ML20064C170

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Responds to Requesting Addl Info on Safety Relief Valve (SRV) Piping & Quencher Device.Questions Re Potential Thermal Gradient Stresses in SRV Discharge Pipe Support in Suppression Pool Do Not Affect Util SRV no-test Proposal
ML20064C170
Person / Time
Site: Perry  FirstEnergy icon.png
Issue date: 12/29/1982
From: Davidson D
CLEVELAND ELECTRIC ILLUMINATING CO.
To: Youngblood B
Office of Nuclear Reactor Regulation
References
NUDOCS 8301040337
Download: ML20064C170 (1)


Text

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Gi E C L E V E l. A N D E L E C T R I C ! L L U 'A i N AT l H G C O M P A N Y P.O. BOX 97 5 P ER RY, OHIO 44081 m T EL EPH oN E (216).7.53-3737 m ADD RESS-10 CENTER RO AD Serving The Best Location in the Nation December 29, 1982 Mr. B. J. Youngblood, Chief Licensing Branch No. I Division of Licensing U. S. Nuclear Regulatory Commission Washington, D. C.

20555 Perry Nuclear Power Plant Docket Nos. 50-440; 50-4'.1 SRV Piping and Quencher Device

Dear Mr. Youngblood:

This letter is provided in response to your letter dated December 14, 1982, requesting additional information regarding safety relief valve (SRV) piping and quencher device. The specific questions relative to potential thermal gradient stresses in the SRV discharge pipe support in the suppression pool area do not affect our SRV no-test proposal. These questions will be responded to separately on or before March 15, 1983.

If you have any questions, please let me know.

Very truly yours,

$1 Dalwy R. Davidson Senior Vice President DRD:kh Ol cc:

J. Silberg, Esq.

O J. Stefano M. Gildner D. Terao i 8301040337 821229 PDR ADOCK 05000440 A

PDR