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Event Notification Report for April 29, 2003
U.S. Nuclear Regulatory Commission Operations Center Event Reports For 04/28/2003 - 04/29/2003 ** EVENT NUMBERS ** 39659 39795 39801 39802 39803 39804 39805 39806 39807 39808 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 39659 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: COOPER REGION: 4 |NOTIFICATION DATE: 03/11/2003| | UNIT: [1] [] [] STATE: NE |NOTIFICATION TIME: 05:23[EST]| | RXTYPE: [1] GE-4 |EVENT DATE: 03/10/2003| +------------------------------------------------+EVENT TIME: 22:38[CST]| | NRC NOTIFIED BY: ANDREW OHRABLO |LAST UPDATE DATE: 04/28/2003| | HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: NON EMERGENCY |MARK SHAFFER R4 | |10 CFR SECTION: | | |AIND 50.72(b)(3)(v)(D) ACCIDENT MITIGATION | | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ |1 N N 0 Refueling |0 Refueling | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | POTENTIAL RAD GROUND RELEASE PATH DISCOVERED DUE TO LOSS OF SECONDARY | | CONTAINMENT | | | | "This notification is being made pursuant to NRC regulation | | 10CFR50.72(b)(3)(v)(D), any event or condition that at the time of discovery | | could have prevented the fulfillment of the safety function of structures or | | systems that are needed to mitigate the consequences of an accident. | | | | "On March 10, 2003 at 22:38, it was determined that the secondary | | containment was inoperable due to a leak in the Z sump manway gasket. The | | plant was in Mode 5, shutdown, performing fuel shuffle when secondary | | containment was declared inoperable. LCO 3.6.4.1 was entered. The fuel | | shuffle was secured at 22:40 after the completion of the fuel move that was | | in progress. No additional Core Alterations or OPDRVs [Operations | | Potentially Draining the Reactor Vessel] were in progress. Upon | | investigation into the secondary containment operability, it was determined | | that a non-Tech Spec surveillance performed on dayshift also rendered | | secondary containment inoperable due to additional leakage pathway via the Z | | sump. A principal safety function of Secondary Containment is to limit the | | ground level release to the environs of airborne radioactive materials | | resulting from a fuel handling accident. | | | | "As a result of the alignment of the Z sump the potential existed that if a | | radioactive release were to occur due to a fuel handling accident, part of | | the filtered release via Standby Gas Treatment System could be a ground | | level release vice a release through the Elevated Release Point. The | | surveillance has been completed and the additional leakage paths that were | | opened due to the surveillance have been sealed. The leaking manway gasket | | was determined to be due to not adequately torquing the gasket bolts. The | | bolts have been retorqued. Secondary containment was reestablished, and was | | declared OPERABLE at 02:55, 3-11-03. | | | | "The NRC Senior Resident has been notified." | | | | * * * RETRACTION TAKEN ON 04/28/03 AT 1123 EDT FROM JIM SUMPTER TO GERRY | | WAIG * * * | | | | "THIS IS A RETRACTION OF EVENT #39659. | | | | "On 3/10/2003 at 2238 CST, Cooper Nuclear Station made an 8 hour 50.72 | | non-emergency notification to the NRC per 50.72 (b)(3)(v)(D). It was | | determined that the secondary containment was inoperable due to a leak in | | the Z sump manway gasket. The plant was performing fuel shuffle at the | | time. LCO 3.6.4.1 was entered. The fuel shuffle was secured at 22:40 after | | completion of the fuel move that was in progress. Investigation determined | | that a non-Tech Spec surveillance performed on dayshift also rendered | | secondary containment inoperable due to an additional leakage pathway via | | the Z sump. As a result of the alignment of the Z sump, the potential | | existed that if a radioactive release were to occur due to a filet handling | | accident, part of the filtered release via the Standby Gas Treatment System | | could be a ground level release. This would potentially result in | | unacceptable dose levels since DBA calculations assulne an elevated release | | point for this accident. Thus, the secondary containment would be unable to | | fulfill its accident mitigation safety function to limit the release to the | | environs of radioactive materials from postulated design basis accidents | | (DBA) to control room occupants and off-site. | | | | "Further evaluation demonstrated that if a fuel handing accident had | | occurred at the time of discovery of the condition, the thyroid doses to | | control room personnel (which are the limiting doses for this accident) | | would have been less than DBA values. Other doses would remain a small | | fraction of 10CFR100 and General Design Criteria 19 limits. This is because | | the plant had been shutdown for 14 days reducing considerably the fuel | | handling accident source term. In addition, the estimated ground level | | release flow rate was a small percentage of the elevated release point flow | | rate. Finally, most of the radiation dose from this accident occurs in the | | first 90 seconds of the event via the unfiltered Reactor Building exhaust. | | Therefore, the secondary containment, which includes the Standby Gas | | Treatment system and the elevated release point, would have performed its | | accident mitigation safety function and was operable." | | | | The licensee will notifiy the NRC Resident Inspector | | | | NRC R4DO (Greg Pick) was notified. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |General Information or Other |Event Number: 39795 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | REP ORG: OHIO BUREAU OF RADIATION PROTECTION |NOTIFICATION DATE: 04/24/2003| |LICENSEE: REPUBLIC ENGINEERED PRODUCTS LLC |NOTIFICATION TIME: 15:59[EDT]| | CITY: LORAIN REGION: 3 |EVENT DATE: 04/03/2003| | COUNTY: STATE: OH |EVENT TIME: [EDT]| |LICENSE#: OH31201480007 AGREEMENT: Y |LAST UPDATE DATE: 04/24/2003| | DOCKET: |+----------------------------+ | |PERSON ORGANIZATION | | |MONTE PHILLIPS R3 | | |TOM ESSIG NMSS | +------------------------------------------------+ | | NRC NOTIFIED BY: SNEE | | | HQ OPS OFFICER: CHAUNCEY GOULD | | +------------------------------------------------+ | |EMERGENCY CLASS: NON EMERGENCY | | |10 CFR SECTION: | | |NAGR AGREEMENT STATE | | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | REPORT OF EXPOSURE OF LICENSEE EMPLOYEES WAS MADE TO THE STATE | | | | The licensee reported the exposure of licensee employees to radiation from a | | TN Technologies model 5174 (serial # B103) fixed gauge containing a 2 curie | | Cs-137 sealed source. The gauge fell approximately 6 feet from its location | | on a coke hopper on approximately 04/03/03. The welds which attached the | | gauge anchoring bolts appear to have failed. The gauge had been in place | | since 1992. The gauge fell with the shutter open onto the first landing of | | the skip pit area. The gauge went un-noticed for a week until April 11 @ | | 1300 when maintenance workers were called to move what was thought to be a | | motor (all labels and markings on the gauge were unreadable). The workers | | spent approximately 1.5 hours rigging and moving the gauge before an | | individual recognized the gauge and secured the area. A contractor, | | Radiometrics, was then called in to secure the gauge. The Ohio department | | of Health was called concerning the incident on April 17 @1400. An on-site | | investigation was done and a dose assessment of affected personnel is in | | progress. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Hospital |Event Number: 39801 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | REP ORG: HOSPITAL OF ST. RAPHAEL |NOTIFICATION DATE: 04/28/2003| |LICENSEE: HOSPITAL OF ST. RAPHAEL |NOTIFICATION TIME: 11:37[EDT]| | CITY: NEW HAVEN REGION: 1 |EVENT DATE: 04/28/2003| | COUNTY: STATE: CT |EVENT TIME: [EDT]| |LICENSE#: 0600200-03 AGREEMENT: N |LAST UPDATE DATE: 04/28/2003| | DOCKET: |+----------------------------+ | |PERSON ORGANIZATION | | |TODD JACKSON R1 | | |FRED BROWN NMSS | +------------------------------------------------+ | | NRC NOTIFIED BY: CHARLES GIGNAC | | | HQ OPS OFFICER: HOWIE CROUCH | | +------------------------------------------------+ | |EMERGENCY CLASS: NON EMERGENCY | | |10 CFR SECTION: | | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | PROVISIONAL REPORT OF MEDICAL MISADMINISTRATION | | | | On 4/22/03, Nuclear Medical Technicians at St. Raphael Hospital received 2 | | vials ( 75 millicurie each) of I-131 that was to be administered to a | | patient later that afternoon. The vials were placed in their normal storage | | location. When the patient arrived, a nuclear technician administered only | | one vial of the I-131 which only gave the patient half of the prescribed | | dose. On 4/23/03, while preparing nuclear medicine for a different patient, | | a technician discovered the second vial of I-131 that was to be administered | | to the patient from the previous day. Upon discovery, the patient and the | | prescribing physician was notified of the error. The physician determined | | that the 27 hour span between doses would have no deleterious effects on the | | patient so the second dose was administered in the afternoon of 4/23/03. | | The intended dosage was 150 millicuries and the received dose was 142.4 | | millicuries. The RSO was notified at 0800 hrs. EDT on 4/24/03 and contacted | | NRC Inspector Richard McKinley who advised the licensee to make this | | notification. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Other Nuclear Material |Event Number: 39802 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | REP ORG: DELTA CONSULTING ENGINEER |NOTIFICATION DATE: 04/28/2003| |LICENSEE: DELTA CONSULTING ENGINEER |NOTIFICATION TIME: 12:03[EDT]| | CITY: GUAYNABO REGION: 2 |EVENT DATE: 04/28/2003| | COUNTY: STATE: PR |EVENT TIME: 10:00[EDT]| |LICENSE#: 522541501 AGREEMENT: N |LAST UPDATE DATE: 04/28/2003| | DOCKET: |+----------------------------+ | |PERSON ORGANIZATION | | |MIKE ERNSTES R2 | | |FRED BROWN NMSS | +------------------------------------------------+ | | NRC NOTIFIED BY: SOUSA | | | HQ OPS OFFICER: CHAUNCEY GOULD | | +------------------------------------------------+ | |EMERGENCY CLASS: NON EMERGENCY | | |10 CFR SECTION: | | |BLO2 20.2201(a)(1)(ii) LOST/STOLEN LNM>10X | | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | STOLEN TROXLER GAUGE | | | | Licensee reported that a Troxler Gauge Model 3430 serial number #029673 | | containing approximately 90 millicuries of Cs-137 and 44 millicuries of | | Am-241 was stolen from a construction site trailer in Guaynabo, PR. sometime | | between the evening of 4/25/03 and 10:00 on 4/28/03. The licensee has | | notified the local law enforcement. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 39803 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: VERMONT YANKEE REGION: 1 |NOTIFICATION DATE: 04/28/2003| | UNIT: [1] [] [] STATE: VT |NOTIFICATION TIME: 14:25[EDT]| | RXTYPE: [1] GE-4 |EVENT DATE: 04/28/2003| +------------------------------------------------+EVENT TIME: 09:00[EDT]| | NRC NOTIFIED BY: MARCUSSEN |LAST UPDATE DATE: 04/28/2003| | HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: NON EMERGENCY |TODD JACKSON R1 | |10 CFR SECTION: | | |HFIT 26.73 FITNESS FOR DUTY | | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | FAILURE TO TAKE FITNESS FOR DUTY TEST | | | | A contract supervisor refused to take a required fitness for duty test this | | morning. This action resulted in him being permanently denied access. His | | work history was reviewed and no discrepancy was found. The individual has | | turned in his resignation. | | | | The NRC Resident inspector will be informed. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 39804 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 04/28/2003| | UNIT: [2] [] [] STATE: NY |NOTIFICATION TIME: 19:27[EDT]| | RXTYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 04/28/2003| +------------------------------------------------+EVENT TIME: 16:45[EDT]| | NRC NOTIFIED BY: GRIFFITH |LAST UPDATE DATE: 04/28/2003| | HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: NON EMERGENCY |TODD JACKSON R1 | |10 CFR SECTION: |JAMES LYONS NRR | |ARPS 50.72(b)(2)(iv)(B) RPS ACTUATION - CRITICA| | |AESF 50.72(b)(3)(iv)(A) VALID SPECIF SYS ACTUAT| | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | REACTOR TRIP FROM 100% POWER DUE TO A TURBINE TRIP | | | | The licensee reported they had a turbine trip possibly due to the loss of | | output breakers which resulted in turbine overspeed causing the trip. The | | reactor trip from 100% was caused by the turbine trip. All rods fully | | inserted and there was no ECCS actuation, however one PORV lifted and | | reseated. All three emergency diesel generators auto started and loaded. | | The 4 reactor coolant pumps lost power, so the reactor was in natural | | circulation from 1645 to 1823 when they restored one coolant pump. The | | plant had lost power restored at 1904. They also had their aux. feedwater | | to auto start as expected due to a low steam generator level. The plant is | | currently stable and they are investigating the cause of the turbine trip. | | | | The NRC Resident Inspector was notified along with the New York Public | | Service Commission | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 39805 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: TURKEY POINT REGION: 2 |NOTIFICATION DATE: 04/28/2003| | UNIT: [3] [] [] STATE: FL |NOTIFICATION TIME: 19:57[EDT]| | RXTYPE: [3] W-3-LP,[4] W-3-LP |EVENT DATE: 04/28/2003| +------------------------------------------------+EVENT TIME: 18:35[EDT]| | NRC NOTIFIED BY: EDDINGER |LAST UPDATE DATE: 04/28/2003| | HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: NON EMERGENCY |MIKE ERNSTES R2 | |10 CFR SECTION: | | |ASHU 50.72(b)(2)(i) PLANT S/D REQD BY TS | | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ |3 N Y 100 Power Operation |0 Hot Standby | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | REDUCED REACTOR POWER FROM 100% TO HOT STANDBY DUE TO INOPERABLE ISOLATION | | VALVE | | | | Unit 3 commenced a load reduction at 1835 to comply with T.S. 3.6.4, | | Containment Isolation Valve. The letdown isolation valve CV-3-200B was | | declared inoperable at 1600 due to indications there may be through valve | | leakage. Letdown is still currently in service. The intent is to isolate | | the letdown penetration once the unit is in mode 3, and affect | | troubleshooting and repairs. | | | | The NRC Resident Inspector will be notified. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |General Information or Other |Event Number: 39806 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | REP ORG: GE NUCLEAR ENERGY |NOTIFICATION DATE: 04/28/2003| |LICENSEE: GE NUCLEAR ENERGY |NOTIFICATION TIME: 21:37[EDT]| | CITY: SAN JOSE REGION: 4 |EVENT DATE: 04/28/2003| | COUNTY: STATE: CA |EVENT TIME: [PDT]| |LICENSE#: AGREEMENT: Y |LAST UPDATE DATE: 04/28/2003| | DOCKET: |+----------------------------+ | |PERSON ORGANIZATION | | |GREG PICK R4 | | |RONALD GARDNER R3 | +------------------------------------------------+TODD JACKSON R1 | | NRC NOTIFIED BY: JASON POST |JACK FOSTER NRR | | HQ OPS OFFICER: CHAUNCEY GOULD | | +------------------------------------------------+ | |EMERGENCY CLASS: NON EMERGENCY | | |10 CFR SECTION: | | |CCCC 21.21 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | INTERIM SURVEILLANCE PROGRAM FOR FUEL CHANNEL BOW MONITORING (PART 21) | | | | The control rod-fuel channel interference evaluation has been completed. It | | determined that BWR/6 and BWR/4 & 5 C-lattice plants with GNF thick/thin | | channels potentially have increased channel bow that can impact fuel bundle | | lift, loads on reactor internals, and control rod operability. An interim | | surveillance program has been developed to augment the surveillance | | requirements in the plant Technical Specifications until other actions, | | which mitigate or limit the potential for control rod-channel interference | | due to channel bow can be identified and implemented. The recommendations | | address the extent and frequency of surveillance actions, and the plants to | | which they should be applied. This surveillance program provides early | | indication of potentially degraded operational performance and assurance | | that action is taken before reaching excessive levels of control rod | | friction. This surveillance plan is limited to BWR/6 and BWR/4 &5 C-lattice | | plants with GNF thick/thin channels and GE control rods. There have been no | | indications of operational or scram problems on BWR/2, 3 and 4 D-lattice | | plants, and as a result, they are excluded from the interim surveillance | | program. | | | | Plants Recommended for Surveillance Program | | | | Clinton Hope Creek | | Nine Mile Point 2 | | Fermi 2 | | Grand Gulf | | River Bend | | LaSalle 1 | | LaSalle 2 | | Limerick 1 | | Limerick 2 | | Perry 1 | | Susquehanna 1 | | Susquehanna 2 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 39807 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 04/29/2003| | UNIT: [] [3] [] STATE: NY |NOTIFICATION TIME: 04:52[EDT]| | RXTYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 04/29/2003| +------------------------------------------------+EVENT TIME: [EDT]| | NRC NOTIFIED BY: CARL SMYERS /JOHN BRAKHIA |LAST UPDATE DATE: 04/29/2003| | HQ OPS OFFICER: HOWIE CROUCH +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: UNUSUAL EVENT |TODD JACKSON R1 | |10 CFR SECTION: |JAMES LYONS NRR | |AAEC 50.72(a) (1) (i) EMERGENCY DECLARED |MICHELE EVANS IRO | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | |3 M/R Y 60 Power Operation |0 Hot Standby | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNUSUAL EVENT DECLARED DUE TO FIRE IN THE TURBINE | | | | The following information was obtained from the licensee via facsimile: | | | | "Class B fire south end of Main High Pressure Turbine located 53 foot | | elevation of turbine building. Reactor and turbine were manually tripped. | | Fire brigade was dispatched. Fire was out in 47 minutes. There were no ESF | | actuations or other anomalies during trip with one exception - letdown | | isolated on low pressurizer [level] and was subsequently restore[d]. No | | injuries." | | | | The NRC Resident Inspector was notified by the licensee. | | | | * * * UPDATE ON 4/29/03 @ 0527 EDT FROM MIKE DONEGAN TO HOWIE CROUCH * * * | | | | The licensee has terminated the NOUE on the basis that the fire is out and | | the plant is stable. | | | | Notified R1DO (Jackson), NRR EO (Lyons), DIRO (Evans), DENVER and FEMA | | (Sullivan). | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 39808 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 04/29/2003| | UNIT: [] [3] [] STATE: NY |NOTIFICATION TIME: 06:01[EDT]| | RXTYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 04/29/2003| +------------------------------------------------+EVENT TIME: 03:13[EDT]| | NRC NOTIFIED BY: MIKE DONEGAN |LAST UPDATE DATE: 04/29/2003| | HQ OPS OFFICER: HOWIE CROUCH +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: NON EMERGENCY |TODD JACKSON R1 | |10 CFR SECTION: |JAMES LYONS NRR | |ARPS 50.72(b)(2)(iv)(B) RPS ACTUATION - CRITICA| | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | |3 M Y 60 Power Operation |0 Hot Standby | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | MANUAL REACTOR TRIP DUE TO FIRE IN THE HIGH PRESSURE TURBINE | | | | | | The following information was received from the licensee via facsimile: | | | | "Class B fire south end of turbine resulted in manual trip of the Rx and | | Turbine. The fire was out in 47 minutes. There were no ESF actuations - | | all systems responded as expected except let down isolated on a low | | pressurizer level. Due to the fire being greater than 15 minutes a [Notice | | of Unusual Event] was entered at 0313 [EDT] and exited at 0520 [see event | | notification 39807]. The plant is currently in Mode 3 Hot Standby." | | | | During the reactor trip, all rods inserted. The electrical bus is stable | | and supplying required plant loads. The other unit on the site was already | | shutdown and unaffected by the fire or reactor trip. Core decay heat is | | being removed using the steam dump to condenser system and the auxiliary | | feedwater system. The extent of damage to the turbine is under investigation | | by the licensee. | | | | The NRC Resident Inspector has been notified by the licensee. | +------------------------------------------------------------------------------+