Letter Sequence Approval |
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Results
- Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval
Other: ML19345B142, ML20024B599, ML20129J487, ML20132B636, ML20133F596, ML20133F656, ML20133F674, ML20134A330, ML20134A495, ML20135B105
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MONTHYEARML19290F6821980-09-15015 September 1980
Informs Commission of Directors Denial Re Suspension of Plant Operations in Light of Volcanic Activity at Mount St Helens.Recommends Effects of Activity on Evacuation Be Considered in Conjunction W/Required Emergency Planning
Project stage: Request
ML19345B1421980-11-21021 November 1980
Forwards Addl Info Re Eruption of Mount St Helens & Effect on Facility Per 801030 Request
Project stage: Other
ML20134A2221983-02-18018 February 1983
Submits Daily Highlights.Usgs & FEMA Transmitted Draft Rept Assessing Potential Hazard to Towns of Kelso & Longview, Wa from Breach of Spirit Lake Natural Dam on Mount St Helens
Project stage: Draft Other
ML20134A2441983-02-24024 February 1983
Informs of Acceptance of plant-specific Licensing Action Re Review of Draft Usgs/Fema Rept on Possible Hazards Posed by Failure of Spirit Lake Dam.Scheduled Target Date Is 830301.Supporting Documentation Encl
ML20134A3301983-03-29029 March 1983
Advises That Charges to TAC 49636 Re Possible Hazards Posed by Failure of Spirit Lake Dam Valid.Tac Not Included in List of plant-specific Licensing Actions for FY83.Related Info Encl
Project stage: Other
ML20133F5421983-04-0101 April 1983
Notification of 830408 Meeting to View Slides of Spirit Lake & Area,To Learn Observations of Visited Areas & to Discuss Future NRC Action
Project stage: Meeting
ML20133F7861983-05-12012 May 1983
Summarizes 830511 Meeting at Corps of Engineers Ofc in Portland,Or Re Determination of Flood Elevations at Facility Resulting from Breach of Debris Barrier at Spirit Lake,Wa. Related Info Encl
Project stage: Meeting
ML20133F5961983-06-0101 June 1983
Certifies That Funds Authorized for Interagency Agreement NRC-03-83-109 Entitled, Analysis of Potential Flood Levels at Trojan Nuclear Power Plant. Estimates Completion of Phase 1 2 Wks After Initiation of Work
Project stage: Other
ML20024B5991983-07-0101 July 1983
Forwards Addl Info Re Potential Mudflows from Hypothetical Failure of Spirit Lake Blockage.Based on Results,Max Columbia River Flood Levels Will Be Below Elevation 39 Ft Mean Sea Level
Project stage: Other
ML20024D4271983-07-25025 July 1983
Forwards Request for Addl Info Re Util 830701 Discussion of Potential Mudflow from Hypothetical Spirit Lake Blockage. Response Requested within 60 Days of Receipt of Ltr
Project stage: RAI
ML20132B6361983-09-15015 September 1983
Forwards Util 830902 Response to NRC Questions on Util 830701 Submittal Re Potential Mudflows from Assumed Failure of Spirit Lake Blockage.Util Consultant Final Rept Also Encl.W/O Rept
Project stage: Other
ML20133F6561983-12-0505 December 1983
Forwards Summary of Corp of Engineers Actions to Solve Spirit Lake Problem
Project stage: Other
ML20132B7591984-02-13013 February 1984
Forwards USGS Geologic Hazards Bulletins Describing Recent Mount St Helens Activity Through 840207 & USGS Review of Recent Corps of Engineers Rept Re Proposed long-term Engineered Solutions to Draining Spirit Lake
Project stage: Approval
ML20134A4831984-02-21021 February 1984
Informs of 840223 Meeting W/Usgs & Util to Discuss Analysis of Flooding Consequences of Breakout of Spirit Lake Blockage at Facility
Project stage: Meeting
ML20134A4951984-03-29029 March 1984
Accepts plant-specific Licensing Action Re Spirit Lake Blockage.Scheduled Target Date Is 840409
Project stage: Other
ML20132C3611984-08-0808 August 1984
Requests Issuance of Final Safety Evaluation Re Refined Sediment Transport Routing Model to Study Impacts of Spirit Lake Breakout on Columbia River.Fema to Util Summarizing USGS Study Encl
Project stage: Approval
ML20133F6741984-12-31031 December 1984
Preliminary Estimate of Possible Flood Evaluation in Columbia River at Trojan Nuclear Power Plant Due to Failure of Debris Dam Blocking Spirit Lake,Wa
Project stage: Other
ML20129H7091985-05-28028 May 1985
Forwards Request for Addl Info Re Response to Generic Ltr 83-28, Generic Implications of Salem ATWS Events, Concerning Position on post-maint Operability Testing of safety-related Components.Response Requested within 45 Days
Project stage: RAI
IR 05000344/19850131985-05-28028 May 1985
Insp Rept 50-344/85-13 on 850402-0513.No Violations Noted. Major Areas Inspected:Operational Safety Verification, Corrective Action,Maint,Surveillance,Followup on Previous Insps,Refueling Activities & Operation
Project stage: Request
ML20128G3561985-06-26026 June 1985
Safety Evaluation Re Util 831104 Response to Generic Ltr 83-28,Item 1.1, Post-Trip Review. Subj to Successful Implementation of Listed recommendations,post-trip Review Program & Procedures Acceptable
Project stage: Approval
ML20128G3351985-06-26026 June 1985
Forwards Safety Evaluation Re 841104 Response to Generic Ltr 83-28,Item 1.1, Post-Trip Review. Post-trip Review Program Acceptable,Subj to Successful Resolution of Independent Assessment of Event Following Trip
Project stage: Approval
ML20132A4401985-07-11011 July 1985
Forwards Safety Evaluation Addressing Generic Ltr 83-28, Item 4.5.1 Re Reactor Trip Sys Reliability (Sys Functional Testing).Util Satisfactorily Completed Actions Required, Based on Commitment to Modify Reactor Trip Breakers
Project stage: Approval
ML20132A4561985-07-11011 July 1985
Safety Evaluation Supporting Util Response to Generic Ltr 83-28,Item 4.5.1 Re Reactor Trip Sys Reliability Based on Commitment to Modify Reactor Trip Breakers
Project stage: Approval
ML20132D3041985-07-16016 July 1985
Forwards Safety Evaluation Concluding That Breakout of Spirit Lake Would Not Affect Safe Operation of Plant.Outlet Tunnel Constructed to Reduce Threat of Potential Debris Dam Failure & Breakout of Lake
Project stage: Approval
ML20132D3111985-07-16016 July 1985
Safety Evaluation Concluding That Breakout of Spirit Lake Would Not Affect Safe Operation of Plant.Outlet Tunnel Reduces Threat of Breakout.Two Map Diagrams Encl
Project stage: Approval
ML20129J4871985-07-19019 July 1985
Provides Addl Response to Generic Ltr 83-28 Re Required Actions Based on Generic Implications of Salem ATWS Events, in Response to NRC 850528 & 0626 Ltrs.Operating Experience Program Developed Per NUREG-0737,Item I.C.5
Project stage: Other
ML20135B1051985-08-28028 August 1985
Discusses LER 84-021 Re Silt Accumulation on Svc Water Strainers on 841011 & 30.Util Solution to Change Strainer Mesh from 10 Mils to 20 Mils Acceptable.Issue Closed
Project stage: Other
ML20135H4801985-09-0505 September 1985
Forwards Revised Safety Evaluation Re Util 850719 Responses to NRC 850626 Open Issues Concerning Generic Ltr 83-28,Item 1.1, Post-Trip Review. Program & Procedures Acceptable
Project stage: Approval
ML20135H4821985-09-0505 September 1985
Safety Evaluation Supporting Util 850719 post-trip Review Program Description & Procedures,Per Item 1.1 of Generic Ltr 83-28
Project stage: Approval
ML20133H7701985-10-10010 October 1985
Safety Evaluation Re Util Response to Generic Ltr 83-28, Item 4.1,concerning Reliability of Reactor Trip Sys.Actions Specified by Item 4.1 Satisfactorily Completed,Based on Licensee Review of Sources of vendor-recommended Mods
Project stage: Approval
ML20133H7541985-10-10010 October 1985
Forwards Safety Evaluation Supporting Util Response to Generic Ltr 83-28,Item 4.1,concerning Reactor Trip Sys Reliability (vendor-related Mods).Actions Specified by Item 4.1 Satisfactorily Completed
Project stage: Approval
ML20133H8401985-10-11011 October 1985
Forwards Safety Evaluation Re Util Response to Generic Ltr 83-28,Items 3.1.1 & 3.1.2 Concerning post-maint Testing to Verify Operability & Guidance for Reactor Trip Sys Components.Util Satisfied Actions Requested by Item 3.1.2
Project stage: Approval
ML20133H8571985-10-11011 October 1985
Safety Evaluation Re Util Response to Generic Ltr 83-28, Items 3.1.1 & 3.1.2 Concerning post-maint Testing to Verify Operability & Guidance for Reactor Trip Sys Components. Licensee Acceptably Satisfied Actions Requested by Items
Project stage: Approval
ML20136C6401985-12-20020 December 1985
Forwards Draft SER Re Tech Spec Changes & Draft Transmittal Ltr to Licensee.Proposed Amend to License NPF-1 Approved. SALP Input Also Encl
Project stage: Draft Approval
ML20141E8951986-04-10010 April 1986
Forwards NRC Review of Us Army Corps of Engineers Study Re Possible Flood Levels at Facility.Study Showed Higher Flood Levels than Design Basis Flood Level.Permanent Flood Protection Unnecessary.Alternative Measures Suggested
Project stage: Approval
1984-02-13
[Table View] |
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July 16, 1985 a M, DISTRIBUTION:
Docket No. 50-344 DOCKt.1 FILE -
PMKreutzer NRC PDR ACRS(10)
L PDR Gray File ORB #3 Rdg Mr. Bart D. Withers HThompson Vice President Nuclear OELD Portland General Electric Company EJordan 121 S. W. Salmon Street BGrimes Portland, Oregon 97204 JPartlow LLazo
Dear Mr. Withers:
SUBJECT:
SAFETY EVALUATION - SPIRIT LAKE / TROJAN PLANT FLOODING Enclosed is the staff's Safety Evaluation addressing the effects of a breakout of Spirit Lake on the Trojan Plant.
Our conclusion that a breakout of Spirit Lake will not affect the safe operation of Trojan is based on a U.S. Geological Survey entitled, " Impact on the Columbia River of an Outburst of Spirit Lake," and a report entitled, " Analysis of Flood Level at Trojan Plant Associated with Hypothetical Failure of Spirit Lake Block-age," by PGE consultants, Simons, Li and Associates, Inc.
A permanent Spirit Lake outlet tunnel has been constructed to lower the Lake level and thus reduce the threat of a potential debris dam failure and breakout of Spirit Lake and the concern of potential flooding of the Trojan Plant.
It is expected that Spirit Lake will be drawn down to a level where the debris dam is stable by September 1985.
In the interim, the USGS and PGE studies provide in-formation that indicates that even if Spirit Lake did break out, the resultant flood level in the Columbia River at the Trojan Plant would not rise as high as plant grade even if the breakout occurred coincident with a 100 year flood dis-charge in the Columbia River.
Sincerely, Edward J. Butcher, Acting Chief Operating Reactors Branch #3 Division of Licensing
Enclosure:
Safety Evaluation cc: See next page
- See previous concurrence page
,, fy ORBf3:DL*
ORB #3:DL*
ORBf%:pt PKreutzer Llazo:dd EJButcher 7/9/85 7/10/85 7/A/85 8507310202 050716 DR ADOCK 0500 4
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'D 6 f c,l k DISTRIBUTION:
Docket No. 50-344 DOCKET FILE PMKreutzer NRC PDR ACRS (10)
L PDR Gray File ORB #3 Rdg Mr. Bart D. Withers HThompson Vice President Nuclear OELD Portland General Electric Company EJordan 121 S. W. Salmon Street BCrimes Portland, Oregon 97204 JPartlow Llazo
Dear Mr. Withers:
SUBJECT:
SAFETY EVALUATION - SPIRIT LAKE / TROJAN PLANT FLOODING Enclosed is the staff's Safety Evaluation addressing the effects of a breakout of Spirit Lake on the Trojan Plant.
Our conclusion that a breakout of Spirit Lake will not affect the safe operation of Trojan is based on a U.S. Geological Survey entitled, " Impact on the Columbia River of an Outburst of Spirit Lake," and a report entitled, " Analysis of Flood Level at Trojan Plant Associated with Hypothetical Failure of Spirit Lake Block-age," by PGE consultants, Simons, Li and Associates, Inc.
A permanent Spirit Lake outlet tunnel has been constructed to lower the Lake level and thus reduce the threat of a potential breakout of Spirit Lake and the con-cern of potential flooding of the Trojan Plant.
It is expected that Spirit Lake will be drawn down to a safe level by September 1985.
In the interim, the USGS and PGE studies provide information that indicates that even if Spirit Lake did break out, the resultant flood level in the Columbia River at the Trojan Plant would not rise as high as plant grade even if the breakout occurred coincident with a 100 year flood discharge in the Columbia River.
Sincerely, Edward J. Butcher, Acting Chief Operating Reactors Branch #3 Division of Licensing
Enclosure:
Safety Evaluation cc: See next page ORB #3:DL ORB #3:0 y ORB!3:DL Pyfquper Llazo:dd EJButcher 7/ej/85 7/IO/85 7/ /85
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