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	Issue date	From	Title	Project stage
ML20236A065	15 October 1975	Butler W Office of Nuclear Reactor Regulation	Informs of Potential Safety Question Re Design of Reactor Pressure Vessel Support Sys for Pwrs.Util Requested to Review Design Bases to Determine If Transient Loads Taken Into Account & Provide Results to NRC within 30 Days	Other
ML20155J779	5 January 1976	Butler W Office of Nuclear Reactor Regulation	Requests Addl Info Re Reactor Vessel Support Design.Info to Be Provided by 760301.W/o Encl	Other
ML20148F281	7 June 1976	Schwencer A Office of Nuclear Reactor Regulation	Forwards Request for Addl Info Re Adequacy of Pressure Vessel Supports When Calculating Subcooled Internal Loads	RAI
ML20244A621	25 January 1978	Stello V Office of Nuclear Reactor Regulation	Forwards Background & Current Status of Review of Asymmetric LOCA Loads for PWR Facilities & Revised Request for Addl Info on Subj	RAI
ML20151J053	6 June 1984	John Miller Office of Nuclear Reactor Regulation	Forwards Request for Addl Info Re Asymmetric LOCA Loads. Addl Info Needed in Order to Complete Safety Evaluation of plant-specific LOCA Analysis.Response Requested by 840731	Approval
ML20138H895	30 June 1985	ABB IMPELL CORP. (FORMERLY IMPELL CORP.) Grubb R Bak W Emerson R	Rev 0 to Leak-Before-Break Evaluation of Reactor Coolant Loop, Final Rept	Other
ML20138H876	25 October 1985	Withers B Portland General Electric	Forwards Rev 0 to 01-0300-1395, Leak-Before-Break Evaluation of Reactor Coolant Loop, Final Rept	Other
ML20210S227	15 May 1986	Terao D Office of Nuclear Reactor Regulation	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	Other
ML20198Q962	31 May 1986	WYLE LABORATORIES Palmer G Jacqueline Thompson Wight G	PG&E - Trojan - 1986 Snubber Valve Failure Analysis	Other
ML20210V194	25 September 1986	Withers B Portland General Electric	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	Other
ML20235Z787	15 October 1986	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) Martin J	Discusses Insp on 860318-0428 & Two Special Insps on 860513- 0612 & 860804-14 & Forwards Notice of Violation & Proposed Imposition of Civil Penalty	Other
ML20215N162	31 October 1986	Withers B Portland General Electric	Forwards Rev 1 to Impell Corp 01-0300-1395, Leak-Before- Break Evaluation of Reactor Coolant Loop, Final Rept. Analysis Revised to Comply w/NUREG-1061,Vol 3	Other
ML20215N167	31 October 1986	ABB IMPELL CORP. (FORMERLY IMPELL CORP.) Emerson R	Rev 1 to, Leak-Before-Break Evaluation of Reactor Coolant Loop	Other
ML031150510	4 August 1987	Miraglia F Office of Nuclear Reactor Regulation	Withdrawn NRC Generic Letter 1987-014: Operator Licensing Examinations	Request
ML20236J874	4 August 1987	Chan T Office of Nuclear Reactor Regulation	Forwards Request for Addl Info Re Util Proposed Application of Leak Before Break Methodology to Eliminate Dynamic Effect of Postulated Primary Loop Pipe Ruptures from Design Basis, Per GDC-4.Response Requested within 30 Days of Ltr Receipt	RAI
ML20237J408	14 August 1987	Duke Energy Tucker H	Provides Info Re Adequacy of Plant Nuclear Svc Water (Rn) Sys,Per SA Varga 870807 Request.Conformance to GDC 5 & 44, Justification of Adequacy of One Rn Pump to Serve Both Units & Actions to Justify Plant Operation Discussed	Other
ML20238B512	25 August 1987	Portland General Electric Cockfield D	Responds to NRC 870804 Request for Addl Info Re Elimination of Dynamic Effects of Postulated Primary Loop Pipe Ruptures from Design Basis for Facility.Addl Time Will Be Required to Evaluate & Adequately Address Each Item of Request	Request
ML20236R788	20 November 1987	Portland General Electric Cockfield D	Advises That Addl Info Requested in NRC Will Not Be Provided on 871231,per .Util Has Changed Contractors for leak-before-break Analysis in Order to Obtain Clarifications.Submittal Will Be Made by 880130	Other
ML20148A533	3 March 1988	WESTINGHOUSE ELECTRIC COMPANY DIV OF CBS CORP. Wiesemann R	Requests That Proprietary WCAP-11699 Be Withheld from Public Disclosure,Per 10CFR2.790.Affidavit Encl	Other
ML20148A525	14 March 1988	Portland General Electric Cockfield D	Forwards Proprietary WCAP-11699 & Nonproprietary WCAP-11700, Technical Justification for Eliminating Large Primary Loop Pipe Rupture as Structural Design Basis for Trojan Plant, leak-before-break Analysis Final Repts	Other
ML20196L189	29 June 1988	Chan T Office of Nuclear Reactor Regulation	Advises That Proprietary WCAP-11699 Will Be Withheld from Public Disclosure (Ref 10CFR2.790),per 880314 Request	Other
ML20151T404	5 August 1988	Chan T Office of Nuclear Reactor Regulation	Forwards Safety Evaluation Supporting Elimination of Postulated Primary Loop Pipe Ruptures from Design Basis for Facility,Per Util 851025 & 861031 leak-before-break Evaluations & WCAP-11699	Approval

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