ML20212E232

Application for Amend to License NPF-1,consisting of Revised Pages for License Change Application 124 & License Change Application 135,adding Steamline Isolation Valves & Valve CV-8825 Back Onto Tech Spec Table 3.6-1

ML20212E232
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	02/26/1987
From:	Cockfield D PORTLAND GENERAL ELECTRIC CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20212E235	List: ML20212E232 ML20245A263
References
TAC-59562, TAC-60618, NUDOCS 8703040298
Download: ML20212E232 (1)

Text

_ - _ _ _ _ _ _ _ _ _ _

/

e M M m W General Bochic Coiiiptsy David W. Cockfield Vice President, Nuclear February 26, 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 Applications 124 and 135 Containment Isolation Valves Pursuant to discussions, attached are revised pages for License Change Application (LCA) 124. This change adds the steamline isolation valves back onto Trojan Technical Specification Table 3.6-1 that were proposed to be deleted in LCA 124. Instead of deleting these valves from the table, a footnote has been added indicating that the Containment Isolation Valve specification does not apply to the steamline isolation valves. This approach has boon accepted by the NRC on recently licensed plants, eg, Wolf Creek and Vogtle.

In addition, Valve CV-8825 (Residual Heat Removal hot leg recirculation) has also been added back onto Table 3.6-1. This valve was proposed to be doloted in LCA 135. In response to your position that this Type IV penetration (as defined in FSAR Section 6.2.4) requires two Containment isolation valves, this valve will remain on Tabic 3.6-1.

Also, the proposed change to exclude the Containment airlocks trom the acceptance criteria for Type B tests is being withdrawn. This is tased on the NRC position that despite the provision in 10 CFR 50 Appendix J, which allows a separate leakage criteria to be applied to airlocks, the airlocks must still meet the requirement that the combined leakage of Type B and C penetrations be less than 0.60 of the maximum allowed Containment leakage.

Sincerely, 8703040298 870226 PDR ADOCK 05000344 PDR P

Attachment Mr. David Kish, Acting Director c: Mr. John B. Martin Regional Administrator, Region V State of Oregon U.S. Nuclear Regulatory Commission Department of Energy Mr. Michael J. Sykes Mr. Rob Barc NRC f<ecident Inspector Chairman of County Commissioners Trojan Nuclear Plant i

P 1 3

' l 121 S.W S+ mon Street Pomand, Oregon 97204

. . .