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MONTHYEARML20204A2801982-08-18018 August 1982
Instructions for Calculation of Offsite Dose from Limiting Primary Sys Break Which Does Not Isolate Primary Containment Vent & Purge Valves
Project stage: Other
ML20076J5441983-08-31031 August 1983
Comments on 810629 Generic Evaluation of NUREG-0737,Item II.E.4.2 Containment Purge & Vent Valve High Radiation Isolation. Automatic Isolation of Containment Purge & Vent Valves on High Containment Radiation Unnecessary
Project stage: Other
ML20084P5971984-04-10010 April 1984
Forwards Final Design Criteria for Resolution of NUREG-0737, Item II.E.4.2(7), Purge & Vent Valve Isolation, Requiring Automatic Isolation of Containment Purge & Vent Valves on High Containment Radiation
Project stage: Other
ML20084L3701984-05-0707 May 1984
Forwards Figures 1 & 2,inadvertently Omitted from 840410 Submittal,Providing Description of Mods Planned to Satisfy Purge & Vent Valve Isolation Requirements of TMI Item II.E.4.2
Project stage: Other
ML20097A7211984-09-0505 September 1984
Proposed Amend to Tech Specs,Reflecting Implementation of NUREG-0737,Item II.E.4.2(7) Re Automatic Closure of Containment Purge & Vent Valves on High Containment Radiation Signal
Project stage: Other
ML20097A7121984-09-0505 September 1984
Application to Amend License NPF-5,changing Tech Specs to Reflect Implementation of NUREG-0737,Item II.E.4.2(7) Re Containment Purge & Vent Valves.Change Adds Limiting Conditions for Operation & Surveillance Requirements
Project stage: Request
ML20128A0331985-06-25025 June 1985
Forwards Inservice Insp Program,1980 Edition of ASME Section XI W/Addenda Through Winter 1981, Effective 860101. Interim Relief Requested in Event That Final Review/Approval Not Provided by Program Effective Date.Fee Paid
Project stage: Request
PNO-II-85-071, on 850724,unit Tripped as Result of High Steam Flow Signal.Caused by Malfunctioning Msiv.Unit out-of-svc for 3 to 5 Days While Valve Repaired & Maint Work Performed1985-07-25025 July 1985
PNO-II-85-071:on 850724,unit Tripped as Result of High Steam Flow Signal.Caused by Malfunctioning Msiv.Unit out-of-svc for 3 to 5 Days While Valve Repaired & Maint Work Performed
Project stage: Request
ML20137F9931985-08-20020 August 1985
Proposed Revs to Tech Spec Tables 3.2-1 & 4.2-1 Re Purge/Vent Valve Isolation
Project stage: Other
ML20137F9761985-08-20020 August 1985
Application for Amend to License DPR-57,reflecting Addition of High Radiation Isolation Signal for Containment Purge & Vent Valves.Fee Paid
Project stage: Request
ML20138B2331985-10-0404 October 1985
Informs That Util on Purge & Vent Mods Contained Proposed Tech Spec Requirements More Restrictive than Those Reviewed by Plant Review Board.Board Will Review Requirements by 851010
Project stage: Other
ML20136A7651985-12-23023 December 1985
Forwards Request for Addl Info Re Inservice Insp Program for Second 10-yr Interval.Response Requested within 30 Days of Ltr Receipt
Project stage: RAI
ML20137E9761986-01-0707 January 1986
Application for Amend to License DPR-57,changing Tech Specs to Add High Radiation Isolation Signal to Containment Purge & Vent Valves.Thirty Days Requested Between Dates of Issue & Effectiveness to Allow Time for Procedure Rev
Project stage: Request
ML20244D7371986-03-11011 March 1986
Forwards Safety Evaluation Accepting BWR Owners Group 850620 Request for Review of Offsite Radiological Consequences for Accidental Releases Not Meeting NUREG-0737, Item II.E.4.2(7).Regulatory Analysis Also Encl
Project stage: Approval
ML20204A2781986-04-28028 April 1986
Forwards Request for Addl Info Re Request for Rev to Tech Specs to Reflect Addition of Closure of Containment Purge & Vent Valves on High Containment Radiation Signal.Response Requested within 60 Days
Project stage: RAI
ML20199K5171986-06-26026 June 1986
Forwards Response to 860428 Request for Info Re Automatic Isolation of Containment Purge & Vent Valves on High Containment Radiation Signal.Procedures for Venting Containment Have Separate Sections for Drywell & Torus
Project stage: Request
ML20235L7161987-07-14014 July 1987
Amends 143 & 78 to Licenses DPR-57 & NPF-5,respectively, Modifying Tech Specs by Adding Limiting Conditions for Operation,Trip Setpoints & Surveillance Requirements for Monitors
Project stage: Other
ML20235L7221987-07-14014 July 1987
Safety Evaluation Supporting Amends 143 & 78 to Licenses DPR-57 & NPF-5,respectively
Project stage: Approval
1985-06-25
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Similar Documents at Hatch |
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Text
Georgs Power Company
. 333 Padmont Avenue.'
At:anta, Georg.a 30308 Telephone 404 5266526 MaIng Alfress- -
Post Offce Box 4545 Asanta Georg.a 30302 b
Georgia Power L T. Gucwa N nymn ewfr,c system Manager Nuclear Engineering ard Chet Nuctear Eroneer NED-85-752 1617N October 4, 1985 Director of Nuclear Reactor Regulation Attention: Mr. John F. Stolz, Chief Operating Reactors Branch No. 4 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D. C.
20555 NRC DOCKETS 50-321, 50-366 OPERATING LICENSES DPR-57, NPF-5 EDWIN I. HATCH NUCLEAR PLANT UNITS 1, 2 PURGE AND VENT MODIFICATIONS Gentlemen:
Georgia Power Company provides the following for your information: Our August 20, 1985, letter on purge and vent modifications contained proposed Technical Specification requirements which,were more restrictive than those reviewed by the Plant Review Board.
Those additional requirements will have been reviewed by the Plant Review Board by October 10, 1985.
If you have any questions, please contact this office.
Very truly yours, f r c;t - - m L. T. Gucwa MJB/mb xc:. H. C. Nix, Jr.
Senior Resident Inspector
-J. N. Grace, (NRC-Region II)
Ot L
'\\0 8510150289 851004 PDR ADOCK 05000321 P
PDR
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