ML18100B037
| ML18100B037 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 04/14/1994 |
| From: | Tosch K NEW JERSEY, STATE OF |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9405020014 | |
| Download: ML18100B037 (3) | |
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State of New Jersey Department of Environmental Protection and Energy Robert C. Shinn, Jr.
Commissioner Division of Environmental Safety, Health, and *Analytical Programs Radiation Protection Programs Bureau of Nuclear Engineering CN 415 Trenton, New Jersey 08625-0415 Tel (609) 987-2032 Fax (609) 987-6354 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 Ladies & Gentlemen:
April 14, 1994
Subject:
Salem Nuclear Generating Station, Unit 1. Docket No. 50-2 7 2
- Lic_en_se Amendment Request,. LCR-9 3-:.2:5.
Replace:nlen-t: of.the
- M'a,iri F~e_dw:at'er. (FW) control and
_Control.* :Sypf3,ss Valy~i;;.* w,it_h _.the, -~!=11n,: F~$.dwater
- Stop : Check
_ Val v~s. for 'the* qorita_irim~~t:--,;r:sol_?ltion. Function'..,. : >' : :
(a)
PSE&~* letter: to NRC,_ dated 2/18/J:99.4:,:. and*."_,,
".: (b) Additional Information, PSE&G letter to NRC, dated 4/6/1994 By letter dated Februa1:y is, 1994, Public Service Electric and Gas Company (PSE&G) submitted the subject license change request to the Nuclear Regulatory Commission (NRC).
The request will impact Technical Specification (TS)
Surveillance 4.6.3.1.2c (to be deleted) and TC 3.6.3, Table 3.6-1 (to be revised).
The following is a description and reason for LCR 93-25, per licensee's statement. The main FW control and their corresponding bypass valves are used for control of the main FW flow during power operation and for FW isolation in response to a steamline/feedline break accident, and were not intended for Containment Isolation.
Systems penetrating Containment are classified as essential and non-essential.
The Salem *main FW system is designated as non-essential.
10 CFR
- 50 "Appendix A, __ G~neral.* nesign. C:J:"iteri~n * (GDc) 57, requires that each line *:Cf:i:::om 'ess~~nfiai,.<<:n:~ no:n~essential systems) which penetrat~s p_;cim9-ry. c_ontai:pme~t,. <<anq, _is riot: *.a *part :.oL*.the-reactor cooling*' system,' and'_" riot. connect.ed* directly. to* the' containment atmosphere, *need tq have at least_ one containment New Jersey Is an Equal Opportunity Employer Recyded Paper
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isolation valve, to be located outsida containment.
Furthermore such valves, shall be located as close to the containment wall as practical, shall be either automatic, or locked closed, or. capable of remote-manual operation.
It further stipulates, that a simple check valve may not be used as the automatic isolation valve.
Per licensee '*s statement, the main FW stop check valves were designed as the main feedwater Containment Isolation valves, but this function was not approved by the NRC at the time of the initial licensing. The concern was that although stop check valves can satisfy the requirements of GDC 57, the original stop check valve at Salem had local-manual operators only and therefore non-remote control capability in the event of an accident.
When in 1990, the licensee submitted an amendment to increase the isolation time of the main FW control valves, and following consultation with the NRC, the licensee opted to transfer the Containment Isolation function from the control and control bypass valves to the stop check valves.
Modifications intended to bring.
the stop check valves into compliance with GDC 57 have included installation of motor operators and additional changes converting the non-safety-related controls into safety~related ones.
The licensee concludes that using the modified check valves for Containment Isolation returns the plant to the originally intended arrangement.
The additional information provided by further clarified the proposed changes requirements and schedule for those valves.
PSE&G on 4/6/94, and surveillance The New Jersey Department of Environmental Protection and Energy's Bureau of Nuclear Engineering (BNE) has reviewed the request in accordance with the requirements of 10 CFR 50.91(b) and has no comments.
If you have any questions, please contact Suren Singh at (609) 987-2039 or Ariadni Kapsalopoulou at (609)_ 987-2052.
Sincerely, Kent w. Tosch, Manager Bureau of Nuclear Engineering
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c:
Anthony J. McMahon, Acting Assistant Director Radiation-Protection Programs, NJ DEP&E David Chawaga, State Liaison Officer - Region I U.S. NRC J. c. Stone, Licensing Project Manager, NRR U.S. NRC
- c. Marschall, Artificial Island Senior Resident Inspector U.S. NRC F. Thomson, Manager Licensing and Regulation, PSE&G
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