ML20154L047

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Documents Understanding of NRC Forwarding Safety Evaluation Re Elimination of Dynamic Effects of Postulated Primary Loop Pipe Ruptures from Design Basis of Facility. Util Analyses Indicate Compliance w/10CFR50,App a & GDC-4
ML20154L047
Person / Time
Site: Crane Constellation icon.png
Issue date: 05/12/1988
From: Wilson R
GENERAL PUBLIC UTILITIES CORP.
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
5000-88-1554, C311-88-2040, NUDOCS 8805310131
Download: ML20154L047 (2)


Text

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p GPU Nuclear Corporation a s ppany New Je sey 07054 201-316-7000 TELEX 136-482 Wnter's Direct Dial Number:

C311 2040 5000-88-1554 May 12, 1988 U.S. Nuclear Regulatory Comission Attention : Document Control Desk Washington, D.C. 20555 Gentlemen :

Three Mile Island Nuclear Station, Unit 1 (TMI-1)

Operating License No. DPR-50 Docket No. 50-289 Asymetric LOCA Loads / Leak Before Break Analysis (TAC 65003)

The purpose of this letter is to document our understanding of your letter dated November 5,1987, which forwarded the NRC Safety Evaluation relating to the elimination of dynamic effects of postulated primary loop pipe ruptures from the design basis of TMI-1.

It is our understanding that your letter and safety evaluation of November 5, 1987, conclude that GPUN has provided sufficient analyses and controls to adequately demonstrate that the the TMI-l primary loop piping complies with GDC-4 of 10 CFR 50 Appendix A and, as such, the dynamic effects of postulated primary loop piping ruptures may be eliminated from the TMI-1 design basis.

These analyses and controls were contained in our submittals of March 20, 1987 (5211-87-2071) and August 21, 1987 (5211-87-2163).

GPUN considers that all NRC staff requirements have been fully satisfied by these submittals.

As a point cf technical clarification, GPUN believes that TMI-l is not limited nor restricted by the use of the material "J,ti" in its current or near term future Leak Before Break (LBB) evaluations.

GPUN does not believe that the use of JM was inappropriate and, as such, will continue to rely on the analysis which uses Jg. as specifieri in our sutmittals, to demonstrate compliance with the revised GDC-4 of 10 CFR 50 Appendix A.

GPUN recognizes that the staff's independent analysis to verify our results used the more conservative material "J ".

It is noted that both GPUN and NRC analyses 1

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a US Nuclear Regulatory Commission Page 2 reached the same conclusion; that by using the approach defined in Volume 3 of NUREG 1061, it is justifiable to eliminate the dynamic effects of postulated primary loop piping ruptures from the TMI-l design basis. GPUN will continue to participate in industry and professional activities (such as ASME Code Committees) to monitor the ongoing dialogue concerning the appropriate use of material JM versus material J -

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F,. Wil on Vice Presi ent and Director, Technical Functions RFW/JA:fg i

cc:

T. Murley W. Russell R. Conte R. Hernan 1

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