ML20054L486

Forwards Pressurizer & Safety Relief Line Piping & Support Evaluation & Action Plan, Per NRC 810929 Generic Ltr 81-36 & Util 820326 Ltr Re TMI Action Plan Item II.D.1, Relief & Safety Valve Testing.

ML20054L486
Person / Time
Site:	Wolf Creek, Callaway, 05000000
Issue date:	07/01/1982
From:	Petrick N STANDARDIZED NUCLEAR UNIT POWER PLANT SYSTEM
To:	Harold Denton Office of Nuclear Reactor Regulation
Shared Package
ML20054L487	List: ML20054L486 ML20054L493
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.D.1, TASK-TM GL-81-36, SLNRC-82-030, SLNRC-82-30, NUDOCS 8207080168
Download: ML20054L486 (2)

Text

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SNUPPS Standardized Nuclear Unit Power Plant System 5 Choke Cherry Road Nicholas A. Petrick Rockville, Meryland 20850 Executive Director (30H 869 8010 July 1, 1982 SLNRC 82- 030 FILE: 5790 SUBJ: NUREG 0737 Item II.D.1 Mr. Harold Denton, Director Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Docket Nos.: STN 50-482 and STN 50-483

Reference:

1. NRC (Eisenhut) letter to all licensees of operating plants and applicants for opcrating licenses and holders of con-struction permits dated September 29, 1981, Revised Schedule for Completion of TMI Action Plan Item II.D.1, Relief and Safety Valve Testing (Generic Letter No. 81-36).

2. SLNRC 82-017 from SNUPPS, NUREG 0737 Item II.d.1, dated 3/26/82.

3. Letter from R. C. Youngdahl, Consumers Power, to H. Denton, NRC, Submittal of PWR Valve Data Package, dated 6/1/82.

Dear Mr. Denton:

In accordance with the initial recommendations of NUREG 0578, Section 2.1.2 as later clarified by NUREG 0737, Item II.D.1 and the USNRC letter (Ref-erence 1) and extended by Reference 2, each Pressurized Water Reactor (PWR)

Utility is to submit a plant specific report demonstrating that the block valve upstream of the pressurizer power-operated relief valve functions properly over the range of expected operating and accident conditions. The demonstration is to be supported by test data.

Block valve listings and test data, to demonstrate that the block valves function properly over the range of expected operating and accident con-ditions, have been supplied to the NRC in Reference 3. As reported by Westinghouse in the attachment to Reference 3, the stem thrust required to close the valve was underpredicted and resulted in supplying the valve A operator with insufficient force to close the valve. Westinghouse has modified the closing load equations and this modification has been incor-

[f0V porated in the SNUPPS block valve and operator sizing combination.

This submittal completes the SNUPPS documentation on block valve operability.

In addition, SHUPPS stated in Reference 2 that an action plan, based on an evaluation of the Generic PWR Safety and Relief Valve Test Program implemented by the Electric Power Research Institute, would be submitted to the NRC by 7/1/82. This action plan would specifically evaluate the test data as app-licable to the SNUPPS plants. 8207080168 820701 PDR ADOCK 05000482 A PDR _ _ _ _

SLNRC 82-NUREG 0737 Item II.D.1 4

SUBJ:

Page 2.

As a result of the evaluations performed for the SNUPPS plants, attached is the " Pressurizer and Safety Relief Line Piping and Support Evaluation and Action Plan."

This attachment provides an interim evaluation of the piping and m pports for SNUPPS plants along with an action plan for full resolution of all items.

This action plan satisfies the 7/1/82 commitment of Reference 2. The SNUPPS plant specific report for piping support evaluations will be submitted to the NRC by 12/31/82, consistent with the reference 2 commitment.

It is anticipated that an action plan for the plant specific safety and relief valve qualification will not be necessary. The plant specific re-

~

port for safety and relief qualification for SNUPPS is scheduled for sub-mittal by 9/30/82, consistent with the Reference 2 commitment date of

. 12/31/82.

Very truly yours,

, - - ,1

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( - Nicholas A. Petrick J0C/nld Attachment cc: G. L. Koester KGE D. T. McPhee KCPL J. H. Neisler NRC/ CAL U. F. Schnell UE T. E. Vandel NRC/WC 1

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