05000280/LER-1980-046, Forwards LER 80-046/03L-0
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Questions
Results Other: 05000280/LER-1980-046, Forwards LER 80-046/03L-0, A01085, Forwards Nonproprietary Response to Questions on Cycle 4 Basic Safety Rept, A01151, Advises of Minor Adjustments to Evaluation Program Re Resolution of Cycle 3 Startup Commitments.Adjustments Are to Optimize Timetable for Critical Path Refueling Activities, B10005, Discusses Small Break LOCA ECCS Performance Results. Primarily Effect Function of Sys Characteristics Such as ECCS Flow Rates,Safety Injection Tank Actuation Pressures & Core Power Level.Supporting Info Encl, B10009, Forwards Reload Safety Analysis, Demonstrating That Cycle 4 Reload Assures Continued Conformance to Design & Safety Limits of Facility, B10015, Forwards Large Break Loca/Eccs Performance Results. Analysis Showed double-ended Cold Leg Guillotine Break at Pump Discharge to Be Limiting Large Break.Review of Results Determined That Applicable Fee Was Submitted 800509, B10028, Forwards Addl Info Re Fuel Design & Physics Calculations Per RA Clark 800620 Request.Response to Question 10 Withheld (Ref 10CFR2.790), B10060, Forwards Addl Info Requested by NRC Re Design Mod to Cycle 4 Fuel Assemblies & QA Program in Effect During Design of Cycle 4 Reload Fuel, B10068, Advises That C-E Owners Group 800215,0630 & 0731 Ltrs Re Asymmetric LOCA Loads Are Applicable to Millstone Unit 2 & Should Be Regarded as Util Response to NRC 780125 Request, B10076, Forwards Nonproprietary & Proprietary Repts, Guide Thimble Inset Design. Withholding Application & Affidavit Encl. Proprietary Version Withheld (Ref 10CFR2.790), B10080, Corrects Typographical Error in Tech Spec Table 3.9-1 of Amend 60 to License DPR-65.Doors 292 & 297,listed as Servicing Solidification Sys Area,Should Be 292 & 207, B10084, Submits Addl Info Re Fuel Misload Analysis Performed in Support of Cycle 4 Reload.Procedures Utilized During Fuel Movement Provide Adequate Assurance That Probability of Fuel Misloading Event Is Sufficiently Low to Preclude Analysis, ML19210C634, ML19210C638, ML19253B386, ML19257A505, ML19296B295, ML19296B298, ML19305E096, ML19309B532, ML19309C217, ML19309G003, ML19312E209, ML19312E212, ML19318A345, ML19323C588, ML19323C595, ML19323D864, ML19323H680, ML19330B446, ML19332A343, ML19337A776, ML19338C766, ML19338E936, ML19344D183, ML20076A987, ML20125A706 | |
MONTHYEARML19256A1121978-10-27027 October 1978
[Table View]Application for Amend to License DPR-35,changing Tech Specs to Accomodate New Steamline Break Protection Sys Scheduled for Installation in Spring of 1979.Fee Paid Project stage: Request ML20037A2061979-03-21021 March 1979 Forwards Proprietary Info Presented to NRC at 790126 Meeting Re Reload Application.Info Withheld (Ref 10CFR2.790) Project stage: Meeting ML20076A9871979-04-27027 April 1979 Forwards Proposed Revision to Tech Specs to Allow Unlimited Containment Purges.Revisions Deal W/Containment Isolation Valves Project stage: Other ML19274G1021979-07-31031 July 1979 Forwards Request for Addl Info to Util Proposed Steam Break Protection Sys & N-1 Loop Operation Project stage: RAI ML19207B9461979-08-28028 August 1979 Forwards Addl Info Supporting Tech Specs Change 35 Re Proposed New Steamline Break Protection Sys,In Response to 790731 Request Project stage: Other ML20125A7061979-08-31031 August 1979 Proposed Revisions to Tech Specs to Add Leak Rate Surveillance Requirements to ECCS & Containment Sys Project stage: Other ML19253B3861979-10-0909 October 1979 Discusses Method for Mitigating Control Element Assembly Guide Tube Wear in Fuel Supplied by Westinghouse for Cycle 4.Util Will Use Westinghouse Sleeve Design Project stage: Other ML19210C6341979-11-0909 November 1979 Responds to Re Resolution of Cycle 3 Startup Commitments.Forwards Rept, Evaluation of Neutron Shield Effectiveness Project stage: Other ML19210C6381979-11-30030 November 1979 Evaluation of Neutron Shield Effectiveness Project stage: Other ML19257A5051979-12-31031 December 1979 Responds to NRC 790913 TMI Lessons Learned Task Force short- Term Requirements.All short-term Requirements Will Be Implemented by 800101.Implementation Rept Encl Project stage: Other ML19296B2951980-02-0808 February 1980 Discusses Fuel Cladding Strain & Fuel Assembly Flow Blockage Models for Facility.Analysis Was Performed for Operating Plants W/Ce Fuel.Forwards Analysis Verifying Compliance W/Eccs Acceptance Criteria Project stage: Other ML19296B2981980-02-29029 February 1980 Verification of Compliance W/Eccs Acceptance Criteria of Code Utilizing Conservative Cladding Rupture Strain & Assembly Flow Blockage Models Project stage: Other ML19344D1831980-02-29029 February 1980 Discusses Slightly Diminished Capacity of Charging Pumps to Inject Concentrated Boric Acid Into RCS Under Test Conditions.Change in Peak Clad Temp Due to Smaller Charging Pump Flow Is Not Significant Enough to Be Reportable Project stage: Other ML19290E3391980-03-0606 March 1980 Forwards Basic Safety Rept, in Support of Cycle 4 Reload. Affidavit Encl.Rept Withheld (Ref 10CFR2.790) & Available in Central Files Only Project stage: Other ML19309B5321980-03-26026 March 1980 Forwards Basic Safety Rept. Proprietary Version Withheld (Ref 10CFR2.790).Affidavit Previously Submitted on 800229 & 760727 Project stage: Other ML19309C2171980-03-31031 March 1980 Outlines Plans for Cycle 4 Reload Outage Steam Generator Insp Per Amend 52 to License DPR-65.Resolution of Cycle 3 Startup Commitments Encl Project stage: Other ML19305E0961980-04-15015 April 1980 Submits Info in Support of Continued Operation W/Sleeved Guide Tubes in Cycle 4.Anticipates That Negligible Guide Tube Sleeve Wear Will Be Measured Project stage: Other ML19309G0031980-04-24024 April 1980 Responds to IE Bulletin 79-13, Cracking in Feedwater Sys Piping. Util Conducted Insp During Aug 1979 Outage.Several Crack Indications in nozzle-to-pipe Welds of Both Steam Generators Were Found.All Repairs Completed Project stage: Other ML19323C5881980-05-0707 May 1980 Forwards Revised Steam Generator Insp. Includes Final Dent Progression Statistics Re Mar 1979 Steam Generator Tube eddy-current Insp.Biases Identified in Testing Procedures Have Been Corrected Project stage: Other ML19323D8641980-05-13013 May 1980 Submits Info Re Proposal for Permanent Type Repair of Containment Electrical Penetrations.Penetration Modules Which Have Experienced Insulation Resistance Degradation, Will Be Replaced Project stage: Other B10002, Forwards Proprietary Version of Basic Safety Rept Addendum, Nuclear Uncertainties, Supplementing Rept Section 4.0. Describes Power Peaking Factor Uncertainty Analysis Used in Reload Fuel Design.Rept Withheld (Ref 10CFR2.790)1980-05-28028 May 1980 Forwards Proprietary Version of Basic Safety Rept Addendum, Nuclear Uncertainties, Supplementing Rept Section 4.0. Describes Power Peaking Factor Uncertainty Analysis Used in Reload Fuel Design.Rept Withheld (Ref 10CFR2.790) Project stage: Supplement ML19312E2091980-05-30030 May 1980 Forwards Addendum to Basic Safety Rept Re Nuclear Uncertainties,Nonproprietary Version Project stage: Other ML19323C5951980-05-31031 May 1980 Steam Generator Insp Project stage: Other ML19312E2121980-05-31031 May 1980 Addendum to Basic Safety Rept Re Nuclear Uncertainties, Nonproprietary Version Project stage: Other B10005, Discusses Small Break LOCA ECCS Performance Results. Primarily Effect Function of Sys Characteristics Such as ECCS Flow Rates,Safety Injection Tank Actuation Pressures & Core Power Level.Supporting Info Encl1980-06-0202 June 1980 Discusses Small Break LOCA ECCS Performance Results. Primarily Effect Function of Sys Characteristics Such as ECCS Flow Rates,Safety Injection Tank Actuation Pressures & Core Power Level.Supporting Info Encl Project stage: Other B10009, Forwards Reload Safety Analysis, Demonstrating That Cycle 4 Reload Assures Continued Conformance to Design & Safety Limits of Facility1980-06-0303 June 1980 Forwards Reload Safety Analysis, Demonstrating That Cycle 4 Reload Assures Continued Conformance to Design & Safety Limits of Facility Project stage: Other B10015, Forwards Large Break Loca/Eccs Performance Results. Analysis Showed double-ended Cold Leg Guillotine Break at Pump Discharge to Be Limiting Large Break.Review of Results Determined That Applicable Fee Was Submitted 8005091980-06-11011 June 1980 Forwards Large Break Loca/Eccs Performance Results. Analysis Showed double-ended Cold Leg Guillotine Break at Pump Discharge to Be Limiting Large Break.Review of Results Determined That Applicable Fee Was Submitted 800509 Project stage: Other ML19329G1251980-06-16016 June 1980 Summary of 800604 Meeting W/Util in Bethesda,Md Re Cycle 4 Reload at Facility W/Westinghouse Fuel.List of Attendees & Agenda Encl Project stage: Meeting ML20244B0591980-06-16016 June 1980 Summary of 800604 Meeting W/Util in Bethesda,Md Re Cycle 4 Reload at Facility W/Westinghouse Fuel.List of Attendees & Agenda Encl Project stage: Meeting ML19310A8971980-06-18018 June 1980 Summary of 800318 Meeting W/Util & Westinghouse Re Cycle 4 Reload W/Westinghouse Fuel Project stage: Meeting ML19326D8271980-06-20020 June 1980 Requests Response to Encl Questions Re Fuel Design & Physics Calculations to Complete Review of Basic Safety Rept Supporting Cycle 4 Reload.Requests That Addl Info Be Provided by 800630 to Meet Review Schedule Project stage: Approval ML19323H6801980-06-30030 June 1980 Reload Safety Analysis Project stage: Other ML19318A3451980-06-30030 June 1980 Large Break Loca/Eccs Performance Results Project stage: Other B10028, Forwards Addl Info Re Fuel Design & Physics Calculations Per RA Clark 800620 Request.Response to Question 10 Withheld (Ref 10CFR2.790)1980-07-0707 July 1980 Forwards Addl Info Re Fuel Design & Physics Calculations Per RA Clark 800620 Request.Response to Question 10 Withheld (Ref 10CFR2.790) Project stage: Other ML19330B4461980-07-22022 July 1980 Forwards Addl Response to Questions on Cycle 4 Basic Safety Rept,In Response to .Info in 800707 Submittal Is Not Proprietary to Westinghouse or C-E Project stage: Other ML19332A3431980-08-0606 August 1980 Forwards Addl Info Requests Re Thermal Hydraulics & Accident & Transient Analysis Sections of Basic Safety Rept, & Cycle 4 Reload Safety Analysis.Requests Addl Info,Requested on 800710,18 & 29,by 800815 to Meet Review Schedule Project stage: Other A01085, Forwards Nonproprietary Response to Questions on Cycle 4 Basic Safety Rept1980-08-14014 August 1980 Forwards Nonproprietary Response to Questions on Cycle 4 Basic Safety Rept Project stage: Other A01151, Advises of Minor Adjustments to Evaluation Program Re Resolution of Cycle 3 Startup Commitments.Adjustments Are to Optimize Timetable for Critical Path Refueling Activities1980-08-14014 August 1980 Advises of Minor Adjustments to Evaluation Program Re Resolution of Cycle 3 Startup Commitments.Adjustments Are to Optimize Timetable for Critical Path Refueling Activities Project stage: Other B10060, Forwards Addl Info Requested by NRC Re Design Mod to Cycle 4 Fuel Assemblies & QA Program in Effect During Design of Cycle 4 Reload Fuel1980-08-27027 August 1980 Forwards Addl Info Requested by NRC Re Design Mod to Cycle 4 Fuel Assemblies & QA Program in Effect During Design of Cycle 4 Reload Fuel Project stage: Other B10061, Application for Amend to License DPR-65,incorporating Proposed Revisions to Tech Specs Required to Support Plant Operation During Cycle 4 Reload1980-08-29029 August 1980 Application for Amend to License DPR-65,incorporating Proposed Revisions to Tech Specs Required to Support Plant Operation During Cycle 4 Reload Project stage: Request ML19338C7661980-08-29029 August 1980 Proposed Revisions to Tech Specs Required to Support Plant Operation During Cycle 4 Reload Project stage: Other 05000280/LER-1980-046, Forwards LER 80-046/03L-01980-09-0808 September 1980 Forwards LER 80-046/03L-0 Project stage: Other ML19338E7681980-09-10010 September 1980 Informs That Review of Responses Re ECCS Evaluation Models Dealing W/Fuel Cladding Swelling & Incidence of Rupture Has Been Completed.Response Acceptable Project stage: Approval B10068, Advises That C-E Owners Group 800215,0630 & 0731 Ltrs Re Asymmetric LOCA Loads Are Applicable to Millstone Unit 2 & Should Be Regarded as Util Response to NRC 780125 Request1980-09-10010 September 1980 Advises That C-E Owners Group 800215,0630 & 0731 Ltrs Re Asymmetric LOCA Loads Are Applicable to Millstone Unit 2 & Should Be Regarded as Util Response to NRC 780125 Request Project stage: Other B10076, Forwards Nonproprietary & Proprietary Repts, Guide Thimble Inset Design. Withholding Application & Affidavit Encl. Proprietary Version Withheld (Ref 10CFR2.790)1980-09-18018 September 1980 Forwards Nonproprietary & Proprietary Repts, Guide Thimble Inset Design. Withholding Application & Affidavit Encl. Proprietary Version Withheld (Ref 10CFR2.790) Project stage: Other B10080, Corrects Typographical Error in Tech Spec Table 3.9-1 of Amend 60 to License DPR-65.Doors 292 & 297,listed as Servicing Solidification Sys Area,Should Be 292 & 2071980-09-22022 September 1980 Corrects Typographical Error in Tech Spec Table 3.9-1 of Amend 60 to License DPR-65.Doors 292 & 297,listed as Servicing Solidification Sys Area,Should Be 292 & 207 Project stage: Other B10084, Submits Addl Info Re Fuel Misload Analysis Performed in Support of Cycle 4 Reload.Procedures Utilized During Fuel Movement Provide Adequate Assurance That Probability of Fuel Misloading Event Is Sufficiently Low to Preclude Analysis1980-09-26026 September 1980 Submits Addl Info Re Fuel Misload Analysis Performed in Support of Cycle 4 Reload.Procedures Utilized During Fuel Movement Provide Adequate Assurance That Probability of Fuel Misloading Event Is Sufficiently Low to Preclude Analysis Project stage: Other ML19338E9361980-09-30030 September 1980 Proposed Revision to Tech Specs 3/4 2-3 for Amend 55 to License DPR-65.Authorizes Performance of Tests at Reduced RCS Inlet Temps in Order to Quantify Secondary Plant Performance Losses.Low Temp Testing Safety Review Encl Project stage: Other ML19337A7761980-09-30030 September 1980 Guide Thimble Inset Design, Nonproprietary Version Project stage: Other B10092, Application to Amend License DPR-65 Authorizing Performance of Tests at Reduced RCS Inlet Temps in Order to Quantify Secondary Plant Performance Losses1980-09-30030 September 1980 Application to Amend License DPR-65 Authorizing Performance of Tests at Reduced RCS Inlet Temps in Order to Quantify Secondary Plant Performance Losses Project stage: Request 1980-05-31 |
| ML18139A743 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 09/08/1980 |
| From: | Joshua Wilson VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| Shared Package | |
| ML18139A744 | List: |
| References | |
| 034, 34, TAC-11348, TAC-11561, TAC-12505, TAC-42846, NUDOCS 8009150274 | |
| Download: ML18139A743 (1) | |
Similar Documents at Surry | |
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| Event date: | |
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| Report date: | |
| 2801980046R00 - NRC Website | |
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p SEP 8 1980
?Jr. James*P. O'Reilly, Director Office of Inspection and Enforcement U.S. Ifoclear Regulatory Commission Region II 101 Harietta Street, Suite 3100 Atlanta, Georgia 30303
Dear ~lr. 0 1 Reilly:
VIRGINIA ELECTRIC AND POWER COMP ANY Surry Power Station P. 0. Box 315 Surry, Virginia 23883 Serial Uo:
034 Docket No:
50-280 License No:
DPR-32 Pursuant to Surry Power Station Technical Specifications, the Virginia Electric and Power. Company hereby submits the following Licensee Event r,eport for Surry Unit No. 1.
Report No.
Applicable Technical Specifications 80-046/031-0 6. 6
- 2. b * ( 2)
This report has been reviewed by the Station Nuclear Safety and Operating Cor.unittee and will be placed on the agenda for the next meeting of the System nuclear Safety and Operating Committee.
Enclosure cc:
Hr. Victor Stello, Director (3)
Office of Inspection and Enforcement 11r. Norn.an Haller, Di rec tor (3)
Office of llanagement and Program Analysis
- s Yorn vi;y, J. L. Wilson Uanager