ML20101G350
| ML20101G350 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 06/11/1992 |
| From: | Feigenbaum T PUBLIC SERVICE CO. OF NEW HAMPSHIRE |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20101G353 | List: |
| References | |
| GL-91-08, GL-91-8, NYN-92079, NUDOCS 9206260002 | |
| Download: ML20101G350 (3) | |
Text
___
e New tiampshire Y
k Ted C. Feigenbaum President and Chief Execvwve Offices i
NYN-92079 4
June 11.1992 United States Nuclear Regulatory Commission i
Washington, D.C.
20555 Attention:
Document Control Desk r
Reference; Facility Operating License No. NPF-86 Docket No. 50-443
Subject:
License Amendment Request 91-06; Removal of Component Lists From Technical Specifications, Generic Letter 91 OS i
Gentlemen:
i 1
New llampshire Yankee (NilY) has enclosed License Amendment Rer,uest 9106. This 1.ict nse Amendment Request is submitted pursuant to 10CFR50.90 and is distributed pursuu s to 10C F R 50.4 The purpose of I icense Amendment Request 91-06 is to propose chngn to the l
Seabrook Station Technical Specifications implementing the guidance of NRC Generic Letter 91-OS " Removal of Component Lists From Technical Specifications? Generic Letter 91-0X i
is intended to improve Technical Specifications as it provides an acceptable alte native means to identifying every component by its plant identification number as it is currentti listed in the tables of Technicai Specification components.
The Technical Specification changes proposed herein bv NHY implement the guidance of Generic 1.etter 91-08 by removing the listing of Secondary Containment Bypass Leakage Paths (Technical Specification Table 3.6-1) and by revising Technical Specification 3.6.3 (Containment Isolation Valves) to specify that locked or scaled closed containment isolation valves may be opened on an intermittent basis under administrat:ve control.
The Bases for Technical Specification 3.6.3 has also been revised to define the administrative controls which are required for the opening of a locked or scaled closed containment isolation valve.
New Hampshire Yankee notes that it s Technical Specifications currently reflect some of the specific improvements afforded by l
Generic Letter 9108. The Seabrook Station Technical Specification improvements previously implemented include the removal of lists for Containment isolation Valves, Containment Penetration Conductor Osercurrent Protection Devices and Motor-Operated Valve Thermal l
Oscrioad Protection. These lists are contained in NHY's Technical Requirements Manual and are duplicated in the Updated Final Safety Analysis Repor.
These documents arc subj e ct to the change control provisions of the Administrative Controls (Section 6) t f Scai> rook Station Technical Specifications.
The list of Secondary Containment Bypass Leat,ge Paths which NHY proposes to remove from Technical Specification will also be added to the Technical Requirements Manual and the Updated Final Safety Analysis Report License Amendment Request 91-06 has been reviewed ano approved by the NilY Stetion Operation Review Committec and 'he Nuclear Safety At.dit Review Committee.
9206260002 920611 M
PDR ADOCK 05000443 V
P PDR 1
l oOrG" New Hampshire Yankee Uivision of Public Service Company of New Hampshire I
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P.O. Box 300
- Seabrook, NH 03874
- Telephone (603) 474 9521 4
i Un!!cd States Nuclear Regulatory Comtaission June 11,1992
~
Attention:
Document Contro! Deck
_ Page two As discussed in the enclosed License Amendmert -Request 91-06,Section V, the proposed changes have been determined not to involve a significant hazards consideration A copy of.~ his letter and the enclosed License nursuant to the siandards of 10CFR50.42.
t Amendment Request 91-06 have been forwarded to the State of New llampshire State Liaison i
Officer puri. aunt to 10CFR50.91(b).
New ilampshire Yankee requests NRC review of License Amendioent Request 9106 and issuance of a license amendment by September 7,-1992 (see enclosed License Amendment Request 91-06,Section VI). New flampshire Yankee is developing a plant modificatica to allow the Containment Compressed Air System to be cross-connected to the Plant Compressed Air System in order to improve saf ety and relir.bility. It is intended that the modification, which woukt require updating Technical Specification Table 3.6 1,'
be implemented.after approval of this License Amendment Request, thereby reducing the number of License Amendments sought by NHY and freeing NRC resources for-other activities.
i Should you hase any questions regarding this -letter, please contact ' Mr. ' Terry L.
Harp. ster. Director of Licensing Services at (603) 474 9521, extension 2765.
Very truly yours,
/
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Ted C. Feigenblium TC F: A LL/act Erclosure i
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e United States Nuclear Regulatory Commission J une 11,1992 Attention:
Document Control Dest Page three cc:
Nir. Thomas T. Ntartin Regional Administrator United Statc3 Nuclear Regulatory Commission Region 1 475 Allendale Road King of Prussia, PA 19406 N1r. (iordon E. Edison, Sr. Project Nt anage r P roje ct Directorate 1-3 Division of Reactor Projects U.S. Nuclear Regulatory Commission Washington, DC 20555 Nir. Noel Dudley NRC Senior Resident inspector P.O. Box 1149 heabrook, Nil 03S74 N1r. George L Iverson, Director New llampshire Office of Emergency N1anagement 107 Pleasant Street Concord. Nil 03301
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