Letter Sequence Request |
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MONTHYEARML20132C7801985-03-0606 March 1985
Forwards SER Re Effects of Breakout of Spirit Lake on Facility.Conclusion That Breakout Will Not Affect Safety Based on Unpublished USGS Study Rept & Subj to Change. Permanent Outlet Tunnel Under Const Will Resolve Concern
Project stage: Request
ML20129J0911985-05-31031 May 1985
Forwards Amend 1 to 10CFR50,App R Review Rept,Per C Trammell Request.Amend Provides Addl Mods in Fire Area E1,withdraws 850208 Exemption Request for Fire Area R1 & Incorporates 850306 Response to Re Safe Shutdown Review
Project stage: Request
ML20138K5081985-10-15015 October 1985
Forwards Safety Evaluation Accepting Util 840731 & 850306 Proposed Revised Sections III.G.3 & Iii.L of 10CFR50,App R Re Alternate Shutdown Capability W/Identified Mods & Compensatory Measures
Project stage: Approval
ML20138K5211985-10-15015 October 1985
Safety Evaluation Concluding That Util Proposed post-fire Alternate Shutdown Design Meets Requirements of 10CFR50,App R,Sections III.G.3 & Iii.L W/Proposed Mods & Interim Measures & Acceptable
Project stage: Approval
ML20136E9851985-11-15015 November 1985
Notification of 851126 Meeting W/Util & NRC Consultants in Columbia County,Or to Discuss Five Requested Exemptions from Requirements of App R,Section Iii.G Re Fire Protection for Four Affected Areas
Project stage: Meeting
ML20138Q0941985-12-20020 December 1985
Responds to NRC 851113 Request for Addl Info Re Util Jul 1984 App R Exemption Requests
Project stage: Request
ML20215H2071986-10-16016 October 1986
Requests Exemption from 10CFR50,App R Requirements Re 20-ft Separation Criteria.Extension of Automatic Sprinkler Sys Planned to Protect Exhaust Fans for Emergency Diesel Generator Rooms from Exposure Fire
Project stage: Other
ML20214A2941986-11-0404 November 1986
Portland General Electric Nuclear Plant Engineering Design Criteria:Extension of Automatic Sprinkler Sys Be (Rdc 84-048) Turbine Bldg Trojan Nuclear Power Plant
Project stage: Other
ML20214G3041986-11-17017 November 1986
Provides Addl Info Re 861016 Request for Exemption from Requirements of 10CFR50,App R.Field Check Verified That Lower Sprinkler Head Not Below All Cable Trays.Sketch of Elevation View Encl
Project stage: Request
ML20211H9541987-02-18018 February 1987
Requests That Dec 1987 Commitment Date Be Extended to Prior to Return to Power Following 1988 Refueling Outage to Complete Installation of Remote Shutdown Panel.Reasons for Extension & App R Commitments Affected by New Panel Listed
Project stage: Other
IR 05000344/19870121987-04-10010 April 1987
Insp Rept 50-344/87-12 on 870330-0403.No Noncompliance or Deviations Noted.Major Areas Inspected:Areas of Design Changes & Mods,Qa Program Measuring & Test Equipment, Followup of Previous Insp Findings & Closure of Open Items
Project stage: Request
ML20206K1271987-04-10010 April 1987
Advises That Implementation Schedule for 10CFR50.48 Fire Protection Mods for Util Determined to Be Completed by End of 1988 Refueling Outage (June 1988).Requests Util Notify NRC If Schedule Not Correct within 30 Days from Ltr Receipt
Project stage: Other
ML20214A2761987-05-0808 May 1987
Requests Withdrawal of Request for Exemption from 10CFR50, App R,Section III.G.2.b in Case of Emergency Diesel Generator Ventilation Exhaust Openings.In Lieu of Exemption, Util Requests NRC Review & Approval of Listed Encls
Project stage: Withdrawal
IR 05000344/19870151987-05-0808 May 1987
Insp Rept 50-344/87-15 on 870415-24.Violations Noted: Failure to Establish & Implement Radiation Protection Procedures,Failure to Provide Instructions to Workers & Failure to Perform Survey & Maintain Records
Project stage: Request
ML20214K0081987-05-20020 May 1987
Responds to NRC Re Schedule for Implementation of 10CFR50.48 Fire Protection Mods.Mods Completed W/Exception of Four Listed Items.Items 1 & 2 Will Be Completed by 1988 Refueling Outage.Items 3 & 4 Will Be Completed by 871231
Project stage: Other
ML20236M8981987-10-27027 October 1987
Environ Assessment & Finding of No Significant Impact Supporting Exemption from Section Iii.G of App R of 10CFR50 Re Fire Protection of Equipment Important to Safe Shutdown
Project stage: Approval
ML20236M8321987-10-27027 October 1987
Forwards Environ Assessment & Finding of No Significant Impact Re Util 840731,850531,861016 & 1117 & s Requesting Exemption from Requirements of Section III.G.2 of App R of Tech Specs
Project stage: Approval
ML20236S4021987-11-12012 November 1987
Safety Evaluation Supporting Exemption from Requirements of 10CFR50,App R,Section III.G.2 Re Fire Protection of Safe Shutdown Capability Requirements
Project stage: Approval
ML20236S3991987-11-12012 November 1987
Forwards Exemption from Requirements of 10CFR50,App R, Section III.G.2 Re Fire Protection of Safe Shutdown Capability Requirements in Response to Util 840731,850531, 861016,1117 & 870508 Requests.Safety Evaluation Also Encl
Project stage: Approval
1986-11-17
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m l!lll PortlandGeneralBectricCoiiiptsiy Ebrt D Wthers Vce Resdert May 31, 1985 Trojan Nuclear Plant Docket 50-344 License NPF-1 Director of Nuclear Reactor Regulation ATTN:
Mr. James R. Miller, Chief Operating Reactors Branch No. 3 Division of Licensing U.S. Nuclear Regulatory Commission Washington DC 20555
Dear Sir:
Amendment 1 to 10 CFR 50 Appendix R Review This letter provides thirteen (13) copies of Amendment 1 to the 10 CFR 50 Appendix R Review Report for the Trojan Nuclear Plant.
Preparation and submittal of this amendment was previously discussed with, and requested by, Mr. Charles Tramell of your staff. The purpose of this amendment is to incorporate the following:
1.
PGE verbal connitments to provide additional modifications in Fire Area El (electrical penstration area outside Containment) as part of the exemption requested for that.trea (Section 5.2.2 of the Report).
2.
PCE letter dated February 8, 1985 withdrawing the exemption request for Fire Area R1 (Section 5.2.4 of the Report).
3.
PGE letter dated March 6,1985 responding to an NRC letter dated January 24, 1985, which transmitted questions related to the safe shutdown review.
4.
Relevant information from continuing PGE design review efforts on Appendix R as follows:
g a.
Structural steel analyses for the Fuel and Auxiliary Buildings (Section 2 and Appendix C).
b.
Updated combustible loading table (Table 2-2).
! ph 8506100011 850531 0
PDR ADOCK 05000344
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PDR 121 SW Symon Etwt Portwd Omgon 97204
Pbrtland General BechicCuingmy Mr. James R. Miller May 31, 1985 Page 2 c.
Updated review results for safe shutdown / spurious operation equipment (Table 3-1), associated circuit resolutions (Tables 3-3 and 3-4a), and safe shutdown success trees (Figures 3-42 through 3-49).
d.
Designation of a new fire area (A4a) in Fire Area A4.
5.
Relevant references to NRC Generic Letter 85-01 in lieu of previous references to the 1984 NRC Regional Workshops on Appendix R.
6.
Typographical corrections and minor technical clarifications and corrections.
We would be pleased to discuss any questions or comments you may have regarding this amendment.
Sincerely, m
a
.__m_
Bart D. Withers Vice President Nuclear Attachments c:
Mr. Lynn Frank, Director State of Oregon Department of gnergy Mr. John B. Martin i
Regional Administrator, Region V U.S. Nuclear Regulatory Commission
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