ML20050B578

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Submits Preliminary Assessment of EPRI PWR Safety & Relief Valve Test Program & Potential Effects of Testing,Per NUREG-0737,Item II.D.1
ML20050B578
Person / Time
Site: Crystal River Duke Energy icon.png
Issue date: 03/31/1982
From: Mardis D
FLORIDA POWER CORP.
To: Eisenhut D
Office of Nuclear Reactor Regulation
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.D.1, TASK-TM 3F-0382-33, 3F-382-33, NUDOCS 8204060083
Download: ML20050B578 (2)


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M Power C O R P O a a t e n se March 31,1982

  1. 3F-0382-33 File: 3-0-26 Mr. Darrell G. Eisenhut, Director Division of Licensing Office of Nuclear Reactor Regulation  ;

U.S. Nuclear Regulatory Commission @ 4 Washington, D.C. 20555 Ss . g

Subject:

Crystal River Unit 3 Docket No. 50-302 f/

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Operating License No. DPR-72 U % N,_I98 h $

NUREG-0737, Item II.D.1 4/fG D?y&

"; J Safety and Relief Valve Testing Program .s g,

Dear Mr. Eisenhut:

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In accordance with NUREG-0737, Item II.D.1 (as revised by your letter dated September 29, 1981) Florida Power Corporation hereby submits our preliminary assessment of the EPRI PWR Safety and Relief Valve Test Pro-gram and the potential effects that this testing may have on Crystal River Unit 3 (CR-3).

Output to date of the EPRI program which are of interest and are applic-able are:

a) Valve Selection / Justification Report, b) Test Condition Justification Report, c) B&W Plant Condition Justification Report, and d) Safety and Relief Valve Test Report.

These documents have been transmitted to you by Mr. David Hoffman of Consumers Power Company on behalf of the participating PNR utilities and are incorporated by reference herein as part of our preliminary response.

In December, 1981, and August, 1981, testing of Safety and Relief t[h Valves, respectively, was completed per the scope of the aforenantioned #

EPRI Program. Based on preliminary review of these results, a 1eneral evaluation has been performed on a plant specific basis and the tollow-hg assessments have been made: 1D

1) Results of the relief valve testing conducted at the Marshall Steam Electric Station and the Wyle/Norco facility indicate, preliminarily, that generally f avorable performance can be
realized under all conditions. Items which may be discovered, during a more detailed review of tests will be evaluated and reported by July 1,1982.

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Darrell G. Eisenhut March 31, 1982 -

Page 2

2) Safety valve testing for the Dresser valves was performed very late in the EPRI program, and, as a result, only a very pre-liminary assessment can be reported at this time. Several items of potential concern have been identified and are under active consideration at this time. It is anticipated, that these items can be resolved in a satisfactory manner, and it is hoped that these items will be resolved to allow incorpora-tion in a July 1,1982, submittal. However, a specifically defined schedule supporting that date is not complete at this time. As the specific items and their respective schedules are formulated, they will be reported to you in a timely manner, prior to July 1,1982.
3) Discharge piping and support evaluations, as reported to you in our August 7, 1981, letter, were performed for Crystal River Unit 3 subsequent to our February 26, 1980 transient.

Our preliminary review of the EPRI valve testing results has shown nothing which would invalidate this analysis. These analyses should satisfy your concern related to the valve operability / discharge piping interface.

Based on the above, FPC's preliminary review has indicated that the per-formance of the safety and relief valves and the associated discharge piping and supports is generally acceptable. Specific items of interest will be further evaluated and resol ved in a manner consistent with prudent criteria to assure that the operation of CR-3 with regard to the health and safety of the public is maintained.

If you have any questions and/or comments, please advise this office.

Very truly yours,

& S MA David G. Mardis Acting Manager Nuclear Licensing Cook (M01)C4-3 cc: Mr. J. P. O'Reilly Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission 101 Marietta St. N.W., Suite 3100 Atlanta, Georgia 30303

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