Letter Sequence RAI |
|---|
|
|
MONTHYEARML20244A4211977-10-24024 October 1977
Forwards Topical Rept Re Fuel Rod Bow Penalties.Application & Affidavit for Withholding Rept Also Encl.Rept Provides Basis for near-term Rev to Fuel Rod Bow Penalties
Project stage: Other
ML19267A3161978-12-29029 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
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
ML20199B5101986-06-13013 June 1986
Reactor Coolant Thermal Expansion Test,Summary of Data & Predictive Curves,Heatup of 860608-10
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
ML20211G4191986-06-16016 June 1986
Rev 0 to Reactor Coolant Thermal Expansion Test Final Predictive Curves,Heatup of 860615-16
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
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
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
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
1986-05-31
[Table View] |
Text
b..*
4 UNITED STATES j
e' t
NUCLEAR REGULATORY COMMisslON f
W ASHINGTON, D. C. 20555 h%, %'Y #
January 26, 1979 Docket No. 50-344 Mr. Charles Goodwin, Jr.
Assistant Vice President Portland General Electric Company 121 S.W. Salmon Street Portland, Oregon 97204
Dear Mr. Goodwin:
In conducting our review of your.hnuary 5,1979 request relating to the revised Westinghouse themal design procedure and the WRB-1 critical heat flux correlation for the Trojan Nuclear Plant, we have det.erminea tnat we will need the additional information identified in the enclosure to continue the review. This request is the same as that telecopied to you on January 18, 1979.
Since receipt of this infonnation is basic to our review, your response is requested as soon as possible. It is likely that further additional information will be needed in order to complete our reviaw.
Three signed originals and forty copies are required.
Please cor. tact us if you have any questions concerning this request.
Sincerely,
/
, piamdts A. Schwencer, Chief Operating Reactors Branch #1 Division of Operating Reactors
Enclosure:
Request for Additional Infomation cc: w/ enclosure See next page 7903010 %
/
Portland General Electric Company January 26, 1979 cc: Mr. H. H. Phillips Portland General Electric Company 121 SW Salmon Street Portland, Oregon 97204 Warren Hastings, Esquire Counsel for Portland General Electric Company 121 SW Salmon Street Portland, Oregon 97204 Mr. J. L. Frewing, Manager Generation Licensing and Analysis Portland General Electric Company 121 SW Salmon Street Portland, Oregon 97204 Columbia County Courthouse Law Library, Circuit Court Room St. Helens, Oregon 97501 Director, Oregon Department of Energy Labor & Industries Building, Rm.111 Salem, Oregon 97310 Richard M. Sandvik, Esquire Counsel for Oregon Energy Facility Siting Counsel and Oregon Department of Energy 500 Daci#ic Buildin-520 5.,
iar,1ii Portland, Oregon 97204 Michael Malmrose U. S. Nuclear Regulatory Comnission Trojan Nuclear Plant P. O. Box 0 Rainier, Oregon 97048
=
REQUEST FOR ADDITIONAL INFORMATION TROJAN NUCLEAR PLANT 1.
Submit the sensitivity factors, Si, used for the Trojan analysis as required by the staff Safety Evaluation Report on WCAP 8567/8568.
" Improved Thermal Design Procedure" (April 10,1978).
2.
If these sensitivity factors have changed from those previously app *cved bv the staff. then a linearity test is recuired by the same staff Safety Evaluation Report. Please either reference previous staff approval for the sensitivity factors you are using or provide the results of such a linearity test.
Acco-ding to the staff SER on WCAP 8567 (referenced in request 1) 3.
sensitivity factors are also required for three loop operating conditions. Please provide these and also the results of the corresponding linearity tests.
4.
Describe how the effect of fuel rod bowing on.DNBR was included in the proposed Technical Specifications chances.
m
