ML20070D003

Forwards Suppl to 820222 Response to Request for Info Re Unresolved Safety Issue A-39 Concerning Safety Relief Valve Pool Dynamic Loads,Per NUREG-0802,NUREG-0783 & NUREG-0763

ML20070D003
Person / Time
Site:	Skagit
Issue date:	12/08/1982
From:	Myers R PUGET SOUND POWER & LIGHT CO.
To:	Harold Denton Office of Nuclear Reactor Regulation
References
REF-GTECI-A-39, REF-GTECI-CO, RTR-NUREG-0763, RTR-NUREG-0783, RTR-NUREG-0802, RTR-NUREG-763, RTR-NUREG-783, RTR-NUREG-802, TASK-A-39, TASK-OR PLN-275, NUDOCS 8212140419
Download: ML20070D003 (4)

Text

l .

o PUGET PObVER December 8,1982 PLN-275 Mr. Ilarold R. Denton, Director Office of Nuclear Reactor Regulation U.S Nuclear Regulatory Commission Washington, D.C. 00055

Subject:

Puget Sound Power & Light Company Skagit/Hanford Nuclear Project, Units 1 & 2 Docket Nos. 50-522 and 50-523 Request for Information on Unresolved Safety Issues

Reference:

Robert V. Myers letter PLN-245 to liarold R. Denton dated February 22, 1982

Dear Mr. Denton:

Attached is additional material in support of our response to Generic Issue A-39 previously transmitted by the above referenced letter. This material discusses our conformance with the NRC resolution of this issue.

Ver y yo rs,

/

4v Robert V. Myer Vice Presiden Generation R urces Attach.

cc: Attached NRC Service List

• R. L. Tedesco, NRC E. G. Adensam, NRC C. W. Moon, NRC P. A. LaGrange, NRC DddDOj982120s A 05000522 PDR Q ny s w-r.,, n~ m, n.~. ~,- m e m

- . ... ~.

Atta:hmet l* to PLN-275 '

GENERIC ISSUE A-39 STATUS OF S/HNP ON SRV POOL DYNAMIC LOADS As stated in our response to Generic Issue A-39 on SRV Pool Dynamic Loads on

. February 22, 1982, the review of Mark IH SRV Loads was being conducted on the

! GESSAR II docket and was applicable to S/HNP. The NRC's review is now completed and three NRC documents, NUREG-0763, NUREG-0802, and NUREG-0783 have been recently issued reflecting the results of this review and the resolution of Generic Issue A-39. The following discusses the S/HNP status with regard to these three documents.

Quencher Loads NUREG-0802, " Safety / Relief Valve Quencher Loads: Evaluation for BWR Mark II and III Containments," presents the results of the staff's evaluation of SRV loads. In response to Question 220.15 (Section 3.8.3) of the PSAR review, we stated that SRV hydrodynamic loads are considered and will be defined using the methodology as described in GESSAR H to the satisfaction of the NRC staff.

Appendix B of NUREG-0802 gives acceptance criteria for Mark III plants using the GE cross-quencher device. Th. S/HNP utilizes the GE cross-quencher device. Appendix B of NUREG-0802 essentially adopts the load definition procedures described in Attachment A to Appendix 3B of GESSAR H, Revision 1. It is our understanding therefore, that conformance to GESSAR II will meet the intent of NUREG-0802. Details of conformance of the S/HNP to the NRC staff requirements will be incorporated in the FSAR.

Pool Temperature Limits NUREG-0783, " Suppression Pool Temperature Limits for BWR Containments" presents the results of the staff evaluation of the safety issue of suppression pool temperature i limits. Acceptance criteria for the pool temperature limits, the events and associated at:sumptions used to analyze pool temperature response, and the suppression pool temperature monitoring systems are included. The resolution applies to Mark III containments such as S/HNP using the SRV cross-quencher device.

Consistent with our commitment to follow GESSAR H, we believe that we will meet the intent of NUREG-0783 and specific plant-unique analysis will be provided in the FSAR as required.

Inplant Testing l NUREG-0763, " Guidelines for SRV Inplant Testing", presents guidance that the NRC

Staff believes should be followed in formulating test programs for In plant Safety-relief l Valves.

A number of inplant tests for other Mark III plants will have been performed prior to the need for testing at S/HNP and it is our intent to take full advantage of these test results. Section 4 of NUREG-0763 states that inplant tests will continue to be required 1

in those plants in which parameters potentially affecting SRV-discharge performance i

are deemed to be plant unique. The staff goes on to say that applicant's may be able to demonstrate that discharge conditions in thier plants are sufficiently similar to conditions previously tested to obviate the need for any new tests or to curtail the scope of new tests.

E _ _ _ _.- - _ _ _ _ _. _ __ _ _ _ _ _ _ _ _ _ _ . . . _ _ _ _ _ _ _ _

Attachment to PLN-275 Section 9 states that for Mark HI applicants the test program should be documented during Final Safety Analysis Reports (FSAR) review. We will address NUREG-0763 at the time of filing the FSAR for S/HNP. In the event that testing is not proposed, justification will be provided using the additional guidelines specified in Section 4.

l f

SKAGIT/HANFORD NUCLEAR PRCUEt'l December 8,1982

• DATe NRC Service List Docket Nos. STN 50-522 and STN 50-523 COctISSIOte NRC STAFF , APPLICANTS (cont . )

Secretary of the m - ission Lee Scott Dewey, Esq. Warren C. Hastings, Esq.

Docketing and Service Branch Counsel for the NRC Staff . Associate Corporate Counsel U.S. Nuclear Regulatory Commission Cffice of the Executive Legal Portland General Electric Company Washington, D.C. 20555 Director 121 S.W. Salmon Street U.S. Nuclear Regulatory Comunission Portland, OR 97204 LICENSING BOARD Washington, D.C. 20555 Richard D. Bach, Esq.

John F. Wolf, Esq., Chairman INTERESTED STATES AND COUNTIES Stoel, Rives, Boley, Fraser & Wyse Administrative Judgt. 2300 Georgia Pacific Bldg.

Atomic Safety and Lice'Ising Board Washington Energy Facility 900 S.W. Fifth Avenue 3409 Shepherd Street Site Evaluation Council Portlard OR 97204 Chevy Chase, MD 20015 Nicholas D. lewis, Chairman Mail Stop PY-ll OrrHER Dr. Frank F. Hooper Olympia, WA 98504 Administrative Judge Nina Bell, Staff Intervenor Atomic Safety and Licensing Board Kevin M. Ryan, Esq. Coalition for Safe Power School of Natural Descurces Washington Assistant Attorney Suite 527, Governor Bldg.

University of Michigan General 408 S.W. Second Avenue Ann Arbor, MI 48190 Temple of Justice Purtland, OR 97204 Olympia, WA 98504 Mr. Gustave A. Linenberger Ralph Cavanagh, Esq.

Administrative Judge Frank W. Ostrander, Jr., Esq. h* ural Resources Defense Council Atomic Safety and Licensing Board Oregon Assistant Attorney General 25 Kearny Street U.S. Nuclear Regulatory Cosuaission 500 Pacific Building San Francisco, CA 94108 Washington, D.C. 20555 520 S.W. Yamhill Portland, OR 97204 Terence L. Thatcher, Esq.

APPEAI. BOARD NWF and OEC Bill Sebero, Chairiman 708 Dekum Bldg.

Stephen F. Ellperin, Esq., Chairman Benton County comunissioner 519 S.W. Wird Avenue Atomic Safety and Licensing P.O. Box 470 Portland, OR 97204 Appeal Board Prosser, WA 99350 U.S. Nuclear Regulatory Cosuaission Robert C. Iothrop, Esq.

Washington, D.C. 20555 APPLICAWrS Attorney for Columbia River Inter-Tribal Fish Commission Christine N. Kohl . F. 'Iheodore Thomsen, Esq. Suite 320 Atomic Safety and Licensing Perkins, Cole, Stone, 8383 N.E. Sandy Blvd.

Appeal Board Olsen & Williams Portland, OR 97220 U.S. Nuclear Regulatory Commission 1900 Washington Bldg.

Washington, D.C. 20555 Seattle, WA 98101 James B. Hovis, Esq.

Yakima Imilan Nat ion Dr. Reginald L. Gotchy David G. Powell, hq. c/o Hovis, Cockrill & Roy Atomic Safety and Licensir>J Iowenstein, Newrsan, Reis & Axelrad 316 North Third Street Appeal Board 1025 Connecticut Avenue N.W. P.O. Box 487 U.S. NL ' lear Regulatory Comunission Washington, D.C. 20036 Yakima, WA 98907 Washington, D.C. 20555 James W. Durham, Esq. Canadian Consulate General Senior Vice President Donald Martens, Consul General Counsel and Secretary 412 Plaza 600 Portland General Electric Company 6th and Stewart Street 121 S.W. Salmon Street Seattle, WA 98101 Portland, OR 97204 10-12-82

• e