Letter Sequence Approval |
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Results
Other: B10927, Provides Summary of Reevaluations of LOCA Based on Identification of Several Assemblies Containing Leaking Fuel Pins & fuel-related Damage Which Necessitated Rev to Cycle 6 Core Loading Pattern, B11486, Forwards Small Break Loca/Eccs Performance Analysis W/Axial Shape Index of -0.10. Encl Analysis Amends Loca/Eccs Analysis Provided in Per 10CFR50,App K-II.1.b. Previous Reviews Re Effects of Reloads Remain Valid, B11561, Forwards Reload Safety Analysis in Support of Cycle 7 Reload.Core Reload Will Not Adversely Affect Plant Safety, B11568, Forwards Results of Core Barrel Insp Performed During Cycle 7 Refueling outage.Through-wall Cracks at Thermal Shield Support Lugs 4 & 5 Not Propagated, B11570, Highlights Recent Major Milestones in Fuel Performance Program.Three Investigations Conducted During Last Half of Cycle 6 Operation & Weld Defects Probed.No Significant mfg- Related Failure Mechanisms Noted, ML20107A012, ML20115J066, ML20126C726, ML20126J181, ML20128D276
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MONTHYEARB10927, Provides Summary of Reevaluations of LOCA Based on Identification of Several Assemblies Containing Leaking Fuel Pins & fuel-related Damage Which Necessitated Rev to Cycle 6 Core Loading Pattern1983-11-0202 November 1983 Provides Summary of Reevaluations of LOCA Based on Identification of Several Assemblies Containing Leaking Fuel Pins & fuel-related Damage Which Necessitated Rev to Cycle 6 Core Loading Pattern Project stage: Other B11437, Application for Amend to License DPR-65,consisting of Proposed Revs to Tech Specs for Preliminary Reload Safety Analysis Re Cycle 7 Refueling1985-02-0606 February 1985 Application for Amend to License DPR-65,consisting of Proposed Revs to Tech Specs for Preliminary Reload Safety Analysis Re Cycle 7 Refueling Project stage: Request ML20107A0121985-02-0606 February 1985 Proposed Tech Spec Changes for Preliminary Reload Safety Analysis Re Cycle 7 Refueling Project stage: Other B11486, Forwards Small Break Loca/Eccs Performance Analysis W/Axial Shape Index of -0.10. Encl Analysis Amends Loca/Eccs Analysis Provided in Per 10CFR50,App K-II.1.b. Previous Reviews Re Effects of Reloads Remain Valid1985-04-11011 April 1985 Forwards Small Break Loca/Eccs Performance Analysis W/Axial Shape Index of -0.10. Encl Analysis Amends Loca/Eccs Analysis Provided in Per 10CFR50,App K-II.1.b. Previous Reviews Re Effects of Reloads Remain Valid Project stage: Other ML20115J0661985-04-30030 April 1985 Small Break Loca/Eccs Performance Analysis W/Axial Shape Index of -0.10 Project stage: Other B11561, Forwards Reload Safety Analysis in Support of Cycle 7 Reload.Core Reload Will Not Adversely Affect Plant Safety1985-06-0505 June 1985 Forwards Reload Safety Analysis in Support of Cycle 7 Reload.Core Reload Will Not Adversely Affect Plant Safety Project stage: Other ML20126C7261985-06-11011 June 1985 Proposed Revs to Tech Spec Sections 3.2.1,Page 3/4 2-1 & 3.2.2.2,Page 3/4 2-6 Re Cycle 7 Reload Project stage: Other B11570, Highlights Recent Major Milestones in Fuel Performance Program.Three Investigations Conducted During Last Half of Cycle 6 Operation & Weld Defects Probed.No Significant mfg- Related Failure Mechanisms Noted1985-06-11011 June 1985 Highlights Recent Major Milestones in Fuel Performance Program.Three Investigations Conducted During Last Half of Cycle 6 Operation & Weld Defects Probed.No Significant mfg- Related Failure Mechanisms Noted Project stage: Other B11568, Forwards Results of Core Barrel Insp Performed During Cycle 7 Refueling outage.Through-wall Cracks at Thermal Shield Support Lugs 4 & 5 Not Propagated1985-06-11011 June 1985 Forwards Results of Core Barrel Insp Performed During Cycle 7 Refueling outage.Through-wall Cracks at Thermal Shield Support Lugs 4 & 5 Not Propagated Project stage: Other B11569, Application for Amend to License DPR-65,revising Tech Spec Sections 3.2.1,Page 3/4 2-1 & 3.2.2.2,Page 3/4 2-6 Re Cycle 7 Reload,Based on Discussions W/Nrc1985-06-11011 June 1985 Application for Amend to License DPR-65,revising Tech Spec Sections 3.2.1,Page 3/4 2-1 & 3.2.2.2,Page 3/4 2-6 Re Cycle 7 Reload,Based on Discussions W/Nrc Project stage: Request ML20128D2851985-06-19019 June 1985 Safety Evaluation Supporting Amend 99 to License DPR-65 Project stage: Approval ML20128D2631985-06-19019 June 1985 Forwards Amend 99 to License DPR-65 & Safety Evaluation. Amend Revises Tech Specs to Modify Allowable Region of Operation When Core Power Distribution Monitored by ex-core Detector Monitoring Sys.Revs Reflect Changes in Cycle 7 Project stage: Approval ML20128D2761985-06-19019 June 1985 Amend 99 to License DPR-65,revising Tech Specs Re Allowable Region of Operation When Core Power Distribution Monitored by ex-core Detector Monitoring Sys Project stage: Other B11590, Forwards Supplemental Info Describing Zone Enriched Assembly Configuration Implemented in Feed Fuel Regions for Cycle 71985-06-25025 June 1985 Forwards Supplemental Info Describing Zone Enriched Assembly Configuration Implemented in Feed Fuel Regions for Cycle 7 Project stage: Supplement ML20126J1811985-06-30030 June 1985 Cycle 7 Final Reload Safety Analysis Project stage: Other 1985-06-11
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June 19, 1985 Docket No. 50-336 DISTRIBUTION:
. Docket File-LTremper NRC PDR RDiggs L PDR ACRS-10 Mr. John F. Opeka, Senior Vice President SECY WJones Nuclear Engineering and Operations ORB #3 Rdg TBarnhart-4 Northeast Nuclear Energy Company HThompson MVirgilio P. O. Box 270 PMKreutzer-3 EJordan Hartford, Connecticut 06141-0270 DB0sborne LJHarmon OELD CMiles
Dear Mr. Opeka:
Gray File +4 BGrimes The Commission has issued the enclosed Amendment No. 99 to Facility Operating License No. DPR-65 for Millstone Nuclear Power Station, Unit No. 2, in response to your application dated February 6,1985 as supplemented June 5 and June 11, 1985.
These revisions to the Technical Specifications modify the allowable region of operation when the core power distribution is monitored by the Excore Detector Monitoring System. These revisions reflect changes in Cycle 7 operating characteristics and allow operation in fuel Cycle 7.
A copy of our Safety Evaluation is also enclosed. The notice of issuance will be included in the Commission's next biweekly Federal Register notice.
Sincerely,
/S/
D. B. Osborne, Project Manager Operating Reactors Branch #3 Division of Licensing
Enclosures:
1.
Amendment No. 99 to DPR-65 2.
Safety Evaluation cc w/ enclosures:
See next page I
ORB #3:DL ORB #.
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0507050069 050619 PDR ADOCK 05000336 P
PDR
Mr. John F. Opeka Millstone Nuclear Power Station Northeast Nuclear Energy Company Unit No. 2 CC:
Gerald Garfield, Esq.
Mr. Wayne D. Romberg Day, Berry & Howard Superintendent Counselors at Law Millstone Nuclear Power Station City Place P. O. Box 128 Hartford, Connecticut 06103-3499 Waterford, Connecticut 06385 Regional Administrator, Region I Mr. Edward J. Mroczka U.S. Nuclear Regulatory Commission Vice President, Nuclear Operations Office of Executive Director for Northeast Nuclear Energy Company Operations P. O. Box 270 631 Park Avenue Hartford, Connecticut 06101 King of Prussia, Pennsylvania 19406 Mr. Charles Brinkman, Manager Washington Nuclear Operations C-E Power Systems Combustion Engineering, Inc.
7910 Woodmont Avenue Bethesda, Maryland 20814 Mr. Lawrence Bettencourt, First Selectman Town of Waterford Hall of Records - 200 Boston Post Road Waterford, Connecticut 06385 Northeast Utilities Service Company ATTN: Mr. Richard R. Laudenat Manager Generation Facilities Licensing Post Office Box 270 Hartford, Connecticut 06101 Arthur Heubner, Director Radiation Control Unit Department of Environmental Protection State Office Building Hartford, Connecticut 06116 Mr. John Shediosky Resident Inspector / Millstone Box 811 Niantic, Connecticut 06357 Office of Policy & Management ATTN: Under Secretary Energy Division 80 Washington Street Hartford, Connecticut 06115