ML20087Q055

Submits Results of 840403 Check Valve Leak Check to Identify Presence of Debris or Split Pin Parts in Pressure Isolation Valves Between RCS & Safety Injection Sys.Results of Cold Rod Test Satisfactory

ML20087Q055
Person / Time
Site:	Point Beach
Issue date:	04/06/1984
From:	Burstein S WISCONSIN ELECTRIC POWER CO.
To:	Harold Denton, John Miller Office of Nuclear Reactor Regulation
References
TAC-54356, NUDOCS 8404100255
Download: ML20087Q055 (2)

Text

IHsconsin Electnc macomr 231 W. MICHIGAN, P.O. BOX 2046, MILWAUKEE, WI 53201 April 6, 1984 Mr. H. R. Denton, Director Office of Nuclear Reactor Regulation U. S. NUCLEAR REGULATORY COMMISSION Washington, D. C. 20555 Attention: Mr. J. R. Miller, Chief Operating Reactors, Branch 3 Gentlemen:

DOCKET NO. 50-266 VALVE INTEGRITY CHECKS AND ROD DROP TEST POINT BEACH NUCLEAR PLANT, UNIT 1 As a result of concerns with the possible presence of debris or split pin parts in the Point Beach Nuclear Plant Unit 1 pressure isolation valves between the reactor coolant system and safety injection system, tests were performed on April 3, 1984 to measure the leak tightness of the below listed check valves and decay heat removal isolation valves. At our March 28, 1984 meeting with members of your staff we had agreed to provide a written confirmation of these tests. The results of the check valve leak check were as follows:

Leak Rate Leak Rate Leak Rate Valve GPM Valve GPM Valve GPM 845A 0 845E O 853C 0 845B 0 845F 0 853D 0 845C 0 853A 0 867A 0 845D 0 853B 0 867B 0 These leak rates also meet the acceptance criteria of Technical Specification Table 15.4.16-1.

Upon securing the decay heat removal system, suction valves MOV-700 and MOV-701 werc leak checked on April 5. Each valve was individaally subjected to a differential pressure of 250 psid. The pressore on the low-pressure sida of the valve was monitored for any increase. No pressure increase was detected and it was concluded that there was no significant leakage through

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Mr. H. R. Denton April 6, 1984 the valves. Return isolation valve MOV-720 was checked shut by position indication. Based on the above checks, operation of these isolation valves was verified.

We also agreed at the March 28 meeting to confirm the satisfactory results of the cold and hot rod drop tests and rod stepping check. We have completed the cold rod drop tests and rod stepping check and expect to finish the hot rod tests during the evening of April 6. The cold rod tests were satisfactory and all drop times were within Technical Specification limits. In order to provide this letter to you prior to unit startup, as requested this morning by Mr. Colburn of your staff, we are submitting this letter with the information prerently available.

Should we experience any difficulties with the hot rod tests, we will notify the NRC Resident Inspector and amend this report in a follow-up letter as appropriate.

If you have any questions concerning these results, please feel free to call.

Very truly yours, 7

G T Executive Vice President Sol Burstein Copy to NRC Resident Inspector

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