U.S. Nuclear Regulatory Commission Operations Center Event Reports For 07/12/95 - 07/13/95 ** EVENT NUMBERS ** 29044 29051 29052 29053 29054 29055 +----------------------------------+ +-----------------------+ |TRANSPORTATION EVENT | |EVENT NUMBER: 29044 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: SOUTHERN NUCLEAR OPERATING COMPANY |NOTIFICATION DATE: 07/10/95 | | CITY: DOTHAN REGION: 2 |NOTIFICATION TIME: 14:42 [ET]| | COUNTY: STATE: AL |EVENT DATE: 07/10/95 | |LICENSE#: NPF-2 & NPF-8 AGREEMENT: Y |EVENT TIME: 10:00[CDT]| | DOCKET: |LAST UPDATE DATE: 07/12/95 | | +-----------------------------+ | |PERSON ORGANIZATION| | |THOMAS DECKER RDO | | |BILL BRACH, NMSS EO | +------------------------------------------------+DICK BANGART OSP | |NRC NOTIFIED BY: CLIFF BUCK |PEKAR, NAT RESP CTR DOT | |HQ OPS OFFICER: DICK JOLLIFFE |WYATT, EMERG OPS CTR DOE | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NTRA TRANSPORTATION EVENT | | |BAB2 20.2201(a)(1)(ii) LOST/STOLEN LNM>10X | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - X-RAY SOURCE LOST AT EMERY WORLDWIDE FACILITY, DAYTON, OHIO - | | | | ON 06/26/95, SOUTHERN NUCLEAR OPERATING COMPANY SHIPPED AN X-RAY SOURCE | | OF NRC LICENSED NUCLEAR MATERIAL (45 MILLICURIES OF Fe-55 AND 5 MILLICURIES | | OF Cd-109) FROM FARLEY NUCLEAR POWER PLANT TO TN TECHNOLOGIES, INC, | | 2555 NORTH I-35, PO BOX 800, ROUND ROCK, TX 78664 (CONTACT: NELSA MEDINA; | | SEE HOO LOG FOR TELEPHONE NUMBER). | | | | THE RADIOACTIVE SOURCE WAS PACKAGED INSIDE A 5 GALLON PAIL (12 INCHES IN | | DIAMETER AND 14 INCHES HIGH) MARKED "RADIOACTIVE". THE HAZARDOUS | | RADIOACTIVE MATERIAL NORMAL FORM IS SOLID, TYPE 'A', EXCEPTED PACKAGE, | | LIMITED QUANTITY OF MATERIAL, 7, UN-2910, EXEMPT FISSILE CLASS, SHIPMENT | | NUMBER #RMS 95-45. THE PAIL WAS PACKED INSIDE AN OUTER CARDBOARD BOX. THE | | ENTIRE PACKAGE WEIGHED 30 POUNDS. | | | | THE PACKAGE WAS SHIPPED BY COMMON CARRIER, EMERY WORLDWIDE, BY TRUCK TO | | DAYTON, OHIO, AND THEN WAS TO BE SHIPPED BY AIR TO ROUND ROCK, TEXAS. | | CONSIGNEE LICENSEE NUMBER IS #TX-LO3524. | | | | AT 1000 (CDT) ON 07/10/95, LICENSEE WAS NOTIFIED BY EMERY WORLDWIDE THAT | | THE SHIPMENT WAS LOST. LICENSEE REQUESTED THAT EMERY WORLDWIDE CONTINUE TO | | ATTEMPT TO LOCATE THE PACKAGE. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR AND WILL NOTIFY THE STATE | | OF ALABAMA. | | | | *** UPDATE @ 1617 EDT ON 7/12/95 ***FROM LICENSEE: GRAVES BY:McGINTY *** | | | | EMERY WORLDWIDE HAS NOTIFIED SOUTHERN NUCLEAR OPERATING COMPANY THAT THE | | RADIOACTIVE SHIPMENT WHICH WAS REPORTED LOST HAD BEEN LOCATED. THE PACKAGE | | WAS IN GOOD CONDITION AND WAS NOT BREACHED. THE PACKAGE WAS FOUND AT | | HERGUS LABS IN VALLEJO, CA. EMERY WORLDWIDE IS PICKING UP THE PACKAGE FOR | | DELIVERY TO THE ORIGINAL DESTINATION, TN TECHNOLOGIES, IN ROUND ROCK, TX. | | THE LICENSEE WILL INFORM THE RESIDENT INSPECTOR. | | | | HOO NOTIFIED R2DO (RANKIN), NMSS EO (BRACH), OSP (BANGART), DOT | | (FINKBEINER), AND DOE (WYATT). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29051 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: GRAND GULF REGION: 2 |NOTIFICATION DATE: 07/12/95 | |UNIT: [1] [ ] [ ] STATE: MS |NOTIFICATION TIME: 03:42 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 07/12/95 | +------------------------------------------------+EVENT TIME: 02:02[CDT]| |NRC NOTIFIED BY: WALTER CADE |LAST UPDATE DATE: 07/12/95 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |WILLIAM RANKIN RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | A/R Y 100 POWER OPERATION | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AUTOMATIC REACTOR SCRAM DUE TO A MAIN TURBINE TRIP ON LOW CONDENSER VACUUM | | | | WITH THE UNIT AT RATED REACTOR POWER, THE LICENSEE RECEIVED INDICATION OF | | LOW CONDENSER VACUUM AND BEGAN TO REDUCE POWER. A FEW MINUTES LATER, THE | | REACTOR AUTOMATICALLY SCRAMMED FROM APPROXIMATELY 80% POWER DUE TO A MAIN | | TURBINE TRIP ON LOW CONDENSER VACUUM. OPERATORS WERE PREPARING TO TRIP THE | | UNIT MANUALLY WHEN THE AUTOMATIC REACTOR SCRAM OCCURRED. PRELIMINARY | | INDICATIONS REVEALED THE FAILURE OF A CONDENSER NECK EXPANSION JOINT SEAL. | | ALL CONTROL RODS FULLY INSERTED, AND ALL SYSTEMS OPERATED AS EXPECTED. | | THERE WERE NO ECCS ACTUATIONS, THE SRVs DID NOT OPEN, AND FEEDWATER WAS | | USED TO RESTORE LEVEL. | | | | THE LICENSEE IS CURRENTLY USING FEEDWATER AND CONTROL ROD DRIVE WATER TO | | CONTROL LEVEL AND IS STILL USING THE CONDENSER, STEAM JET AIR EJECTOR, AND | | SEAL STEAM CONDENSER FOR PRESSURE CONTROL. THE LICENSEE PLANS TO COOL THE | | UNIT DOWN MORE BEFORE BREAKING CONDENSER VACUUM. CONDENSER VACUUM IS | | CURRENTLY ABOUT 25 INCHES (NORMAL) IN ONE CONDENSER AND ABOUT 5 INCHES IN | | THE LOW PRESSURE CONDENSER. | | | | THE LICENSEE NOTIFIED THE RESIDENT INSPECTOR. | | | | *** UPDATE RECEIVED AT 0617 ON JULY 12, 1995, FROM CADE BY TROCINE *** | | | | FOLLOWING THE REACTOR SCRAM, THE LICENSEE CLOSED THE MSIVs AND WAS | | CONTROLLING PRESSURE AND LEVEL USING THE SRVs AND RCIC. AT 0426 (CDT), THE | | LICENSEE RECEIVED A LOW LEVEL SCRAM SIGNAL DUE TO REACTOR WATER LEVEL | | SHRINKAGE WHEN THE SRVs WERE CLOSED. ALL CONTROL RODS WERE ALREADY FULLY | | INSERTED AT THE TIME. REACTOR WATER LEVEL DROPPED TO -20 INCHES, AND THE | | LOW LEVEL SCRAM SETPOINT WAS +11.4 INCHES. NO OTHER INITIATIONS OCCURRED. | | SUPPRESSION POOL TEMPERATURE IS CURRENTLY AT ABOUT 97øF AND WAS AS HIGH AS | | ABOUT 100øF FOLLOWING THE TRANSIENT. | | | | THE LICENSEE NOTIFIED THE RESIDENT INSPECTOR. THE R2DO (RANKIN) WAS | | NOTIFIED BY THE NRC OPERATIONS CENTER. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29052 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 07/12/95 | |UNIT: [ ] [3] [ ] STATE: NY |NOTIFICATION TIME: 13:00 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 07/10/95 | +------------------------------------------------+EVENT TIME: 10:25[EDT]| |NRC NOTIFIED BY: AL FROBBRICH |LAST UPDATE DATE: 07/12/95 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN KINNEMAN 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 3 | N Y 50 POWER OPERATION | 54 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - UNIT 3 OPERATED BELOW NOMINAL OPERATING PRESSURE FOR TWO DAYS - | | | | AT 1025 ON 07/10/95, WITH UNIT 3 AT 50% POWER, THE LICENSEE REDUCED PLANT | | PRESSURE FROM A NOMINAL VALUE OF 2235 +/- 30 PSIG (THE VALUE UTILIZED FOR | | THE ACCIDENT ANALYSIS DESCRIBED IN THE FSAR) TO 1950 PSIG IN ORDER TO TAKE | | ACTION FOR A LEAKING RCS SAFETY VALVE. THE UNIT 3 TECHNICAL SPECIFICATION | | SAFETY LIMIT CURVE DOES NOT PROVIDE A MINIMUM RCS PRESSURE FOR OPERATION, | | IT ONLY PROVIDES A MAXIMUM PRESSURE LIMIT. THE SAFETY VALVES ARE SET AT | | 2485 +/- 1% PSIG. THE LICENSEE THEN INCREASED POWER WITHOUT INCREASING | | PLANT PRESSURE TO THE REQUIRED OPERATING RANGE. | | | | AT 1200 ON 07/12/95, THE LICENSEE DETERMINED THAT UNIT 3 WAS IN AN | | UNANALYZED CONDITION THAT COULD POTENTIALLY SIGNIFICANTLY COMPROMISE PLANT | | SAFETY. | | | | THE LICENSEE IS TAKING CORRECTIVE ACTION WHICH INCLUDES RAISING RCS | | PRESSURE TO WITHIN NOMINAL RANGE AND REDUCING REACTOR POWER TO 52% BY 1330. | | THE LICENSEE PLANS TO SUBMIT AN LER ON THIS EVENT TO THE NRC. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29053 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SEQUOYAH REGION: 2 |NOTIFICATION DATE: 07/12/95 | |UNIT: [1] [ ] [ ] STATE: TN |NOTIFICATION TIME: 14:11 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 07/07/95 | +------------------------------------------------+EVENT TIME: 12:00[EDT]| |NRC NOTIFIED BY: KEN MEADE |LAST UPDATE DATE: 07/12/95 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |WILLIAM RANKIN RDO | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | - UNIT 1 10 CFR PART 50, APPENDIX 'R', CABLE SEPARATION REQUIREMENT | | NONCOMPLIANCE - | | | | AT 1200 ON 07/07/95, THE LICENSEE DISCOVERED THAT CABLES TO THE UNIT 1 RCS | | PRESSURIZER PORV (#1-PCV-68-334) AND THE EMERGENCY POWER SUPPLY CABLES FOR | | THE RCS PRESSURIZER BLOCK VALVE (#1-FCV-68-333) WERE NOT SEPARATED BY A | | DISTANCE IN COMPLIANCE WITH 10 CFR PART 50, APPENDIX 'R', CABLE SEPARATION | | REQUIREMENTS. | | | | UNIT 2 TECHNICAL SPECIFICATION SECTION 2.C.13.C REQUIRES COMPLIANCE WITH 10 | | CFR PART 50, APPENDIX 'R', REQUIREMENTS, AND UNIT 2 LICENSE CONDITION 2.H | | REQUIRES A 24-HOUR TELEPHONE NOTIFICATION TO THE NRC WHENEVER THERE IS A | | NONCOMPLIANCE WITH THE APPENDIX 'R' CABLE SEPARATION REQUIREMENTS. THE | | UNIT 1 LICENSE CONDITION DOES NOT REQUIRE A TELEPHONE NOTIFICATION TO THE | | NRC WHENEVER THERE IS A NONCOMPLIANCE WITH APPENDIX 'R' CABLE SEPARATION | | REQUIREMENTS. HOWEVER, THE LICENSEE IS NOTIFYING THE NRC OF THIS UNIT 1 | | APPENDIX 'R' CABLE SEPARATION REQUIREMENT NONCOMPLIANCE AS AN INFORMATION | | CALL. | | | | THE LICENSEE HAS ESTABLISHED A 1-HOUR ROVING FIRE WATCH IN THE AREA OF | | NONCOMPLIANCE UNTIL PERMANENT CORRECTIVE ACTIONS ARE COMPLETED. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29054 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BRUNSWICK REGION: 2 |NOTIFICATION DATE: 07/12/95 | |UNIT: [1] [ ] [ ] STATE: NC |NOTIFICATION TIME: 14:34 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 07/12/95 | +------------------------------------------------+EVENT TIME: 10:49[EDT]| |NRC NOTIFIED BY: JOHN REINSBURROW |LAST UPDATE DATE: 07/12/95 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |WILLIAM RANKIN 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 Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | -ESF ACTUATION SIGNALS DUE TO RPS BUS 'B' VOLTAGE DROP FOR UNKNOWN REASONS- | | | | AT 1049, THE VOLTAGE ON RPS BUS 'B' DROPPED FROM APPROXIMATELY 115 VOLTS | | TO APPROXIMATELY 97 VOLTS FOR LESS THAN 1 SECOND FOR UNKNOWN REASONS. THIS | | CAUSED UNIT 1 TO RECEIVE A DIVISION II HALF SCRAM SIGNAL ON BOTH THE | | AUTOMATIC AND MANUAL CHANNELS; ISOLATION SIGNALS ON DIVISION II PRIMARY | | CONTAINMENT ISOLATION SYSTEM GROUP 1 (REACTOR SAMPLE VALVES), GROUP 2 | | (DRYWELL DRAIN VALVES), GROUP 3 (RWCU SYSTEM VALVES), GROUP 6 (CONTAINMENT | | ATMOSPHERE CONTROL VALVES), REACTOR BUILDING VENTILATION SYSTEM, AND | | SECONDARY CONTAINMENT; AND AN INITIATION SIGNAL ON THE STANDBY GAS | | TREATMENT SYSTEM. | | | | AFTER VERIFYING THAT A VALID SCRAM SIGNAL DID NOT EXIST, THE LICENSEE RESET | | ALL SYSTEMS TO NORMAL BY 1158. THE LICENSEE IS INVESTIGATING THE CAUSE OF | | THE ESF ACTUATION SIGNAL. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29055 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: WASHINGTON NUCLEAR REGION: 4 |NOTIFICATION DATE: 07/12/95 | |UNIT: [2] [ ] [ ] STATE: WA |NOTIFICATION TIME: 21:38 [ET]| |RX TYPE: [2] GE-5 |EVENT DATE: 07/12/95 | +------------------------------------------------+EVENT TIME: 17:00[PDT]| |NRC NOTIFIED BY: JOHN S. SIMS |LAST UPDATE DATE: 07/12/95 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BLAINE MURRAY 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 99 POWER OPERATION | 99 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - SERVICE WATER SYSTEM DISCHARGE TRENCH SEDIMENT SAMPLES WERE FOUND TO HAVE | | LEVELS OF COBALT-60 THAT WERE HIGHER THAN THE NATIONAL POLLUTANT DISCHARGE | | ELIMINATION SYSTEM (NPDES) PERMIT LIMIT - | | | | AS PART OF BASELINE STUDIES BEING PERFORMED FOR THE NPDES PERMIT RENEWAL | | PROCESS, SEDIMENT SAMPLES WERE TAKEN FROM A SERVICE WATER SYSTEM DISCHARGE | | TRENCH. AN OFFSITE LABORATORY ANALYZED THE SAMPLES AND FOUND COBALT-60 | | LEVELS OF 5580 - 5870 pCi/Kg. THIS IS NOT IN COMPLIANCE WITH THE | | LICENSEE'S CURRENT NPDES PERMIT WHICH HAS A LIMIT OF 2500 pCi/Kg, AND A | | PRELIMINARY REPORT HAS BEEN SENT TO THE WASHINGTON (STATE) DEPARTMENT OF | | ECOLOGY. CONFIRMATORY SAMPLES ARE BEING ANALYZED, AND A FOLLOW-UP REPORT | | WILL BE MADE TO THE STATE TOMORROW. THE LICENSEE IS DETERMINING ITS | | CORRECTIVE ACTION. | | | | THE LICENSEE NOTIFIED THE RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+