U.S. Nuclear Regulatory Commission Operations Center Event Reports For 11/27/96 - 11/29/96 ** EVENT NUMBERS ** 31093 31362 31369 31384 31385 31386 31387 31388 31389 31390 +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 31093 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: LASALLE COUNTY STATION |NOTIFICATION DATE: 10/04/96 | | CITY: REGION: 3 |NOTIFICATION TIME: 15:35 [ET]| | COUNTY: STATE: IL |EVENT DATE: 09/28/96 | |LICENSE#: AGREEMENT: Y |EVENT TIME: 12:00[CDT]| | DOCKET: |LAST UPDATE DATE: 11/27/96 | | +-----------------------------+ | |PERSON ORGANIZATION| | | | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: MR. SUBALUSKY |VERN HODGE NRR | |HQ OPS OFFICER: DOUG WEAVER | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |CCCC 21.21 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | PART 21 NOTIFICATION ON WKM MODEL 70-13 PNEUMATIC ACTUATORS | | | | ANCHOR DARLING VALVE COMPANY PERFORMED EFFECTIVE DIAPHRAGM AREA (EDA) | | TESTING ON THE VARIOUS WKM MODEL 70-13 PNEUMATIC ACTUATORS (SIZES 35, 70, | | 140, 280). THE PRELIMINARY TEST RESULTS INDICATED THAT THE ORIGINAL | | EFFECTIVE DIAPHRAGM AREA VALUES USED TO CALCULATE THE BENCH SET AND SUPPLY | | AIR SET POINTS WERE INCORRECT. THESE ACTUATORS ARE USED ON VARIOUS PRIMARY | | CONTAINMENT ISOLATION VALVES AND THESE VALVES MAY NOT PROVIDE ADEQUATE | | SYSTEM ISOLATION UNDER DESIGN ACCIDENT CONDITIONS. | | | | LASALLE UNIT ONE IS IN COLD SHUTDOWN AND UNIT TWO IS IN THE REFUEL MODE. | | | | * * * UPDATE RECEIVED BY FAX AT 1508 ON 11/27/96, TAKEN BY WEAVER * * * | | | | DESIGN CHANGES FOR ALL AFFECTED PRIMARY CONTAINMENT ISOLATION SYSTEM (PCIS) | | AND REACTOR CORE ISOLATION SYSTEM (RCIC) VALVES HAVE BEEN INITIATED TO MAKE | | THE REQUIRED SETTING ADJUSTMENTS TO ENSURE ADEQUATE DESIGN MARGINS. BOTH | | UNITS WILL REMAIN IN A CONDITION THAT DOESN'T REQUIRE VALVE DESIGN | | OPERATION UNTIL THE PROBLEM IS CORRECTED. | | | | THE LICENSEE SUBMITTED AN LER ON THIS TOPIC ON 10/28/96. AN UPDATED LER | | WILL BE SUBMITTED ON 12/02/96. THE HOO NOTIFIED VERN HODGE OF THIS UPDATE. | | | | | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31362 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SOUTH TEXAS REGION: 4 |NOTIFICATION DATE: 11/20/96 | |UNIT: [1] [ ] [ ] STATE: TX |NOTIFICATION TIME: 17:55 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 11/20/96 | +------------------------------------------------+EVENT TIME: 16:00[CST]| |NRC NOTIFIED BY: LOUIS PETER |LAST UPDATE DATE: 11/27/96 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |WILLIAM JOHNSON 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 OF A WESTINGHOUSE 480-VOLT CIRCUIT BREAKER IN A NON-SEISMICALLY | | QUALIFIED POSITION [HOO NOTE: SIMILAR NOTIFICATIONS HAVE BEEN RECEIVED | | FROM SUSQUEHANNA, COMANCHE PEAK, THREE MILE ISLAND, AND OYSTER CREEK. REFER | | TO EVENT NUMBERS 31279, 31322, 31323, AND 31325 FOR ADDITIONAL | | INFORMATION.] | | | | THE LICENSEE FOUND A WESTINGHOUSE 480-VOLT CIRCUIT BREAKER IN CLASS-1E | | SWITCHGEAR IN THE "REMOVE" POSITION. WITH THE BREAKER IN THAT POSITION, | | THE SWITCHGEAR IS NOT SEISMICALLY QUALIFIED. THE BREAKER IS A SPARE AND | | HAS BEEN RACKED INTO THE "DISCONNECT" POSITION. IN THIS POSITION, THE | | SWITCHGEAR IS QUALIFIED. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE 1337EST 11/27/96 FROM JON PIERCE BY S.SANDIN * * * | | | | "THIS IS A SUPPLEMENT TO A NOTIFICATION CALLED IN ON 11/20/96. AT 1755EST, | | A SPARE BREAKER ON 4.16KV SWITCHGEAR E1B WAS FOUND RACKED OUT PAST THE | | DISCONNECT POSITION. IN THIS CONDITION THE BREAKER DOES NOT MEET ITS | | SEISMIC QUALIFICATION. THE BREAKER HAS BEEN RETURNED TO THE DISCONNECT | | POSITION AND CURRENTLY MEETS ITS SEISMIC QUALIFICATION. | | | | "THE SOUTH TEXAS PROJECT CONDUCTED AN EVALUATION OF THIS EVENT AND | | DETERMINED ON 11/27/96 AT 1150 THAT THE AS FOUND CONDITION WAS OUTSIDE THE | | DESIGN BASIS. ALTHOUGH NOT CURRENTLY IN THIS CONDITION, WE ARE REPORTING | | THIS EVENT PER 10CFR50.72(b)1(ii)(B)." | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. NOTIFIED R4DO(CAIN). | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |HOSPITAL | |EVENT NUMBER: 31369 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: UNIVERSITY OF CINCINNATI |NOTIFICATION DATE: 11/22/96 | | CITY: CINCINNATI REGION: 3 |NOTIFICATION TIME: 10:27 [ET]| | COUNTY: HAMILTON STATE: OH |EVENT DATE: 11/21/96 | |LICENSE#: 34-06903-05 AGREEMENT: N |EVENT TIME: 02:30[EST]| | DOCKET: |LAST UPDATE DATE: 11/27/96 | | +-----------------------------+ | |PERSON ORGANIZATION| | |MADERA RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: V. MORRIS | | |HQ OPS OFFICER: BOB STRANSKY | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |LADM 35.33(a) MED MISADMINISTRATION | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | MEDICAL MISADMINISTRATION | | | | A PATIENT WAS GIVEN A 48.1 mCi DOSE OF I-131 IN SOLUTION TO BE TAKEN ORALLY | | THROUGH A STRAW. THE PATIENT BEGAN INGESTING THE SOLUTION, THEN BLEW BACK | | THROUGH THE STRAW, CAUSING A PORTION OF THE SOLUTION TO BE SPLASHED UPON | | HER FACE, CLOTHING, AND BEDDING. THE LICENSEE ESTIMATES THAT THE PATIENT | | INGESTED APPROXIMATELY 38 mCi OF THE SOLUTION. THE ATTENDING PHYSICIAN HAS | | DETERMINED THAT THE DOSE INGESTED IS SUFFICIENT TO PERFORM THE INTENDED | | ACTION, SO NO ADDITIONAL DOSAGE WILL BE GIVEN. | | | | THE LICENSEE HAS ALREADY CONTACTED NRC REGION 3 (MADERA) REGARDING THIS | | EVENT. | | | | | | ***UPDATE ON 11/27/96 @ 11:08 BY MORRIS TO GOULD*** THE LICENSEE IS | | RETRACTING THIS EVENT SINCE IT HAS BEEN DETERMINED BY THE AUTHORIZING USER | | PHYSICIAN, THE AMOUNT OF DOSAGE THE PATIENT INGESTED WAS THE MINIMUM AMOUNT | | SUFFICIENT TO PERFORM THE INTENDED ACTION. THEREFORE, THIS EVENT IS NOT | | REPORTABLE. THE REG 3 RDO(LANKSBURY) WAS NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31384 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VOGTLE REGION: 2 |NOTIFICATION DATE: 11/27/96 | |UNIT: [1] [ ] [ ] STATE: GA |NOTIFICATION TIME: 10:14 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 11/27/96 | +------------------------------------------------+EVENT TIME: 08:46[EST]| |NRC NOTIFIED BY: MEYER |LAST UPDATE DATE: 11/27/96 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PIERCE SKINNER 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 STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE PLANT HAD A REACTOR TRIP FROM 100% POWER DUE TO A TURBINE TRIP. | | | | THIS OCCURRED WHILE THEY WERE PERFORMING MAINTENANCE ON THE MAIN GENERATOR | | STATOR COOLING PANEL, AT WHICH TIME A METAL TAG CAME IN CONTACT WITH A | | WIRING TERMINAL STRIP, SHORTING OUT POWER TO THE PANEL. THIS CAUSED A 2 OF | | 3 HIGH TEMPERATURE ACTUATION(FAIL HIGH ON POWER LOSS). AN AUTOMATIC | | GENERATOR TRIP WAS THE RESULT THAT CAUSED THE REACTOR TRIP. ALL RODS FULLY | | INSERTED INTO THE CORE, NO STEAM GENERATOR SAFETY VALVES LIFTED, AND THE | | STEAM GENERATOR ATMOSPHERIC VALVES ACTUATED FOR A SHORT PERIOD OF TIME. THE | | STEAM GENERATOR ATMOSPHERIC VALVES CLOSED WITHIN 5 MINS AND THEN THE STEAM | | DUMPS TOOK CONTROL. THE MOTOR DRIVEN AUX FEED PUMPS STARTED AS EXPECTED AND | | NO SAFETY INJECTION OCCURRED. THE RI WAS INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 31385 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: N. CAROLINA DIV OF RAD PROTECTION |NOTIFICATION DATE: 11/27/96 | | CITY: RALEIGH REGION: 2 |NOTIFICATION TIME: 10:45 [ET]| | COUNTY: STATE: NC |EVENT DATE: 11/27/96 | |LICENSE#: AGREEMENT: Y |EVENT TIME: 10:05[EST]| | DOCKET: |LAST UPDATE DATE: 11/27/96 | | +-----------------------------+ | |PERSON ORGANIZATION| | |PIERCE SKINNER RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: COX | | |HQ OPS OFFICER: CHAUNCEY GOULD | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE N.C. DIVISION OF RAD PROTECTION REPORTED THAT ONE OF THEIR LICENSEES | | (CABARRUS MEMORIAL HOSPITAL) REPORTED A MISSING COBALT 57 SOURCE. | | | | DURING INVENTORY OF SEALED SOURCES, A 50 MICROCURIE COBALT 57 CHECK SOURCE | | (SER #NES289) WAS MISSING. THEY SUSPECT THE SOURCE MAY BE LOST IN THE | | LINENS WHICH ARE SENT TO AN OFF SITE CONTRACT LINEN COMPANY(MAPLE SPRINGS | | IN HICKORY N.C.). AT PRESENT THE LICENSEE IS LOOKING FOR THE SOURCE AND | | THE STATE REQUESTED THAT THE LICENSEE OBTAIN A CONTRACTOR TO HELP LOCATE | | THE MISSING SOURCE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31386 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PRAIRIE ISLAND REGION: 3 |NOTIFICATION DATE: 11/27/96 | |UNIT: [1] [2] [ ] STATE: MN |NOTIFICATION TIME: 11:12 [ET]| |RX TYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 11/27/96 | +------------------------------------------------+EVENT TIME: 09:30[CST]| |NRC NOTIFIED BY: LARRY HENRY |LAST UPDATE DATE: 11/27/96 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |ROGER LANKSBURY 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 +------------------------------------------------------------------------------+ | PRELIMINARY ANALYTICAL RESULTS INDICATE THAT SOME OF THE SPENT FUEL STORAGE | | RACKS HAVE EXPERIENCED A SIGNIFICANT LOSS OF BORON CARBIDE FROM THE | | BORAFLEX PANELS. | | | | "THE PRAIRIE ISLAND SPENT FUEL STORAGE RACKS UTILIZE BORAFLEX PANELS AS A | | NEUTRON ABSORBER. PRELIMINARY RESULTS FROM THE PRAIRIE ISLAND SPECIFIC | | VERSION OF THE EPRI RACKLIFE COMPUTER PROGRAM INDICATE THAT SOME OF THE | | PRAIRIE ISLAND SPENT FUEL STORAGE RACK CELLS HAVE EXPERIENCED A SIGNIFICANT | | LOSS OF THE BORON CARBIDE FROM THE BORAFLEX PANELS. THIS INFORMATION, IN | | COMBINATION WITH INFORMATION PUBLISHED IN EPRI INTERIM REPORT TR-103300, | | INDICATES THAT THOSE SPENT FUEL STORAGE RACK CELLS ARE OUTSIDE THEIR DESIGN | | BASIS AND OUTSIDE THE REQUIREMENTS OF TECHNICAL SPECIFICATION 5.6.A.1.b, | | WITH A MARGIN TO CRITICALITY OF LESS THAN 5% ASSUMING NO SOLUBLE BORON IN | | THE SPENT FUEL POOL WATER. A LICENSE AMENDMENT REQUEST, WHICH REQUESTS | | APPROVAL OF A CRITICALITY ANALYSIS FOR THE PRAIRIE ISLAND SPENT FUEL | | STORAGE RACKS WITH NO CREDIT FOR BORAFLEX PANELS AND INSTEAD UTILIZING | | CREDIT FOR SOLUBLE BORON, WAS SUBMITTED ON JULY 28, 1995. IN THE INTERIM, | | ADMINISTRATIVE CONTROLS HAVE BEEN IMPLEMENTED TO ENSURE THAT THE SPENT FUEL | | POOL SOLUBLE BORON CONCENTRATION IS MAINTAINED AT A LEVEL ADEQUATE TO | | ENSURE K-EFF FOR THE SPENT FUEL STORAGE RACKS WILL REMAIN LESS THAN 0.95." | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31387 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: GRAND GULF REGION: 4 |NOTIFICATION DATE: 11/27/96 | |UNIT: [1] [ ] [ ] STATE: MS |NOTIFICATION TIME: 13:22 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 11/27/96 | +------------------------------------------------+EVENT TIME: 09:06[CST]| |NRC NOTIFIED BY: CARL EHRHARDT |LAST UPDATE DATE: 11/27/96 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CHARLES CAIN 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 | M/R Y 0 STARTUP | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LOSS OF BOTH CRD PUMPS DURING STARTUP - MANUAL SCRAM | | | | DURING REACTOR STARTUP, THE CONTROL ROD DRIVE (CRD) SYSTEM EXPERIENCED A | | LOSS OF SUCTION PRESSURE DUE TO A LOW CONDENSATE STORAGE TANK (CST) LEVEL. | | THE REACTOR MODE SWITCH WAS PLACED IN SHUTDOWN PER PROCEDURE AND ALL | | CONTROL RODS FULLY INSERTED. THE PLANT WAS CRITICAL BELOW THE POWER RANGE | | AT THE TIME OF THE SCRAM. | | | | CST LEVEL INDICATED 25-26 FEET AT THE TIME OF THE EVENT, THIS IS | | APPROXIMATELY 6 FEET OVER THE STANDPIPE IN THE CST OR THE POINT WHERE CRD | | SUCTION IS LOST. I&C IS INVESTIGATING THE LEVEL TRANSMITTER FOR THE CST. | | | | THIS 6 FEET DIFFERENCE EQUATES TO APPROXIMATELY 50,000 GALLONS OF WATER. | | THE AMOUNT OF TIME THE TRANSMITTER HAS BEEN INOPERABLE IS NOT KNOWN. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31388 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: LASALLE REGION: 3 |NOTIFICATION DATE: 11/27/96 | |UNIT: [1] [2] [ ] STATE: IL |NOTIFICATION TIME: 13:46 [ET]| |RX TYPE: [1] GE-5,[2] GE-5 |EVENT DATE: 11/26/96 | +------------------------------------------------+EVENT TIME: 16:45[CST]| |NRC NOTIFIED BY: LARRY BLUNK |LAST UPDATE DATE: 11/27/96 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |ROGER LANKSBURY RDO | |NLTR LICENSEE 24 HR REPORT | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | DISCOVERY THAT DIESEL FIRE PUMP (DFP) INSPECTIONS ARE NOT PERFORMED DURING | | SHUTDOWN AND THAT PORTIONS OF THE INSPECTIONS ARE NOT PERFORMED ON AN | | 18-MONTH FREQUENCY AS REQUIRED BY THE PLANT TECHNICAL SPECIFICATIONS | | | | LASALLE TECHNICAL SPECIFICATION 4.7.5.1.2.C REQUIRES THAT OPERABILITY OF | | EACH DIESEL-DRIVEN FIRE SUPPRESSION PUMP BE DEMONSTRATED DURING SHUTDOWN AT | | LEAST ONCE EVERY 18 MONTHS BY SUBJECTING THE DIESEL TO AN INSPECTION IN | | ACCORDANCE WITH PROCEDURES PREPARED IN CONJUNCTION WITH THE MANUFACTURER'S | | RECOMMENDATIONS FOR THE CLASS OF SERVICE. THE DFPs HAVE BEEN INSPECTED IN | | ACCORDANCE WITH PROCEDURES THAT WERE PREPARED IN CONJUNCTION WITH THE | | MANUFACTURER'S RECOMMENDATIONS; HOWEVER, THE INSPECTIONS WERE NOT PERFORMED | | DURING SHUTDOWN AS REQUIRED BY THE TECHNICAL SPECIFICATIONS. FURTHERMORE, | | THE INSPECTIONS ARE CURRENTLY PERFORMED AT INTERVALS OF 6 MONTHS, 12 | | MONTHS, AND 24 MONTHS AS SUGGESTED BY THE MANUFACTURER (CUMMINS), AND THESE | | FREQUENCIES DIFFER FROM THE FREQUENCY SPECIFIED IN TECHNICAL SPECIFICATION | | 4.7.5.1.2.C (18 MONTHS). AS A RESULT, FROM A VERBATIM COMPLIANCE | | STANDPOINT, THE LICENSEE HAS NOT BEEN IN COMPLIANCE WITH TECHNICAL | | SPECIFICATION REQUIREMENT 4.7.5.1.2.C DUE TO THE FACTS THAT THE INSPECTIONS | | WERE NOT PERFORMED DURING SHUTDOWN AND THAT PORTIONS OF THE INSPECTIONS | | WERE NOT PERFORMED ON AN 18-MONTH FREQUENCY. | | | | BECAUSE THE PORTIONS OF THE INSPECTIONS PERFORMED AT THE 24-MONTH FREQUENCY | | ARE NOT CURRENT IN ACCORDANCE WITH THE 18-MONTH FREQUENCY SPECIFIED BY THE | | TECHNICAL SPECIFICATIONS, BOTH THE '0A' AND '0B' DFPs WERE DECLARED TO BE | | INOPERABLE AS OF 1645 ON NOVEMBER 26, 1996. THE MAINTENANCE AND | | INSPECTIONS REQUIRED TO RETURN THE DFPs TO OPERABLE STATUS ARE CURRENTLY | | SCHEDULED TO BE PERFORMED ON THE '0A' DFP DURING THE WEEK BEGINNING | | DECEMBER 2, 1996, AND ON THE '0B' DFP DURING THE WEEK BEGINNING DECEMBER 9, | | 1996. | | | | ACTION STATEMENT B.1 OF TECHNICAL SPECIFICATION 3.7.5.1 REQUIRES THAT A | | BACKUP FIRE SUPPRESSION WATER SYSTEM BE ESTABLISHED WITHIN 24 HOURS WHEN | | THE FIRE SUPPRESSION WATER SYSTEM IS INOPERABLE. WHILE BOTH THE '0A' AND | | '0B' DFPs REMAIN FULLY AVAILABLE, THE STATION SERVICE WATER SYSTEM HAS BEEN | | ESTABLISHED AS A BACKUP FIRE SUPPRESSION WATER SYSTEM IN ACCORDANCE WITH | | STATION PROCEDURES. | | | | THE LICENSEE HAS NOTIFIED THE NRC RESIDENT INSPECTOR AND PLANS TO NOTIFY | | NRC REGION 3 MANAGEMENT. THE LICENSEE ALSO PLANS TO ISSUE A SPECIAL REPORT | | WITHIN 14 DAYS AND A LICENSEE EVENT REPORT WITHIN 30 DAYS. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31389 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 11/27/96 | |UNIT: [1] [ ] [ ] STATE: CT |NOTIFICATION TIME: 14:42 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 11/27/96 | +------------------------------------------------+EVENT TIME: 14:26[EST]| |NRC NOTIFIED BY: RAY PALMIERI |LAST UPDATE DATE: 11/27/96 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JAMES JOYNER RDO | |AINC 50.72(b)(2)(iii)(C) POT UNCNTRL RAD REL | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | BOTH STEAM TUNNEL RADIATION MONITORS FAILED A SURVEILLANCE | | | | BOTH STEAM TUNNEL RADIATION MONITORS FAILED THE DOWN SCALE SURVEILLANCE. | | NORMALLY, IF BOTH MONITORS WERE TO FAIL DOWN SCALE, STANDBY GAS TREATMENT | | (SBGT) WOULD START AUTOMATICALLY. IN THE AS FOUND CONDITION A FAILURE OF | | BOTH MONITORS IN THE DOWN SCALE POSITION WOULD NOT HAVE STARTED SBGT. | | | | THE CONDITION HAS BEEN ATTRIBUTED TO INSTRUMENT DRIFT. BOTH MONITORS HAVE | | BEEN RECALIBRATED AND SATISFACTORILY RETESTED. BOTH MONITORS HAD BEEN | | SUCCESSFULLY TESTED ABOUT ONE MONTH AGO. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31390 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DRESDEN REGION: 3 |NOTIFICATION DATE: 11/27/96 | |UNIT: [ ] [2] [ ] STATE: IL |NOTIFICATION TIME: 16:04 [ET]| |RX TYPE: [1] GE-1,[2] GE-3,[3] GE-3 |EVENT DATE: 11/27/96 | +------------------------------------------------+EVENT TIME: 13:15[CST]| |NRC NOTIFIED BY: GRANT |LAST UPDATE DATE: 11/27/96 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |ROGER LANKSBURY RDO | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | HPCI INOPERABLE DUE TO WATER AND SEDIMENT IN THE OIL RESERVOIR | | | | A SAMPLE FROM THE HIGH PRESSURE COOLANT INJECTION (HPCI) PUMP OIL RESERVOIR | | INDICATED THAT THE OIL CONTAINS 0.45% WATER AND SEDIMENT. THE HPCI PUMP | | HAS BEEN DECLARED INOPERABLE AND THE PLANT IS IN A 7 DAY SHUTDOWN LCO. THE | | RESERVOIR WAS SAMPLED BECAUSE OF A HIGH LEVEL ALARM. FURTHER MONITORING | | REVEALED CONTINUING IN LEAKAGE INTO THE OIL RESERVOIR. THE SOURCE OF THE | | WATER HAS NOT BEEN CONFIRMED. | | | | THE LICENSEE IS DEVELOPING PLANS TO CORRECT THIS CONDITION. | +------------------------------------------------------------------------------+