ML19318C877

Forwards Amend 26 to FSAR

ML19318C877
Person / Time
Site:	Byron, Braidwood
Issue date:	06/27/1980
From:	Naughton W COMMONWEALTH EDISON CO.
To:	Harold Denton Office of Nuclear Reactor Regulation
Shared Package
ML19318C878	List: ML19318C877
References
NUDOCS 8007020408
Download: ML19318C877 (5)

Text

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je~~'N Commonwealth Edison - - - --

/ ) One First National Plin, Chicigo, Illinois

~ i Address Reply to: Post Office Box 767 Tliis DOCUMENT CO:h A,hata a

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,/ Chicago, Illinois 60690 'P00R QUAUTY M3ES June 27, 1980 Mr. Harold R. Denton, Director Of fice of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555

Subject:

Byron Station Units 1 and 2 and Braidwood Station Units 1 and 2 L

Amendment No. 26, FSAR Amendment, to the Application for Construction Permits and Operating Licenses NRC Docket Nos. 50-454, 50-455, 50-456, and 50-457 References (a): Septem.5er 5, 1979 letter from L. S. Rubenstein to C. Re ad transmitting third set of first.

round que.tions on Byron and Braidwood OL application (b): November 8, 1979 letter from L. S. Rubenstein to D. L. Peoples transmitting fnurth set of first round questions on Byron and Braidwood OL ,

application (c): February 29, 1980 letter from G. Florelli to C.

Reed transmitting IE Inspection Report Nos.

50-456/80-01 and 50-457/80-01 (d): April 28, 1980 letter from L. S. Rubenstein to D. L. Peoples transmitting sixth set of first round questions on Byron and Braidwood OL application (e): March 21, 1980 letter from W. F. Naughton to H.

R. Denton transmitting Byron and Braidwood FSAR Amendment No. 25

Dear Mr. Denton:

The application for construction permits and operating licenses for Byron Station Units 1 and 2 and Braidwood. Station Units 1 and 2, docketed September 20, 1973 in NRC Docket Nos. 50-454, 50-455, 50-456 and 50-457 are hereby amended by submittal of Amendment No. 26 pursuant to Section 50.34 of 10 CFR 50. In 8 0070 2 0 4&F. g* .

1

Mr. -Harold R.- Denton, Director -

June 27, 1980

.Page 2 addition ~to~valuntary text and response revisions, this amendment l contcins Commmonwealth Edison Company responses to a portion of the

-additional first round questions generated by the NRC Staff in References (a) and (b). Also, a change to Appendix A, Regulatory Guide 1.88, is included to satisfy an item raised in Reference (c),

4 an IE Inspection Report.

1 Specifically, this amendment responds to 58 of the 75 Reactor Systems Branch questions of Reference (b) which were renumbered'in Reference (d). Attachment I contains a list of those questions answered in this amendment. Attachment 2 contains a list of those 17 questions unanswered.

In addition, this amendment responds to the Quality Assurance Branch (Initial Test Program) questions (Series 42).0) of Reference (a), a portion of which were answered in Reference (e).

. Those questions answered in this amendment are also listed in

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Attachment 1. Attachment 2 contains those still unanswered and Attachment 3 contains a list of those answered in Amendment No. 25, Reference (e).

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Please. address any questions that you might have concerning this matter to this office.

Three (3) signed originals and fifty-seven (57) copies of this amendment are submitted for your review and approval.

Very truly yours,

(

William F. Naughto Nuclea- L icensing dministrator Pressurized Water Reactors WFN: rap

, Attachments SUBSCRIBED and SWORN to be forege this ,Q~/ -r# , day o f- Qw ,.1980

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. Notary Pu6lic 4'750 l

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NRC Docket Nos. 50-454/455 456/457 ATTTACHMENT 1-List of' Round One Questions Answered

.In Byron /Braidwood FSAR Amendment No. 26 I. Reactor Systems Branch (Series 212.12 through 212.86)

The following questions have been responded to in this amendment:

212.13 212.41 through 212.56

-212.14 212.59 through 212.64 212.18 212.66 through 212.69 212.21 through 212.23 212.71 through 212.78 212.26 through 212.30 212.80 212.32 through 212.39 212.82 through 212.84 212.86 l

II. Quality Assurance Branch (Series 423.1 through 423.21) ihe following questions have been responded to in this amendment:

423.2' 423.15 423.4 423.17 423.12(Parts 13 and 24) l l

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NRC Docket Nos. 50-454/455 50-456/457 ATTACHMENT 2 List of Round One Questions Not Answered In Byron /Braidwood FSAR Amendment No. 26 I. Reactor Systems Branch (Series 212.12 through 212.86)

The following questions will be answered in future FSAR amendments:

212.12 212.40 212.15 through 212.17 212.57 212.19 212.58 212.20 212.65 212.24 212.70 212.25 212.79 212.31 212.81 212.85 II. Quality Assurance Branch (Series 423.0 through 423.21)

The following questions will be answered in future FSAR amendments:

423.12 (Part 23 only) and 423.21 i

il I

NRC Docket Nos. 50-454/455 50-456/457 ATTACHMENT 3 List of Quality Assurance Branch (Series 423.0)

Questions Answercd in Byron /Braidwood FSAR Amendment No. 25 The following Qual.ity Assurance Branch (Series 423.0) questions were answered in Byron /Braidwood FSAR Amendment No. 25:

423.1 '

423.3 423.5 through 423.11 423.12 (Parts 1 through 12 and 14 through 22) 423.13 423.14 423.16 423.18 through 423.20 l