ML20071Q310

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Forwards Response to NRC ,Question 640.2,re SER Outstanding Issue 21,Section 13.5.2.2 on Reanalysis of Transients & Accidents & Development of Emergency Operating Procedures.Submittal Suppls 821116 Response
ML20071Q310
Person / Time
Site: Perry  FirstEnergy icon.png
Issue date: 12/21/1982
From: Edelman M
CLEVELAND ELECTRIC ILLUMINATING CO.
To: Youngblood B
Office of Nuclear Reactor Regulation
References
IEB-80-17, NUDOCS 8212290305
Download: ML20071Q310 (2)


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THE CLEVELAND ELECTRIC ILLUMIN ATING COMPANY P.o. box 97 m P ERRY. OHIO 44081 5 T EL EPHoNE (216) 259-3737 5 ADD RESS-10 CENT E R Ro AD Semng The Best Location in the Nation December 21, 1982 Air. B. 3. 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; 50-441 Additional Information on SER Outstanding Issue No. 21

Dear Air. Youngblood:

This letter and its attachment is provided in response to your letter of September 8,1982. This supplements our letter of November 16, 1982, regarding SER Out-i standing Issue No. 21 (SER Section 13.5.2.2, Reanalysis of Transients and Accidents; Development of Emergency Operating Procedures).

In the attachments to our letter dated November 16, 1982, we omitted the response to 640.2. Our response to 640.2 is attached herewith.

If you have any questions, please contact me.

Very truly yours, Aiurray R. Edelman Vice President Nuclear Group N1RE:mb cc: Jay Silberg, Esq.

John Stefano Alax Gildner Jim Clifford R. Stratman 8212290305 021221 PDR ADOCK 05000440 E

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640.2 Provide your Reactivity Control (ATWS) procedure. The procedure should meet the requirements of IE Sulletin 80-17, " Failure of Control

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Rods to insert During a Scram at a BWR".

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RESPONSE

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Revision 2 of the Emergency Procedure Guidelines incorporated the requirements 1

j for reactivity control in abnormal plant conditions including a failure of the scram

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system. Thus, there will not be a Reactivity Control Procedure as such. Rather, i

such procedures are addressed as part of the Plant Emergency Instructions which I

i are currently in preparation as outlined in the response to 640.1 above. The requirements of IE Bulletin 80-17 " Failure of 76 of 185 Control Rods to Fully insert During a Scram at a BWR" have been incorporated in Rev. 2 of the Emergency j

Procedure Guidelines.

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