Letter Sequence Other |
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Results
Other: 05000344/LER-1985-013-01, Forwards Rev 0 to 01-0300-1471, Preliminary Thermal Expansion Evaluation of Reactor Coolant Loop for Trojan Nuclear Plant, as Clarification of LER 85-013-01 in Response to 860430 Telcon, ML19267A316, ML19274E248, ML19274E250, ML20197E758, ML20198Q962, ML20198R016, ML20198R908, ML20198R985, ML20198S019, ML20198S051, ML20199B502, ML20199B510, ML20202C354, ML20204F441, ML20206F998, ML20210S227, ML20210V194, ML20211G407, ML20211G419, ML20212D368, ML20235K098, ML20235Z787
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MONTHYEARML19267A3161978-12-29029 December 1978
Informs That Due to Control Bldg Proceeding,The Mod to Operating Status Alarms of Diesel Generators Will Not Be Completed Until 790131
Project stage: Other
ML19261B7371979-01-26026 January 1979
Forwards Request for Addl Info in Order to Complete Review Re Revised Westinghouse Thermal Design Procedure & WRB-1 Critical Heat Flux Correlation.Requests Response as Soon as Possible
Project stage: RAI
ML19259B6041979-02-0707 February 1979
Forwards Request for Addl Info Re Revised Westinghouse Thermal Design Procedure & Critical Heat Flux Correlation for Facility
Project stage: RAI
ML19274E2481979-03-15015 March 1979
Forwards License Change Application 50 to Amend License NPF-1 Re Radiological Tech Specs.Certificate of Svc & Class III Fee Encl
Project stage: Other
ML19274E2501979-03-15015 March 1979
License Change Application 50 to Amend License NPF-1 Re Radiological Tech Specs
Project stage: Other
ML19254F2471979-10-31031 October 1979
Supplements 790315 License Change Application 50 Incorporating 10CFR50,App I,Radiological Effluent Tech Specs.Includes Spec Implementing 40CFR50.Util to Implement 10CFR190 Until Application 50 Approved & Issued as Amend
Project stage: Supplement
ML20197E7581986-01-31031 January 1986
Rev 0 to Preliminary Thermal Expansion Evaluation of Reactor Coolant Loop for Trojan Nuclear Plant
Project stage: Other
05000344/LER-1985-013-01, Forwards Rev 0 to 01-0300-1471, Preliminary Thermal Expansion Evaluation of Reactor Coolant Loop for Trojan Nuclear Plant, as Clarification of LER 85-013-01 in Response to 860430 Telcon1986-05-0909 May 1986
Forwards Rev 0 to 01-0300-1471, Preliminary Thermal Expansion Evaluation of Reactor Coolant Loop for Trojan Nuclear Plant, as Clarification of LER 85-013-01 in Response to 860430 Telcon
Project stage: Other
ML20210S2271986-05-15015 May 1986
Trip Rept of 860510-11 Site Visit to Participate in Licensee Cold Walkdown of Reactor Coolant Loop Piping & Components, Including Supports,To Assess Whether Cause of LER 85-013, Rev 1 Determined
Project stage: Other
IR 05000344/19860171986-05-19019 May 1986
Insp Rept 50-344/86-17 on 860505-09.No Noncompliance or Deviations Noted.Major Areas Inspected:Onsite Review Committee,Qa Test & Measurement Equipment Program & Surveillance Program
Project stage: Request
ML20198S0511986-05-23023 May 1986
Interim Rept of Independent Review of Trojan Nuclear Plant Reactor Coolant Loop Thermal Movements Evaluation Program. Supporting Info Encl
Project stage: Other
ML20198Q9621986-05-31031 May 1986
PG&E - Trojan - 1986 Snubber Valve Failure Analysis
Project stage: Other
ML20198Q9281986-06-0303 June 1986
Forwards Test Rept 17822, PG&E - Trojan - 1986 Snubber Valve Failure Analysis, Rev 0 to Temporary Plant Test TPT-166, RCS Thermal ... & Westinghouse Amend 3,Rev 2 to Procedure ISI-205,per NRC 860529 Meeting Request
Project stage: Meeting
ML20198R9081986-06-0404 June 1986
Forwards Impell Summary Rept, Evaluation of Reactor Coolant Loop for Restrained Thermal Expansion,Trojan Nuclear Plant
Project stage: Other
ML20206G7531986-06-0505 June 1986
Concludes That Adequate Assurance of RCS Integrity Demonstrated for Mode 3,hot Standby,Based on Review of 860521,0603 & 04 Ltrs & 860521 Meeting.Safety Evaluation Will Be Issued After Certification Received
Project stage: Approval
ML20198S0191986-06-0606 June 1986
Forwards Documentation from Bechtel Corp Re Review & Evaluation of Final Results of RCS Thermal Expansion Analysis & Hot Leg Shell Analysis Performed by Impell Corp. Encl Info Should Close Out Concerns in
Project stage: Other
ML20199B5101986-06-13013 June 1986
Reactor Coolant Thermal Expansion Test,Summary of Data & Predictive Curves,Heatup of 860608-10
Project stage: Other
ML20199B5021986-06-13013 June 1986
Forwards Temporary Plant Test TPT-166, Reactor Coolant Thermal Expansion Test,Summary of Data & Predictive Curves, Heatup of 860608-10, Per .Future Monitoring Program Will Be Documented by 861001
Project stage: Other
ML20211G4191986-06-16016 June 1986
Rev 0 to Reactor Coolant Thermal Expansion Test Final Predictive Curves,Heatup of 860615-16
Project stage: Other
ML20211G4071986-06-16016 June 1986
Forwards Rev 0 to Temporary Plant Test TPT-166, Reactor Coolant Thermal Expansion Test Final Predictive Curves Heatup of 860615-16, Demonstrating That Acceptance Criteria Met
Project stage: Other
ML20202C3541986-06-26026 June 1986
Informs That Remote Monitoring of Electronic Instrumentation Will Be Used to Assure That Steam Generator Snubbers Allow RCS Thermal Movement,Per 860616 Safety Evaluation.Only Remote Monitoring Will Be Repeated During Each Heatup
Project stage: Other
ML20198R9851986-06-30030 June 1986
Rev 0 to Evaluation of Reactor Coolant Loop for Restrained Thermal Expansion,Trojan Nuclear Plant, Summary Rept
Project stage: Other
ML20198R0161986-06-30030 June 1986
Rev 0 to Temporary Plant Test TPT-166, RCS Thermal Expansion Test. Addl Info on Insp of Cast Stainless Steel Hot Leg Elbows Encl
Project stage: Other
ML20206F9981986-06-30030 June 1986
SER in Support of Conclusion That Util Adequately Addressed Technical & Programmatic Aspects of Cause & Effects of Restrained Thermal Growth of Rcs.Ser Re Util Response to TMI Item III.D.3.4, Control Room Habitability Also Encl
Project stage: Other
ML20204F4411986-07-22022 July 1986
Rev 0 to Temporary Plant Test Procedure TPT-175, RCS Thermal Expansion Long-Term Monitoring
Project stage: Other
ML20210L7201986-09-24024 September 1986
Summary of 860529 Meeting W/Util in Bethesda,Md Re Inoperable Steam Generator Hydraulic Snubbers Relationship to Restrained Thermal Growth of Rcs.Supporting Info Encl
Project stage: Meeting
ML20210V1941986-09-25025 September 1986
Informs of Results of RCS Thermal Expansion Monitoring Performed During Wk of 860902.Measurements Acceptable.Data Will Be Taken When RCS Temp Reaches 340 F,In Lieu of Holding Temp at 340 F for Analysis & Evaluation
Project stage: Other
ML20235Z7871986-10-15015 October 1986
Discusses Insp on 860318-0428 & Two Special Insps on 860513- 0612 & 860804-14 & Forwards Notice of Violation & Proposed Imposition of Civil Penalty
Project stage: Other
ML20212D3681986-12-19019 December 1986
Submits Assessment of Impact of Replacing Graphite Shims W/ Carbon Steel Shims on Hot Leg Pipe Whip Restraints.Potential Effect on RCS Piping in Event of Future Contact Between Hot Leg Piping & Whip Restraints Addressed
Project stage: Other
ML20235K0981987-09-30030 September 1987
Informs That Periodicity of RCS Thermal Expansion Monitoring Surveillances Returned to Normal Following Completion of Twice Per Shift Exam to Detect Possible RCS Leakage as Reported to NRC on 870724
Project stage: Other
1986-05-09
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[htt D WWirs Vce Presad June 6, 1986 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:
Reactor Coolant System (RCS) Thermal Expansion Issue In response to your letter of June 5, 1986, attached is documentation from the Bechtel Corporation discussing their review and evaluation of the final results of the RCS thermal expansion analysis and hot les shell analysis performed by our consultant, the Impell Corporation. In addition, the documents provide affirmation by Bechtel of the general conclusions of the analysis. This information is considered to be sufficient to permit your review of this issue and permit the Trojan Nuclear Plant to return to power operation.
Attachment A to this letter is a copy of the May 23, 1986 interim report by Bechtel Corporation.
It describes their evaluation of the Impell analysis as of that date.
It should be noted that several questions were raised in that report that subsequently have been resolved and incorporated by Impell in their analyses. The resolution of these concerns is addressed in the letter from Bechtel Corporation provided as Attachment B.
Attachment C is a letter from Bechtel documenting their review and conclusions concerning the Temporary Plant Test, TPT 166, describing the RCS heat-up monitoring program.
Bechtel has been requested by PCE to look into several additional areas other than just the analyses performed by Impell Corporation. These areas include results of the monitoring program, pipe whip restraint operability, 8606100295 860606 ADOCKOSOOg4 PDR VP*b I
121 S W Sirrcn St eet. Paar>J Oreyn 97204 1
l s
W Gerier-d MCortyxviy Mr. Steven A. Varga June 6, 1986 Page 2 and snubber reliability. A final Bechtel report addressing all of these areas is not expected for some time. However, the information provided in this letter should be adequate to close out the concerns raised in your June 5 latter and permit the Trojan Nuclear Plant to return to power operation.
Sincerely, e
a-_;
Bart D. Withers Vice President Nuclear
~
Attachments c:
Mr. John B. Martin Regional Administrator, Region V U.S. Nuclear Regulatory Commission Mr. Lynn Frank, Director State of Oregon Department of Energy 4
P k'TrojanNuclearPlant Mr. Steven A. Varga 4
Docket 50-344 June 6, 1986 Attachment A License NPF-1 Bechtel Power Corporation Engr 5ee'5-Con 11'ucto 1 Fdiv Bese Street San Franersco. Californe Ma# A00ress-P O Bos 3965 San 8rancesco CA W119 In reply please reference:
Doc. Control No.
IC24570 BP-12476 Mr. R. L. Steele Manager, Nuclear Plant Engineering Portland General Electric Company 121 S. W. Salmon Street Portland, Oregon 97204 Attention:
R. J. Wehage-
Subject:
Portland General Electric Company Trojan Nuclear Plant - Job 11760-176 Peer Review of Reactor Coolant Loop Movements
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Gentlemen:
Attached are 10 copies of the Interim Report of the Independent Review of Trojan Nuclear Plant Reactor Coolant Loop Evaluation Program. This version covers the technical aspects of the situation to date. We intend to finalize the report after review of the Impell detailed evaluation report and after implementation of corrective actions by PGE.
If there are questions on the report, please do not hesitate to call me.
Very truly yours, R. W. r osse Project Engineer
Attachment:
Interim Report cc: G. Zi=mer=an - PGr W. Sak -
I=pell TLS/47
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