ML18100B000
| ML18100B000 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 04/06/1994 |
| From: | Hagan J Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| LCR-93-25, NLR-N94060, NUDOCS 9404180137 | |
| Download: ML18100B000 (3) | |
Text
Public Service Electric and Gas Company Joseph J. Hagan Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-1200 Vice President - Nuclear Operations
.APR O 6 1994*
NLR-N94060 LCR 93-25 United States Nuclear Regulatory Commission Document Control Desk Washington, D.C.
20555 Gentlemen:
ADDITIONAL INFORMATION TO SUPPORT AMENDMENT REQUEST SALEM GENERATING STATION UNIT NO. 1 FACILITY OPERATING LICENSE NO. DPR-70 DOCKET NO. 50-272 Public Service Electric and Gas Company (PSE&G) submitted a Facility Operating License amendment request in a letter dated February 18, 1994.
The proposed amendment request replaced the main feedwater control and control bypass valves with the main feedwater stop check valves for the Containment Isolation Function.
Based on subsequent conversations with Mr. J. Stone, Salem NRR Project Manager, we are providing additional information concerning main feedwater stop check valve involvement in the Inservice Testing (IST) and Generic Letter (GL) 89-10 Programs, and justification for their exemption from Appendix J Type C leakage testing.
The main feedwater stop check valves (BF-22s) are included in our IST Program.
These valves can not be exercised during power operation because the Salem station is not licensed for 3-loop operation.
They are full stroke exercised during cold shutdown per ASME Section XI, Paragraph IWV-3522.
The check valve stop feature is accomplished by a motor operator.
These Limitorque motor operators are included in the GL 89-10 Program for static testing.
PWR main feedwater isolation valves are exempt from Appendix J Type C leakage testing.
These valves connect to the steam generator and are not exposed, during normal or post-LOCA operations, to either the Containment atmosphere or the Reactor Coolant System.
Valve isolation is based on steam generator functional requirements.
The steam generator and connecting 9404180137 6~868~72
~DR ADOCK PDR AGD,
Document Control Desk N;LR-N94060 2
APR 0 61994*
lines are a closed system inside Containment as defined by the NRC Standard Review Plan.
Salem UFSAR Table 6.2-13 lists those Containment Isolation Valves not subject to Type c leak rate testing.
The BF-22s are included in this list.
Thus, the #
footnote for the 11-14 BF-22s on Table 3.6-1 Containment Isolation Valves merely identifies these valves as exempt from Type C leak testing, and provides consistency between the Salem UFSAR and the Salem Technical Specifications.
Should you have any questions on this transmittal, please contact us.
c Mr. T. T. Martin, Administrator - Region I
- u. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. J. c. Stone, Licensing Project Manager - Salem
- u. S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Rockville, MD 20852 Mr. c. Marschall (S09)
USNRC Senior Resident Inspector Mr. K. Tosch, Manager, IV NJ Department of Environmental Protection Division of Environmental Quality Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625
REF:
NLR-N94060 STATE OF NEW JERSEY SS.
COUNTY OF SALEM J. J. Hagan, being duly sworn according to law deposes and says:
I am Vice President - Nuclear Operations of Public Service Electric and Gas Company, and as such, I find the matters set forth in the above referenced letter,. concerning the Salem Generating Station, Unit Nos. 1 and 2, are true to the best of my knowledge, information and belief.
Subscribed and sworn to before me
,,-thi/ "!JJ ~J_ day of ~))_
1994
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