LR-N02-0400, Change to Commitment Regarding 4166 Volt Switchgear Room Suppression
| ML023380011 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 11/25/2002 |
| From: | John Carlin Public Service Enterprise Group |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| LR-N02-0400 | |
| Download: ML023380011 (3) | |
Text
PSEG Nuclear LLC P 0. Box 236, Hancocks Bndge, New Jersey 08038-0236 NOV 2 5 2002 0 PSEG Nuclear LLC United States Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 CHANGE TO COMMITMENT REGARDING 4160 VOLT SWITCHGEAR ROOM SUPPRESSION SALEM GENERATING STATION UNIT NOS. I AND 2 DOCKET NOS. 50-272 AND 50-311 The purpose of this letter is to update PSEG's commitment associated with the resolution of suppression system deficiencies in the 4160 Volt Switchgear Room.
As stated in letter LR-N02-0084, dated April 19, 2002, PSEG's plan was to maintain the manually operated Carbon Dioxide system in the 4160 Volt Switchgear Room and that modifications to achieve the proper carbon dioxide concentration in this area would be completed by the end of November 2002.
PSEG has been actively pursuing actions to determine the discharge time to achieve the proper carbon dioxide concentration for the 4160 Volt Switchgear Room. In May 2002, tracer gas testing was performed to determine the amount of leakage from the 4160 Volt Switchgear Room. As discussed in Special Report 50-311/02-003-00 submitted on June 3, 2002, the leakage measured during the testing was greater than anticipated. As a result of this testing, the carbon dioxide system in this area was impaired and compensatory actions were established in accordance with the Fire Protection Program. A root cause investigation was conducted, the results of which were communicated in Supplemental Special Report 50-311/02-003-01 issued on August 1, 2002. The Supplemental Report identified the cause as design issues associated with the carbon dioxide isolation dampers and operation of the Switchgear and Penetration Area Ventilation (SPAV) system supply fans during a carbon dioxide discharge.
Prior to the tracer gas testing, the modifications necessary to resolve this issue were believed to be limited to changing the carbon dioxide discharge timer setpoint to provide for a longer discharge time. Based on the tracer gas testing and root cause analysis discussed above, the previous approach is no longer feasible. As a result, PSEG will not be able to resolve the carbon dioxide concentration concern by the end of November 2002. PSEG is currently re evaluating the options (modifications to ventilation systems, different fire A, DIo 95-2168 REV 7/99
Document Control Desk 2
NOV 2 5 2002 LR-N02-0400 suppression systems, changes to the design & licensing basis, review of industry experience, etc.) in order to resolve the fire suppression concerns in this area as expeditiously as possible without challenging the safety of the plant. An assessment of the current carbon dioxide suppression capabilities is being performed to determine the ability of the system to perform the intent of its design function (suppress the fire until manual fire fighting activities are initiated to extinguish the fire). At the completion of this assessment, a determination will be made regarding the overall resolution of the fire suppression system in the 4160 Volt Switchgear Room.
Therefore, PSEG Nuclear is revising our commitment to complete modifications to achieve the proper carbon dioxide system concentration in the 4160 Volt Switchgear Room to the following:
"PSEG is currently re-evaluating the options in order to resolve the fire suppression concerns in the 4160 Volt Switchgear Room. The resolution strategy and schedule for completion as a result of this re-evaluation will be issued by the end of March 2003."
If you have any questions regarding this submittal, please contact Brian Thomas at 856-339-2022.
Sincre N.
on Carin ce President - Nuclear Reliability and Technical Support
Document Control Desk 3
I'0V 2 5 2002 LR-N02-0400 C
Mr. H. J. Miller, Regional Administrator U. S. Nuclear Regulatory Commission - Region 1 475 Allendale Road King of Prussia, PA 19406 U. S. Nuclear Regulatory Commission ATIN: Mr. R. Fretz, Licensing Project Manager - Salem Mail Stop 08B2 Washington, DC 20555 USNRC Senior Resident Inspector - Salem (X24)
Mr. K. Tosch, Manager, IV Bureau of Nuclear Engineering P.O. Box 415 Trenton, NJ 08625