AND WILL BE DISCARDED AS EXTRANEOUS MATERIAL. THIS EVENT | | IS BEING REPORTED TO THE NRC AS AN UNANALYZED CONDITION WHILE SHUTDOWN. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33240 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOPER REGION: 4 |NOTIFICATION DATE: 11/09/97 | |UNIT: [1] [ ] [ ] STATE: NE |NOTIFICATION TIME: 02:14 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 11/08/97 | +------------------------------------------------+EVENT TIME: 23:00[CST]| |NRC NOTIFIED BY: FRED SCHIZAS |LAST UPDATE DATE: 11/09/97 | |HQ OPS OFFICER: FANGIE JONES +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PHIL HARRELL 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | POSTULATED FAILURE OF A SUPPORT SYSTEM DURING A DESIGN BASIS LOCA/LOOP. | | | | A PLANT DESIGN CHANGE (#90-085), IMPLEMENTED IN DECEMBER 1991, INSTALLED | | A FILTER/DEMINERALIZER SKID ON THE REACTOR EQUIPMENT COOLING (REC) SYSTEM. | | THE SKID OPERATING IN CONSTANT SAMPLING MODE OF ABOUT 600 CC/MIN WOULD | | DRAIN THE REC SYSTEM DURING A DESIGN BASIS LOSS OF COOLANT/LOSS OF OFFSITE | | POWER (LOCA/LOOP) ACCIDENT IN ABOUT 20 TO 24 HOURS. THE LOSS OF POWER | | WOULD STOP MAKEUP TO THE REC SYSTEM FROM THE DEMINERALIZED WATER SYSTEM. | | THE REC SYSTEM IS REQUIRED TO SUPPORT THE REACTOR CORE ISOLATION COOLING | | (RCIC) SYSTEM AND THE EMERGENCY CORE COOLING (ECC) SYSTEM DURING ABNORMAL | | AND ACCIDENT CONDITIONS AND MUST BE ABLE TO FULFILL ITS INTENDED FUNCTION | | FOR 30 DAYS FOLLOWING A DESIGN BASIS LOCA/LOOP ACCIDENT. | | | | THE CONSTANT SAMPLING WAS SECURED ON 11/04/97 ONCE IT WAS DETERMINED THAT | | THE REC SYSTEM COULD NOT MEET ITS SUPPORT FUNCTION TO THE RCIC AND ECC | | SYSTEMS. IT WAS DETERMINED ON 11/08/97 THAT THIS EVENT IS REPORTABLE TO | | THE NRC PER 10CFR50.72. | | | | IT IS NOTED THAT THE ESSENTIAL SERVICE WATER SYSTEM CAN BACK UP THE REC | | SYSTEM VIA CROSS TIES OPERATED FROM THE CONTROL ROOM. NO CREDIT IS TAKEN | | FOR THIS CAPABILITY IN THE PLANT'S CURRENT LICENSING BASIS. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33241 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BYRON REGION: 3 |NOTIFICATION DATE: 11/09/97 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 17:39 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 11/09/97 | +------------------------------------------------+EVENT TIME: 15:21[CST]| |NRC NOTIFIED BY: MARK SMITH |LAST UPDATE DATE: 11/09/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MIKE JORDAN RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - BORON DILUTION PREVENTION SYSTEM INADVERTENTLY ACTUATED DURING A TEST - | | | | UNIT 1 IS IN MODE 5 (COLD SHUTDOWN) IN A REFUELING OUTAGE. | | | | WHILE PERFORMING A DISCRIMINATOR BIAS VOLTAGE DETERMINATION SURVEILLANCE | | TEST ON THE UNIT 1 SOURCE RANGE NUCLEAR INSTRUMENTS CHANNEL N31, THE | | TECHNICIAN RETURNED THE BORON DILUTION PREVENTION SYSTEM (BDPS) TEST/NORMAL | | SWITCH FROM THE TEST POSITION TO THE NORMAL POSITION. THIS CAUSED AN | | ARTIFICIAL INCREASE IN THE CHANNEL N31 COUNT RATE WHICH CAUSED THE FLUX | | DOUBLING MODULE IN COMPUTER CARD #NM-107 TO INITIATE A BDPS ACTUATION. | | | | AT NO TIME WAS THERE AN ACTUAL POSITIVE REACTIVITY ADDITION. | | | | THE TECHNICIAN INCORRECTLY DETERMINED THAT THE BDPS WAS BLOCKED DURING | | THE TEST DUE TO MISTAKING THE "BDPS BYPASS" ANNUNCIATOR LIGHT FOR THE | | "BDPS BLOCKED" ANNUNCIATOR LIGHT. THE TEST PROCEDURE DOES NOT SPECIFY | | WHICH ANNUNCIATOR WINDOW OR ANNUNCIATOR TITLE SHOULD BE USED TO DETERMINE | | THE STATUS TO THE BDPS DURING THE TEST. | | | | THE LICENSEE IS DETERMINING CORRECTIVE ACTIONS AND WILL REVISE THE TEST | | PROCEDURE AS NECESSARY. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33242 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PEACH BOTTOM REGION: 1 |NOTIFICATION DATE: 11/09/97 | |UNIT: [2] [ ] [ ] STATE: PA |NOTIFICATION TIME: 18:07 [ET]| |RX TYPE: [2] GE-4,[3] GE-4 |EVENT DATE: 11/09/97 | +------------------------------------------------+EVENT TIME: 15:25[EST]| |NRC NOTIFIED BY: CAMERON CAMPBELL |LAST UPDATE DATE: 11/09/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LEANNE HARRISON 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 2 | A/R Y 100 POWER OPERATION | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - AUTO Rx SCRAM FROM 100% POWER DUE TO MAIN TURBINE/MAIN GENERATOR TRIP - | | | | THE MAIN GENERATOR OUTPUT BREAKERS OPENED FOR UNKNOWN REASONS WHICH CAUSED | | THE MAIN TURBINE TO TRIP WHICH CAUSED THE REACTOR TO AUTO SCRAM FROM 100% | | POWER. ALL CONTROL RODS INSERTED COMPLETELY EXCEPT CONTROL ROD #38-39 | | WHICH STOPPED AT THE 02 POSITION. CONTROL ROOM OPERATORS IMMEDIATELY DROVE | | THE CONTROL ROD COMPLETELY INTO THE CORE TO THE 00 POSITION. THE ALTERNATE | | ROD INSERTION SYSTEM ACTUATED (ESF ACTUATION) DUE TO HIGH REACTOR PRESSURE. | | THE 'C' SAFETY/RELIEF VALVE LIFTED DUE TO HIGH REACTOR PRESSURE AND THEN | | IMMEDIATELY RESEATED. THE 'B' RECIRC PUMP TRIPPED, AS EXPECTED. STEAM IS | | BEING DUMPED TO THE MAIN CONDENSER. | | | | UNIT 2 IS STABLE IN CONDITION 3 (HOT SHUTDOWN). | | | | THE LICENSEE IS INVESTIGATING THE ROOT CAUSE OF THIS EVENT. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+