Letter Sequence RAI |
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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 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 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 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 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 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 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 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 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 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 1984-02-13
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NRC PDR RBallard L PDR RCodell Docket No. 50-344 JUL 2 51983 NSIC WJohnston ORB #3 Rdg RVollmer DEisenhut GClainas Mr. Bart D. Withers OELD Vice President Nuclear EJordan Portland General Electric Company JTaylor ACRS-10 121 S. W. Salmon Street Portland, Oregon 97204 Gray File RAClark-PMKreutzer-3
Dear Mr. Withers:
CTrammeli In conducting our review o'f your_. letter, of July 1,1983_ relating to Spirit Lake, we have determined that we will need the additional infomation identified in th' _ e'nclosure to' continue our review.
e In order for us to maintal' hur review schedule, your response is n
requested within 30 days of your receipt of this'le.tter..
Following receipt of your 're3ponse, we request that a meeting be held in Bethesda with you,an_d your. consultant to discuss this matter in more detail. Weplantoalsohaveourconsultan't(USGS). attend.
For planning purposes, the, meeting should be held about two weeks after we receive your response.
Please contact.your NRC Project Manager who can make detaile~d arrangements..
The reporting and/or recordkeeping requirements contained in this letter affect fewer than ten respondents; themfore, OMB clearance is not required under P.L.,96-511.
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Please contact us if you h'av'e any questions concerning this request.
Sincerely, Original slaned by Robert A. Clark Robert A. Clark, Chief Operating Reactors Branch f3 Division of Licensing
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Enclosure:
Request for Additional Information cc w/ enclosure:
See next page gRADOCKo8050015 e307i5 05000344 p
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Portland G:neral Electric Company Michael Malmros, Resident Inspector
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U. S. Nuclear Regulatory Commission Trojan Nuclear Plant P. O. Box 0 Rainier, Oregon 97048 Robert M. Hunt, Chairman Board of County Commissioners Columbia County St. Helens, Oregon 97501 Donald W. Godard, Supervisor Siting and Regulation Oregon Department of Energy Labor and Industries Building Room 111 Salem, Oregon 97310 Regional Administrator Nuclear Regulatory Commission, Region V Office of Executive Director for Operations 1450 Maria Lane, Suite 210 Walnut Creek, California 94596 i
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HYDROLOGIC ENGINEERING SECTION
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Additional Questions " Potential Mudflow 1
from a Hypothetical Failure of: Spirit Lake Blockage" (July 1,1983 response from PGE)
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1.
The report appears to be a summary of a more detailed analysis and report.
F As such, however, it does not contain the information necessary to enable us to evaluate it.
If you have a more complete report please provide'it.
I 2.'
The important case of a mu'dflow during a low Columbia: River flowrate,
-with consequent high sedimentation in the Columbia River, followed by -
a large flowrate has been neglected.- Records have shown that high flow-rates (1,000,000 CFS) have followed periods of low flow by only a few days.
Analyse the potential-for flooding of the site by'this scenario, or justify why this case was not considered..
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'3.
Item 1.3 The procedure used to reduce the sediment concentrations from 39, 52, 'and 65 percent to 20, 30, and 45 percent respectively, as summarized in Table 1 should be discussed and all assumptions should be justified.
3 For example, what is the basis for reducing the volume of material into j
the Cowlitz by 40% (column 2)? What is the basis for the ratio of sand to finer material of 2 to 1-(columns 3 and 4)? Etc.
4.
Item-1.4 Please explain the basis' for the 30 percent moisture assumption.
p Is this figure based on available pore volume or on total volume of. dry-
[
solid? What porosity was used and what is its basis?
5.
Item.1.6 What is the basis for assuming a Columbia River sediment
- concentration of 500 ppm? What effect would varying'this concentration l
have onLyour results?
6.
Several references are used in the. text, but are not documented. For example, the "Colby method" in item 2.4.
Provide the references.
i
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7.
Item 2.5 Define the tenn " bulking factor",
8.
Item 2.6 Give basis for your assumption that the shape of the mudflow sedi-ment deposit at the confluence of the Cowlitz and Columbia rivers can be ratfoed from the configuration of the deposition following the May 18, 1980 t-mudflow.
That mudflow deposition was rather flat compared to other known mudflow slopes.
What is the sensitivity of your results to variations in y:
the slope of deposited sediments?
9.-
Item 3.4 Give basis for calculations of sediment load. Were formulas employed derived from relationships for sediment transport in rivers?
If so, justify that these formulas are acceptable for the very-high sediment loads of the present case.
- 10. Item 3.8 Why is 400,000 CFS the "most reasonable Columbia River flow i_
to evaluate"? Is there a probabilistic basis for this conclusion?
i a.
_,,. 11. Table 1 (a) Column 8 is unclear. Arithmetically, it appears that the expression should be (col 6 + col 4)/1.4. Explain the meaning of the value 1.4, and why it is used here.
l (b) - Explain the difference between column 1 and 2.-
Also, why is " material"'
used in column 1 and " sand, silt and clay" used in column 2?
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