ML19268D013

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Forwards Application of SSES-Test Measurement Results to Overall Loading of Suppression Chamber of Shoreham Plant by Depressurization Processes, Revision 1.Encl Withheld (Ref 10CFR2.790) & Available in Central Files Only
ML19268D013
Person / Time
Site: Shoreham File:Long Island Lighting Company icon.png
Issue date: 08/18/1980
From: Novarro J
LONG ISLAND LIGHTING CO.
To: Harold Denton
Office of Nuclear Reactor Regulation
Shared Package
ML19268D014 List:
References
SNRC-494, NUDOCS 8008280349
Download: ML19268D013 (1)


Text

,

I LONG ISLAND LIGHTING COM PANY FLt*O a,affag ,

SHOREHAM NUCLE AR POWER STATION P.O. BOX sib. NORTH COUNTRY RO AD e WADING RIVE R. N.Y.11792 August 18, 1980 SNRC-494 j Mr. Harold R. Denton, Director .

Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 SHOREHAM NUCLEAR POWER STATION - UNIT 1 DOCKET NO. 50-322

Dear Mr. Denton:

Enclosed are fifteen (15) copies (five bound, remainder unbound) of the lead plant generic report entitled " Application of the SSES-Test Measurement Results to the Overall Loading of the Suppression Chamber of the Shoreham Plant by Depressurization Process - Revision 1" prepared by Kraftwerk Union for Long Island Lighting Company. This submittal represents the comple-tion of our commitment to submit information on the lead plant ~

generic T-quencher load definition program discussed with the NRC Staff and consultants on June 13, 1980 and confirms the preliminary copy of this repore given to Mr. Tsung Ming Su of th.e NRC Staff on June 19, 1980. Differences between this submittal and the preliminary version are limited to editorial

. changes or corrections. It is aur understanding that NRC Staff' are presently reviewing this material and expect to include the lead plant generic T-quencher methodology in a future NUREG as an alternative method for calculating air clearing loads in a Mark II, KWU T-quencher plant.

Please note that this material contains confidential information and trade secrets and will be included in the Proprietary Supple-ment to the Shoreham Plant Design Assessment for SRV and LOCA Loads (Design Assessment Report - DAR) upon completion of the NRC review. Accordingly, we are requesting the Staff to with-hold this report from public disclosure pursuant to the Affidavit prepared under 10 CFR 92.790(b) and submitted by our letter SNRC-352 dated December 29, 197S. g j 5

Very dbul yours, /[/3' '

) cQt 4o dt c y-

, U' /W% LPoR arro, PDR

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J. P. N Proj e ct' Manager 74,c Shoreham Nuclear Iower Station JEM/cc Enclosures cc: J. Higgins (NRC) 8 0'dTh so 3 @ h