ML20054J032

Forwards Final Duplicate Design Approval W/Topics Considered Outside Scope of Design Approval Listed.Review Schedule Will Not Be Advanced Due to Significant Time Until Const Completion

ML20054J032
Person / Time
Site:	Braidwood
Issue date:	06/16/1982
From:	Eisenhut D Office of Nuclear Reactor Regulation
To:	Stiede W COMMONWEALTH EDISON CO.
References
NUDOCS 8206250398
Download: ML20054J032 (7)

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Docket File bcc: TERA L8#1 Rdg. PDR JUN 16122 JYoungblood LPDR MRushbrook NSIC KKiper ACRS(16)

SChesnut Docket Hos.: STM 50-456' DEisenhut and STN 50-457 SHanauer RMattson m Mtj ,

JKramer 3 Mr. Wayne L. Stiede RVollmer C j q Assistant Vice President RHartfield, MPA '

C D Conmorwealth Edison Company OELD-DHassel/JSc &

O. 'O e Ato%M',? " f Post Office Box 767 OIE ~ 9 Chicago, Illinois 60690 Mp, #7p

Dear Mr. Stiede:

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Subject:

Braiducod Station, Units 1 and 2, SER Scope and Schedule 4 Ird \

Your 11 arch 16,1982 letter to Harold R. Denton provided your description of the extent of duplication between the Byron and Braidwood Stations and proposed a Braidwood safety review that would be of reduced scope and schedule in canoarison to that of Byron.

We have reviewed Attachment A to your letter in which you list the Braidwood site-specific FSAR infomation. This information was reviewed in preparation of the staff's Final Duplicate Design Approval (F00A) for the Byron Station design, which we have enclosed in this letter. Appendix A to this FDDA is the staff's determination of the topics that are outside the scope of the FDDA. In general, this list includes the items you listed. However, we have also included utility-oriented items, such as procedures and organization, which, while they may be the same for Byron and Braidwood, are considered to be administrative and not part of a duplicate design.

The F00A documents the staff's approval of the Byron design for duplication and is applicable to the Braidwood Station, in accordance with 10 CFR Part 50, Appendix N and the Commission's Standardization Policy of August 31, 1978. The approved Byron standardized design will be used and relied upon by the staff during its safety review of Braidwood, subject to the conditions listed in the FDDA.

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The present schedule for the Braidwood SER is Decerher,1983 which is based upon allowing 16 months from the SER publication to the projected fuel load da te. We have determined that it would not be appropriate to advance the Braidwood review schedule because of the significant time until construction completion. If you wish to meet with the staff to discuss these matters further, please contact the Braidwood project manager, Kenneth Kiper (301/492-7037).

Sincerely,

,e by 10 Darrell G. Eisenhut, Director

[S Division of Licensing Office of Huclear Reactor Regulation

Enclosure:

As stated cc: See next page

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Mr. Louis 0. DelGeorge Director of Nuclear Licensing Commonwealth Edison Company Post Office Box 767 Chicago, Illinois 60690 cc: Mr. William Kortier Atomic Power Distribution Westinghouse Electric Corporation Post Office Box 355 Pittsburgh, Pennsylvania 15230 .

Paul M. Murphy, Esq.

Isham, Lincoln & Beale One First National Plaza 42nd Floor Chicago, Illinois. 60603 - -

C. Allen Bock, Esq.

Post Office Box 342 .

Urbana, Illinois 61801 ,

Thomas J. Gordon, Esq.

Waaler, Evans & Gordon 2503 S. Neil Champaign, Illinois 61820 Ms. Bridget Little Rorem Appleseed Coordinator ,.

117 North Lin' den Street Essex, Illinois 60935 .

Mr. Edward R. Crass -c Nuclear Safeguards and Licensing Division Sargent & Lundy Engineers .

55 East Monroe Street Chicago, Illinois 60603 U.. S. Nuclear R.egulatory Commission Rdsident> Inspectors Office RR#1, Box 79 Braceville, Illinois 60407 Mr. James G. Keppler U. S. NRC, Region III -

799 Roosevelt Road Glen Ellyn, Illinois 60137 e

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l COMMONWEALTH EDIS0N COMPANY DuCKET NOS. 50-454, 455, 456, 457 Byron Station Duplicate Design j Final Duplicate Design Approval (FDDA) l i

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1. The Commonwealth Edison Company has submitted to the Nuclear Regulatory Commission's (NRC) staff for its review a proposed design for major

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portions of a nuclear power reactor and associated balance of plant which may be duplicated or replicated at different sites by one or more utility appl icants. The design is described in the Byron /Braidwood Station Final Safety Analysis Report (FSAR) along with 37 amendments thereto.

2. The Byron /Braidwood FSAR contains standardized design infomation in accordance with 10 CFR Part 50, Appendix N, for licenses to operate power reactors of duplicate design at multiple sites. The duplicate design encompasses the nuclear steam supply system, balance of plant systems as well as associated auxiliary systems. The Byron reference design is designed to operate at a core themal power level of 3425 megawatts.

3. The Byron reference design has been reviewed by the NRC staff and by the Advisory Committee on Reactor Safeguards (ACRS) for specific application to the Byron site in Ogle County, Illinois. The results of the NRC staff evaluation of the Byron references design are presented in the Safety Evaluation Report (SER) (NUREG-0876) dated February 1982. The ACRS comments are set forth in its letter of March 9,1982 ( Appendix G of NUREG-0876, Supplement 1).

4. Based on its review, and the findings set forth in Section 23 of the SER, the NRC staff haPconcluded that subject to the conditions set forth herein, the infomation provided in the Byron /Braidwood FSAR with respect to the major portions of the design encompassed by the Byron /Braidwood FSAR as they apply to the Byron Station, complies with the requirements of 10 CFR Part 50, Appendix N and the NRC's " Statement on Standardization of Nuclear Power Plants", dated August 31,1978, (43FR38954) and is acceptable for incorporation by reference in applications for operating licenses. In accordance with the above and subject to the conditions set forth herein. ,..

the approved Byron ' standardized design shall be utilized and relied upon by the staff in its review of duplicated or replicated plants which incorpor-ates by reference the approved design, unless there exists significant new infomation which substantially affects the detemination set forth in this Final Duplicate Design Approval or other good cause.

5. Duplicate or Replicate plant applications which incorporate the standard Byron design may be reviewed to evaluate the compatibility of the design with site-related characteristics; changes to the duplicate plant design; the status of matters identified for the duplicate plant design in the SER and Supplements thereto, or matters subsequently identified by the Advisory Committee on Reactor Safeguards, or during public hearings on applications referencing the duplicate plant design. Differences between major contractors

and the manner in which any duplicate plant conforms to the Commission's regulations which have become effective since the issuance of the FDDA may also be reviewed by staff for duplicate or replicate plants which incorporate the Byron design.

6. This Final Duplicate Design Approval is applicable to those systems and design features of the design described and evaluated in Sections 1 through 18 of the Byron SER. Those systems listed in Appen' dix A to this FDDA are not within the scope of the duplicate design and are not included in this Final Duplicate Design Approval.

7. This Final Duplicate Design Approval and all constructions permit and operating license applications incorporating it by reference, are subject to all applicable provisions of the Atomic Energy Act of 1954, as amended, and the rules and regulations and Orders of the Commission now or hereafter in effect. >

8. This Final Duplicate Design approval does not constitute a commitment to issue a permit or license or in any way affect the authority of the Commission, Atomic Safety and Licensing Appeal Board, Atomic Safety Licensing Boards and other presiding officers in any proceeding under Subpart G of 10 CFR Part 2.

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Appendix A Systems / Topics Not Included in FDDA (in SER Sections 2 through 18)

I. Site-related matters, including:

1. Site investigation program including geography and demography, geology-seisnology, foundation engineering, hydrology, and meteorology (Sections 2.1 - 2.5);

2. Site-related design criteria, such as wind and tornado loadings (Section 3.3), flood level (Section 3.4), missile protection (Section 3.5), and seismic design (Section 3.7);

3. Radiological consequences of accidents (Sections 6.4 and 15.4).

4. Radioactive releases - liquid (Section 11.2) and gaseous effluents (Section 11.3).

II. Changes from the Byron Station design, including:

1. Offsite power systems (Section 8.2);

2. Water systems - ultimate heat sink (Section 9.2);

3. Pumphouse ventilation system (Section 9.4.6), pumphouse diesel generator fuel oil system (Section 9.5);

4. Circulating water system (Section 10.4.5);

III. Utility-oriented safety related matters, including -

1. ALARA policy (Sections 12.1.1 and 12.1.3);

2. Radiation protection organization and procedures ,.. .

(Section 12.5.1 and 12.5.3);

3. Organizational structure (Section 13.1);

4. Operator traini.ng (Section 13.2);

5. Emergency plan (Section 13.3);

6. Operational review (Section 13.4);

7. Plant procedures (Section 13.5);

8. Industrial security (Section 13.6); .

9. Quality assurance (Section 17);

2-IV. Other items, including

1. RCPB materials and reactor vessel materials (Sections 5.2 and 5.3);

2. Inservice inspection program (Section 6.6);

3. Fire protection program (Section 9.5.1);

4. Secondary water chemistry program (Section 10.3.3);

5. Plant shielding (TMI Item II.B.2) (Section 12.3);

6. Initial test program (Section 14);

7. Human factors review (Section 18);

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