LD-85-042, Requests That Encl Forward Referenceability Provision Be Included in 850802 Application for Amend to CESSAR Final Design Approval,Per Section 8.3.6(1) of Commission Policy Statement on Severe Reactor Accidents..

Requests That Encl Forward Referenceability Provision Be Included in 850802 Application for Amend to CESSAR Final Design Approval,Per Section 8.3.6(1) of Commission Policy Statement on Severe Reactor Accidents..

ML20134P103
Person / Time
Site:	05000470
Issue date:	08/30/1985
From:	Scherer A ABB COMBUSTION ENGINEERING NUCLEAR FUEL (FORMERLY
To:	Harold Denton Office of Nuclear Reactor Regulation
References
LD-85-042, LD-85-42, STN-50-470F, NUDOCS 8509060135
Download: ML20134P103 (2)

Text

C-E Power Systems Tel. 203/688-1911

m. Combustion Engineenng. Inc. Telex 99297

• 1000 Prospect Hill Road Windsor, Connecticut 06095 H POWERSYSTEMS August 30, 1985 STN 50-470F LD 042 Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555

Subject:

Forward Referenceability

Reference:

C-E letter LD-85-035, A. E. Scherer to H. R. Denton,

" Application for Amendment of the CESSAR Final Design Approval", August 2, 1985

Dear Mr. Denton:

Combustion Engineering is very pleased to see the issuance of the Commission's

" Policy Statement on Severe Reactor Accidents Regarding Future Designs and-Existing Plants". In accordance with Section B.3.b(1) of the policy, Combustion Engineering requests that FDA-2 for CESSAR be amended to permit its reference in new CP and OL applications. The second option in the policy for reference designs which had been previously granted a Final Design Approval states that the request must include a suitable interface requirement to ensure that referencing CP and OL applications will satisfy each of the criteria in Section B.2 of the policy. Such an interface is prosided in the attachment to this letter and will be included in Anendment 11 of CESSAR.

The above Reference recently requested an amendment to the CESSAR FDA. We understand that issuance of the amendment is expected to occur at the end of September. We, therefore, request that the forward referenceability provision be included in that amendment.

If you have any question, please feel free to contact me or Mr. G. A. Davis of my staff at (203) 285-5207.

• Yery truly yours, COMBUSTION ENGINEERING, INC.

m, 8509060135 050830 -

PDR ADOCK050g0 A Director Nuclear Licensing AES: bks Attachment [ON I ll l

1.1.3.3.2 Point Interfaces The physical connections between CESSAR design scope systems and the 80P are designated point interfaces. They are shown by the " flags" on the CESSAR design scope system piping and instrumentation diagrams (P&ID's). Point

interfaces are defined in Categories A, G, H, I, K, N, 0, and P of the individual system interface requirements cections.

! 1.1.3.4 Identification of Relevant Guidance Documents Each system's interface section includes a listing of General Design Criteria (GDC), Regulatory Guides, industry codes and standards which C-E considers relevant to the design of the base system. The GDCs, Regulatory Guides, codes and standards are not impond as interface requirements unless speci-fically identified as such in the individual CESSAR/ BOP interface categories.

1.1.3.5 Severe Reactor Accidents For those System 80 plants that did not reference the CESSAR preliminary design approval in application for a construction permit, the criteria and procedural requirements stated in the 1985 NRC policy statement on severe

! reactor accidents must te met. These requirements are:

a. Demonstration of compliance with the procedural requirements and criteria of the current Comission regulations, including the Three Mile Island requirements for new plants as reflected in the CP Rule [10 CFR 50.34(f)];

b. Demonstration of technical resolution of all applicable Unresolved Safety Issues and the medium-and high-priority Generic Safety Issues, including a special focus on assuring the reliability of decay heat removal systems and the reliability of both AC and DC electrical supply systems;

c. Completion of a Probabilistic Risk Assessment (PRA) and consideration of the severe accident vulnerabilities the PRA exposes along with the insights that may add to the assurance of no undue risk to public health and safety; and

d. Completion of a staff review of the design with a conclusion of safety acceptability using an approach that stresses deterministic engineering analysis and judgement complemented by PRA.

1.1.4 CESSAR ORGANIZATION CESSAR is organized to respond to the Regulatory Guide 1.70, Revision 2

" Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants", September, 1975.

Amendment No. 11 1.1-6 August 30, 1985

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