ML20052C023

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Forwards Plant Unique Analysis Rept, Vols 1-5,per SER Requirements.Rept Describes Analyses Conducted for Suppression Chamber,Vent Sys,Suppression Chamber Internals & Safety Relief Valve Discharge Piping Per NUREG-0661
ML20052C023
Person / Time
Site: Fermi DTE Energy icon.png
Issue date: 04/30/1982
From: Tauber H
DETROIT EDISON CO.
To: Tedesco R
Office of Nuclear Reactor Regulation
Shared Package
ML20052C024 List:
References
RTR-NUREG-0661, RTR-NUREG-0798, RTR-NUREG-661, RTR-NUREG-798 EF2---56-942, NUDOCS 8205040274
Download: ML20052C023 (2)


Text

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Vc resident Engmeereg and Construction Dehoit Edison FE75==

April 30, 1982 EF2 - 56,942

/ 9 4 Mr. R. L. Tedesco .g, Assistant Director for Licensing Division of Licensing O ggO Spb/

U. S. Nuclear Regulatory Commission Washington, D. C. 20555 L- [g 4Pg d 7

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Dear Mr. Tedesco:

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References:

(1) Enrico Fermi Atomic Power Plant, Unit 2 NRC Docket No. 50-341 (2) NUREG-0798, " Safety Evaluation Report, Enrico Fermi Atomic Power Plant, Unit No. 2", July, 1981 and Supplement No. 1, September, 1981 (3) NUR EG-06 61, " Safety Evaluation Report, Mark I Containment Long-Term Program", July, 1980 (4) NRC Letter, March 23, 1982, B. J.

Youngblood to H. Tauber, " Review of Fermi 2 Containment Analysis"

Subject:

Submittal of Plant Unique Analysis Report Enclosed please find 39 copies of Volumes I through V of the Fermi 2 Long Term Program Plant Unique Analysis Report (LTP-PUAR). This submittal is for your review and responds to Staff requirements provided in SER Sections 3 8.1, 3.8.2 and 3 9 3 and SER Supplement No. 1 Section 3.8.4 and 3 9 3 (see Reference 2).

This LTP-PUAR describes the analyses which have been conducted for the Fermi 2 suppression chamber, vent system, suppression chamber internals and safety

, relief valve discharge piping. The Staff's criteria set forth in NUREG-0661 (see Reference 3) has been used in these analyses as a basis for acceptance of analysis methods and results.

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,,v c-R. L. Tedesco April 30, 1982 EF2 - 56,942 Page 2 The remainder of the Staff's requirements provided in SER Sections 3 8.1, 3.8.2, and 3 9 3, and SER Supplement No. 1 Section 3.8.4, 3 9 3 and 3 10 will be submitted in separate reports. The schedule for sub-mittal of the remaining information needed for the Staff to complete its review of the Fermi 2 containment analysis, and analysis of piping and equipment asso-ciated with the containment, was discussed with thn Staff in a meeting on March 11, 1982 and subsequently summarized in the Reference 4 NRC letter.

The reference 4 NRC letter requires the submittal of a report on the safety relief valve (SRV) control system modifications required to limit the containment hydro-dynamic loads due to safety relief valve operations.

The design parameters of the SRV control system are determined by the Fermi 2 primary system analyses, which are currently underway. Preliminary primary system analysis results did not indicate the absolute need for modifications to the SRV control system.

Edison is proceeding to finalize the primary system analysca, and in parallel, evaluating the safety aspects of potential control system modifications.

The results and conclusions of the enclosed LTP-PUAR will not be affected by the results of the final pri-mary system analysis, or any future commitment by Edison to modify the SRV control system. Edison will submit a report to the Staff when these evaluations are complete.

If you have any questions, please contact Mr. L. E.

Schuerman (313-649-7562).

Sincerely,

/

Enclosures cc: L. L. Kintner J. Ranlet (Brookhaven National Laboratories)(w/2 enclosures)

W.'Seagraves (Franklin Research Institute)(w/1 enclosure) l..._