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MONTHYEARML20137N9351986-01-31031 January 1986
Proposed Corrections to Tech Specs 4.0.2,4.4.6.1,3.4.9.3 & Table 3.6-1
Project stage: Other
ML20137N8961986-01-31031 January 1986
Forwards Application for Amend to License NPF-1,consisting of Change Application 135,providing Miscellaneous Corrections to Tech Specs 4.0.2,4.4.6.1,3.4.9.3 & Table 3.6-1.W/Certificate of Svc.Fee Paid
Project stage: Request
ML20137N9091986-01-31031 January 1986
Application for Amend to License NPF-1,consisting of License Change Application 135,making Miscellaneous Corrections to Tech Specs 4.0.2,4.4.6.1,3.4.9.3 & Table 3.6-1
Project stage: Request
ML20197J9501986-05-16016 May 1986
Revised Application 135 to Amend License NPF-1,correcting Typos & Editorial Errors,Deleting Valve CV-8825 from Table 3.6-1 & Allowing Manual Valve MD-059 to Be Periodically Opened Under Administrative Control
Project stage: Other
ML20207D0821986-12-22022 December 1986
Forwards Revised Pages for License Change Application 124 to License NPF-1,changing Table 3.6-1 to Add Seven of Eight Valves Previously Deleted from Table,For Review & Approval. Valve MO-8106 Should Remain Deleted from Table
Project stage: Other
ML20212E2321987-02-26026 February 1987
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
Project stage: Request
ML20245A2631987-02-26026 February 1987
Proposed Tech Specs,Consisting of Revised Pages for License Change Application 124 & License Change Application 135, Adding Steamline Isolation Valves & Valve CV-8825 Back Onto Table 3.6-1 & Excluding Containment Airlocks from Criteria
Project stage: Other
ML20206B5621987-04-0202 April 1987
Forwards Amend 126 to License NPF-1 & Safety Evaluation. Amend Provides Editorial Corrections to Tech Spec Sections 4.4.6.1.b & 3.4.9.3 & Revises Table 3.6-1 to Permit Administrative Control of Valve MD-059 Operation
Project stage: Approval
ML20206A6221987-04-0303 April 1987
Revised Tech Spec Page 7,clarifying License Change Application 124 Re power-operated Valves
Project stage: Other
ML20205T3551987-04-0303 April 1987
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
Project stage: Other
ML20149J8711988-02-10010 February 1988
Requests That Util Provide Revised Significant Hazards Discussion,Based on 870226 & 0403 Revs to 850729 Application for Amend to License NPF-1,changing Tech Specs Re Containment Leak Testing & Containment Isolation Valves
Project stage: Other
ML20151E4441988-07-11011 July 1988
Forwards Amend 147 to License NPF-1 & Safety Evaluation. Amend Revises Surveillance Requirements in Tech Spec Section 3/4.6.1.1, Containment Integrity
Project stage: Approval
ML20151L3921988-07-25025 July 1988
Forwards Amend 147 to License NPF-1 & Safety Evaluation. Amend Revises Surveillance Requirements for Tech Spec Section 3/4.6.1.1,Containment Integrity
Project stage: Approval
1987-04-02
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W General Bochic Coiiiptsy m
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 ADOCK 05000344 PDR PDR P
Attachment c:
Mr. John B. Martin Mr. David Kish, Acting Director Regional Administrator, Region V State of Oregon U.S. Nuclear Regulatory Commission Department of Energy Mr. Rob Barc Mr. Michael J. Sykes NRC f<ecident Inspector Chairman of County Commissioners Trojan Nuclear Plant i
P 3 1
l 121 S.W S+ mon Street Pomand, Oregon 97204
.
