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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 THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!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. |
+------------------------------------------------------------------------------+