U.S. Nuclear Regulatory Commission Operations Center Event Reports For 09/04/98 - 09/08/98 ** EVENT NUMBERS ** 34734 34735 34736 34737 34738 34739 34740 34741 34742 34743 34744 34745 34746 34747 34748 34749 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34734 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VOGTLE REGION: 2 |NOTIFICATION DATE: 09/04/98 | |UNIT: [ ] [2] [ ] STATE: GA |NOTIFICATION TIME: 02:36 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 09/04/98 | +------------------------------------------------+EVENT TIME: 00:24[EDT]| |NRC NOTIFIED BY: DAVID McCARY |LAST UPDATE DATE: 09/04/98 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | A/R Y 100 POWER OPERATION | 0 HOT STANDBY | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNIT 2 EXPERIENCED AN AUTOMATIC TURBINE TRIP/REACTOR TRIP FROM 100% POWER | | DURING SURVEILLANCE TESTING. | | | | "AT APPROXIMATELY 0024EDT UNIT 2 AUTOMATICALLY TRIPPED DUE TO A TURBINE | | TRIP/REACTOR TRIP 125VDC TRIP SIGNAL. ALL SYSTEMS FUNCTIONED AS REQUIRED, | | INCLUDING AN AUX FEEDWATER ACTUATION, AND THE PLANT IS STABLE IN MODE 3 AT | | THIS TIME. AN ESFAS SLAVE RELAY BLOCK TEST FOR TRIP OF BOTH MAIN FEED | | PUMPS AND TURBINE TRIP WAS IN PROGRESS AT THE TIME OF THE TRIP. | | INVESTIGATION AS TO THE ACTUAL CAUSE OF THE TRIP IS IN PROGRESS." | | | | ALL CONTROL RODS FULLY INSERTED WITH NO PRIMARY/SECONDARY SAFETIES OR | | RELIEFS LIFTING DURING THE TRANSIENT. BOTH MOTOR-DRIVEN AND THE | | STEAM-DRIVEN AUXILIARY FEEDWATER PUMPS AUTOSTARTED AS EXPECTED. DECAY HEAT | | IS BEING REMOVED VIA THE STEAM DUMPS TO THE MAIN CONDENSER WITH MAKEUP FEED | | SUPPLIED BY THE AFW SYSTEM. ALL ECCS EQUIPMENT IS AVAILABLE. | | | | THE LICENSEE HAS NO ESTIMATE FOR RESTART AND HAS INFORMED THE NRC RESIDENT | | INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34735 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: GINNA REGION: 1 |NOTIFICATION DATE: 09/04/98 | |UNIT: [1] [ ] [ ] STATE: NY |NOTIFICATION TIME: 11:15 [ET]| |RX TYPE: [1] W-2-LP |EVENT DATE: 09/04/98 | +------------------------------------------------+EVENT TIME: 07:40[EDT]| |NRC NOTIFIED BY: DOUGLAS PETERSON |LAST UPDATE DATE: 09/04/98 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DAVID LEW RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | Unit experienced Control Room HVAC shift to recirc mode due to radon caused | | by a temperature inversion. | | | | "At 0740 [on 9/4/98 the Unit] started experiencing R-36 & R-37 (Control | | Room Noble Gas and Particulate Monitors) alarms which put the Control Room | | HVAC system on recirc. [The Control Room] had [the] Radiation Protection | | Shift Tech (RP Tech) draw an independent air sample to confirm monitors | | response. The sample confirmed that the monitors are actually responding to | | radon gas as a result of a temperature inversion. The sample showed only | | daughter products of radon with a half-life of less than an hour." | | | | The licensee notified the Resident Inspector. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 34736 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 09/04/98 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 13:56 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 09/03/98 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 14:00[EDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 09/04/98 | | CITY: PIKETON REGION: 3 +-----------------------------+ | COUNTY: PIKE STATE: OH |PERSON ORGANIZATION| |LICENSE#: GDP-2 AGREEMENT: N |ROGER LANKSBURY RDO | | DOCKET: 0707002 |LARRY CAMPER, NMSS EO | +------------------------------------------------+ | |NRC NOTIFIED BY: KEITH WILLIAMSON | | |HQ OPS OFFICER: BOB STRANSKY | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NBNL RESPONSE-BULLETIN | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | 24-Hour NRC Bulletin 91-01 report | | | | Facility personnel discovered that a nuclear criticality safety approval | | (NCSA) requirement was not being maintained in laboratory storage area room | | 120 of the X-710 Laboratory. A container (poly bottle) was found in this | | storage area in a non-secured holder, violating requirement #2 of | | NCSA_0710_077_A00. Requirement #2 states, in part: "storage areas shall | | have securely anchored holders designed to physically maintain the required | | spacing." This condition constitutes a loss of one control ("A" - spacing) | | in the double contingency matrix for contingency event A/B.7.1. Control "B" | | (mass/moderation) was maintained throughout this event. Control "A" was | | immediately established. | | | | The improper anchoring of a single poly bottle holder has a low safety | | significance. The failure of a single poly bottle holder is bounded by | | placing two containers in contact, which was examined in the NCSE. | | | | The NRC resident inspector has been informed of this event. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |HOSPITAL | |EVENT NUMBER: 34737 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: CLEVELAND CLINIC FOUNDATION |NOTIFICATION DATE: 09/04/98 | | CITY: CLEVELAND REGION: 3 |NOTIFICATION TIME: 15:02 [ET]| | COUNTY: CUYAHOGA STATE: OH |EVENT DATE: 08/11/98 | |LICENSE#: 34-00466-01 AGREEMENT: N |EVENT TIME: 00:00[EDT]| | DOCKET: |LAST UPDATE DATE: 09/04/98 | | +-----------------------------+ | |PERSON ORGANIZATION| | |ROGER LANKSBURY RDO | | |MICHAEL WEBER EO | +------------------------------------------------+ | |NRC NOTIFIED BY: XIAOWEI ZHU | | |HQ OPS OFFICER: BOB STRANSKY | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |LADM 35.33(a) MED MISADMINISTRATION | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | Potential underdose due to apparent discrepancy between dose calibrator and | | activity information provided by vendor. | | | | The licensee has identified an apparent discrepancy between activities | | dispensed by a dose calibrator and information provided by Amersham Corp. | | The licensee reported that the dose calibrator was set using information | | provided by Amersham, but that the vendor information could not be readily | | verified because the isotope (yttrium-90) is a á emitter. | | | | Using a scintillation counter, the licensee recently calculated the | | activity of a sample using a liquid scintillation detector, and determined | | that the activity of the sample was 20% lower than that stated in the | | vendor's information. This would have resulted in an underdose to patients | | of 20%. The licensee will contact NRC Region 3 regarding this event. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34738 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: RIVER BEND REGION: 4 |NOTIFICATION DATE: 09/04/98 | |UNIT: [1] [ ] [ ] STATE: LA |NOTIFICATION TIME: 15:18 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 09/04/98 | +------------------------------------------------+EVENT TIME: 00:00[CDT]| |NRC NOTIFIED BY: HUSTON |LAST UPDATE DATE: 09/04/98 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |IAN BARNES RDO | |AINA 50.72(b)(2)(iii)(A) POT UNABLE TO SAFE SD | | |AINB 50.72(b)(2)(iii)(B) POT RHR INOP | | |AINC 50.72(b)(2)(iii)(C) POT UNCNTRL RAD REL | | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | Emergency diesel generators may not have been capable of performing safety | | function from 1985 to 1990. | | | | "During review and evaluation of issues involving the air supply to the | | Division I and II diesel generator pneumatic control systems, it was | | determined that, under a specific sequence of events, the diesel generators | | may not have been capable of performing their safety function prior to | | making procedure revisions in 1990. This condition existed from initial | | startup in 1985 until 1990. In 1990, provisions were added to operating | | procedures to direct operators to provide a bottled air supply to the | | diesel pneumatic control system if diesels were required for extended | | emergency operation and the installed air compressors were not available to | | supply air pressure. Prior to 1990, specific, detailed instructions were | | not provided for these actions, and thus it is assumed that actions to | | provide a bottled air supply may not have been implemented. If air pressure | | to the pneumatic control system had been lost on either diesel during | | emergency operation, the diesel would have tripped, and restart capability | | would not have been available. While loss of both diesel generators due to | | this condition is unlikely, this condition has been determined to represent | | a condition that alone could have prevented the fulfillment of a safety | | function and is reportable under 10 CFR 50.72(b)(2)(iii). | | | | "In June 1998, a condition related to the air supply for the pneumatic | | control system was identified and reported voluntarily to the NRC in LER | | 98-003 (dated July 24, 1998). The condition was determined to be not | | reportable at that time based on the procedural actions that had been in | | place since 1990 In addition, actions were taken after identification of | | the condition in June 1998 to provide additional assurance of the | | availability of air to the pneumatic control system. LER 98-003 will be | | revised to provide additional information on this condition." | | | | The NRC resident inspector has been informed of this event by the licensee. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34739 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 09/04/98 | |UNIT: [ ] [ ] [3] STATE: CT |NOTIFICATION TIME: 15:59 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 09/04/98 | +------------------------------------------------+EVENT TIME: 15:45[EDT]| |NRC NOTIFIED BY: ROBERT SMITH |LAST UPDATE DATE: 09/04/98 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DAVID LEW RDO | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | | | | | 3 | N Y 100 POWER OPERATION | 100 POWER OPERATION | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | The licensee notified the State of Connecticut regarding a smaller than | | reported discharge from the plant. | | | | "The make up waste neutralization sump discharge (discharge serial number | | 001C-4) at Unit 3 is regulated under the station NPDES permit. Data | | reported to Environmental Services for the monthly discharge monitoring | | report indicated that the sump was discharged on July 24, 1998. The | | discharge volume reported to the Connecticut Department of Environmental | | Protection (DEP) was 33,000 gallons in accordance with information provided | | for the report. It was later discovered that the actual volume discharged | | on July 24, 1998 was approximately 25,000 gallons. In accordance with | | Section 22a-430-3(j)(9)(C) of the Regulations of Connecticut State | | Agencies, if data submitted for a permit is found to be erroneous, he or | | she must report it to the DEP Commissioner verbally within 72 hours." | | | | The NRC resident inspector will be informed by the licensee. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34740 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FERMI REGION: 3 |NOTIFICATION DATE: 09/04/98 | |UNIT: [2] [ ] [ ] STATE: MI |NOTIFICATION TIME: 21:38 [ET]| |RX TYPE: [2] GE-4 |EVENT DATE: 09/04/98 | +------------------------------------------------+EVENT TIME: 18:27[EDT]| |NRC NOTIFIED BY: DAVID COSEO |LAST UPDATE DATE: 09/04/98 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |ROGER LANKSBURY RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 2 | M/R Y 70 POWER OPERATION | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | Manual reactor scram due to reactor pressure and power perturbations during | | unit shutdown. | | | | While shutting down the reactor to enter the sixth refueling outage, | | operators manually scrammed the reactor after observing reactor power | | perturbations of approximately 12 to 15% peak to peak. At the time of the | | event, reactor power and total core flow were at 70% of rated. All control | | rods inserted completely, and all systems functioned as expected. No | | safety/relief valves lifted, and no ECCS systems initiated. Containment | | isolation valve groups 4, 13 and 15 closed when reactor vessel water level | | reached the Level 3 setpoint; but have since been reset. Reactor vessel | | water level has been restored to its normal operating band. | | | | The licensee also reported observing perturbations on the turbine control | | valve summation recorder, and the moisture separator reheater flow | | recorders. The licensee is investigating this event, but stated that it | | appeared to be similar to an event that occurred in 7/98 (see EN #34540). | | The acting NRC resident inspector has been informed of this event by the | | licensee. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34741 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BRUNSWICK REGION: 2 |NOTIFICATION DATE: 09/05/98 | |UNIT: [1] [ ] [ ] STATE: NC |NOTIFICATION TIME: 17:55 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 09/05/98 | +------------------------------------------------+EVENT TIME: 15:53[EDT]| |NRC NOTIFIED BY: BILL WOODBURY |LAST UPDATE DATE: 09/05/98 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PIERCE SKINNER RDO | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | High Pressure Coolant Injection (HPCI) Declared Inoperable | | | | On 09/05/98, HPCI system was declared inoperable due to a through wall leak | | on an instrument line for the system flow measurement orifice. The leak is | | located on a threaded connection and measures approximately 0.25" long. The | | leak was discovered while looking for leaks (leak tightness inspection) | | during quarterly operational surveillance testing of the HPCI system. The | | leak rate is 0.125 gpm when HPCI is operating and 60 drops/min when HPCI is | | not operating. HPCI was declared inoperable and a 14 day Limiting Condition | | of Operation was entered for HPCI per Technical Specification 3.5. All | | other Emergency Core Cooling Systems and RCIC are fully operable if needed. | | | | | | The leak will be repaired and system testing completed prior to restoring | | HPCI system to an operable status. | | | | The NRC Resident Inspector was notified of this event by the Licensee. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34742 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OYSTER CREEK REGION: 1 |NOTIFICATION DATE: 09/05/98 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 20:35 [ET]| |RX TYPE: [1] GE-2 |EVENT DATE: 09/05/98 | +------------------------------------------------+EVENT TIME: 19:45[EDT]| |NRC NOTIFIED BY: J. FREEMAN |LAST UPDATE DATE: 09/05/98 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DAVID LEW RDO | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 99 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | Technical Specification Shutdown entered due to "B" Isolation Condenser | | being isolated and declared inoperable. | | | | At 2030 EDT a plant shutdown was initiated due to the "B" Isolation | | Condenser being declared inoperable. The "B" Isolation Condenser has | | indication of a tube leak and it has been isolated. The Isolation Condenser | | will not be repaired prior to the 7 day Limiting Condition of Operation | | (Technical Specification 3.8). Therefore Oyster Creek is required to be in | | Cold Shutdown within the next 30 hours. There was no release and the "B" | | Isolation Condenser tube bundle will be replaced. All other Emergency Core | | Cooling Systems and the Emergency Diesel Generators are fully operable if | | needed. | | | | The NRC Resident Inspector was be notified of this event by the Licensee. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 34743 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 09/06/98 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 17:01 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 09/06/98 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 08:50[EDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 09/06/98 | | CITY: PIKETON REGION: 3 +-----------------------------+ | COUNTY: PIKE STATE: OH |PERSON ORGANIZATION| |LICENSE#: GDP-2 AGREEMENT: N |ROGER LANKSBURY RDO | | DOCKET: 0707002 |MICHAEL WEBER EO | +------------------------------------------------+ | |NRC NOTIFIED BY: STEVE MAY | | |HQ OPS OFFICER: LEIGH TROCINE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NCFR NON CFR REPORT REQMNT | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | SMOKE DETECTOR ACTUATION DUE TO A VERY SMALL UF6 RELEASE (24-HOUR REPORT) | | | | THE FOLLOWING TEXT IS A PORTION OF A FACSIMILE RECEIVED FROM PORTSMOUTH: | | | | "ON SEPTEMBER 6, 1998, AT 0850 HOURS, OPERATIONS PERSONNEL DISCOVERED THAT | | A TECHNICAL SAFETY REQUIREMENT SAFETY SYSTEM (UF6 SMOKE DETECTOR) HAD | | ACTUATED DUE TO A UF6 RELEASE. THE ACTUATION OCCURRED IN THE X-333 PROCESS | | BUILDING ON CELL 33-3-3, STAGE 1. THE CELL WAS TAKEN OFF STREAM AND SHUT | | DOWN. | | | | "THERE WAS NO LOSS OF HAZARDOUS/RADIOACTIVE MATERIAL [AND THERE WERE NO] | | RADIOACTIVE/RADIOLOGICAL CONTAMINATION EXPOSURE[S] AS A RESULT OF THIS | | EVENT." | | | | THE UF6 RELEASE WAS REPORTED TO BE THE RESULT OF A VERY SMALL UF6 LEAK FROM | | A COMPRESSOR MOTOR SHAFT ON CELL 33-3-3, STAGE 1, WHICH OPERATES AT GREATER | | THAN ATMOSPHERIC PRESSURE IN THAT AREA. A SITE EMERGENCY TEAM RESPONDED TO | | THE INCIDENT. IT WAS REPORTED THAT THERE WAS NO WIPE CONTAMINATION ON THE | | FLOOR OR IN THE VICINITY OF THE LEAK, AND ALL SAMPLING IN THE AREA WAS | | REPORTED TO BE LESS THAN DETECTABLE. THERE WERE NO SYSTEM ACTUATIONS OTHER | | THAN ANNUNCIATION OF THE SMOKE DETECTOR, AND IT WAS REPORTED THAT ALL | | SAFETY SYSTEMS FUNCTIONED AS REQUIRED. IN ADDITION, THERE WERE NO PERSONNEL | | INJURIES OR EXPOSURES AS A RESULT OF THIS EVENT. | | | | PORTSMOUTH PERSONNEL NOTIFIED THE NRC RESIDENT INSPECTOR AND THE DEPARTMENT | | OF ENERGY SITE REPRESENTATIVE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34744 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CATAWBA REGION: 2 |NOTIFICATION DATE: 09/06/98 | |UNIT: [ ] [2] [ ] STATE: SC |NOTIFICATION TIME: 17:47 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 09/06/98 | +------------------------------------------------+EVENT TIME: 14:05[EDT]| |NRC NOTIFIED BY: JEFFERY BRADLEY |LAST UPDATE DATE: 09/06/98 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PIERCE SKINNER RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | LOSS OF POWER TO 4160 VOLT 'B' TRAIN ESSENTIAL BUS '2ETB,' AUTOMATIC START | | OF AUXILIARY FEEDWATER PUMP '2B,' OPERATION OF TRAIN 'A' CONTROL ROOM AREA | | VENTILATION, AND LIFTING OF A POWER OPERATED RELIEF VALVE DUE TO PERSONNEL | | ERROR | | | | THE FOLLOWING TEXT IS A PORTION OF A FACSIMILE RECEIVED FROM THE LICENSEE: | | | | "ON SEPTEMBER 6, 1998, AT 1405 HOURS, CATAWBA UNIT 2 WAS IN MODE 5 AT THE | | START OF AN END-OF-CYCLE REFUELING OUTAGE. PLANT PERSONNEL WERE IN THE | | PROCESS OF REMOVING THE '2B' EMERGENCY DIESEL GENERATOR (EDG) FROM SERVICE | | IN ORDER TO PERFORM OUTAGE RELATED MAINTENANCE. THE '2B' EDG HAD ALREADY | | BEEN PLACED IN THE MAINTENANCE MODE. AS PERSONNEL WERE DISCONNECTING | | POTENTIAL TRANSFORMERS (PT) IN THE EDG BREAKER CUBICLE IN THE TRAIN 'B' | | ESSENTIAL SWITCHGEAR ('2ETB'), THEY OPENED THE WRONG PT DRAWER. THIS CAUSED | | A BLACKOUT ON '2ETB.' | | | | "[AT THE TIME OF THE EVENT,] THE PLANT WAS PREPARING TO GO WATER SOLID IN | | THE PRESSURIZER IN PREPARATION FOR A CRUD BURST. AS A RESULT, THERE WAS | | LIMITED STEAM SPACE AVAILABLE IN THE PRESSURIZER TO ACCOMMODATE EXPANSION | | OF THE REACTOR COOLANT SYSTEM (RCS). | | | | "UPON LOSS OF POWER TO '2ETB,' VALVE '2NV-294,' THE CENTRIFUGAL CHARGING | | PUMP DISCHARGE CONTROL VALVE, WENT FULLY OPEN, WHICH RESULTED IN MAXIMUM | | CHARGING FLOW TO THE RCS. THE INCREASE IN CHARGING FLOW RESULTED IN THE | | LIFTING OF PRESSURIZER POWER OPERATED RELIEF VALVES (PORV) '2NC-32B.' IT IS | | ESTIMATED THAT THE PORVs LIFTED 12 TO 14 TIMES. | | | | "THE FOLLOWING ENGINEERED SAFETY FEATURES (ESF) ACTUATIONS OCCURRED: | | | | 1. [AN] UNDERVOLTAGE CONDITION [OCCURRED] ON ESSENTIAL SWITCHGEAR '2ETB' | | ([THE] '2B' [EDG] DID NOT START SINCE IT WAS IN MAINTENANCE MODE.) | | | | 2 THE TRAIN 'B' MOTOR DRIVEN AUXILIARY FEEDWATER PUMP AUTOMATICALLY | | STARTED. | | | | 3. TRAIN 'A' OF THE CONTROL ROOM VENTILATION SYSTEM AUTOMATICALLY | | STARTED [THE IDLE PRESSURE FILTER TRAIN]." | | | | WHEN RCS PRESSURE REACHED THE LTOP (LOW TEMPERATURE OVERPRESSURE | | PROTECTION) SETPOINT OF 400 POUNDS, THE PORVs BEGAN TO CYCLE AND RELIEVED | | TO THE PRESSURIZER RELIEF TANK (PRT). ALL OF THE DISCHARGE WAS CONTAINED IN | | THE PRT, AND THE PRT RUPTURE DISCS REMAINED INTACT. IT WAS REPORTED THAT IT | | APPEARED THAT ONLY ONE PORV MAY HAVE LIFTED AND THAT IT RESEATED PROPERLY. | | THE LICENSEE'S ENGINEERING STAFF IS CONTINUING TO RESEARCH THE DATA. | | | | THERE WAS FUEL IN THE CORE AT THE TIME OF THIS EVENT, AND THE 'A' RESIDUAL | | HEAT REMOVAL PUMP WAS RUNNING AND PROVIDING COOLING. HOWEVER, ONE OF THREE | | COMPONENT COOLING WATER PUMP WAS LOST WHEN POWER WAS LOST ON UNIT 2 TRAIN | | 'B' ESSENTIAL BUS '2B.' | | | | THE LICENSEE REPORTED THAT ALL SYSTEMS FUNCTIONED AS REQUIRED. THE | | ESSENTIAL POWER SPECIFICATIONS WERE MET, AND THE UNIT IS NOT CURRENTLY IN | | ANY LIMITING CONDITIONS FOR OPERATION AS A RESULT OF THIS EVENT. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR, AND THE NRC RESIDENT | | INSPECTOR IS CURRENTLY ON SITE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34745 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BRAIDWOOD REGION: 3 |NOTIFICATION DATE: 09/06/98 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 22:57 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 09/06/98 | +------------------------------------------------+EVENT TIME: 21:07[CDT]| |NRC NOTIFIED BY: LARRY BROOKS |LAST UPDATE DATE: 09/06/98 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: UNUSUAL EVENT +-----------------------------+ |10 CFR SECTION: |ROGER LANKSBURY RDO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |WILLIAM BATEMAN EO | |AARC 50.72(b)(1)(v) OTHER ASMT/COMM INOP |BERNICE CARR FEMA | |AESF 50.72(b)(2)(ii) ESF ACTUATION |ROSEMARY HOGAN IRD | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | UNUSUAL EVENT DECLARED DUE TO A LOSS OF UNIT 1 OFFSITE POWER WHICH RESULTED | | FROM A LIGHTNING STRIKE | | | | A LIGHTNING STRIKE OCCURRED ON SITE AT 2107 CDT ON 9/6/98 WHILE UNIT 1 WAS | | IN COLD SHUTDOWN AS PART OF A REFUELING OUTAGE. THE LIGHTNING STRIKE CAUSED | | A LOSS OF OFFSITE POWER TO UNIT 1 DUE TO THE LOSS OF THE UNIT SYSTEM | | AUXILIARY TRANSFORMERS. SMOKE AND CHARRING WERE OBSERVED, BUT THERE WAS NO | | FIRE. IT IS CURRENTLY BELIEVED THAT LIGHTNING MAY HAVE STRUCK A CRANE | | OUTSIDE CONTAINMENT LOCATED IN CLOSE PROXIMITY TO THE SYSTEM AUXILIARY | | TRANSFORMERS. BOTH UNIT 1 EMERGENCY DIESEL GENERATORS STARTED AND HAVE | | PICKED UP THE EMERGENCY SAFEGUARD FEATURES BUSES. SHUTDOWN COOLING WAS NOT | | LOST. THE LICENSEE DECLARED AN UNUSUAL EVENT AT 2115 CDT. | | | | THE LICENSEE IS CURRENTLY INVESTIGATING THIS EVENT AND IS LOOKING FOR | | DAMAGE IN THE SWITCHYARD. THE LICENSEE PLANS TO KEEP THE UNIT IN MODE 5 AND | | TO PLACE THE UNIT IN MODE 6 WHEN CORRECTIVE ACTIONS ARE COMPLETED. THE | | LICENSEE MAY EXIT THE UNUSUAL EVENT WHEN THE SYSTEM AUXILIARY TRANSFORMERS | | ARE RESTORED. | | | | THERE WAS ONE PERSONNEL INJURY ASSOCIATED WITH THIS EVENT. A | | NONCONTAMINATED INDIVIDUAL RECEIVED AN ELECTRIC SHOCK DUE TO THE LIGHTNING | | STRIKE AND WAS TRANSPORTED OFFSITE TO A LOCAL HOSPITAL VIA AMBULANCE. IT | | WAS REPORTED THAT THE INDIVIDUAL APPEARED TO BE OKAY BUT WAS TRANSPORTED TO | | THE HOSPITAL BECAUSE THE INJURY INVOLVED ELECTRICAL SHOCK. | | | | UNIT 2 WAS UNAFFECTED AND REMAINS OPERATING AT 100% POWER. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR AND APPLICABLE STATE AND | | LOCAL AGENCIES. | | | | * * * UPDATE AT 0024 ON 9/7/98 BY TOM PETELLE TO JOLLIFFE * * * | | | | THE ABOVE LOSS OF OFFSITE POWER CAUSED BY A LIGHTNING STRIKE ON A CRANE | | NEAR THE UNIT 1 CONTAINMENT ALSO CAUSED A LOSS OF POWER TO THE UNIT 1 | | RADIATION MONITOR RM-11. THIS, IN TURN, RESULTED IN THE ESF ACTUATIONS OF | | THE CONTAINMENT VENTILATION, CONTROL ROOM VENTILATION, AUXILIARY BUILDING | | VENTILATION, AND FUEL BUILDING VENTILATION SYSTEMS. | | | | THE LICENSEE ALSO DETERMINED THAT THE LOSS OF METEOROLOGICAL RECORDERS AND | | COMPUTER POINTS MAY BE A LOSS OF EMERGENCY ASSESSMENT. NEARBY STATIONS WERE | | USED AS ALTERNATE MEANS. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | THE NRC OPERATIONS OFFICER NOTIFIED THE R3DO ROGER LANKSBURY. | | | | * * * UPDATE AT 0733 9/7/98 FROM CAL WALRATH TO JOLLIFFE * * * | | | | AT 0555 CDT ON 9/7/98, THE LICENSEE DETERMINED THAT UNIT 1 SUSTAINED NO | | DAMAGE, RESTORED OFFSITE POWER, AND TERMINATED THE UNUSUAL EVENT. | | | | THE LICENSEE NOTIFIED STATE AND LOCAL OFFICIALS AND THE NRC RESIDENT | | INSPECTOR OF THE TERMINATION OF THE UNUSUAL EVENT. | | | | THE NRC OPERATIONS OFFICER NOTIFIED THE R3DO ROGER LANKSBURY, NRR EO BILL | | BATEMAN, AND FEMA GENE CANUPP. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34746 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: NINE MILE POINT REGION: 1 |NOTIFICATION DATE: 09/07/98 | |UNIT: [1] [2] [ ] STATE: NY |NOTIFICATION TIME: 13:40 [ET]| |RX TYPE: [1] GE-2,[2] GE-5 |EVENT DATE: 09/07/98 | +------------------------------------------------+EVENT TIME: 13:00[EDT]| |NRC NOTIFIED BY: FRANK SIENCZAK |LAST UPDATE DATE: 09/07/98 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DAVID LEW RDO | |AARC 50.72(b)(1)(v) OTHER ASMT/COMM INOP | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | NATIONAL WEATHER SERVICE TONE ALERT RADIO SYSTEM INOPERABLE | | | | The National Weather Service tone alert radio system, which is part of the | | prompt notification system, was declared out of service as a result of a | | severe thunderstorm. This system serves a small portion of the population | | within the 10 mile EPZ. All prompt notification system sirens have been | | tested and are available. Additionally, the paging system used to notify | | the Site Emergency Response Organization is out of service due to the same | | thunderstorm. The telephone notification system is available to notify the | | Site Emergency Response Organization. | | | | The NRC resident inspector will be informed of this event by the licensee. | | | | * * * Update 1453 9/7/98 from Sienczak taken by Stransky * * * | | | | At 1410, the Oswego County reception center was declared out of service due | | to storm damage to the New York State Fairgrounds, where the center is | | located. The licensee is working with the county to develop compensatory | | actions. The NRC resident inspector will be informed. Notified R1DO (Lew). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34747 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FITZPATRICK REGION: 1 |NOTIFICATION DATE: 09/07/98 | |UNIT: [1] [ ] [ ] STATE: NY |NOTIFICATION TIME: 13:51 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 09/07/98 | +------------------------------------------------+EVENT TIME: 13:00[EDT]| |NRC NOTIFIED BY: NICK AVRAKOTAS |LAST UPDATE DATE: 09/07/98 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DAVID LEW RDO | |AARC 50.72(b)(1)(v) OTHER ASMT/COMM INOP | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | NATIONAL WEATHER SERVICE TONE ALERT RADIO SYSTEM INOPERABLE | | | | The National Weather Service tone alert radio system, which is part of the | | prompt notification system, was declared out of service as a result of a | | severe thunderstorm. This system serves a small portion of the population | | within the 10 mile EPZ. All prompt notification system sirens have been | | tested and are available. Additionally, the paging system used to notify | | the Site Emergency Response Organization was out of service due to the same | | thunderstorm, but has since been returned to service. The telephone | | notification system is also available to notify the Site Emergency Response | | Organization. | | | | The NRC resident inspector has been informed of this event by the licensee. | | | | * * * Update 1440 9/7/98 from Avrakotos taken by Stransky * * * | | | | At 1410, the Oswego County reception center was declared out of service due | | to storm damage to the New York State Fairgrounds, where the center is | | located. The licensee is working with the county to develop compensatory | | actions. The NRC resident inspector will be informed by the licensee. | | Notified R1DO (Lew). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34748 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: LIMERICK REGION: 1 |NOTIFICATION DATE: 09/07/98 | |UNIT: [1] [2] [ ] STATE: PA |NOTIFICATION TIME: 14:42 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 09/07/98 | +------------------------------------------------+EVENT TIME: 13:50[EDT]| |NRC NOTIFIED BY: REINER |LAST UPDATE DATE: 09/08/98 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DAVID LEW RDO | |AESS 50.72(b)(1)(v) EMERGENCY SIREN INOP | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | EMERGENCY SIRENS OUT OF SERVICE DUE TO SEVERE WEATHER | | | | "Due to a severe storm with high winds that passed through our region, | | power was lost to 58 of 165 emergency county alert sirens. The 58 | | inoperable sirens are divided between three counties as follows: 7 Berks | | County, 31 Montgomery County and 20 Chester County. This event is | | considered a major loss of emergency sirens. | | | | Emergency siren status will be monitored during power restoration and | | repairs will be made as necessary." | | | | The NRC resident inspector will be informed of this event by the licensee. | | | | * * * UPDATE at 0440 on 09/08/98 by Greg Sosson to Jolliffe * * * | | | | As of 0358 on 09/08/98, 11 of 165 emergency county alert sirens remain | | operable. Seven sirens are located in Montgomery County, three in Chester | | County, and one in Berks County. Repairs are being made to the remaining | | inoperable emergency sirens. | | | | The licensee plans to notify the NRC Resident Inspector. | | | | The NRC Operations Officer notified the R1DO Dave Lew. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34749 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: WASHINGTON NUCLEAR REGION: 4 |NOTIFICATION DATE: 09/08/98 | |UNIT: [2] [ ] [ ] STATE: WA |NOTIFICATION TIME: 02:32 [ET]| |RX TYPE: [2] GE-5 |EVENT DATE: 09/07/98 | +------------------------------------------------+EVENT TIME: 19:45[PDT]| |NRC NOTIFIED BY: MIKE KELLER |LAST UPDATE DATE: 09/08/98 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |IAN BARNES RDO | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | CONTROL ROOM EMERGENCY FILTRATION SYSTEMS INOPERABLE DUE TO A FAILED DAMPER | | | | AT 1945 PDT, DURING A ROUTINE PERFORMANCE OF THE CONTROL ROOM EMERGENCY | | FILTRATION SYSTEM 'B' OPERABILITY TEST, A CONTROL ROOM VENTILATION DAMPER | | FAILED TO AUTOMATICALLY CLOSE AS REQUIRED WHEN THE CONTROL ROOM EMERGENCY | | FILTRATION FAN 'B' WAS STARTED. THIS FAILURE OF THE DAMPER TO CLOSE | | RESULTED IN A BREACH TO THE CONTROL ROOM ENVELOPE AND INOPERABILITY OF | | BOTH CONTROL ROOM EMERGENCY FILTRATION SYSTEMS. | | | | AT 2006 PDT, THE LICENSEE CLOSED THE DAMPER, RESTORED THE CONTROL ROOM | | ENVELOPE, AND DECLARED THE CONTROL ROOM EMERGENCY FILTRATION SYSTEM | | OPERABLE. | | | | THE LICENSEE PLANS TO DETERMINE THE CAUSE OF THE FAILURE OF THE DAMPER | | TO CLOSE. | | | | THE LICENSEE PLANS TO INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+