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
[Table View] |
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| ML20071P933 |
| Person / Time |
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| Site: |
Hatch  |
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| Issue date: |
12/20/1982 |
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| From: |
Gucwa L
GEORGIA POWER CO. |
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| To: |
Office of Nuclear Reactor Regulation |
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| References |
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| RTR-NUREG-0578, RTR-NUREG-0737, RTR-NUREG-578, RTR-NUREG-737, TASK-2.B.3, TASK-TM GL-82-05, GL-82-5, TAC-48451, TAC-48452, TAC-48505, TAC-48506, NUDOCS 8212290151 |
| Download: ML20071P933 (1) |
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Similar Documents at Hatch |
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Text
oma row cowy 333 Piedvd A <enue A!!a"ta G.;, ma 30308 TehSnore 404 526 6S26 MOng AJJws, Per Offse Box 4545 A
Ama c~o amo2 December 20, 1982 Georgia Power Power Generation Department Director of Nuclear Reactor Regulation U.S. Nuclear Regulatory Connission Washington, D. C.
20555 NRC 00CKETS 50-321, 50-366 OPERATING LICENSES DPR-57, NPF-5 EDWIN I. HATCH NUCLEAR PLANT UNITS 1, 2 POST TMI REQUIREMENT II.B.3 IMPLEMENTATION SCHEDULE Gentlemen:
Georgia Power Company's letter of June 7,1982, proposed a schedule for implementation of a number of NUREG-0737 requirements in response to the NRC's Generic Letter 82-05.
Among these requirements was Item II.B.3
" Post-Accident Sampling Capability".
It was estimated that this modification would be implemented in Plant Hatch Unit 1 by the end of the outage following cycle SB, which is currently in progress.
Georgia Power Company hereby revises our estimate of the completion date for the implementation of Item II.B.3 in Unit 1 to April 1,
1983.
As discussed with Mr. Morton Fairtile on December 16, 1982, this redefinition of completion date is necessary due to the shortening of the Unit 1 outage by approximately seven weeks from the estimates in effect at the time of our June 7, 1982 letter. Although work on this system is being expedited to the extent possible, it is not expected that full implementation can be accomplished by the revised expected startup date of early February 1983.
As discussed in our June 7, 1982 letter, interim measures for obtaining reactor coolant and d.ywell atmosphere samples under post-accident conditions were provided in response to NUREG-0578.
Because of this interim sampling capability, and because the calendar date estimated for the completion of the Unit 1 outage at the time of our June 7, 1982 letter corresponded approximately to the present April I estimate (albeit not defined as such in that letter), we consider the health and safety of the public to be unaffected by this redefinition of the completion date.
Please contact this office if you have any questions concerning this matter.
Yours very truly,
[I 4%
L. T. Gucwa JH/wb xc:
J. T. Beckham, Jr.
H. C. Nix, Jr.
J. P. O'Reilly Senior Resident Inspector b
8212290151 821220 PDR ADOCK 05000321 P
PDR