ML20069H807

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Informs of Pipe Stress & Support Analyses for 10 Safety Relief Valve Discharge Lines Re SER Issue II.D.1, Safety Relief Valve Test Program, Per NRC 820708 Request.All Pipe Stresses & Support Loads within Design Allowables
ML20069H807
Person / Time
Site: Shoreham File:Long Island Lighting Company icon.png
Issue date: 04/06/1983
From: James Smith
LONG ISLAND LIGHTING CO.
To: Harold Denton
Office of Nuclear Reactor Regulation
References
SNRC-868, NUDOCS 8304120230
Download: ML20069H807 (3)


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LONG ISLAND LIGHTING COMPANY l

j SHOREHAM NUCLEAR POWER STATION L-mmwM P.O. BOX 6 fis, NORTH COUNTRY ROAD e WADING RIVER, N.Y.11797 D' nt Dial Number m

April 6, 1983 SNRC-868 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C.

20555 SER Issue II.D.1 - SRV Test Program Shoreham Nuclear Power Station - Unit 1 Docket No. 50-322

Reference:

(1)

Letter NRC (Mr. A.

Schwencer) to LILCO (. r. M.

S.

M Pollock) dated July 8, 1982 (2)

Letter SNRC-812, dated December 15, 1982

Dear Mr. Denton:

In response to the reference (1) letter for additional information on the Safety Relief Valve (SRV) Operability Test Program Results, and their applicability to the Shoreham SRVs, the reference (2) letter (with attachments 1 and 2) was submitted to provide all pertinent information requested.

It was stated that all drywell piping and one wetwell SRV discharge line had been analyzed and found to be well within design allowables.

It was also stated that for completeness the remaining 10 SRV discharge lines in the wetwell would also be analyzed.

The pipe stress and support analyses for the remaining 10 SRV dis-charge lines have been performed to include the effect of the dynamic fluid forces from the alternate shutdown cooling mode liquid discharge, the deadweight of the water in the lines, the concurrent thermal effects, and the effect of an assumed concurrent safe-shutdown earthquake.

As expected, all pipe stresses and support loads were well within design allowables.

The verification that the Shoreham SRV discharge piping is adequately supported to sustain the effects of a low pressure liquid discharge 8304120230 030406

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Z April 6, 19'83 2

Mr.: Harold R.,Denton

. SNRC-868 is therefore complete.

Based on the supplemental information provided herein, we;believe the staff.has sufficient'information to complete their review of this issue.

Should you have any questions, please' contact ~this office.

L.

- 1 J.

L.

Smith Manager, Special Projects Shoreham Nuclear Power Station RWG:bc cc: ;J. Higgins

' All Parties Listed'in' Attachment 1

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4 ATTACll??ENT 1 Lawrence Brenner, Esq.

11erbert 11. Brokm, 'Esq.

Administrative Judge Lawrence Coe Lanpher, Esq.

. Ato aic Safety and Licensing Karla'J. Letsche, Esq.

Board Panel Kirkpatrick, Lockhart, 11111 U.S. Nuclear Regulatory Commission Christopher & Phillips Washington, D.C.

20555 8th Floor

'1900 M Street, N.W.

Washington, D.C.

20036 Dr.' Peter A. Morris Administrative Judge Atomi.c Safety and Licensing Mr. Marc W. Goldsmith Board Panel Energy Research Group U.S. Nuclear Regulatory Commission 4001 Totten Pond Road Washington, D.C.

20555 Waltham, Massachusetts 02154

- Dr. James 11. Carpenter MilB Technical Associates Administrative Judge 1723 Hamilton Avenue Atomic Safety and Licensing Suite K Board Panel

~ San Jose, California 95125 U.S. Nuclear Regulatory Commission Washington, D.C.

20555 Stephen B. Latham, Esq.

Twomey, Latham & Shea Daniel F.

Brown, Esq.

33 West Second. Street Attorney P.O. Box 398 Atomic Safety and Licensing Riverhead, New York 11901 Board Panel U.S. Nuclear Regulatory Cocmission Washington, D.C.

20555 Ralph Shapiro, Esq.

Cammer and Shapiro, P.C.-

9~ East 40th Street Bernard M.

Bordenick, Esq.

New York, New York 10016 David A. Repka, Esq.

o U.S. Nuclear Regulatory Cort. mission Washington, D.C.

20555-

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Matthew J. Kelly, Esq.

State of New York James Dougherty Departmcht of Public Service i

3045 Porter Street Thrco Empire' State Plaza l

Washington, D.C.-

20008 Albany, New York 12223-D 4

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