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Event Notification Report for January 21, 2003








                    U.S. Nuclear Regulatory Commission

                              Operations Center



                              Event Reports For

                           01/17/2003 - 01/21/2003



                              ** EVENT NUMBERS **



39508  39519  39520  39521  39522  39523  39525  39526  



+------------------------------------------------------------------------------+

|General Information or Other                     |Event Number:   39508       |

+------------------------------------------------------------------------------+

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| REP ORG:  OK DEQ RAD MANAGEMENT                |NOTIFICATION DATE: 01/14/2003|

|LICENSEE:  ST FRANCIS HOSPITAL                  |NOTIFICATION TIME: 15:02[EST]|

|    CITY:  TULSA                    REGION:  4  |EVENT DATE:        01/13/2003|

|  COUNTY:                            STATE:  OK |EVENT TIME:        19:30[CST]|

|LICENSE#:  OK-07163-01           AGREEMENT:  Y  |LAST UPDATE DATE:  01/15/2003|

|  DOCKET:                                       |+----------------------------+

|                                                |PERSON          ORGANIZATION |

|                                                |GARY SANBORN         R4      |

|                                                |FRED BROWN           NMSS    |

+------------------------------------------------+                             |

| NRC NOTIFIED BY:  MIKE BRODERICK               |                             |

|  HQ OPS OFFICER:  JASON FLEMMING               |                             |

+------------------------------------------------+                             |

|EMERGENCY CLASS:          NON EMERGENCY         |                             |

|10 CFR SECTION:                                 |                             |

|NAGR                     AGREEMENT STATE        |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

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                                   EVENT TEXT                                   

+------------------------------------------------------------------------------+

| AGREEMENT STATE REPORT INVOLVING LOST SOURCES                                |

|                                                                              |

| The Licensee reported the loss of five 0.355 microcurie, I-125 brachytherapy |

| seeds.  The seeds were model # IAI-125A and they were inventoried upon       |

| receipt from the manufacturer, Iso-Aid.  The seeds were being washed prior   |

| to sterilization (this is a deviation from procedure) and the licensee       |

| believes they were washed down the drain to the public sewer system.  The    |

| Licensee reports that surveys do not indicate that they are in the sink or   |

| trap.                                                                        |

|                                                                              |

| ***UPDATE 01/15/03 1202 EST MIKE BRODERICK TO MIKE NORRIS***                 |

|                                                                              |

| The seeds are actually 0.355 millicurie sources.  Notified NMSS (Brown) and  |

| R4DO (Sanborn).                                                              |

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+------------------------------------------------------------------------------+

|Power Reactor                                    |Event Number:   39519       |

+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+

| FACILITY: BEAVER VALLEY            REGION:  1  |NOTIFICATION DATE: 01/17/2003|

|    UNIT:  [] [2] []                 STATE:  PA |NOTIFICATION TIME: 14:35[EST]|

|   RXTYPE: [1] W-3-LP,[2] W-3-LP                |EVENT DATE:        01/17/2003|

+------------------------------------------------+EVENT TIME:        11:30[EST]|

| NRC NOTIFIED BY:  KEN TIEFENTHAL               |LAST UPDATE DATE:  01/17/2003|

|  HQ OPS OFFICER:  HOWIE CROUCH                 +-----------------------------+

+------------------------------------------------+PERSON          ORGANIZATION |

|EMERGENCY CLASS:          NON EMERGENCY         |RICHARD BARKLEY      R1      |

|10 CFR SECTION:                                 |                             |

|APRE 50.72(b)(2)(xi)     OFFSITE NOTIFICATION   |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

+-----+----------+-------+--------+-----------------+--------+-----------------+

|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                                   

+------------------------------------------------------------------------------+

| OFFSITE NOTIFICATION DUE TO VIOLATION OF DISCHARGE PERMIT                    |

|                                                                              |

| The following information was obtained from a facsimile from the Licensee:   |

|                                                                              |

| "On 1/17/2003 at 1130 hours, the Beaver Valley Power Station received        |

| notification that an operator found raw sewage running from the Unit 2       |

| Sewage Treatment Plant through a slightly open connection and immediately    |

| closed the isolation valve, stopping the flow.                               |

|                                                                              |

| "Assessment by the Beaver Valley response determined that a sewage removal   |

| vendor had previously attempted to pump sludge from a plant sewage system,   |

| but nothing came out.  He then apparently only partially closed the          |

| isolation valve and left the site.  Subsequently, sewage began to flow out.  |

| Approximately 750 gallons of sewage was released down a storm sewer [drain]. |

| An unknown quantity of sewage entered the Ohio River via Peggs Run.          |

| Approximately 50 gallons of sewage remaining on the surface at the local     |

| location is being cleaned up.                                                |

|                                                                              |

| "Pennsylvania Department of Environmental Protection (DEP) has been          |

| notified.                                                                    |

|                                                                              |

| "This event is being reported pursuant to 10 CFR 50.72(b)(2)(xi) as a        |

| situation related to the protection of the environment for which             |

| notification to other government agencies have been made. The NRC resident   |

| has been notified."                                                          |

|                                                                              |

| The notification to the Pennsylvania DEP was made due to a violation of the  |

| plant's discharge permit.                                                    |

+------------------------------------------------------------------------------+



+------------------------------------------------------------------------------+

|Power Reactor                                    |Event Number:   39520       |

+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+

| FACILITY: SUMMER                   REGION:  2  |NOTIFICATION DATE: 01/17/2003|

|    UNIT:  [1] [] []                 STATE:  SC |NOTIFICATION TIME: 16:28[EST]|

|   RXTYPE: [1] W-3-LP                           |EVENT DATE:        01/17/2003|

+------------------------------------------------+EVENT TIME:        14:43[EST]|

| NRC NOTIFIED BY:  PHILLIP ROSE                 |LAST UPDATE DATE:  01/17/2003|

|  HQ OPS OFFICER:  HOWIE CROUCH                 +-----------------------------+

+------------------------------------------------+PERSON          ORGANIZATION |

|EMERGENCY CLASS:          NON EMERGENCY         |JAY HENSON           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   |

+-----+----------+-------+--------+-----------------+--------+-----------------+

|1     N          Y       100      Power Operation  |95       Power Operation  |

|                                                   |                          |

|                                                   |                          |

+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   

+------------------------------------------------------------------------------+

| TECHNICAL SPECIFICATION REQUIRED SHUTDOWN DUE TO FAILED SURVEILLANCE ON      |

| REACTOR TRIP BREAKER                                                         |

|                                                                              |

| The following information was obtained from the licensee via facsimile:      |

|                                                                              |

| "At 11:40 [EST] on January 17, 2003, during surveillance testing of the 'B'  |

| train Reactor Trip Breaker (RTB), the breaker  spuriously opened.  This      |

| caused the RTB to fail its surveillance test and be declared inoperable.     |

| The facility Technical Specifications (TS), LCO 3.3.1 (Reactor Trip System   |

| Instrumentation), Action 8 of Table 3.3-1 requires 6 hours to Mode 3, Hot    |

| Standby.  Rework activities were begun but the station commenced a power     |

| decrease at 14:43 [EST] to comply with the requirements of the TS.           |

|                                                                              |

| "At 15:10 [EST] on January 17, 2003, the activities, including retesting     |

| were completed and the breaker was declared operable at which time the plant |

| exited from the TS Limiting Condition for Operability Action.  At this time  |

| the power decrease was stopped.  Power was held stable at 95% awaiting       |

| completion of all paperwork associated with this surveillance test.  Power   |

| ascension commenced at 15:55 [EST]."                                         |

|                                                                              |

| Determined from the Licensee that the Reactor Trip Breaker spuriously opened |

| after it was closed during the test.  The breaker was replaced with another  |

| breaker and the surveillance test was performed on the new breaker           |

| successfully.                                                                |

|                                                                              |

| The Licensee has informed the NRC Resident Inspector.                        |

+------------------------------------------------------------------------------+



+------------------------------------------------------------------------------+

|Power Reactor                                    |Event Number:   39521       |

+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+

| FACILITY: SUSQUEHANNA              REGION:  1  |NOTIFICATION DATE: 01/19/2003|

|    UNIT:  [1] [] []                 STATE:  PA |NOTIFICATION TIME: 12:19[EST]|

|   RXTYPE: [1] GE-4,[2] GE-4                    |EVENT DATE:        01/19/2003|

+------------------------------------------------+EVENT TIME:        10:11[EST]|

| NRC NOTIFIED BY:  DAVID WALSH                  |LAST UPDATE DATE:  01/19/2003|

|  HQ OPS OFFICER:  GERRY WAIG                   +-----------------------------+

+------------------------------------------------+PERSON          ORGANIZATION |

|EMERGENCY CLASS:          NON EMERGENCY         |RICHARD BARKLEY      R1      |

|10 CFR SECTION:                                 |TAD MARSH            NRR     |

|ASHU 50.72(b)(2)(i)      PLANT S/D REQD BY TS   |MOHAMED SHANBAKY     R1      |

|                                                |                             |

|                                                |                             |

|                                                |                             |

+-----+----------+-------+--------+-----------------+--------+-----------------+

|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |

+-----+----------+-------+--------+-----------------+--------+-----------------+

|1     N          Y       77       Power Operation  |50       Power Operation  |

|                                                   |                          |

|                                                   |                          |

+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   

+------------------------------------------------------------------------------+

| SUSQUEHANNA UNIT 1 SHUTDOWN REQUIRED BY TECHNICAL SPECIFICATIONS             |

|                                                                              |

| The following is taken from a facsimile sent by the licensee:                |

|                                                                              |

| "At 10:11 hrs on 1/19/2003 Susquehanna Unit 1 began a shut down required by  |

| Technical Specifications.                                                    |

|                                                                              |

| "At 13:06 hrs on 1/16/2003 the 'B' diesel generator was being returned to    |

| service following maintenance. This placed Unit 1 and Unit 2 into a 72 hour  |

| LCO (3.8.1 Cond. B). During its operability run, the governor exhibited      |

| erratic operation and the diesel was shut down. The 'E' diesel generator was |

| re-substituted for the 'B' and an operability run was initiated. During the  |

| run, the 'E' diesel generator tripped on reverse power. Station personnel    |

| continue to troubleshoot the unrelated problems with the diesel generators.  |

| Initial engineering analysis has determined that there is no common mode     |

| failure with these 2 problems or with the remaining 3 operable diesel        |

| generators.                                                                  |

|                                                                              |

| "The 72 hour LCO for inoperability of 1 Diesel Generator (3.8.1 Cond. B)     |

| will expire at 13:06 hrs today. This will require both Unit 1 and Unit 2 to  |

| enter LCO 3.8.1 Cond. F, which requires both units to be in Hot Shutdown     |

| within 12 hours and Cold Shutdown within 36 hours.                           |

|                                                                              |

| "An additional ENS report will be made when power reduction begins on Unit   |

| 2."                                                                          |

|                                                                              |

| The licensee has notified the NRC Resident Inspector of this event and plans |

| to make a press release.                                                     |

|                                                                              |

| * * * UPDATE 1600EST ON 1/19/03 FROM DAVID WALSH TO S. SANDIN * * *          |

|                                                                              |

| "At 15:38 hrs on 1/19/2003 the 'E' diesel generator was declared operable.   |

| This returned the station to 4 operable diesel generators and allowed        |

| exiting the LCO 3.8.1 Cond. B and Cond. F.  Power reduction on Unit 1 was    |

| halted at approximately 50%.  Unit 2 remained at 100% power.  Current plans  |

| are to return Unit 1 to 100% power."                                         |

|                                                                              |

| The licensee is reviewing whether a press release will be made.  Also, the   |

| licensee informed the NRC resident inspector of this update.  Notified       |

| R1DO(Barkley) and NRR EO(Marsh).                                             |

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+------------------------------------------------------------------------------+

|Power Reactor                                    |Event Number:   39522       |

+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+

| FACILITY: NORTH ANNA               REGION:  2  |NOTIFICATION DATE: 01/19/2003|

|    UNIT:  [] [2] []                 STATE:  VA |NOTIFICATION TIME: 14:59[EST]|

|   RXTYPE: [1] W-3-LP,[2] W-3-LP                |EVENT DATE:        01/19/2003|

+------------------------------------------------+EVENT TIME:        12:52[EST]|

| NRC NOTIFIED BY:  B. J. BROWN                  |LAST UPDATE DATE:  01/19/2003|

|  HQ OPS OFFICER:  GERRY WAIG                   +-----------------------------+

+------------------------------------------------+PERSON          ORGANIZATION |

|EMERGENCY CLASS:          NON EMERGENCY         |JAY HENSON           R2      |

|10 CFR SECTION:                                 |                             |

|AMED 50.72(b)(3)(xii)    OFFSITE MEDICAL        |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

+-----+----------+-------+--------+-----------------+--------+-----------------+

|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |

+-----+----------+-------+--------+-----------------+--------+-----------------+

|                                                   |                          |

|2     N          N       0        Refueling        |0        Refueling        |

|                                                   |                          |

+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   

+------------------------------------------------------------------------------+

| CONTAMINATED,  INJURED WORKER TRANSPORTED TO LOCAL MEDICAL FACILITY          |

|                                                                              |

| The following is taken from a facsimile from the licensee:                   |

|                                                                              |

| "At 1252 today, a worker in a Contaminated Area in Unit 2 Containment became |

| overheated and required medical attention. The first aid team responded and  |

| required that the individual be transported while he was still contaminated. |

| The individual has 100K [100,000] dpm by direct frisk on his skin in the     |

| area of his face and 10K [10,000] dpm by direct frisk on his clothing he was |

| wearing. He was transported by local Rescue Squad. While in the ambulance he |

| was decontaminated by HP [Health Physics] personnel that were assisting.     |

| Medical College of Virginia (MCV) was notified of a potentially contaminated |

| person that was enroute. The individual is still being transported to MCV    |

| where he will receive medical treatment. The individual and ambulance are    |

| now clean and all contaminated material will be transported back to NAPS     |

| [North Anna Power Station]"                                                  |

|                                                                              |

| The contaminated, injured worker was working on the installation of the      |

| blind flange on the fuel transfer tube. The North Anna Unit 2 reactor is     |

| refueled.                                                                    |

|                                                                              |

| The licensee will notify the NRC Resident Inspector of this event.           |

+------------------------------------------------------------------------------+



+------------------------------------------------------------------------------+

|Power Reactor                                    |Event Number:   39523       |

+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+

| FACILITY: SOUTH TEXAS              REGION:  4  |NOTIFICATION DATE: 01/19/2003|

|    UNIT:  [1] [2] []                STATE:  TX |NOTIFICATION TIME: 21:25[EST]|

|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        01/19/2003|

+------------------------------------------------+EVENT TIME:        12:55[CST]|

| NRC NOTIFIED BY:  GREG JANAK                   |LAST UPDATE DATE:  01/19/2003|

|  HQ OPS OFFICER:  GERRY WAIG                   +-----------------------------+

+------------------------------------------------+PERSON          ORGANIZATION |

|EMERGENCY CLASS:          NON EMERGENCY         |GARY SANBORN         R4      |

|10 CFR SECTION:                                 |TAD MARSH            NRR     |

|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   |

+-----+----------+-------+--------+-----------------+--------+-----------------+

|1     N          Y       100      Power Operation  |100      Power Operation  |

|2     N          N       0        Hot Standby      |0        Hot Standby      |

|                                                   |                          |

+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   

+------------------------------------------------------------------------------+

| VARIOUS SYSTEM ACTUATIONS AS A RESULT OF THE LOSS OF OFFSITE POWER           |

|                                                                              |

| The following information was received via facsimile:                        |

|                                                                              |

| "At 1255 hrs on January 19, 2003, Unit 1 was in Mode 1 at 100% power and     |

| Unit 2 was in Mode 3 with Trains A and D reactor coolant pumps (RCP)         |

| running. While placing a surge reactor in the switchyard in service the Unit |

| 1 standby transformer received a lockout and total loss of the North bus.    |

|                                                                              |

| "Unit 1 experienced a loss of offsite power (LOOP) to ESF Trains B & C. Both |

| the Train B & Train C emergency diesel generators (EDG) started as expected. |

| The Train C sequencer operated as expected and the Train C components        |

| automatically loaded, However, the Train B sequencer failed resulting in the |

| manual loading of the Train B components in accordance with station          |

| off-normal procedures. This resulted in TS 3.0.3 entry in Unit 1 due to the  |

| loss of two (2) offsite power sources and the B train EDG (due to the        |

| failure of the B Train sequencer). There was a loss of letdown in Unit 1     |

| when Train C isolated. Letdown was restored at 1313 hrs. At 1345 Unit 1      |

| exited TS 3.0.3 when offsite power was restored to B Train. At 1406, offsite |

| power was restored to C Train. The cause of the fault in the switchyard and  |

| failed Train B sequencer are under Investigation.                            |

|                                                                              |

| "In Unit 2, Train A was aligned to the Unit 1 Standby transformer therefore, |

| Unit 2 experienced a LOOP to ESF Train A. Train A emergency diesel generator |

| automatically started and loaded as expected. As a result of the LOOP, Unit  |

| 2 experienced a loss of circulating water and loss of condenser vacuum. The  |

| Steam Generators (SGs) were already being supplied by the Auxiliary          |

| Feedwater system therefore no interruption to SG cooling. In addition, both  |

| Train A and Train D reactor coolant pumps tripped resulting in entry into TS |

| 3.4.1.2, action B & C (boron control limitations and ensure Rx trip breakers |

| open). There was a loss of charging due to the LOOP resulting in a Loss of   |

| RCP seal injection, however, component cooling water flow to the thermal     |

| barrier maintained seal cooling. Charging has been restored to supply seal   |

| injection. At 1840, when starting RCP 2A, pressurizer PORV 655A opened and   |

| reseated due to a pressure spike. Unit 1 remains at 100% power and Unit 2    |

| remains in Mode 3."                                                          |

|                                                                              |

| The licensee informed the NRC resident inspector.                            |

+------------------------------------------------------------------------------+



+------------------------------------------------------------------------------+

|Power Reactor                                    |Event Number:   39525       |

+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+

| FACILITY: MCGUIRE                  REGION:  2  |NOTIFICATION DATE: 01/20/2003|

|    UNIT:  [1] [2] []                STATE:  NC |NOTIFICATION TIME: 14:40[EST]|

|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        01/20/2003|

+------------------------------------------------+EVENT TIME:        10:40[EST]|

| NRC NOTIFIED BY:  DENNIS MOORE                 |LAST UPDATE DATE:  01/20/2003|

|  HQ OPS OFFICER:  RICH LAURA                   +-----------------------------+

+------------------------------------------------+PERSON          ORGANIZATION |

|EMERGENCY CLASS:          NON EMERGENCY         |JAY HENSON           R2      |

|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  |

|2     N          Y       100      Power Operation  |100      Power Operation  |

|                                                   |                          |

+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   

+------------------------------------------------------------------------------+

| RANDOM FITNESS FOR DUTY TEST FAILURE                                         |

|                                                                              |

| "A non-licensed contract supervisor tested positive during a random test.    |

| The employee's access to the plant has been restricted." Contact the HOO for |

| additional details.                                                          |

|                                                                              |

| The NRC Resident Inspector was notified.                                     |

+------------------------------------------------------------------------------+



+------------------------------------------------------------------------------+

|Power Reactor                                    |Event Number:   39526       |

+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+

| FACILITY: BEAVER VALLEY            REGION:  1  |NOTIFICATION DATE: 01/20/2003|

|    UNIT:  [] [2] []                 STATE:  PA |NOTIFICATION TIME: 20:13[EST]|

|   RXTYPE: [1] W-3-LP,[2] W-3-LP                |EVENT DATE:        01/20/2003|

+------------------------------------------------+EVENT TIME:        14:30[EST]|

| NRC NOTIFIED BY:  JAMES WITTER                 |LAST UPDATE DATE:  01/20/2003|

|  HQ OPS OFFICER:  RICH LAURA                   +-----------------------------+

+------------------------------------------------+PERSON          ORGANIZATION |

|EMERGENCY CLASS:          NON EMERGENCY         |JOHN ROGGE           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   |

+-----+----------+-------+--------+-----------------+--------+-----------------+

|                                                   |                          |

|2     N          Y       100      Power Operation  |100      Power Operation  |

|                                                   |                          |

+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   

+------------------------------------------------------------------------------+

| SERVICE WATER SYSTEM VALVE PIT PIPING PENETRATION SEAL                       |

|                                                                              |

| "On 1/20/2003 at 1430 hours, the Beaver Valley Power Station control room    |

| was notified by Engineering that a penetration seal previously installed in  |

| a wall which separates two service water system valve pits may have not been |

| adequate. A review of the supporting analysis shows that this penetration    |

| seal may not be qualified to withstand the hydraulic pressure which could    |

| result from a postulated internal flooding event occurring due to a service  |

| water system pipe failure filling the valve pit and its above compartment    |

| prior to operator intervention. A failure of this seal during a postulated   |

| internal flooding event may result in the loss of motor operated valve       |

| movement in both trains of the service water system that would be needed     |

| following a design basis accident (DBA).                                     |

|                                                                              |

| "This design basis calculation and the penetration seal capability are       |

| continuing to be evaluated. However, this seal could potentially have        |

| prevented the service water system from meeting single failure criterion     |

| during a postulated service water system pipe failure. Therefore, Technical  |

| Specification (TS) 3.7.4.1 was entered due to less than two trains of        |

| service water system being operable as a conservative decision based upon    |

| the limited information immediately available to show acceptable seal        |

| integrity at the postulated conditions. The TS Action requires restoration   |

| of two independent service water system trains within 72 hours. Actions are  |

| in progress to install a qualified seal which will prevent the unacceptable  |

| flooding conditions from being able to occur.                                |

|                                                                              |

| "This condition is being reported pursuant to 10 CFR 50.72(b)(3)(ii) as an   |

| unanalyzed condition that significantly degraded plant safety since this     |

| seal has been installed for five months and may have invalidated the         |

| independence between the two service water system trains. The NRC resident   |

| has been notified of the degraded condition."                                |

+------------------------------------------------------------------------------+