ML20042A232
| ML20042A232 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood, LaSalle, 05000000 |
| Issue date: | 03/19/1982 |
| From: | Schroeder C COMMONWEALTH EDISON CO. |
| To: | Schwencer A Office of Nuclear Reactor Regulation |
| References | |
| 3681N, NUDOCS 8203230230 | |
| Download: ML20042A232 (2) | |
Text
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,,[ CN Commonwealth Edison
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XECElWED March 19, 1982 M 2 81982 > '-
E 88 #ma twa %gg amm ama EC Mr. A. Schwencer, Chie f f
Licensing Branch #2 Division o f Licensing U.
S. Nuclear Regulatory Commission Washington, DC 20555
Subject:
LaSulle County Station Units 1 & 2 Deletion o f Topical Report CE-1-A from FSAR Chapter 17 NRC Docket No. 50-373 and 50-374
Dear Mr. Schwencer:
The purpose o f this letter is to request your approval to delete the tex t o f Commonwealth Edison Topical Report CE-1-A from Chapter 17 of the LaSalle FSAR.
Currently, Chapter 17 o f the LaSalle County Station FSAR contains an outdated version o f Topical Report CE A.
During the life of the station, the Topical Report CE-1-A will be changed and revised numerous times.
Since its submittal in June,1975, the NRC has specifically approved nineteen (19) revisions to this document.
The FSAR, however, will be revised eventually only~on an annual basis.
In order to avoid confusion and assure that anyone referring to the " Commonwealth Edison Company Quality Assurance Program for Nuclear Generating Stations" ( Topical Report CE-1-A) is utilizing an up-to-date document as approved by the NRC, it is requested that you approve deletion of the Topical Report CE-1-A from the tex t o f Chapte r 17.
The enclosed one-page Chapter 17 from the Byron /Braidwood FSAR provides an example tha t the NRC has previously accepted for cther Commonwealth Edison Company Nuclear Stations.
Please contact this of fice if there are any questions in this matter.
Very truly yours, N
3f/9/87 C. W. Schroeder Nuclear Licensing Administrator i
1m I
cc:
NRC Resident Inspector - LSCS Enclosure 6
I 8203230230 B20319
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PDR ADOCK 050003 3 3,
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B/B-FSAR AMENDMENT 22 SEPTEMBER 1979 i
(I CHAPTER 17.0 - OUALITY ASSURANCE The quality assurance program for the Byron and Braidwood Stations is conducted in accordance with the Commonwealth Edison Company Quality Assurance Program for Nuclear Generating Stations.
This program was initially submitted to the Nuclear Regulatory Commission in June 1975, as Topical Report CE-1.
By letter of December 29, 1975, the NRC's Chief of Quality Assurance Branch, Division of Reactor Licensing, informed Commonwealth Edison's Executive Vice President, Mr. W.
B. Behnke, that this Topical Report CE-1 was an acceptable program for the design, procurement, con-struction and operations activities within Commonwealth Edison's scope of work for nuclear power plants.
Instructions were given to reference this Topical Report in Section 17 of License applicati,ons.
Therefore the Commonwealth Edison Topical Report CE-1-A, Revision 7 and all subsequent revisions unless otherwise noted in this chapter, is the basis for the Quality Assurance Program at the Byron /Braidwood Stations.
Section 2.2 of the above referenced topical report provides for compliance with certain regulatory guides and ANSI standards.
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Any exceptions taken to the requirements of these guides are found in Appendix A of this FSAR.
Otherwise, Byron /Braidwood Stations are in compliance with the guides and ANSI standards.
Subsection 3.2.1.1 of the FSAR states that Safety category I systems or portions of systems and components meet the require-ments of Appendix B to 10CFR50.
Those structures, systems, and components classified as Safety Category I, therefore, are under control of the QA program and are listed in Table 3.2-1.
Where only portions of a system are classified as Safety Category I, the P&ID's identify the boundary between Safety Category I and Safety Category II.
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17.0-1 1
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