ML20205T355

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Clarifies License Change Application 124 to License NPF-1, Revising Tech Spec 4.6.3.1.3 Re Testing of Power Operated Valves.Valves Should Be Tested Per Tech Spec 4.0.5.Revised Page 7 of 21 Encl
ML20205T355
Person / Time
Site: Trojan File:Portland General Electric icon.png
Issue date: 04/03/1987
From: Cockfield D
PORTLAND GENERAL ELECTRIC CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20205T360 List:
References
TAC-59562, NUDOCS 8704070271
Download: ML20205T355 (1)


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m bIV dYd David W. Cockfield Vice President, Nuclear April 3, 1987 Trojan Nuclear Plant Docket 50-344 License NPF-1 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington DC 20555

Dear Sir:

License Change Application 124 Containment Isolation Valves Pursuant to discussions with Mr. Terence Chan of your staff, we have decided to clarify License Change Application 124. The change proposed to Trojan Technical Specification 4.6.3.1.3 implied that power-operated valves listed on Table 3.6-1 would not have to be tested; that was not the intent of the change. As pointed out by Mr. Chan, the interpretation of the existing Technical Specification 4.6.3.1.3 is that the power-operated valves are to be tested to verify the isolation time established for them by the Inservice Testing Program, ie, pursuant to Technical Specification 4.0.5. A revised Page 7 of 21 to reflect this clarification to License Change Application 124 is attached.

Sincerely, Attachment c: Mr. John B. Martin Regional Administrator, Region V U.S. Nuclear Regulatory Commission i

k Mr. David Kish, Acting Director State of Oregon Department of Energy Mr. R. C. Barr NRC Resident Inspector Trojan Nuclear Plant 8704070271 870403 (%h

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