United States Nuclear Regulatory Commission - Protecting People and the Environment
Home > NRC Library > Document Collections > Reports Associated With Events > Event Notification Reports > 2002

Event Notification Report for August 23, 2002

                    
                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           08/22/2002 - 08/23/2002

                              ** EVENT NUMBERS **

39067  39136  39137  39138  39143  39144  39145  

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   39067       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: HOPE CREEK               REGION:  1  |NOTIFICATION DATE: 07/16/2002|
|    UNIT:  [1] [] []                 STATE:  NJ |NOTIFICATION TIME: 18:15[EDT]|
|   RXTYPE: [1] GE-4                             |EVENT DATE:        07/16/2002|
+------------------------------------------------+EVENT TIME:        13:19[EDT]|
| NRC NOTIFIED BY:  DANIEL J. BOYLE              |LAST UPDATE DATE:  08/22/2002|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |JAMES LINVILLE       R1      |
|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          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| TECH SPEC 3.0.3 ENTERED AFTER DECLARING BOTH TRAINS OF CONTROL ROOM          |
| VENTILATION INOPERABLE                                                       |
|                                                                              |
| "On 7/16/02 at 1319 hours, the Hope Creek Generating Station experienced a   |
| trip of the in-service 'B' train of Control Room Ventilation and it's        |
| associated Chiller. The standby 'A' Train attempted to start, but it's       |
| chilled water pump tripped precluding a successful start. This condition     |
| rendered both trains of Control Room Emergency Filtration INOPERABLE. In     |
| accordance with Technical Specifications 3.7.2, both trains were declared    |
| Inoperable and Technical Specification 3.0.3 was entered. At 1400 hours the  |
| 'B' Control Room Ventilation train was successfully restored to service and  |
| Operable status and Technical Specification 3.0.3 was exited. This event is  |
| being reported in accordance with 10CFR50.72(b)(3)(v) because both trains of |
| Control Room Emergency filtration were unavailable for approximately 40      |
| minutes. There was no power reduction associated with this event. No         |
| additional safety related equipment was inoperable at the time of the        |
| event.                                                                       |
|                                                                              |
| "The initiating condition is still under investigation, but is believed to   |
| have been induced as the result of an associated cooling coil fill evolution |
| that caused a low head tank level and potential air induction that resulted  |
| in the trip of the in-service cooling train and subsequently the standby     |
| train. As of the time of this report the 'A' Control Room Emergency          |
| Filtration Train is still inoperable pending completion of fill and vent of  |
| the supporting chilled water system."                                        |
|                                                                              |
| The licensee will inform the Lower Alloways Creek Township and has informed  |
| the NRC Resident Inspector.                                                  |
|                                                                              |
| ***RETRACTION ON 08/22/02 AT 1021 ET BY ERV PARKER TAKEN BY MACKINNON****    |
|                                                                              |
| "Subsequent evaluation determined that if a postulated accident had occurred |
| during the time that both trains of the Control Room Emergency Ventilation   |
| system were INOPERABLE, control room dose would be less than the acceptance  |
| criteria specified in 10CFR50.67 and Regulatory Guide 1.183 and bounded by   |
| our current analysis.  The site boundary doses are not affected.  The dose   |
| impact of the condition as it existed would be bounded by the current        |
| analysis.  Thus, the safety function would have been fulfilled, and the      |
| notification event number 39067 is retracted"  R1DO (Cliff Anderson)         |
| notified.                                                                    |
|                                                                              |
| The NRC Resident Inspector will be notified of this event by the licensee.   |
+------------------------------------------------------------------------------+

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   39136       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: NINE MILE POINT          REGION:  1  |NOTIFICATION DATE: 08/19/2002|
|    UNIT:  [] [2] []                 STATE:  NY |NOTIFICATION TIME: 10:36[EDT]|
|   RXTYPE: [1] GE-2,[2] GE-5                    |EVENT DATE:        08/19/2002|
+------------------------------------------------+EVENT TIME:        02:32[EDT]|
| NRC NOTIFIED BY:  ELI DRAGOMER                 |LAST UPDATE DATE:  08/22/2002|
|  HQ OPS OFFICER:  RICH LAURA                   +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |CLIFFORD ANDERSON    R1      |
|10 CFR SECTION:                                 |                             |
|AINC 50.72(b)(3)(v)(C)   POT UNCNTRL RAD REL    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| REACTOR BUILDING EMERGENCY RECIRCULATION UNIT COOLER ANOMALY IDENTIFIED      |
| DURING ROUTINE SURVEILLANCE TEST                                             |
|                                                                              |
| "On August 19, 2002 at 0232, Reactor Building Emergency Recirculation Unit   |
| Cooler, 2HVR*413A, was declared inoperable due to Reactor Building Emergency |
| Recirculation Unit Cooler Inlet Damper, 2HVR*AOD6A, not reaching its full    |
| open position during testing. Failure of 2HVR*AOD6A to fully open may affect |
| the flow-rate through the Reactor Building Emergency Recirculation Unit      |
| Cooler and may prevent the Standby Gas Treatment System from performing its  |
| Post-LOCA Secondary Containment drawdown function. The manual operating      |
| mechanism was returned to its withdrawn position and 2HVR*AOD6A was verified |
| to be capable of being fully opened. Opposite train components were          |
| inspected to confirm that a similar condition does not exist on Train "B".   |
| This notification is being made as a conservative measure. Evaluation        |
| coritinues into the actual affect on Post-LOCA drawdown function."           |
|                                                                              |
| The NRC Resident Inspector was notified.                                     |
|                                                                              |
| * * * 1410EDT on 8/22/02 from Dave Richardson to S. Sandin * * *             |
|                                                                              |
| The licensee is retracting this report based on the following:               |
|                                                                              |
| "The purpose of this communication is to retract event report number 39136   |
| which was initiated at 1030 hours on 08-19-2002, by Nine Mile Point Unit 2.  |
| This event, reported under 10CFR50.72 (b)(3)(v)(C), involved unplanned       |
| inoperability of a Reactor Building Emergency recirculation unit cooler due  |
| to its inlet damper being found partially overridden shut.                   |
|                                                                              |
| "Evaluation revealed that, when called upon to reposition to its emergency   |
| position, the damper was approximately 97% open. Based on Engineering        |
| analysis, with the damper in this position, there is 'no appreciable         |
| increase in system resistance' that would adversely impact the HVR (reactor  |
| building ventilation) or GTS (standby gas treatment) system flowrates.  As a |
| result, this condition would not have precluded the aforementioned systems   |
| from performing their respective safety functions."                          |
|                                                                              |
| The licensee informed the NRC Resident Inspector.  Notified R1DO(Anderson).  |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   39137       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  WA DIVISION OF RADIATION PROTECTION  |NOTIFICATION DATE: 08/19/2002|
|LICENSEE:  URS CORPORATION                      |NOTIFICATION TIME: 16:33[EDT]|
|    CITY:  CENTRALIA                REGION:  4  |EVENT DATE:        08/19/2002|
|  COUNTY:                            STATE:  WA |EVENT TIME:             [PDT]|
|LICENSE#:  WN-I0172-1            AGREEMENT:  Y  |LAST UPDATE DATE:  08/19/2002|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |WILLIAM JOHNSON      R4      |
|                                                |THOMAS ESSIG         NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  TERRY C. FRAZEE (e-mail)     |                             |
|  HQ OPS OFFICER:  MIKE NORRIS                  |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| AGREEMENT STATE REPORT INVOLVING THEFT OF MOISTURE/DENSITY GAUGE             |
|                                                                              |
| "The licensee reported the theft of a Campbell Pacific Nuclear               |
| moisture/density gauge (model MC-1DRP, serial number MD01005902). The gauge  |
| contained a 1.85 GBq (50 [millicuries]) Am-Be source and a 0.37 GBq (10      |
| [millicuries]) Cs-137 source. An authorized user had been working at a       |
| temporary job site for two weeks. On Sunday, August 18 at 8:00 p.m. the      |
| authorized user parked his pick-up truck in the parking lot of a local motel |
| in Centralia. The gauge was in back under the locked canopy, but visible.    |
| The gauge box was locked but not secured within the bed of the truck. When   |
| the authorized user went out to his truck at 6:00 a.m. on Monday the 19th    |
| the gauge was gone. The back window of the canopy had been forced open.      |
| Nothing else was missing from the truck (not much else of value was in the   |
| truck). The theft was reported to the Centralia police and to the licensee's |
| RSO. The RSO notified the Department."                                       |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   39138       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  ALABAMA RADIATION CONTROL            |NOTIFICATION DATE: 08/19/2002|
|LICENSEE:  UNIVERSITY OF SOUTHERN ALABAMA       |NOTIFICATION TIME: 16:47[EDT]|
|    CITY:  MOBILE                   REGION:  2  |EVENT DATE:        06/28/2002|
|  COUNTY:                            STATE:  AL |EVENT TIME:             [CDT]|
|LICENSE#:  582                   AGREEMENT:  Y  |LAST UPDATE DATE:  08/19/2002|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |MARK LESSER          R2      |
|                                                |THOMAS ESSIG         NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  JIM McNEES (fax)             |                             |
|  HQ OPS OFFICER:  MIKE NORRIS                  |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| AGREEMENT STATE REPORT INVOLVING 2 MEDICAL MISADMINISTRATIONS                |
|                                                                              |
| "Alabama licensee identifies two misadministrations from previous year.      |
|                                                                              |
| "By telephone notification on June 28, 2002 the University of South Alabama  |
| (Alabama Radioactive Material License No. 582) notified the State of Alabama |
| that during their annual Quality Management Program review they identified   |
| two possible misadministrations of Iodine-131 from the previous year.        |
|                                                                              |
| "By letter dated July 8, 2002, and received by the State of Alabama on July  |
| 11, 2002, the University of South Alabama confirmed that a review of the     |
| records revealed that:                                                       |
|                                                                              |
| "A. On April 3,2002, a patient was given 3.9 [millicuries] of iodine-131 for |
| a total body diagnostic scan when 3.0 [millicuries] had been prescribed by   |
| the authorized user. The administered dose exceeded the prescribed dose by   |
| 30%; and                                                                     |
|                                                                              |
| "B. On August 7,2001, a patient was administered 0.702 [millicuries] of      |
| iodine-131 for a whole body diagnostic scan when 0.500 [millicuries] had     |
| been prescribed by the authorized user. The administered dose exceeded the   |
| prescribed dose by 40%.                                                      |
|                                                                              |
| "In both cases the patients attending physician concluded that these doses   |
| had 'no clinical significance to either patient and therefore no untoward    |
| effects.'  He ordered that this not be reported to the patients.             |
|                                                                              |
| "According to the licensee, these events occurred because the nuclear        |
| medicine staff was operating under a window wider than the 20% maximum       |
| deviation allowed in the 420-3-26-.07(2)(m)1.b of the Alabama Rules for      |
| Control of Radiation. The licensee stated that the nuclear medicine          |
| department had been using criteria from an article published in the Journal  |
| of Nuclear Medicine which 'quoted NRC regulations with a greater             |
| tolerance.'                                                                  |
|                                                                              |
| "The licensees corrective action was to notify nuclear medicine staff        |
| members both verbally and in writing of the current Alabama regulations. The |
| State of Alabama considers the licensee's actions to be appropriate and the  |
| matter closed."                                                              |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Hospital                                         |Event Number:   39143       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  VA NATIONAL HEALTH  PHYSICS PRGM     |NOTIFICATION DATE: 08/22/2002|
|LICENSEE:  VA MEDICAL CENTER                    |NOTIFICATION TIME: 12:34[EDT]|
|    CITY:  NORTH PORT               REGION:  1  |EVENT DATE:        08/20/2002|
|  COUNTY:                            STATE:  NY |EVENT TIME:             [EDT]|
|LICENSE#:  31-13511-05           AGREEMENT:  Y  |LAST UPDATE DATE:  08/22/2002|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |CLIFFORD ANDERSON    R1      |
|                                                |FRED BROWN           NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  GARY WILLIAMS                |                             |
|  HQ OPS OFFICER:  FANGIE JONES                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|LADM 35.33               MED MISADMINISTRATION  |                             |
|ISAF 30.50(b)(2)         SAFETY EQUIPMENT FAILUR|                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| REPORT OF POSSIBLE MISADMINISTRATION AND/OR SAFETY EQUIPMENT FAILURE         |
|                                                                              |
| On 8/20/02 a patient was being prepared for treatment in a Co-60 teletherapy |
| unit by two technicians when the beam turned on with no operator action.     |
| The beam was on for about 50 seconds.  The event is being investigated and   |
| the unit has been placed out-of-service.  It is unknown at this time whether |
| the patient was in position or not and received an exposure to the right or  |
| wrong site.  The investigation will determine if there was an actual         |
| misadministration, exposure to the wrong area.  The two technicians'         |
| dosimeters were processed and the results showed no exposure in excess of    |
| limits, actual reading was 20 millirem for both badges.                      |
|                                                                              |
| The licensee will update this report when more information is determined.    |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   39144       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MILLSTONE                REGION:  1  |NOTIFICATION DATE: 08/22/2002|
|    UNIT:  [] [] [3]                 STATE:  CT |NOTIFICATION TIME: 17:06[EDT]|
|   RXTYPE: [1] GE-3,[2] CE,[3] W-4-LP           |EVENT DATE:        08/22/2002|
+------------------------------------------------+EVENT TIME:        16:33[EDT]|
| NRC NOTIFIED BY:  MICHAEL MARTELL              |LAST UPDATE DATE:  08/22/2002|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |CLIFFORD ANDERSON    R1      |
|10 CFR SECTION:                                 |                             |
|AUNA 50.72(b)(3)(ii)(B)  UNANALYZED CONDITION   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|                                                   |                          |
|3     N          Y       95       Power Operation  |95       Power Operation  |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| UNANALYZED CONDITION CONCERNING STEAM GENERATOR ATMOSPHERIC RELIEF VALVE     |
| BYPASS VALVES                                                                |
|                                                                              |
| Historical analysis deficiencies associated with the steam generator         |
| atmospheric dump bypass valves, a condition that during a fire could cause   |
| seriously degrade the safety of the plant.                                   |
|                                                                              |
| "The system affected is main steam, there are no actuation signals.  The     |
| cause is historical analysis deficiencies.  There are no affects on the      |
| plant.  There are no actions taken or planned at this time and there is no   |
| additional information.  The NRC Resident Inspector was notified.  The State |
| and Local Authorities have been notified."                                   |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   39145       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MCGUIRE                  REGION:  2  |NOTIFICATION DATE: 08/22/2002|
|    UNIT:  [] [2] []                 STATE:  NC |NOTIFICATION TIME: 17:25[EDT]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        08/22/2002|
+------------------------------------------------+EVENT TIME:        16:50[EDT]|
| NRC NOTIFIED BY:  DENNIS MOORE                 |LAST UPDATE DATE:  08/22/2002|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          UNUSUAL EVENT         |KEN BARR             R2      |
|10 CFR SECTION:                                 |JOHN HANNON          NRR     |
|AAEC 50.72(a) (1) (i)    EMERGENCY DECLARED     |JOSEPH HOLONICH      IRO     |
|APRE 50.72(b)(2)(xi)     OFFSITE NOTIFICATION   |KEN CIBOCH           FEMA    |
|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     M/R        Y       100      Power Operation  |0        Hot Standby      |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| UNIT 2 DECLARED AN UNUSUAL EVENT DUE TO A FIRE IN THE TURBINE BUILDING       |
|                                                                              |
| "Fire in Turbine Building at H2 Dryer lasting for greater than 15 minutes.   |
| Fire out at 1655 [hours]. Fire reported at 1633 [hours]."                    |
|                                                                              |
| The Fire Brigade responded and extinguished the fire.  The Hydrogen Dryer    |
| has been isolated.  Offsite assistance was not requested. There were no      |
| injuries reported.  A preliminary assessment revealed extensive damage to    |
| the Hydrogen Dryer as a result of the fire.  The cause of the fire is under  |
| investigation.  There were no maintenance activities, e.g., welding, in      |
| progress at the time.                                                        |
|                                                                              |
| Operators manually tripped Unit 2.  All rods fully inserted.  The plant      |
| responded as expected. No secondary reliefs lifted.  Auxiliary Feedwater     |
| autostarted to maintain Steam Generator water levels.  The Main Condenser is |
| in-service removing decay heat via the main steam dumps.  Cooldown limits    |
| were not exceeded during the transient.  Unit 2 will remain in mode 3        |
| pending completion of the investigation.                                     |
|                                                                              |
| The licensee informed state/local agencies and the NRC Resident Inspector.   |
|                                                                              |
| * * * UPDATED AT 1855 EDT ON 8/22/02 BY DENNIS MOORE TO FANGIE JONES * * *   |
|                                                                              |
| Unusual Event terminated at 1830 EDT.  The fire extinguished when the        |
| hydrogen isolation valve was closed, automatic sprinkler system actuated     |
| which allowed personnel access to the isolation valve.                       |
|                                                                              |
| The licensee notified the NRC Resident Inspector.  Notified the R2DO (Ken    |
| Barr), NRR EO (John Hannon), IRO (Joe Holonich), and  FEMA (David Barden).   |
|                                                                              |
| * * * UPDATED AT 2023EDT ON 8/22/02 BY WAYNE HOYLE TO S. SANDIN * * *        |
|                                                                              |
| The licensee furnished the following additional information:                 |
|                                                                              |
| "On August 22, 2002 at 1636 hours, a manual reactor trip was initiated on    |
| McGuire Unit 2 in response to a fire in a hydrogen dryer in the hydrogen     |
| supply to the Unit 2 Turbine Generator.  As a result of the fire, the        |
| hydrogen supply to the turbine generator experienced a low pressure          |
| condition and plant operators manually tripped the reactor (RPS Actuation)   |
| to prevent damage to the turbine generator.  Following the trip, the Unit 2  |
| Auxiliary Feedwater Pumps started due to loss of Unit 2 Main Feedwater Pumps |
| (Auxiliary Feedwater System Actuation).  Subsequent to the start of the Unit |
| 2 Auxiliary Feedwater Pumps, the 2C Steam Generator experienced a HI-HI      |
| water level.  Level was restored and the water level in all four Steam       |
| Generators is currently in the normal band for existing plant conditions.    |
|                                                                              |
| "The fire in the Unit 2 hydrogen dryer has been extinguished.  Plant         |
| equipment necessary to safely shutdown Unit 2 operated correctly and the     |
| Unit is stable and in Mode 3. The Unit 2 Auxiliary Feedwater Pumps are still |
| running supplying the Steam Generators.  An investigation into the cause of  |
| the fire is in progress.                                                     |
|                                                                              |
| "The NRC Resident Inspector has been notified."                              |
|                                                                              |
| Notified R2DO(Barr).                                                         |
+------------------------------------------------------------------------------+