Letter Sequence Other |
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Results
Other: ML19350D413, ML19350D417, ML20028C826, ML20032D142, ML20041F645, ML20054E028, ML20054E548, ML20054F828, ML20054F837, ML20069B852, ML20070W176, ML20071P933, ML20077J689, ML20080E860
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MONTHYEARML20003F4831981-04-0202 April 1981
Application to Amend License DPR-57,revising Diesel Generator Operability Requirements When Reactor Is in Shutdown or Refuel Modes & Fuel Is Not in Reactor Pressure Vessel
Project stage: Request
ML20003F5031981-04-0202 April 1981
Proposed Changes to Tech Spec Page 3.9-6
Project stage: Request
ML19350D4131981-04-0808 April 1981
Amend 82 to License DPR-57,relieving Licensee of Necessity to Maintain Two Operable Diesel Generators When Fuel Has Been Removed from Reactor Vessel
Project stage: Other
ML19350D4171981-04-0808 April 1981
Notice of Issuance & Availability of Amend 82 to License DPR-57
Project stage: Other
ML20032D1421981-11-0404 November 1981
Requests Exception to NUREG-0737,Item II.F.1.2 Re Effluent Monitoring of Radioiodines for Accident Conditions
Project stage: Other
ML20041F6451982-03-0505 March 1982
Responds to Re Deviations from Design Specs or Schedule Implementing NUREG-0737 Item II.F.1.3,accident Monitoring.Due to Inability to Obtain Parts & Documentation for Complete Installation,Extension Was Requested on 811104
Project stage: Other
ML20054E0281982-04-20020 April 1982
Forwards Completion Schedule for NUREG-0737 Requirements & Explanation of Requested Extensions of Schedule for Certain Items
Project stage: Other
ML20054E5481982-06-0404 June 1982
Forwards Response to 820505 Generic Ltr 82-10 Re post-TMI Requirement Implementation Schedule,Per NUREG-0737
Project stage: Other
ML20054F8371982-06-0707 June 1982
Forwards NUREG-0737 post-TMI Requirements Implementation Schedule Revision & Explanation in Response to Generic Ltr 82-05 & 820526 Request.Info Supersedes
Project stage: Other
ML20054F8281982-06-11011 June 1982
Revises Implementation Completion Date to Sept 1983 for NUREG-0737,Item II.K.3.22 Re Automation of Reactor Core Isolation Cooling Suction Transfer
Project stage: Other
ML20071P9331982-12-20020 December 1982
Revises Estimated Completion Date for Implementation of NUREG-0737,Item II.B.3 to 830401,in Response to Generic Ltr 82-05.Interim Sampling Capabilities Per NUREG-0578 Provided in
Project stage: Other
ML20028C8261983-01-0707 January 1983
Notifies of Intention to Revise Schedule for Implementation of NUREG-0737,Items I.C.1, Revise Emergency Procedures & III.A.2.2, Meteorological Data, in Response to Generic Ltr 82-33
Project stage: Other
ML20070Q7891983-01-18018 January 1983
Informs That Response to NRC 821217 Request for Addl Info in Support of post-implementation Review of NUREG-0737,Items II.F.1.4,II.F.1.5 & II.F.1.6 Cannot Be Submitted within 30 Days.All Requested Info Will Be Submitted by 830419
Project stage: Request
ML20070W1761983-02-11011 February 1983
Advises That Implementation of NUREG-0737,Items II.F.1(1) Re Noble Gas Effluent Monitor & II.F.1(2) Re Sampling & Analysis of Plant Effluents,Will Be Delayed Until 830315 Due to Component Failure
Project stage: Other
ML20069B8521983-03-11011 March 1983
Revises Estimated Completion Date to 830701 for Implementation of NUREG-0737,Item II.B.3, Post-Accident Sampling. Grab Sample Analysis Will Be Used in Interim
Project stage: Other
ML20077J6891983-08-15015 August 1983
Clarifies Re Schedule for Implementation of NUREG-0737,Item II.F.1(1), Noble Gas Effluent Monitor & II.F.1(2), Sampling & Analysis of Plant Effluents. Third high-range Monitor Installed.Implementation Completed
Project stage: Other
ML20080E8601984-02-0303 February 1984
Discusses Time at Which Hydrogen Monitoring Is Initiated. Intent of TMI Item II.F.1(6) Is to Ensure Timely Hydrogen Monitoring in Event of Core Uncovery During Loca.Definition for Onset of LOCA Undefinable
Project stage: Other
1982-06-04
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Director of Nuclear Reactor Regulation 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 IMPLEMENTATION SCHEDULE CLARIFICATION FOR NUREG-0737 II.K.3.22 Gentlemen:
Our letter of June 7,1982, provided a schedule for implementation for various NUREG-0737 ret.uirements in response to your letter of March 17, 1982 (Generic letter number 82-05).
The schedule provided therein was referenced to the first refueling outage after the anticipated completion of an item.
Mr. Morton Fairtile noted in a telephone conversation with a member of our staff on June 11, 1982, that this method of reference resulted in a schedule for completion of Item II.K.3.22, Automation of Reactor Core Isolation Cooling (RCIC) Suction Transfer which was misleadingly long.
As stated in the " Schedule Explanation", Enclosure 2 to our June 7, 1982 letter, provisions for installation will be or have been made on Unit 1 and 2,
respectively, during the 1982 refueling outages in those areas inaccessible during normal operation.
These provisions will allow installation of a qualified level switch, which is pending procurement, while the units are in operation.
It is our intention to conduct such installation after receipt of the subject switch regardless of the operational condition of the respective unit.
The expected delivery date for the subject switches is June of 1983.
We have, therefore, scheduled installation by September 1983.
The references to the scheduled completion date for Item II.K.3.22 can be revised to September 1983 rather than the listed "End of Refueling outage following cycle 6 (for Unit 1, cycle 4 for Unit 2), currently scheduled for Spring, 1984" in Enclosures 1 and 2 of our June 7, 1982 letter.
We hope that this clarification adequately addresses the questions raised by Mr.
Fairtile.
ndt 8206170365 820611 PDR ADOCK 05000321 P
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t Georgia Power d Director of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission June 11, 1982 Page Two If further information or clarification is required, please contact this office.
Yours truly, 7g.f. d. Zu um W. A. Widner WEB /mb xc:
H. C. Nix, Jr.
R. F. Rogers, III J. P. O'Reilly (NRC-Region II)
