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MONTHYEARML20129B1521985-06-30030 June 1985
Suppls NRC 840726 Safety Evaluation Re Reactor Trip Breaker Shunt Trip Mod,Per Util 850329 Submittal Re Item 8.Response & Addl Info Acceptable.Tech Specs Re Independent Testing of Undervoltage & Shunt Trip Attachment Required
Project stage: Approval
ML20133H4051985-08-0202 August 1985
Notifies of Plans to Modify Tech Specs Based on Westinghouse Owners Group Recommendations Consistent W/Generic Ltr 85-09. License Change Application Will Be Submitted by 851101 If Owners Group Undertakes No Program
Project stage: Other
ML20135G3441985-09-12012 September 1985
Notifies That Expressing Intent to Participate in Westinghouse Owners Group (WOG) Effort Re Generic Ltr 85-09 Reviewed.Westinghouse Owners Group Members Should Propose plant-specific Tech Spec Changes
Project stage: Other
ML20138N6451985-10-30030 October 1985
Advises of Intent to Participate in Westinghouse Owners Group Program to Optimize Reactor Trip Breaker Maint & Surveillance Practices Per Generic Ltr 85-09.Owners Group Proposals Listed
Project stage: Other
ML20210G2491986-09-23023 September 1986
Informs That Westinghouse Owners Group Recommendations Re Tech Spec Requirements for Reactor Trip Breaker Maint & Surveillance & Bypass Breaker Testing Unacceptable.Tech Spec Changes Consistent W/Generic Ltr 85-09 Should Be Submitted
Project stage: Other
ML20215H1971986-10-17017 October 1986
Advises That License Change Application,Addressing Generic Ltr 85-09,will Be Submitted within 60 Days of Approval of Rev 2 to License Change Application 117,per 861007 Telcon W/T Chan
Project stage: Other
ML20215K7861987-06-22022 June 1987
Forwards Application to Amend License NPF-1,consisting of License Change Application 132,revising Operability Requirements for Reactor Trip Breakers & Surveillance Requirements for Manual Reactor Trip & Breakers.Fee Paid
Project stage: Request
ML20215K8131987-06-22022 June 1987
Application for Amend to License NPF-1,consisting of License Change Application 132,revising Operability Requirements for Reactor Trip Breakers & Surveillance Requirements for Manual Reactor Trip & Breakers
Project stage: Request
ML20215K8381987-06-22022 June 1987
Proposed Tech Spec Table 3.3-1,revising Operability Requirements for Reactor Trip Breakers & 4.3-1,revising Surveillance Requirements for Manual Reactor Trip,Reactor Trip Breakers & Bypass Breakers
Project stage: Other
ML20195G8111987-12-0101 December 1987
Forwards Amend 137 to License NPF-1 & Safety Evaluation. Amend Revises Tech Specs Table 3.3-1, Reactor Trip Sys (RTS) Instrumentation & Table 4.3-1, RTS Instrumentation Surveillance Requirements, Per Generic Ltr 85-09
Project stage: Approval
1985-09-12
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October 17, 1986 Bart D W4hers Vce Prthyt 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 Commission Washington DC 20555
Dear Sir:
Technical Specifications for Generic Letter 85-09,
Reference:
- 1) NRC (Chan) to PGE (Withers) letter dated September 23, 1986, Generic Letter 85-09 and Item 4.3 of Generic Letter 83-28.
Reference 1 directed PCE to submit Technical Specification changes con-sistent with Generic Letter 85-09 (Technical Specifications for Generic Letter 83-28, Item 4.3).
The Technical Specification changes requested in Reference 1 affect the same Technical Specification pages that are presently being reviewed by the NRC in a separate License Change Applica-tion, LCA 117. Revision 2 (Reactor Protection System and Engineered Safety Feature Actuation System Technical Specifications). Following discussion with Terence Chan on October 7, 1986, it was agreed that Technical Specif1-cation changes to address Generic Letter 85-09 should be submitted after LCA 117, Revision 2 is approved. This avoids the problems experienced in the past with more than one LCA affecting the same Technical Specifications and the inherent difficulties in reviewing and approving these changes at the same time.
Therefore, au LCA addressing Generic Letter 85-09 will be submitted within 60 days of approval of LCA 117, Revision 2.
Sincerely g Bart D. Withers Vice President Nuclear c:
Mr. Lynn Frank, Director State of Oregon Department of Energy 8610230017 861017 PDR ADOCK 05000344 0
PDR 1
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