ML20137U660

Forwards Addl Info Per NUREG-0737,Item II.D.1 Re Pressurizer Safety Valve Upper Level Position in Response to Question 9. Review by Crosby Valve & Gage Co Shows Attached Ring Setting Info Correct

ML20137U660
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	02/13/1986
From:	Withers B PORTLAND GENERAL ELECTRIC CO.
To:	Varga S Office of Nuclear Reactor Regulation
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.D.1, TASK-TM TAC-51292, NUDOCS 8602190282
Download: ML20137U660 (4)

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m mmme 3 M b1ptzW But D Wahers Vco P esdert February 13, 1986 Trojan Nuclear Plant Docket 50-344 License NPF-1 Director of Nuclear Reactor Regulation ATTN: Mr. Steven A. Varga Director, PWR-A Project Directorate No. 3 U.S. Nuclear Regulatory Comission Washington DC 20555

Dear Mr. Varga:

Request for Additional Information NUREG-0737. Item II.D.1

Reference:

PGE (B. D. Withers) to NRC (S. A. *varga) Letter Dated December 31, 1985 In the referenced letter, it was stated that additional information regard-ing pressurizer safety valve upper ring level position was being sought from Crosby Valve and Cage Company.In response to Question 9. The informa-tion is attached. In addition, a review by Crosby of their records shows the attached ring setting information to be correct, superseding the previously reported data.

If you have any questions, please advise.

Sincerely,

.W hP' Vice President Nuclear Attachment

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c: Regional Administrator, Region V U.S. Nuclear Regulatory Commission AD - J. KNIGIIT (ltr only)

Office of Executive Director for Etl (II ALLARD )

Operations EICSB (ROSA) 1450 Maria Lane, suite 210 Pstl ( GA.OlI LL )

Walnut Creek CA 94596 Rsn (I1ERLINGER)

Mr. Lynn Frank, Director State of Oregon Department of Energy 86021902B2 860213 PDR ALDCK 05000344 g%

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Trojan Nuclear Plant Mr. S. A. Varga Docket 50-344 February 13, 1986 License NPF-1 Attachment Page 1 of 2 ADDITIONAL INFORMATION RECARDING SAFETY VALVE RING SETTINGS The Trojan pressurizer safety valve ring setting information is listed in Table 1.

The safety valve ring settings remain those that were as shipped from Crosby. The EPRI testing gave positions of the two adjusting rings in terms of notches relative to the level position. However, the field settings as shipped by Crosby are given in terms of notches relative to the highest-locked position. For the lower ring, the highest-locked position coincides with the level position. However, for the upper ring, the level position and highest-locked position are not the same. Column 3 of Table 1 details the relationship between the level and highest-locked positions for the upper ring. By subtracting Column 3 from the upper ring setting in Column 2, the upper ring setting in notches relative to the level position is obtained, and this is shown in Column 4.

The ring settings for the valves supplied by Crosby to Westinghouse for Portland General Electric Company were established by the same methods as the "as stamped" final ring settings for the 6M6 safety valve tested at EPRI.

These methods include the performance of a steam operational test on each and every 6M6 Style HB pressurizer safety valve to determine the best suited ring setting to assure proper and stable valve performance. The final "as shipped" ring settings will vary between valves as a result of these tests to compensate for slight variations in valve internal dimen-sions and other factors which are critical to valve performance. The Model 6M6 valve (used at Trojan) is known to have rings that require a large adjustment in notches to make any difference in valve performance.

A change of 10-20 notches in ring position was noted by Crosby as having little effect on valve performance.

Comparison should be based only on those EPRI tests performed with final "as shipped" ring settings which are the following:

900 Series tests - Test Number 929, 931, and 932 1400 Series tests - All tests The 900 Series tests performed with the lowered ring positions are not representative of present fleid ring settings.

Based on the above and providing the cumulative acoustic and steady-state pressure drop is less than that experienced during the EPRI tests, Crosby believes the present ring settings would result Jn valve performance similar to that experienced during the EPPI tests.

Trojan Nuclear Plant Mr. S. A. Varga Docket 50-344 February 13, 1986 License NPF-1 Attachment j Page 2 of 2 PGE-1039 contains information that the Trojan pressure drops were less than that experienced during the EPRI tests, therefore, the valves should' perform acceptably.

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I GVB/kal 0280P.286

TABLE 1 COLUMN 1 COLUMN 2 COLUMN 3 COLUMN 4 As Shipped Valve Ring Upper Ring Level Settings, Notches Position, Notches Upper Ring Relative to Highest- Relative to Setting, Notches Trojan Safety Locked Position Highest-Locked Relative to Valve Number Upper Lower Position _ Level Position PSV-8010A -275 '- 18 -148 -127 PSV-80108 -275 -18 -158 -117 PSV-8010C -285 -18 -167 -118

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