ML20215F701

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Forwards Control Room Accessibility Procedure PRI-5,per 860930 & 1103 Commitments.Listed Item Re Verification of Main Steam Dump Valves Will Be Corrected in Future Submittal Per Sser 2 (NUREG-1002).W/o Encl
ML20215F701
Person / Time
Site: Byron, Braidwood, 05000000
Issue date: 12/15/1986
From: Hunsader S
COMMONWEALTH EDISON CO.
To: Harold Denton
Office of Nuclear Reactor Regulation
References
RTR-NUREG-1002 2528K, NUDOCS 8612240034
Download: ML20215F701 (2)


Text

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fg 3 One Fwst Nabonal Plaza. Checa00, lHinois 5

/ Address Reply to: Post Omco Box 767 k/ Chica00. IRinois 80000 0767 December 15, 1986 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC. 20555

Subject:

Byron Station Units 1 and 2 Braidwood Station Unit 1 Control Room Accessibility Procedure (PRI-5)

NRC Docket Nos. 50-454. 50-455 and 50-456

Reference:

(a)

September 30, 1986 A.D. Miosi letter to H.R. Denton (b)

November 3, 1986 S.C. Hunsader letter to H.R. Denton (c)

December 12 1986 S.C. Hunsader letter to H.R.

Denton (d)

NUREG-1002 Safety Evaluation Report, Supplement No.

2, dated October, 1986

Dear Mr. Denton:

Reference (a) provided the results of the review for spurious operation of the Reactor Head Vent Valves for Braidwood Unit 1.

Reference (b) provided the same information for Byron Unit 2.

Both letters provided a commitment to change the Control Room Inaccessibility procedure (PRI-5) based upon the results of the review and analysis.

Reference (c) provided a response to Section 9.5.1.4 of NUREG-1002 Supplement No. 2 and provided an advance copy of changes to the PRI-5 procedures for a fire in the Auxiliary Electrical I

Equipment room.

Attached, please find two copies of the PRI-5 procedures, Revision 54, respectively for Byron Station Units 1 and 2 and Braidwood Station Unit 1.

These address the commitments of the above submittals.

Page 10 of 94 of the Braidwood Unit 1 procedure states;

" Locally verify main steam dumps valves el_osed:

IMS003A thru M l

(426' K4 to K8 TB)".

This reference should be IMS004A thru M.

This item will be corrected in a future submittal.

8612240034 861215

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PDR ADOCK 050004S4 PDR E

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. These are being forwarded to you for your review and acceptance.

Please address any questions or comments to this office.

One signed original and fifteen copies of this letter are being provided for your review.

Very truly yours, t

J d

k S.

C. Hunsader Nuclear Licensing Administrator

/klj cc:

J.

Stevens L. Olshan 2528K l

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