U.S. Nuclear Regulatory Commission Operations Center Event Reports For 01/10/97 - 01/13/97 ** EVENT NUMBERS ** 31519 31565 31566 31567 31568 31569 31570 31571 31572 31573 31574 31575 31576 31577 31578 31579 31580 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31519 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOK REGION: 3 |NOTIFICATION DATE: 12/29/96 | |UNIT: [ ] [2] [ ] STATE: MI |NOTIFICATION TIME: 15:31 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 12/29/96 | +------------------------------------------------+EVENT TIME: 14:50[EST]| |NRC NOTIFIED BY: TILLY |LAST UPDATE DATE: 01/10/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GARY SHEAR RDO | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | THE LICENSEE REPORTED THAT THEY HAD ENTERED LCO ACTION STATEMENTS SEVERAL | | TIMES UNKNOWINGLY SINCE 11/01/96. | | | | THIS CONDITION WAS DUE TO A COMBINATION OF EQUIPMENT BEING REMOVED FROM | | SERVICE IN ONE SAFETY RELATED TRAIN, AND TECHNICAL SPECIFICATION (TECH | | SPEC) INOPERABILITY OF THE OPPOSITE TRAIN'S EDG. THE TRAIN "A" EDG WAS | | INOPERABLE DUE TO ITS INABILITY TO FULLY COMPLY WITH THE LOAD SHED | | REQUIREMENTS OF THE EDG TECH SPEC. THE LOAD SHED FAILURE WAS DUE TO FAILURE | | TO RE-INSTALL THE TRIP FUSES(OR CONTROL POWER FUSES FOR THE CIRCUIT | | BREAKERS) ON A SINGLE 600 V AC CIRCUIT BREAKER WHICH SUPPLIES POWER TO UNIT | | 2 CONTAINMENT LIGHTING CIRCUITS. WITHOUT THESE FUSES INSTALLED, THE BREAKER | | WOULD NOT TRIP AND LOAD SHED WOULD NOT OCCUR. THE FUSES WERE FOUND REMOVED | | AT 12:30 ON 12/29/96 AND REPLACED AT 13:05 ON 12/29/96. THESE FUSES MAY | | HAVE BEEN REMOVED SINCE 11/01/96. DURING THE PERIOD FROM 11/01-12/29/96 | | THERE MAY HAVE BEEN INSTANCES WHERE EQUIPMENT MAY HAVE BEEN REMOVED FROM | | SERVICE ON SAFETY TRAIN "B" WHILE THE TRAIN "A" EDG WAS INOPERABLE, PUTTING | | THE PLANT IN A LCO ACTION STATEMENT. THE EVENT WAS DETERMINED TO BE | | REPORTABLE AT 14:50 ON 12/29/96 AFTER CONSULTATION WITH LICENSING AND | | MANAGEMENT PERSONNEL. | | | | THE LICENSEE IS CONTINUING FURTHER ANALYSIS OF THE EVENT TO DETERMINE IF | | THE FAILURE TO INSTALL THE FUSES IMPAIRED THE EDG FUNCTION. BASED ON THE | | SMALL LOAD CARRIED BY THIS LIGHTING BREAKER, THIS EVENT IS NOT BELIEVED TO | | HAVE HAD ANY POTENTIAL SAFETY SIGNIFICANCE. THE LICENSEE NOTIFIED THE | | RESIDENT INSPECTOR. | | | | * * * UPDATE 1047 1/10/97 FROM MARY BETH DEPUYDT TAKEN BY STRANSKY * * * | | | | THIS EVENT NOTIFICATION IS BEING RETRACTED. THE FOLLOWING IS TEXT FROM A | | FACSIMILE SUBMITTED BY THE LICENSEE: | | | | "DURING THE SUBSEQUENT INVESTIGATION OF THE EVENT. ELECTRICAL SYSTEMS | | ENGINEERING EVALUATED BOTH THE STEADY STATE AND DYNAMIC IMPACT OF THIS | | EVENT ON THE EDG. THE INABILITY OF THE 21D3 BREAKER TO AUTOMATICALLY OPEN | | WITH A LOOP SIGNAL PRESENT WOULD ADD ONLY 95 KW OF LOAD TO THE EDG FOR A | | MAXIMUM OF 3405 KW, REMAINING BELOW ITS RATED CONTINUOUS CAPACITY OF 3500 | | KW. THE PRESENCE OF THE ADDITIONAL 95 KW LOAD WOULD ALSO NOT INTERFERE WITH | | THE EDG'S ABILITY TO SUCCESSFULLY SEQUENCE AND LOAD THE SAFETY RELATED | | EQUIPMENT ASSOCIATED WITH THE 2CD EDG, AS VERIFIED IN A CALCULATION | | PERFORMED BY ENGINEERING. SINCE THE OPERABILITY OF THE 2CD EDG WAS NOT | | IMPACTED, THIS EVENT IS NOT REPORTABLE AND THE NOTIFICATION PREVIOUSLY MADE | | ON DECEMBER 29, 1996 IS RETRACTED." R3DO (LEW MILLER) NOTIFIED | | | | THE NRC RESIDENT INSPECTOR WILL BE INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31565 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CLINTON REGION: 3 |NOTIFICATION DATE: 01/10/97 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 06:32 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 01/10/97 | +------------------------------------------------+EVENT TIME: 03:22[CST]| |NRC NOTIFIED BY: TIM HOLLAND |LAST UPDATE DATE: 01/10/97 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LEW MILLER 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 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | WHILE CONDUCTING A SURVEILLANCE TEST AN UNEXPECTED SINGLE ROD SCRAM | | OCCURRED. | | | | THE LICENSEE WAS CONDUCTING SURVEILLANCE TEST 90-31-16, HALF MANUAL SCRAM, | | WHEN ROD 40-17 EXPERIENCED A SINGLE ROD SCRAM FROM THE 00 POSITION. THE | | CAUSE OF THE SCRAM WAS A BLOWN "A" SCRAM SOLENOID FUSE. THE FUSE MAY HAVE | | BLOWN EARLIER IN THE TESTING SO THE ROD STAYED DEENERGIZED WHEN THE "B" | | SOLENOID WAS TESTED. | | | | THE FUSE HAS BEEN REPLACED AND THE LICENSEE IS INVESTIGATING THE CAUSE OF | | THE BLOWN FUSE. THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | ***RETRACTION ON 01/10/97 @ 1748 EST BY DAVID HODEL TAKEN BY MACKINNON*** | | | | THE ACTUATION OF THE SCRAM SIGNAL FOR ROD 40-17 WAS INVALID. THE ROD | | RECEIVED A SCRAM SIGNAL AS A RESULT OF A BLOWN FUSE ON THE "A" SCRAM | | SOLENOID DURING A SURVEILLANCE TEST 9031.16 ON THE "B" SCRAM SOLENOID, AND | | THE ACTUATION OF THE ROD'S SCRAM SOLENOIDS OCCURRED AFTER THE ROD 40-17 WAS | | ALREADY FULL IN. THE SAFETY FUNCTION HAD ALREADY BEEN COMPLETED. R3DO (LEW | | MILLER) NOTIFIED. | | | | THE NRC RESIDENT INSPECTOR WILL BE INFORMED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 31566 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: NC STATE DIVISION OF RAD PROTECTION |NOTIFICATION DATE: 01/10/97 | | CITY: N. WILKESBORO REGION: 2 |NOTIFICATION TIME: 09:09 [ET]| | COUNTY: WILKES STATE: NC |EVENT DATE: 01/03/97 | |LICENSE#: AGREEMENT: Y |EVENT TIME: 00:00[EST]| | DOCKET: |LAST UPDATE DATE: 01/10/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |CHRISTENSEN RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: S. JEFFRIES | | |HQ OPS OFFICER: BOB STRANSKY | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NAGR AGREEMENT STATE | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LOSS OF FIVE SEALED RADIOACTIVE CALIBRATION SOURCES | | | | THE STATE OF NORTH CAROLINA REPORTED THAT FIVE SEALED CALIBRATION SOURCES | | HAD BEEN INADVERTENTLY REMOVED FROM A MOBILE NUCLEAR MEDICINE SERVICE VAN. | | THE VAN BEING USED BY THE STATE LICENSEE HAD BEEN PARKED AT THE RYDER TRUCK | | RENTAL FACILITY IN N. WILKESBORO. ON 12/30/96, THE LICENSEE WAS NOTIFIED BY | | RYDER THAT THE VEHICLE HAD BEEN CLEANED OUT AND MOVED TO THE RYDER FACILITY | | IN CHARLOTTE. AFTER BEING NOTIFIED BY THE LICENSEE, NC STATE DRP PERSONNEL | | VISITED THE FACILITY IN CHARLOTTE AND FOUND NO RADIOACTIVE MATERIAL IN THE | | VEHICLE. THE LICENSEE REPORTED THAT FIVE SEALED CALIBRATION SOURCES HAD | | BEEN STORED IN THE VAN WHILE IT WAS PARKED IN N. WILKESBORO. THE ACTIVITIES | | AND ISOTOPES OF THE SOURCES ARE: 250 ęCi Cs-137, 15 mCi Co-57, 5 mCi Co-57, | | 100 ęCi Co-60, AND 250śCi Ba-133. THE STATE IS CURRENTLY CONDUCTING AN | | INVESTIGATION OF THIS EVENT AND IS ATTEMPTING TO LOCATE THE SOURCES. THE | | STATE HAS ALREADY CONTACTED NRC REGION 2 REGARDING THIS REPORT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31567 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: POINT BEACH REGION: 3 |NOTIFICATION DATE: 01/10/97 | |UNIT: [1] [ ] [ ] STATE: WI |NOTIFICATION TIME: 11:27 [ET]| |RX TYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 01/10/97 | +------------------------------------------------+EVENT TIME: 09:37[CST]| |NRC NOTIFIED BY: RON WINGET |LAST UPDATE DATE: 01/10/97 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LEWIS MILLER RDO | |AUNA 50.72(b)(1)(ii)(A) UNANALYZED COND OP | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 90 POWER OPERATION | 90 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE HAS DETERMINED THAT A CABLE SEPARATION ISSUE FOR NON-SAFETY | | RELATED LOADS COULD CAUSE SAFETY RELATED INVERTERS TO OVERLOAD. | | | | THE LICENSEE DETERMINED THAT A SINGLE FAILURE COULD RENDER AUTOMATIC | | ACTUATION OF CONTAINMENT SPAY INOPERABLE. SIMULTANEOUS FAULT OF LOADS ON | | "1402 AND 1403" INSTRUMENT BUSES COULD CAUSE THE INVERTER POWER SUPPLIES TO | | SHUT DOWN. THIS COULD RESULT IN TWO INSTRUMENT BUSES NOT HAVING POWER. | | THIS IN TURN RENDERS AUTO-ACTUATION OF CONTAINMENT SPRAY INOPERABLE. THE | | FAULT COULD RESULT DUE TO THE CABLES TO THREE NON-SAFETY LOADS NOT | | CONFORMING TO CABLE SEPARATION CRITERIA. | | | | THE LICENSEE DECLARED CONTAINMENT SPRAY INOPERABLE AND ENTERED A ONE HOUR | | TECH SPEC LCO. THE CORRECTIVE ACTION WAS TO OPEN THE "1403" INSTRUMENT | | BREAKER TO THE NON-SAFETY LOADS. REDUNDANT INDICATIONS ARE AVAILABLE FOR | | THE DEENERGIZED INSTRUMENTATION. THE PLANT WAS IN THE LIMITING CONDITION | | FOR 20 MINUTES. LONG TERM CORRECTIVE ACTION IS BEING EVALUATED. THE | | LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31568 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PILGRIM REGION: 1 |NOTIFICATION DATE: 01/10/97 | |UNIT: [1] [ ] [ ] STATE: MA |NOTIFICATION TIME: 12:02 [ET]| |RX TYPE: [1] GE-3 |EVENT DATE: 01/10/97 | +------------------------------------------------+EVENT TIME: 10:50[EST]| |NRC NOTIFIED BY: TOM CAMPBELL |LAST UPDATE DATE: 01/10/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |HAROLD GRAY RDO | |DDDD 73.71 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | SAFEGUARDS INFORMATION MAILED IMPROPERLY. IMMEDIATE COMPENSATORY MEASURES | | TAKEN UPON DISCOVERY. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. | | | | SEE HOO LOG FOR DETAILS. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31569 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SAN ONOFRE REGION: 4 |NOTIFICATION DATE: 01/10/97 | |UNIT: [1] [2] [3] STATE: CA |NOTIFICATION TIME: 14:26 [ET]| |RX TYPE: [1] W-3-LP,[2] CE,[3] CE |EVENT DATE: 01/09/97 | +------------------------------------------------+EVENT TIME: 12:00[PST]| |NRC NOTIFIED BY: CLAY WILLIAMS |LAST UPDATE DATE: 01/10/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CHRIS VANDENBURGH RDO | |NLTR LICENSEE 24 HR REPORT | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 DECOMMISSIONED | 0 DECOMMISSIONED | | 2 | N N 0 REFUELING | 0 REFUELING | | 3 | N Y 100 POWER OPERATION | 100 POWER OPERATION | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | MONTHLY INSPECTION OF ALL ACTIVE VEHICLE BARRIERS SYSTEMS NOT COMPLETED | | WITHIN SPECIFIED TIME LIMIT FOR THE MONTH OF DECEMBER. | | | | THE FOLLOWING TEXT IS FROM A FACSIMILE SENT BY THE LICENSEE: | | | | "THIS NOTIFICATION IS FROM SAN ONOFRE UNITS 1, 2, AND 3 AND IS BEING MADE | | IN ACCORDANCE WITH CONDITION 2.G OF THE FACILITY OPERATING LICENSES FOR | | UNITS 2 AND 3, WHICH REQUIRES EDISON TO REPORT VIOLATIONS OF LICENSE | | CONDITION 2.E WITHIN 24 HOURS. CONDITION 2.E STATES, IN PART: "SCE SHALL | | FULLY IMPLEMENT AND MAINTAIN IN EFFECT ALL PROVISIONS OF THE | | COMMISSION-APPROVED PHYSICAL SECURITY ... PLAN. | | | | "FOLLOWING A REVIEW OF STATION RECORDS, EDISON MANAGEMENT CONCLUDED AT 1200 | | ON 01/09/97 THAT SOME PORTIONS OF THE PHYSICAL SECURITY PLAN (PSP) VEHICLE | | BARRIER SYSTEM (VBS) MONTHLY INSPECTIONS WERE NOT COMPLETED ON TIME. THE | | PSP REQUIRES MONTHLY INSPECTIONS OF ALL ACTIVE VBS BOLLARDS. WHILE THE | | DAILY OPERATIONAL VERIFICATIONS HAD BEEN PERFORMED ON TIME, THE MONTHLY | | INSPECTION OF THE VBS FOR DECEMBER 1996 WAS NOT COMPLETED WITHIN ITS | | REQUIRED INTERVAL. THIS INSPECTION WAS SUBSEQUENTLY PERFORMED ON 01/09/97. | | | | "EDISON HAS TAKEN APPROPRIATE ACTIONS TO ENSURE COMPLIANCE WITH PSP. | | BECAUSE EDISON CONFIRMED THE VBS REMAINED OPERABLE DURING THIS PERIOD, | | EDISON BELIEVES THE SAFETY SIGNIFICANCE OF THIS OCCURRENCE IS LOW. | | | | "AT THE TIME OF THIS REPORT, UNIT 1 REMAINED PERMANENTLY DEFUELED, UNIT 2 | | WAS SHUTDOWN FOR REFUELING AND UNIT 3 WAS OPERATING AT ABOUT 100% POWER." | | | | THE NRC RESIDENT INSPECTOR WILL BE NOTIFIED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 31570 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: ITT INDUSTRIES |NOTIFICATION DATE: 01/10/97 | | CITY: CITY OF INDUSTR REGION: 4 |NOTIFICATION TIME: 16:07 [ET]| | COUNTY: STATE: CA |EVENT DATE: 01/10/97 | |LICENSE#: AGREEMENT: Y |EVENT TIME: 16:07[PST]| | DOCKET: |LAST UPDATE DATE: 01/10/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |VERN HODGE RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: TED HOLDREDGE | | |HQ OPS OFFICER: JOHN MacKINNON | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |CDEG 21.21(c)(3)(i) DEFECTS/NONCOMPLIANCE | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | A SITUATION HAS BEEN DISCOVERED (IN THE BARTON MODEL 753 GAGE PRESSURE | | ELECTRONIC TRANSMITTERS) THAT ITT BARTON BELIEVES MAY REPRESENT A | | SUBSTANTIAL HAZARD IN SOME OF THESE INSTRUMENTS THAT ITT HAS MANUFACTURED. | | THIS HAZARD IS SULFUR INDUCED CORROSION OF THE #40 AWG COPPER STRAIN GAGE | | LEAD WIRES AND THE BERYLLIUM COPPER LINK CLIP. | | | | ITT INDUSTRIES (ITT BARTON) LOCATED AT 900 S. TURNBULL CANYON RD., P.O BOX | | 1882, CITY OF INDUSTRY, CA. NOTIFIED WESTINGHOUSE ENERGY CENTER LOCATED AT | | 4350 NORTHERN PIKE, MONROVILLE, PA. OF THIS POTENTIAL 10 CFR PART 21 | | NOTIFICATION ON 01/10/97. | | | | ITT BARTON SUPPLIES MODEL 753 GAGE PRESSURE ELECTRONIC TRANSMITTERS TO THE | | COMMERCIAL NUCLEAR POWER INDUSTRY FOR USE IN SAFETY RELATED APPLICATIONS | | THROUGH WESTINGHOUSE NUCLEAR ENERGY. A SITUATION HAS BEEN DISCOVERED THAT | | ITT BARTON BELIEVES MAY REPRESENT A SUBSTANTIAL SAFETY HAZARD IN SOME OF | | THESE INSTRUMENTS THAT THEY HAVE MANUFACTURED. THIS SITUATION INVOLVES | | SULFUR INDUCED CORROSION OF THE #40 AWG COPPER STRAIN GAGE LEAD WIRES AND | | THE BERYLLIUM COPPER LINK CLIP. UNTIL RECENTLY, ITT BARTON WAS NOT ABLE TO | | ASCERTAIN THE SOURCE OF THE SULFUR CONTAMINATION AND BELIEVED THAT THE | | LIMITED OCCURRENCES OF THIS PROBLEM ORIGINATED OUTSIDE THE FACTORY. | | ITT BARTON UNCOVERED THAT THE CORK GASKET USED WITH THE BOURDON TUBE | | TRANSDUCER HOUSING CAUSED CORROSION OF COPPER AND COPPER ALLOY PARTS. IN | | ADDITION, INTERVIEWS WITH INSTRUMENT ASSEMBLY PERSONNEL UNCOVERED A | | SITUATION WHICH INDICATED THAT SOME LINK ADJUST ASSEMBLIES USED IN THE | | MODEL 753 TRANSMITTER MAY HAVE BEEN CONTAMINATED WITH DOW CORNING MOLYKOTE | | (MOLYBDENUM DISULFIDE). CORRECTIVE ACTIONS IMPLEMENTED IN THE FACTORY | | INCLUDED REMOVAL OF ALL GASKETS OF CONCERN, SUBSTITUTION OF A GASKET MADE | | FROM A MORE STABLE MATERIAL, ASSEMBLY PROCEDURE UPGRADES, OPERATOR | | TRAINING, AND CLEANING OF ALL EXISTING LINK ADJUST ASSEMBLIES. | | THE EXISTENCE OF THE SULFUR INDUCED CORROSION CAN BE SEEN IN AN OPERATING | | INSTRUMENT IN THE FORM OF ABNORMAL DRIFT(i.e., DRIFT IN EXCESS OF NORMALLY | | EXPERIENCED DRIFT FOR THE PARTICULAR UNIT MONITORED OVER A PERIOD OF DAYS | | AT STEADY STATE CONDITIONS). THE DIRECTION OF THE STRAIN GAGE LEAD WIRE | | CORROSION DRIFT CAN BE HIGH OR LOW DEPENDING ON THE CORROSION RATE | | APPLICABLE TO THE COMPRESSION OR TENSION STRAIN GAGE LEADS. LINK CLIP DRIFT | | DIRECTION IS ALWAYS NEGATIVE. THE ELECTRICAL LEAD CORROSION DRIFT IS CAUSED | | BY THE INCREASE IN RESISTANCE OF THE CIRCUIT AS THE CORROSION REDUCES THE | | DIAMETER OF THE LEAD WIRES WHILE THE LINK CLIP CORROSION DRIFT IS CAUSED BY | | MATERIAL STRETCHING AS THE LINK CLIP THICKNESS IS REDUCED. THERE IS NO | | DIFFERENCE BETWEEN A SAFETY RELATED AND A NON SAFETY RELATED MODEL 753 WITH | | RESPECT TO THIS CORROSION CONCERN. THIS CONCERN IS LIMITED TO THE MODEL 753 | | TRANSMITTER BECAUSE OF THE USAGE OF THE SULFUR CONTAMINATED COMPONENTS. | | | | NUCLEAR POWER PLANTS OF CONCERN ARE: 1) SOUTH CAROLINA ELECTRIC & GAS (V.C. | | SUMMER ), 2) DUQUESNE LIGHT (BEAVER VALLEY), AND PACIFIC GAS & ELECTRIC | | (DIABLO CANYON). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31571 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 01/10/97 | |UNIT: [ ] [ ] [3] STATE: CT |NOTIFICATION TIME: 16:47 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 01/10/97 | +------------------------------------------------+EVENT TIME: 16:16[EST]| |NRC NOTIFIED BY: BARRY PINKOWITZ |LAST UPDATE DATE: 01/10/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |HAROLD GRAY RDO | |AINB 50.72(b)(2)(iii)(B) POT RHR INOP | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | HIGH ENERGY LINE BREAK DOOR LEFT OPEN DURING BATTERY REPLACEMENT. | | | | THE HIGH ENERGY LINE BREAK DOOR TO THE UNIT 3 TRAIN "A" 4160V SWITCHGEAR | | ROOM WAS LEFT OPEN BETWEEN 8 TO 12 HOURS DURING STATION BATTERY | | REPLACEMENT. A HOT WATER HEATING LINE TRAVERSES IN FRONT OF THE HIGH ENERGY | | LINE BREAK DOOR WHICH WAS OPEN. IF THE HOT WATER HEATING LINE HAD BROKEN | | WHILE THE DOOR WAS OPEN THE STEAM FROM THE BROKEN LINE COULD HAVE ENTERED | | INTO THE VITAL 4160V SWITCHGEAR ROOM WHICH COULD HAVE RESULTED IN A LOSS OF | | POWER TO THE RHR PUMPS AND THE SERVICE WATER PUMPS. UPON DISCOVERY OF THIS | | SITUATION LICENSEE CLOSED THE DOOR. A FIRE WATCH WAS POSTED AT THE DOOR | | WHILE IT WAS OPENED BUT THE LICENSEE SAID THAT THEY WOULD NOT ASSUME THAT | | THE FIRE WATCH WOULD HAVE CLOSED THE DOOR IF THE HOT WATER LINE HAD BROKEN. | | LICENSEE NOTIFIED THE STATE OF CT. OF THIS EVENT. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 31572 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: ALARON, WAMPUM, PA. |NOTIFICATION DATE: 01/10/97 | | CITY: WAMPUM REGION: 1 |NOTIFICATION TIME: 17:07 [ET]| | COUNTY: STATE: PA |EVENT DATE: 01/06/97 | |LICENSE#: 37-20826-01 AGREEMENT: N |EVENT TIME: 12:00[EST]| | DOCKET: |LAST UPDATE DATE: 01/10/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |HAROLD GRAY (REG 1) RDO | | | | +------------------------------------------------+CHRISTENSEN (REG 2) RDO | |NRC NOTIFIED BY: J WALLACE | | |HQ OPS OFFICER: JOHN MacKINNON | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ALARON WAS NOTIFIED BY CHEM NUCLEAR (BARNWELL, SC) THAT THE SLEEPING CAB OF | | THE TRUCK WHICH CARRIED 68 DRUMS OF COMPACTED RADIOACTIVE WASTE TO | | BARNWELL, SC., FROM ALARON HAD A RADIATION LEVEL OF 5mrem/hr (LIMIT IS | | 2mrem/hr). | | | | ALARON LOCATED IN WAMPUM, PA. WAS NOTIFIED BY CHEM NUCLEAR (BARNWELL, SC) | | ON 01/06/97 THAT A TRISTATE MOTOR TRANSIT CO. TRUCK HAD BEEN USED TO SHIP | | 68 DRUMS OF COMPACTED RADIOACTIVE WASTE FROM ALARON TO BARNWELL HAD | | RADIATION LEVELS IN THE SLEEPING CAB OF THE TRUCK OF 5mrem/hr. THE TRUCK | | LEFT ALARON LOCATED IN WAMPUM TO DELIVER THE RADIOACTIVE DRUMMED MATERIAL | | TO BARNWELL ON 12/30/96 BUT ARRIVED IN THE MORNING AT BARNWELL ON 12/31/96. | | THE DRIVER SAID THAT HE HAD SLEPT IN THE SLEEPING CAB FOR 8 HOURS. THE | | DRIVERS DOSE FROM SLEEPING IN THE CAB FOR 8 HOURS WAS CALCULATED TO BE | | 40mrem. THE LICENSEE SAID THAT THE DRIVERS TOTAL RADIOACTIVE DOSE DRIVING | | THE DRUMS OF RADIOACTIVE WASTE TO BARNWELL, SC FROM WAMPUM, PA WAS 60mrem. | | LICENSEE THINKS THAT THE DRIVER HAD BEEN INFORMED THE SLEEPING CAB | | RADIATION LEVEL WAS 5mrem/hr INSTEAD OF BEING BELOW 2mrem/hr. | | | | LICENSEE SAID THAT THE TRISTATE MOTOR TRANSIT COMPANY'S ADDRESS IS P.O. BOX | | 1233, OSBORNE RD., BARNWELL, SC. | | | | LICENSEE HAD ALREADY NOTIFIED NRC REGION 1 AND TALKED WITH DUNCAN WHITE | | ABOUT THIS INCIDENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31573 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CALVERT CLIFFS REGION: 1 |NOTIFICATION DATE: 01/10/97 | |UNIT: [1] [2] [ ] STATE: MD |NOTIFICATION TIME: 17:29 [ET]| |RX TYPE: [1] CE,[2] CE |EVENT DATE: 01/10/97 | +------------------------------------------------+EVENT TIME: 17:15[EST]| |NRC NOTIFIED BY: J GROOMS |LAST UPDATE DATE: 01/10/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |HAROLD GRAY 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 +------------------------------------------------------------------------------+ | SPENT FUEL WAS MOVED WHILE THE AUXILIARY BUILDING SUPPLY FANS WERE TAGGED | | OUT FOR MAINTENANCE. | | | | ON 01/06/97 AT 0630 THE SUPPLY FANS IN THE AUXILIARY BUILDING WERE TAGGED | | OUT FOR MAINTENANCE. EACH DAY THIS WEEK BETWEEN THE HOURS OF 0730 AND 1530 | | HOURS SPENT FUEL WAS MOVED IN THE SPENT FUEL POOL AREA. LICENSEE SECURED | | MOVING SPENT FUEL AT 1115 EST TODAY (01/10/97) WHEN A QUESTION AROSE AS TO | | WHETHER THE SUPPLY FANS IN THE AUXILIARY BUILDING NEEDED TO BE OPERABLE | | WHEN SPENT FUEL WAS BEING MOVED IN THE SPENT FUEL POOL AREA. NORMALLY IF A | | SPENT FUEL HANDLING ACCIDENT OCCURRED ALL THE RADIOACTIVE AIRBORNE | | PARTICLES WOULD FLOW THROUGH CHARCOAL HEPA FILTERS BEFORE BEING RELEASED TO | | THE OUTSIDE ATMOSPHERE. IF A SPENT FUEL ACCIDENT OCCURRED WHILE THE SUPPLY | | FANS TO THE AUXILIARY BUILDING WERE TAGGED OUT NOT ALL THE AIR FLOW WOULD | | BE THROUGH THE SPENT FUEL POOL CHARCOAL HEPA FILTERS. SOME OF THE AIR WOULD | | FLOW THROUGH THE REGULAR WASTE PROCESSING VENTILATION SYSTEM WHICH HAS ONLY | | HEPA FILTER (NO CHARCOAL IN THE FILTERS). | | ALL SPENT FUEL MOVEMENT HAS BEEN SECURED UNTIL THE SUPPLY FANS TO THE | | AUXILIARY BUILDING HAVE BEEN RESTORED TO SERVICE. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31574 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DIABLO CANYON REGION: 4 |NOTIFICATION DATE: 01/10/97 | |UNIT: [1] [2] [ ] STATE: CA |NOTIFICATION TIME: 22:01 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 01/10/97 | +------------------------------------------------+EVENT TIME: 10:15[PST]| |NRC NOTIFIED BY: HIETT |LAST UPDATE DATE: 01/10/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CHRIS VANDENBURGH 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 | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | FEMALE GREEN SEA TURTLE FOUND IN THE UNIT 1 INTAKE STRUCTURE. | | | | IN ACCORDANCE WITH THE ENVIRONMENTAL PROTECTION PLAN (SECTION 4.1) AND | | SECTION 4.5.1 OF PLANT PROCEDURE EV1.ID3 (ENVIRONMENTAL PROTECTION PLAN | | REPORTING), THE LICENSEE IS MAKING NOTIFICATION THAT A GREEN FEMALE SEA | | TURTLE WAS FOUND IN THE UNIT 1 INTAKE STRUCTURE. THE TURTLE WAS LIFTED TO | | THE INTAKE DECK BY A MOBILE CRANE. THE TURTLE WAS TRANSPORTED BY A BOAT | | 0.25 MILES OUTSIDE THE DIABLO CANYON POWER PLANT INTAKE COVE AND RELEASED. | | DIABLO CANYON NOTIFIED THE NATIONAL MARINE FISHERIES SERVICE OF THIS EVENT. | | | | THE NRC RESIDENT INSPECTOR WILL BE INFORMED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31575 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DIABLO CANYON REGION: 4 |NOTIFICATION DATE: 01/11/97 | |UNIT: [1] [2] [ ] STATE: CA |NOTIFICATION TIME: 02:56 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 01/10/97 | +------------------------------------------------+EVENT TIME: 23:45[PST]| |NRC NOTIFIED BY: DAVID PIERCE |LAST UPDATE DATE: 01/11/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CHRIS VANDENBURGH 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 | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE DISCOVERED DURING A GENERIC LETTER 96-06 REVIEW, A CONDITION | | WHICH COULD RENDER PASS SAMPLING CAPABILITY INOPERABLE. | | | | "AS PART OF OUR GL96-06, WE'VE IDENTIFIED SOME CONTAINMENT PENETRATIONS | | THAT WOULD BE POTENTIALLY SUBJECT TO OVER-PRESSURIZATION. WHILE | | CONTAINMENT INTEGRITY WOULD BE MAINTAINED, WE CANNOT CONCLUSIVELY | | DEMONSTRATE THAT FUNCTIONALITY OF THE RCS HOT LEG SAMPLING SYSTEM IS | | ASSURED POST-LOCA. | | | | THE UNIT 1 LICENSE CONDITION 2.C.(6)e, "POST ACCIDENT SAMPLING," REQUIRES | | POST ACCIDENT SAMPLING CAPABILITY IN ACCORDANCE WITH NUREG-0737, ITEM | | II.B.3 THIS LICENSE CONDITION REQUIRES THE CAPABILITY TO PROMPTLY OBTAIN | | SAMPLES OF THE REACTOR COOLANT UNDER DEGRADED CORE CONDITIONS AND PERFORM | | RADIOISOTOPIC AND CHEMICAL ANALYSIS ON THE SAMPLES. | | | | THE ABOVE MENTIONED CONDITIONS RENDER THE INSIDE CONTAINMENT PASS SAMPLE | | POINTS INOPERABLE. THE PASS RHR PUMP DISCHARGE SAMPLE POINTS, WHICH ARE | | LOCATED OUTSIDE CONTAINMENT, ARE NOT AFFECTED BY THIS CONDITION. | | | | WHILE THIS ISSUE IS NOT REALLY A CONCERN FOR A LARGE BREAK LOCA, IT IS A | | CONCERN FOR SMALL TO MEDIUM SIZE LOCAs. IT IS NOT A CONCERN FOR THE LBLOCA | | BECAUSE IN THIS CASE EVEN IF THE SYSTEM WAS TOTALLY FUNCTIONAL, THERE WOULD | | BE INSUFFICIENT PRESSURE LEFT IN THE RCS TO PROVIDE SUFFICIENT DRIVING HEAD | | IN ORDER TO EVEN OBTAIN A SAMPLE. IN THE CASE OF SBLOCA, WE KNOW THAT THE | | CONTAINMENT WILL BE HOT ENOUGH FOR A LONG ENOUGH PERIOD OF TIME TO | | POTENTIALLY CAUSE THE OVER-PRESSURIZATION BEFORE WE CAN SUFFICIENTLY COOL | | DOWN TO PLACE RHR IN SERVICE. ONCE RHR IS IN SERVICE (>3 HOURS AT 100ųF/HR | | COOLDOWN RATE), WE CAN USE THE RHR SAMPLE POINTS TO ASSESS RCS CONDITIONS. | | | | IN ACCORDANCE WITH UNIT 1 LICENSE CONDITION 2.G, PG&E IS CONSERVATIVELY | | REPORTING THAT UNIT 1 LICENSE CONDITION 2.C.(6)e AND UNITS 1 & 2 TECHNICAL | | SPECIFICATION 6.8.4.e HAVE NOT BEEN MET TO THIS POTENTIALLY DEGRADED PASS | | CAPABILITY." | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31576 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: ZION REGION: 3 |NOTIFICATION DATE: 01/11/97 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 09:08 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 01/11/97 | +------------------------------------------------+EVENT TIME: 07:13[CST]| |NRC NOTIFIED BY: DON NOLDIN |LAST UPDATE DATE: 01/11/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LEWIS MILLER RDO | |AINB 50.72(b)(2)(iii)(B) POT RHR INOP | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 40 POWER OPERATION | 40 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNIT 1 RESIDUAL HEAT REMOVAL (RHR) SYSTEMS DECLARED INOPERABLE UPON | | DISCOVERY THAT THE EMERGENCY CORE COOLING SYSTEM (ECCS) SUMP COVER LACKED | | VENT HOLES AS DESIGNED. | | | | "THE RECIRCULATION SUMP COVER IS DESIGNED TO HAVE TWO-1" VENT HOLES IN THE | | TOP TO PREVENT THE FORMATION OF A LOOP SEAL WHICH COULD IMPEDE THE SUCTION | | TO ALL ECCS PUMPS WHICH RELY ON THE RECIRCULATION SUMP FOR THEIR SUCTION | | DURING COLD LEG RECIRCULATION OPERATIONS FOLLOWING A LOCA. THE UNIT HAS | | BEEN RAMPED TO 40% POWER TO PERFORM THE INVESTIGATION. THE VENT HOLES WERE | | FOUND NOT TO EXIST. SIXTEEN-3/8" HOLES WERE DRILLED IN THE SUMP COVER TO | | PROVIDE A VENT PATH. UPON DISCOVERY TS 3.8.3 WAS ENTERED PLACING UNIT 1 ON | | A 4 HOUR LCO TO HOT SHUTDOWN. AT 0747CST THE REPAIRS WERE COMPLETED AND TS | | 3.8.3 WAS EXITED." | | | | THIS DISCREPANCY WAS IDENTIFIED FOLLOWING A SYSTEM WALKDOWN ON UNIT 2. THE | | UNIT 2 RECIRCULATION SUMP COVER DID NOT HAVE THE REQUIRED VENT HOLES AS | | WELL. HOWEVER, SINCE UNIT 2 IS IN COLD SHUTDOWN NO LCOs WERE APPLICABLE. | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | SEE EVENT # 31577 FOR SAME PROBLEM WITH UNIT 2 RECIRCULATION SUMP COVER. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31577 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: ZION REGION: 3 |NOTIFICATION DATE: 01/11/97 | |UNIT: [ ] [2] [ ] STATE: IL |NOTIFICATION TIME: 15:03 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 01/11/97 | +------------------------------------------------+EVENT TIME: 10:30[CST]| |NRC NOTIFIED BY: NOLDIN |LAST UPDATE DATE: 01/11/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LEWIS MILLER 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNIT 2 RECIRCULATION SUMP COVER WAS FOUND NOT TO HAVE 2 ONE INCH VENT HOLES | | IN IT AND THE EXPECTED GAP BETWEEN THE SUMP COVER PLATE AND THE SUMP WAS | | DETERMINED TO BE NOT MEASURABLE. | | | | "A PHYSICAL INSPECTION OF THE UNIT 1 RECIRCULATION SUMP COVER DETERMINED | | THE 2 ONE INCH VENT HOLES DID NOT EXIST PER THE DESIGN. IN ADDITION, THE | | EXPECTED GAP BETWEEN THE SUMP COVER PLATE AND THE SUMP WAS DETERMINED TO BE | | NOT MEASURABLE. WITH THAT DATA AND PREVIOUS KNOWLEDGE THAT THE 1 INCH VENT | | HOLES DID NOT EXIST ON THE UNIT 2 RECIRCULATION SUMP COVER, A DECISION WAS | | MADE TO PHYSICALLY INSPECT UNIT 2 TO DETERMINE IF A GAP COULD BE MEASURED. | | MECHANICS ENTERED UNIT 2 APPROXIMATELY 1030 ON 11JAN97 AND DETERMINED THAT | | THE GAP WAS NOT CAPABLE OF BEING MEASURED AND A DECISION WAS MADE TO DRILL | | THE NECESSARY VENT HOLES IN THE COVER. THE COVER WAS REMOVED, THE HOLE | | DRILLED AND THE COVER WAS REPLACED BY 1140, 11JAN97." | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT. | | | | SEE EVENT # 31576 FOR PROBLEM WITH UNIT 1 RECIRCULATION SUMP COVER. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31578 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BEAVER VALLEY REGION: 1 |NOTIFICATION DATE: 01/11/97 | |UNIT: [ ] [2] [ ] STATE: PA |NOTIFICATION TIME: 17:41 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 01/11/97 | +------------------------------------------------+EVENT TIME: 16:45[EST]| |NRC NOTIFIED BY: GEORGE STOROLIS |LAST UPDATE DATE: 01/11/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |HAROLD GRAY RDO | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 HOT STANDBY | 0 HOT STANDBY | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LICENSEE ENTERED TECH SPEC 3.0.3 WHEN RECIRCULATION SPRAY SYSTEM (RSS) | | SAFEGUARDS ROOM FLOOD PROTECTION SEAL WERE NOT IN ACCORDANCE WITH UFSAR. | | | | "AT 1550 HOURS LICENSEE ENTERED TECHNICAL SPECIFICATION 3.0.3 FOR COOLDOWN | | TO MODE 5 (COLD SHUTDOWN). BASED UPON ENGINEERING REVIEW, IT HAS BEEN | | DETERMINED THAT UNIT 2 DESIGN BASIS REQUIREMENTS FOR FLOOD PROTECTION WERE | | NOT MAINTAINED." | | | | "IT WAS IDENTIFIED THAT THE RSS SAFEGUARDS ROOM FLOOD PROTECTION SEALS WERE | | NOT IN ACCORDANCE WITH USFAR. IN THE ABSENCE OF THESE SEALS, EQUIPMENT IN | | THE SAFEGUARDS BUILDING REQUIRED FOR LONG TERM RECIRCULATION FOLLOWING A | | DESIGN BASIS ACCIDENT (DBA) MAY NOT BE CAPABLE OF PERFORMING ITS INTENDED | | FUNCTION, ASSUMING A DESIGN BASIS FLOOD EVENT OCCURS." | | | | "THE IDENTIFIED SEALS ARE BEING REPAIRED/REPLACED. AN ACTION PLAN IS BEING | | DEVELOPED TO ADDRESS OTHER AREAS POTENTIALLY AFFECTED IN UNIT 2. THE | | APPLICABILITY OF THIS TO UNIT 1 IS BEING REVIEWED BY MANAGEMENT AND | | NECESSARY ACTIONS WILL BE TAKEN AS REQUIRED." THE SEAL SHOULD BE REPLACED | | IN THE NEXT 24 HOURS. | | | | THE NRC RESIDENT INSPECTOR WILL BE INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 31579 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: GEOMECHANICS |NOTIFICATION DATE: 01/11/97 | | CITY: ELIZABETH REGION: 1 |NOTIFICATION TIME: 19:01 [ET]| | COUNTY: ALLEGHENY STATE: PA |EVENT DATE: 01/11/97 | |LICENSE#: 37-17332-01 AGREEMENT: N |EVENT TIME: 14:30[EST]| | DOCKET: |LAST UPDATE DATE: 01/11/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |HAROLD GRAY RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: WALTER LORENCE | | |HQ OPS OFFICER: JOHN MacKINNON | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NDAM DAMAGE MEASURE GAUGE | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TROXLER MOISTURE DENSITY GAUGE DAMAGED BY MOVING EQUIPMENT. | | | | AT 1430 ON 01/11/97 AT PENN CENTER WEST IN THE PITTSBURGH AREA A TROXLER | | MOISTURE DENSITY GAUGE (MODEL # 3430, SERIAL # 26129) WAS SEVERELY DAMAGED | | WHEN A PIECE OF CONSTRUCTION EQUIPMENT RAN OVER IT. THE LICENSEE | | (GeoMechanics LOCATED AT 600 MUNER DR., P.O. BOX 386, ELIZABETH, PA) | | NOTIFIED APPLIED HEALTH PHYSICS OF THE INCIDENT. APPLIED HEALTH PHYSICS | | SENT A PERSON TO THE SITE. THE APPLIED HEALTH PHYSICS PERSON TOOK RADIATION | | READINGS AND SWIPES AROUND THE SITE AND OF THE DAMAGED TROXLER MOISTURE | | DENSITY GAUGE. THE SWIPES ARE AT THIS TIME BEING COUNTED. THE SHIELDING TO | | THE TROXLER MOISTURE DENSITY GAUGE WAS DAMAGED. THE TROXLER MOISTURE | | DENSITY GAUGE WAS WRAPPED IN PLASTIC, PLACED IN A CONTAINER, AND SHIELDING | | WAS PLACED AROUND THE CONTAINER. AT THIS TIME THE CONTAINER CONTAINING THE | | GAUGE IS LOCKED INSIDE A STORAGE TRAILER. RADIATION LEVELS ARE LESS THAN | | 1mrem/hr AT ONE FOOT FROM THE SHIELDING AROUND THE CONTAINER. APPLIED | | HEALTH PHYSICS WILL PICK UP THE TROXLER MOISTURE DENSITY GAUGE ON 01/13/97 | | AND THEN SEND IT BACK TO TROXLER. THE TROXLER MOISTURE DENSITY GAUGE | | CONTAINS 8mCis of Cs-137 and 40mCis of AMERICIUM-BERYLLIUM. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31580 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 01/12/97 | |UNIT: [ ] [ ] [3] STATE: CT |NOTIFICATION TIME: 08:44 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 01/12/97 | +------------------------------------------------+EVENT TIME: 08:33[EST]| |NRC NOTIFIED BY: MIKE GENTRY |LAST UPDATE DATE: 01/12/97 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |HAROLD GRAY RDO | |AINB 50.72(b)(2)(iii)(B) POT RHR INOP | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | A HIGH ENERGY LINE BREAK BARRIER WAS BLOCKED OPEN DUE TO HUMAN ERROR. | | | | A SECURITY GUARD BLOCKED OPEN A CONTROL BUILDING HIGH ENERGY LINE BREAK | | BARRIER (A HATCH TYPE DOOR) FOR MOST OF 1/11/97. THE LICENSEE WAS | | REPLACING THE STATION BATTERY IN THAT ROOM AND THE GUARD ALSO OPENED A | | SECURITY DOOR WHICH HE WAS GUARDING. THE LICENSEE HAS NOT DETERMINED THE | | GUARD'S EXACT THOUGHT PROCESS AT THIS TIME. THE LICENSEE INFORMED STATE | | AND LOCAL GOVERNMENT AND THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+