U.S. Nuclear Regulatory Commission Operations Center Event Reports For 01/17/95 - 01/18/95 ** EVENT NUMBERS ** 28113 28191 28229 28245 28246 28247 28248 28249 28250 28251 28252 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28113 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: ZION REGION: 3 |NOTIFICATION DATE: 12/06/94 | |UNIT: [ ] [2] [ ] STATE: IL |NOTIFICATION TIME: 13:18 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 12/06/94 | +------------------------------------------------+EVENT TIME: 11:30[CST]| |NRC NOTIFIED BY: CARLSON |LAST UPDATE DATE: 01/17/95 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JORGENSEN 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 81 POWER OPERATION | 81 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNIT OUTSIDE DESIGN BASIS FOR 19 HOURS DURING PERIOD OF 10/31/94 - 11/1/94 | | DUE TO INOPERABILITY OF TWO EMERGENCY DIESEL GENERATORS. | | | | ON NOVEMBER 10, 1994, THE UNIT 0 (SHARED) EMERGENCY DIESEL GENERATOR (EDG) | | WAS DECLARED INOPERABLE FOR UNIT 2, DUE TO A MALFUNCTIONING CONTROL SWITCH, | | WHICH HAD BEEN DISCOVERED ON OCTOBER 29, 1994. (THE LICENSEE DID NOT | | DETERMINE THAT THE MALFUNCTION OF THE SWITCH RENDERED THE UNIT 0 EDG | | INOPERABLE UNTIL NOVEMBER 10, 1994.) THE SWITCH WAS REPAIRED, AND THE EDG | | DECLARED OPERABLE ON NOVEMBER 11, 1994. COINCIDENTALLY, THE 2A EDG WAS | | DECLARED INOPERABLE ON OCTOBER 31, 1994 DUE TO A MALFUNCTIONING LIGHT BULB | | ON THE CONTROL PANEL. THE 2A EDG WAS REPAIRED AND RETURNED TO SERVICE ON | | NOVEMBER 1, 1994. | | | | ON DECEMBER 6, THE LICENSEE DETERMINED THAT BOTH EDGs HAD BEEN INOPERABLE | | SIMULTANEOUSLY FOR 19 HOURS AND 43 MINUTES DURING THE PERIOD OF 10/31/94 TO | | 11/1/94, PLACING THE UNIT OUTSIDE OF ITS DESIGN BASIS. THE NRC RESIDENT | | INSPECTOR HAS BEEN INFORMED OF THIS EVENT BY THE LICENSEE. | | | | * * * UPDATE 1533 1/17/95 FROM OBERMBT TO STRANSKY * * * | | | | THE LICENSEE IS RETRACTING THIS EVENT. UPON FURTHER REVIEW OF THE EVENT, | | THE LICENSEE HAS DETERMINED THAT THE ENS NOTIFICATION WAS NOT REQUIRED AND | | THE SUBJECT EVENT IS NOT REPORTABLE UNDER 10 CFR 50.73. THE DESIGN BASIS | | ASSUMED IN THE ORIGINAL REPORTABILITY DETERMINATION IS NOT THE CORRECT | | DESIGN BASIS. THEREFORE, THE OPERABILITY DETERMINATION MADE ON 10/31/94 | | REGARDING THE '0' EDG WAS REASONABLE. THE NRC RESIDENT INSPECTOR HAS BEEN | | INFORMED BY THE LICENSEE. NOTIFIED R3DO (CREED). | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28191 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OCONEE REGION: 2 |NOTIFICATION DATE: 12/27/94 | |UNIT: [1] [2] [3] STATE: SC |NOTIFICATION TIME: 17:28 [ET]| |RX TYPE: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-LP |EVENT DATE: 12/27/94 | +------------------------------------------------+EVENT TIME: 16:45[EST]| |NRC NOTIFIED BY: DAVE NIX |LAST UPDATE DATE: 01/17/95 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |STEVEN VIAS 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | 3 | N Y 100 POWER OPERATION | 100 POWER OPERATION | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - ALL 3 UNITS IN SHUTDOWN LCO DUE TO INOPERABLE Rx BUILDING SPRAY SYSTEMS - | | | | LICENSEE WAS REVIEWING THE PLANT ABNORMAL PROCEDURE FOR THE LOSS OF LOW | | PRESSURE INJECTION FOR EACH UNIT. LICENSEE DETERMINED THAT DURING A | | POSTULATED LOSS OF COOLANT ACCIDENT IN WHICH A SINGLE FAILURE DISABLES | | 1 OF THE 2 REACTOR BUILDING EMERGENCY SUMP LINES, THIS PROCEDURE INSTRUCTS | | THE CONTROL ROOM OPERATORS TO STOP BOTH REACTOR BUILDING SPRAY PUMPS PRIOR | | TO SWAPPING THE SUCTION PATH FROM THE BORATED WATER STORAGE TANK TO THE | | REACTOR BUILDING EMERGENCY SUMP. | | | | THIS CONDITION IS BEYOND THE DESIGN BASIS ASSUMPTIONS OUTLINED IN THE | | MAXIMUM HYPOTHETICAL ACCIDENT (MHA) PER THE NRC SAFETY EVALUATION REPORT | | (SER) FOR THE OCONEE NUCLEAR STATION UPDATED FINAL SAFETY ANALYSIS REPORT. | | THIS SER REQUIRES OPERABILITY OF THE REACTOR BUILDING SPRAY SYSTEM TO | | MITIGATE THE CONSEQUENCES OF AN MHA. | | | | AT 1645, LICENSEE DECLARED ALL 3 REACTOR BUILDING SPRAY SYSTEMS INOPERABLE | | AND ENTERED TECH SPEC LCO A/S 3.0 WHICH REQUIRES ALL 3 UNITS TO BE PLACED | | IN HOT SHUTDOWN MODE WITHIN 12 HOURS. LICENSEE ADMINISTRATIVELY IS NOT | | REQUIRED TO BEGIN ACTUAL POWER REDUCTION FOR THE FIRST 6 HOURS. | | | | LICENSEE INTENDS TO REVISE THE ABNORMAL PROCEDURE FOR EACH UNIT SUCH THAT | | UPON FAILURE OF THE SUCTION LINE FROM THE REACTOR BUILDING EMERGENCY SUMP | | TO THE LOW PRESSURE INJECTION/REACTOR BUILDING SPRAY PUMPS, THE CONTROL | | ROOM OPERATORS WILL BE INSTRUCTED TO STOP 1 LOW PRESSURE INJECTION PUMP | | WHICH WILL LEAVE 1 LOW PRESSURE INJECTION PUMP AND 1 REACTOR BUILDING SPRAY | | PUMP RUNNING. THIS LINEUP WILL MEET ALL DESIGN BASIS ASSUMPTIONS SPECIFIED | | IN THE MHA. | | | | LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE AT 2232 BY OWENS ENTERED BY HOO JOLLIFFE * * * | | | | AT 2225, LICENSEE REVISED ALL 3 ABNORMAL PROCEDURES AND EXITED TECH SPEC | | LCO A/S 3.0. | | | | ALL 3 UNITS REMAINED AT 100% POWER THROUGHOUT THIS EVENT. | | | | LICENSEE PREPARED A SAFETY EVALUATION OF THIS CONDITION IN ACCORDANCE WITH | | 10CFR50.59. | | | | LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | | | | HOO NOTIFIED R2DO STEVE VIAS. | | | | * * * UPDATE 1448 1/17/95 BY PATTERSON TO STRANSKY * * * | | | | THE LICENSEE IS RETRACTING THIS NOTIFICATION. FURTHER EVALUATION HAS SHOWN | | THAT THE 10 CFR PART 100 DOSE LIMITS WOULD NOT HAVE BEEN EXCEEDED. | | THEREFORE, THE PLANT WAS NOT OPERATING OUTSIDE OF ITS DESIGN BASIS. THE | | NRC RESIDENT INSPECTOR HAS BEEN INFORMED. NOTIFIED R2DO(BARR) | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |HOSPITAL | |EVENT NUMBER: 28229 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: SAINT MARYS HOSPITAL |NOTIFICATION DATE: 01/11/95 | | CITY: GREEN BAY REGION: 3 |NOTIFICATION TIME: 12:49 [ET]| | COUNTY: STATE: WI |EVENT DATE: 01/11/95 | |LICENSE#: 48-12786-01 AGREEMENT: N |EVENT TIME: 08:45[CST]| | DOCKET: |LAST UPDATE DATE: 01/17/95 | | +-----------------------------+ | |PERSON ORGANIZATION| | |ROY CANIANO RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: CINDY HAUPT | | |HQ OPS OFFICER: WILLIAM HUFFMAN | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |LADM 35.33(a) MED MISADMINISTRATION | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | WRONG DIAGNOSTIC RADIOISOTOPE ADMINISTERED. | | | | 4.2 MILLICURIES OF THALLIUM-201 FOR HEART SCAN PRESCRIBED. | | | | 2.6 MILLICURIES OF TECHNETIUM-99m FOR LUNG SCAN ADMINISTERED. | | | | DISCOVERED IMMEDIATELY AFTER INJECTION. | | | | WRONG SYRINGE USED. | | | | NO ADVERSE HEALTH EFFECTS ANTICIPATED. | | | | PATIENT AND PHYSICIAN INFORMED. | | | | * * * UPDATE 1452 1/17/95 BY ZEUSKE TO STRANSKY * * * | | | | THE LICENSEE IS RETRACTING THIS EVENT BASED UPON DISCUSSIONS WITH NRC | | REGION 3 (D. WIEDEMAN), BECAUSE THE DOSE TO THE PATIENT DUE TO THE | | ADMINISTRATION OF THE INCORRECT ISOTOPE IS BELOW THE REPORTING REQUIREMENT. | | NOTIFIED R3DO (CREED). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28245 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOPER REGION: 4 |NOTIFICATION DATE: 01/17/95 | |UNIT: [1] [ ] [ ] STATE: NE |NOTIFICATION TIME: 01:10 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 01/16/95 | +------------------------------------------------+EVENT TIME: 23:39[CST]| |NRC NOTIFIED BY: RATZLAFF |LAST UPDATE DATE: 01/17/95 | |HQ OPS OFFICER: TIM McGINTY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |TOM STETKA 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 +------------------------------------------------------------------------------+ | PRIMARY CONTAINMENT NITROGEN SUPPLY AND TIP VALVES WILL RE-OPEN UPON | | RESETTING A GROUP TWO ISOLATION SIGNAL IF THEIR RESPECTIVE SWITCHES ARE | | LEFT IN THE "OPEN" POSITION. | | | | USAR (UPDATED SAFETY ANALYSIS REPORT) SAFETY DESIGN BASIS FOR PCIS (PRIMARY | | CONTAINMENT ISOLATION SYSTEM) SPECIFIES THAT PRIMARY CONTAINMENT ISOLATION | | VALVES WILL NOT RESET WHEN THE ISOLATION SIGNAL IS RESET. NUREG-0578 ALSO | | ADDRESSES THIS DESIGN CONDITION, STATING SPECIFICALLY THAT "OPERATOR ACTION | | TO TAKE THE VALVE CONTROL SWITCH TO CLOSE, TO ENSURE THE VALVE WILL NOT | | RE-OPEN ON ISOLATION RESET". THE ENGINEERING EVALUATION HAS DETERMINED | | THIS TO BE "INAPPROPRIATE" FOR PRIMARY CONTAINMENT NITROGEN SUPPLY AND TIP | | VALVES . | | | | THE PRIMARY CONTAINMENT MOV 13-XX SERIES OF VALVES (PRIMARY CONTAINMENT | | NITROGEN SUPPLY) AND THE TRAVERSING IN-CORE PROBE (TIP) VALVES ARE | | AUTOMATICALLY RE-OPENED WHEN THE GROUP TWO ISOLATION SIGNAL IS RESET, IF | | THEIR RESPECTIVE CONTROL SWITCHES ARE IN THE OPEN POSITION. THE SWITCH | | DESIGN IS SUCH THAT THE OPEN POSITION IS A "MAINTAIN POSITION" WHEN | | SELECTED. THIS PROBLEM WAS EVALUATED DUE TO A CONDITION REPORT THAT HAD | | BEEN INITIATED. | | | | THE LICENSEE WILL BE FURTHER EVALUATING THIS CONDITION TO ASSESS THE NEED | | FOR CORRECTIVE ACTION. THE LICENSEE INFORMED THE RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28246 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 01/17/95 | |UNIT: [2] [ ] [ ] STATE: NY |NOTIFICATION TIME: 02:09 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 01/17/95 | +------------------------------------------------+EVENT TIME: 00:39[EST]| |NRC NOTIFIED BY: SANTINI |LAST UPDATE DATE: 01/17/95 | |HQ OPS OFFICER: TIM McGINTY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MOHAMED SHANBAKY RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 2 | A/R Y 89 POWER OPERATION | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TURBINE TRIP/RX TRIP ON LOW TURBINE CONTROL AUTO-STOP OIL PRESSURE. | | | | UNIT 2 EXPERIENCED A TURBINE TRIP ON TURBINE CONTROL OIL "AUTO-STOP". THE | | COINCIDENCE IS 2 OUT OF 3 AUTO-STOP OIL PRESSURE < 45 psig. THE REACTOR | | TRIPPED ON THE TURBINE TRIP. THE CAUSE OF THE LOW AUTO-STOP OIL PRESSURE | | IS UNDER INVESTIGATION. ALL AUTOMATIC ACTIONS OCCURRED AS REQUIRED FOR | | BOTH TURBINE AND REACTOR TRIPS, AND ALL SYSTEMS FUNCTIONED AS REQUIRED. THE | | UNIT IS STABLE IN HOT STANDBY. | | | | IP-2 WAS OPERATING AT 89% POWER FOR FUEL OPTIMIZATION AND DUE TO A SMALL | | (4-5 gpd) TUBE LEAK ON THE #24 STEAM GENERATOR. THE ATMOSPHERIC STEAM | | DUMPS WERE NOT UTILIZED FOR STEAMING IN RESPONSE TO THE TRIP. CURRENTLY, | | ALL STEAM IS BEING DIRECTED TO SECONDARY LOADS AND THERE IS NO NEED TO | | STEAM TO THE MAIN CONDENSER OR VIA THE ATMOSPHERIC STEAM DUMPS TO REMOVE | | HEAT. ALL RODS FULLY INSERTED ON THE RX TRIP, AND THERE WERE NO PROBLEMS | | WITH THE TRANSFER OF ELECTRICAL BUSES. NO PRIMARY OR SECONDARY RELIEF | | VALVES LIFTED IN RESPONSE TO THE TRIP. ALL ECCS's AND EDG's ARE OPERABLE | | AND IN STANDBY. THE STEAM GENERATORS ARE BEING FED VIA THE AUXILIARY BOILER | | FEED PUMPS. | | | | THE LICENSEE WILL INFORM THE RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28247 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SAN ONOFRE REGION: 4 |NOTIFICATION DATE: 01/17/95 | |UNIT: [1] [2] [3] STATE: CA |NOTIFICATION TIME: 06:00 [ET]| |RX TYPE: [1] W-3-LP,[2] CE,[3] CE |EVENT DATE: 01/17/95 | +------------------------------------------------+EVENT TIME: 02:25[PST]| |NRC NOTIFIED BY: MAHER |LAST UPDATE DATE: 01/17/95 | |HQ OPS OFFICER: TIM McGINTY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |TOM STETKA RDO | |DDDD 73.71 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 DECOMMISSIONED | 0 DECOMMISSIONED | | 2 | N Y 97 POWER OPERATION | 97 POWER OPERATION | | 3 | N Y 97 POWER OPERATION | 97 POWER OPERATION | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ASSAULT MADE WITHIN THE PROTECTED AREA (TWO INDIVIDUALS HAD A FIGHT). | | IMMEDIATE COMPENSATORY MEASURES TAKEN UPON DISCOVERY. INDIVIDUALS WERE | | NON-SUPERVISORY AND ARE NOT LICENSED OPERATORS. LICENSEE INFORMED THE | | RESIDENT INSPECTOR. SEE HOO LOG FOR DETAILS. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28248 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: WATTS BAR REGION: 2 |NOTIFICATION DATE: 01/17/95 | |UNIT: [1] [2] [ ] STATE: TN |NOTIFICATION TIME: 14:46 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 01/17/95 | +------------------------------------------------+EVENT TIME: 00:00[EST]| |NRC NOTIFIED BY: HAMILTON |LAST UPDATE DATE: 01/17/95 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BARR 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 UNDER CONSTRUCT | 0 UNDER CONSTRUCT | | 2 | N N 0 UNDER CONSTRUCT | 0 UNDER CONSTRUCT | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | CONTRACT SUPERVISOR TESTED POSITIVE FOR ILLEGAL SUBSTANCE (MARIJUANA) USE | | DURING RANDOM DRUG TEST. THE INDIVIDUAL'S SITE ACCESS HAS BEEN TERMINATED. | | SEE HOO LOG FOR ADDITIONAL INFORMATION. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28249 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VERMONT YANKEE REGION: 1 |NOTIFICATION DATE: 01/17/95 | |UNIT: [1] [ ] [ ] STATE: VT |NOTIFICATION TIME: 16:02 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 01/17/95 | +------------------------------------------------+EVENT TIME: 15:50[EST]| |NRC NOTIFIED BY: McKENNEY |LAST UPDATE DATE: 01/17/95 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PASCIAK 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 +------------------------------------------------------------------------------+ | UNIT OUTSIDE OF DESIGN BASIS DUE TO INOPERABLE CONTROL ROOM VENTILATION | | INLET DAMPER. | | | | DURING PREVENTIVE MAINTENANCE TESTING OF THE CONTROL ROOM VENTILATION | | SYSTEM, AN INLET DAMPER FAILED TO OPERATE. THE DAMPER IS REQUIRED TO | | ISOLATE IN THE EVENT OF A POSTULATED ACCIDENT IN ORDER TO MAINTAIN CONTROL | | ROOM HABITABILITY. WITHOUT THE CLOSURE OF THIS DAMPER, CONTROL ROOM | | OPERATORS WOULD RECEIVE RADIATION DOSES IN EXCESS OF THOSE PERMITTED BY 10 | | CFR PART 100. THE LICENSEE IS CURRENTLY DETERMINING A COURSE OF ACTION, | | BUT EXPECTS A NEED TO REPLACE THE DAMPER. THE LICENSEE HAS NOTIFIED THE | | STATE OF VERMONT AND WILL NOTIFY THE NRC RESIDENT INSPECTOR OF THIS EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28250 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: GRAND GULF REGION: 2 |NOTIFICATION DATE: 01/17/95 | |UNIT: [1] [ ] [ ] STATE: MS |NOTIFICATION TIME: 16:25 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 01/17/95 | +------------------------------------------------+EVENT TIME: 14:50[CST]| |NRC NOTIFIED BY: STAFFORD |LAST UPDATE DATE: 01/17/95 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BARR 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 +------------------------------------------------------------------------------+ | TWO 4160V ESF BREAKER CABINETS FOUND IN CONDITION OUTSIDE OF SEISMIC | | ANALYSIS | | | | DURING A SYSTEM ENGINEERING WALKDOWN, TWO SPARE 4160V BREAKERS LOCATED IN | | TWO SEPARATE ESF BREAKER CABINETS WERE FOUND IN THE DISENGAGED POSITION, | | WHICH DOES NOT MEET SEISMIC QUALIFICATIONS. THE BREAKERS WERE IMMEDIATELY | | RACKED IN TO THE "DISCONNECT" POSITION. THE LICENSEE IS INSTALLING CAUTION | | TAGS ON ALL BREAKER CABINETS TO PREVENT RECURRENCE OF THIS TYPE OF | | SITUATION. THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28251 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FITZPATRICK REGION: 1 |NOTIFICATION DATE: 01/17/95 | |UNIT: [1] [ ] [ ] STATE: NY |NOTIFICATION TIME: 17:31 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 12/08/94 | +------------------------------------------------+EVENT TIME: 00:00[EST]| |NRC NOTIFIED BY: ZAREMBA |LAST UPDATE DATE: 01/17/95 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PASCIAK RDO | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | CONTRACT SUPERVISOR AND CONTRACT WORKER FALSIFIED DOSIMETRY INFORMATION TO | | IMPROPERLY GAIN ACCESS TO RADIOLOGICALLY CONTROLLED AREA. | | | | THE LICENSEE NOTIFIED THE NRC OPERATIONS CENTER OF A POTENTIAL 10 CFR 50.9 | | VIOLATION BY TWO CONTRACT INDIVIDUALS. THE LICENSEE HAS DISCOVERED THAT | | TWO CONTRACT INDIVIDUALS (A SUPERVISOR AND A WORKER) VIOLATED PLANT | | RADIATION PROTECTION PROCEDURES AND MADE SEVERAL ENTRIES INTO THE PLANT | | RADIOLOGICALLY CONTROLLED AREA (RCA) DURING 12/8/94 - 12/9/94 WITHOUT | | FOLLOWING PLANT PROCEDURES FOR DOSIMETRY ISSUANCE AND CHECK IN WITH | | RADIATION PROTECTION STAFF. | | | | EARLIER IN DECEMBER, THE CONTRACT SUPERVISOR HAD ESCORTED A CONTRACT WORKER | | INTO THE RCA, BUT HAD RETAINED THE WORKER'S THERMO-LUMINESCENT DOSIMETER | | (TLD) UPON HIS DEPARTURE FROM THE SITE. WHEN A SECOND CONTRACT WORKER | | REQUIRED ESCORTED ACCESS TO THE RCA ON 12/8/94, THE SUPERVISOR PROVIDED HIM | | WITH THE PREVIOUS WORKER'S TLD, AND INSTRUCTED HIM TO SIGN IN AS THE | | PREVIOUS INDIVIDUAL. THE LICENSEE HAS INTERVIEWED THE SUPERVISOR, WHO HAS | | ADMITTED TO PROVIDING THE TLD TO THE VISITOR, AND INSTRUCTING HIM TO SIGN | | IN UNDER A DIFFERENT NAME. THE CONTRACT SUPERVISOR WAS ESCORTED OFFSITE, | | AND HIS SITE ACCESS HAS BEEN REVOKED. | | | | THE LICENSEE HAS PROCESSED THE TLD, AND DETERMINED THAT NEITHER CONTRACT | | WORKER HAD RECEIVED A MEASURABLE DOSE. THE LICENSEE IS CURRENTLY REVIEWING | | ALL RECORDS OF VISITORS ONSITE WHO HAVE BEEN ISSUED TLDs IN ORDER TO ASSURE | | THAT THIS WAS AN ISOLATED INSTANCE. THIS INFORMATION WAS PROVIDED TO THE | | NRC REGION 1 ACTING REGIONAL ADMINISTRATOR TODAY (1/17/95). | | | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28252 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DRESDEN REGION: 3 |NOTIFICATION DATE: 01/17/95 | |UNIT: [ ] [2] [ ] STATE: IL |NOTIFICATION TIME: 19:49 [ET]| |RX TYPE: [1] GE-1,[2] GE-3,[3] GE-3 |EVENT DATE: 01/17/95 | +------------------------------------------------+EVENT TIME: 18:15[CST]| |NRC NOTIFIED BY: McDONALD |LAST UPDATE DATE: 01/17/95 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CREED RDO | |ADEG 50.72(b)(1)(ii) DEGRAD COND DURING OP | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 97 POWER OPERATION | 97 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | CONTAINMENT ISOLATION VALVE FOR DRYWELL OXYGEN ANALYZER FAILED LOCAL LEAK | | RATE TEST. | | | | THE FOLLOWING IS TEXT OF A FACSIMILE SUBMITTED BY THE LICENSEE: | | | | "WHILE PERFORMING LOCAL LEAK RATE TEST ON DRYWELL OXYGEN ANALYZER PRIMARY | | CONTAINMENT ISOLATION VALVE 2-9205B CONTAINMENT LEAKAGE EXCEEDED TECH SPEC | | LIMIT OF 0.6 La. REDUNDANT ISOLATION VALVE TESTED SATISFACTORILY AND PER | | TECH SPEC 3.7.D2 POWER OPERATION MAY CONTINUE PROVIDED REDUNDANT ISOLATION | | VALVE IS TAKEN OUT OF SERVICE CLOSED." | | | | THE UNIT IS CURRENTLY IN A 7 DAY LIMITING CONDITION FOR OPERATION DUE TO | | THE OXYGEN ANALYZER BEING DECLARED INOPERABLE. THE LICENSEE PLANS TO | | RETURN THE OXYGEN TO SERVICE WITH THREE OF THE FOUR SAMPLE LINES OPERABLE. | | THE NRC RESIDENT INSPECTOR WILL BE INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+