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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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Georg a Pow Company 333 Pedrnant Avenue Atlanta. Gecwg!a 30308
- Telephone 404 526-6526 MaAng Address Pos' Offce Box 4545 m
At anta. Georgia 30302 Georgia Power Power Generation Department -
44 August 31, 1983 Director of Nuclear Reactor Regulation Attention: Mr. John F. Stolz, Chief Operating Reactors Branch No. 4 Division of Licensing U. S. Nuclear Regulatory Consnission Washirgton, D. C.
20555 NRC DOCKm s 50-321, 50-366 OPERATING LICENSES DPR-57, NPF-5 ENIN I. HATCI NUCLEAR PIANP UNITS 1, 2 NUREG-0737 ITDi II.E.4.2(7) CONTAINMENT PUIGE AND VENT VALVE HIGH PADIATION ISOLATION Gentlemen:
The NR Owners Group subnitted a generic evaluation of the subject item by T. J. Dente's letter of June 29, 1981.
The Owners Group position, which was endorsed by Georgia Power Conpany (GPC) was that automatic isolation of contairunent purge and vent valves on high containment radiation was not necessary for Mark I and II plants.
%e basis for this conclusion was that:
(1) the purge and vent valves are normally closed, (2) there are existing separate, diverse signals for automatic closure of these valves, (3) various signals would alert operators to manually close these valves, and (4) the radiological consequences of a break which would not automatically isolate the purge and vent valves are acceptably low.
Additional information supporting this position was provided by the Owners Group in a November 19, 1981, meeting and by T. J. Dente's letter of June 14, 1982.
l Your letter of July 29, 1981, transmitted to GPC two NRC staff Safety Evaluations in which it was concluded that the Owners Group position was not acceptable.
%e staff considers a high radiation isolation signal necessary l
to reduce the reliance on operator action and on indirect parameters such as l
high drywell pressure and low reactor water level for timely isolation of I
purge and vent valves.
t i
8309070229 830831 PDR ADOCK 05000321 P
PDR
Georgia Power A Director of Nuclear Reactor Regulation Attention: Mr. John F. Stolz, Chief Operating Reactors Branch No. 4 August 31, 1983 Page Two While GPC shares the staff's desire to prevent an excessive release of radioactivity through purge and vent valves during accident conditions, we maintain-that the present containment isolation design at Plant Hatch adequately serves this purpose. We consider the addition of a high radiation signal for purge and vent valve isolation an unnecessary conservatism.
However, we are willing to make this modification to the Hatch units in the interest of resolving Item II.E.4.2(7). GPC will sutait a description of the intended modification by November 1,
1983.
Installation will take place during the first refueling outage follc, wing conpletion of _ design and parts procurement. We estimate that this will be accomplished for Unit 1 by the end of the refueling outage following Cycle 7, currently scheduled for 1985, and for Unit 2 by the end of the refueling outage followi-- Cycle 5, currently scheduled for 1985.
Because this modification represent.s an increase in the conservatism of the contairnent isolation design rather than correction of a deficiency, GPC considers no interim compensatory measures necessary and plans no action in this regard.
Please contact this office if there are any questions.
Very truly yours, qv H. C. Nix, Jr.
General Manager JH/mb xc:
J. T. Beckham, Jr.
Senior Resident Inspector t
l J. P. O'Reilly (NRC-Region II) l 700775 W
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