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Event Notification Report for February 10, 2003



                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           02/07/2003 - 02/10/2003

                              ** EVENT NUMBERS **

39573  39574  

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   39573       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BEAVER VALLEY            REGION:  1  |NOTIFICATION DATE: 02/07/2003|
|    UNIT:  [1] [] []                 STATE:  PA |NOTIFICATION TIME: 15:54[EST]|
|   RXTYPE: [1] W-3-LP,[2] W-3-LP                |EVENT DATE:        02/07/2003|
+------------------------------------------------+EVENT TIME:        14:08[EST]|
| NRC NOTIFIED BY:  ROBERT G. HADDOCK            |LAST UPDATE DATE:  02/07/2003|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |JAMES NOGGLE         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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| UNANALYZED CONDITION RELATED TO A POTENTIAL DISCHARGE OF THE C02 FIRE        |
| SUPPRESSION SYSTEM                                                           |
|                                                                              |
| "On 2/7/2003 at 1408 hours, the Beaver Valley Power Station control room was |
| notified by Engineering that a potential pressure transient from a discharge |
| of the C02 total flooding fire suppression system in the East and West Cable |
| Vaults at Beaver Valley Unit 1 (BV-1) could result in an unanalyzed          |
| condition. This pressure transient could cause the fire barriers within the  |
| subject areas to be structurally challenged, resulting in the potential for  |
| a postulated fire in one fire area to spread to an adjacent fire area. This  |
| condition could invalidate the assumptions made in the BV-1 fire protection  |
| safe shutdown analysis per 10 CFR 50 Appendix R. This condition was          |
| discovered following engineering's evaluation of a Condition Report          |
| initiated on 2/5/03 concerning the potential for a C02 discharge in the      |
| above areas that could have resulted in a breach of the fire barriers        |
| between adjacent fire areas. The automatic C02 suppression system in the     |
| East and West Cable Vaults was defeated on 2/5/03 at 2150 hours in response  |
| to the initial identified concern and a fire watch was established in the    |
| affected areas. These compensatory measures eliminate the potential for C02  |
| overpressure transient condition in the affected areas.                      |
|                                                                              |
| "This condition is being reported pursuant to 10 CFR 50.72(b)(3)(ii) as an   |
| unanalyzed condition that significantly degrades plant safety since a        |
| potential discharge of the C02 fire suppression system in response to a      |
| postulated fire could have invalidated the assumptions made in the BV-1 fire |
| protection safe shutdown analysis per 10 CFR 50 Appendix R. The NRC resident |
| has been notified of the degraded condition."                                |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Other Nuclear Material                           |Event Number:   39574       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  INDIANA DEPARTMENT OF TRANSPORTATIO  |NOTIFICATION DATE: 02/09/2003|
|LICENSEE:  INDIANA DEPARTMENT OF TRANSPORTATION |NOTIFICATION TIME: 07:10[EST]|
|    CITY:  INDIANAPOLIS             REGION:  3  |EVENT DATE:        02/09/2003|
|  COUNTY:                            STATE:  IN |EVENT TIME:        04:20[EST]|
|LICENSE#:  13-26341-01           AGREEMENT:  N  |LAST UPDATE DATE:  02/09/2003|
|  DOCKET:  03032463                             |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |KENNETH RIEMER       R3      |
|                                                |MELVYN LEACH         NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  TOM JOHN                     |                             |
|  HQ OPS OFFICER:  RICH LAURA                   |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|NINF                     INFORMATION ONLY       |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| DAMAGED TROXLER GAUGE AT CONSTRUCTION SITE                                   |
|                                                                              |
| The RSO from the Indiana Department of Transportation reported a damaged     |
| Troxler gauge at a new construction site located approximately 1 mile west   |
| of the Indianapolis Airport.  A bulldozer drove over the Troxler gauge.  The |
| gauge belongs to the State of Indiana. The gauge was a model number 3440 and |
| had the serial number 19699.   The gauge contained approximately 8           |
| millicuries Cs-137 and 40 millicuries of Am-241/Be.  The operating rod       |
| handle on the top of the gauge was bent over such that the plate on the      |
| bottom was stuck open.  The RSO performed a radiological survey.  The gauge  |
| casing was intact and no leakage was found.  No personnel contaminations or  |
| radiation overexposures were observed.  The RSO roped off the area. The RSO  |
| planned to transport the gauge back to the facilities shielded room.         |
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