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 to 830701 for Implementation of NUREG-0737,Item II.B.3, Post-Accident Sampling. Grab Sample Analysis Will Be Used in Interim| ML20069B852 |
| Person / Time |
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| Site: |
Hatch  |
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| Issue date: |
03/11/1983 |
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| From: |
Beckham J
GEORGIA POWER CO. |
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| To: |
Stolz J
Office of Nuclear Reactor Regulation |
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| References |
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| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.B.3, TASK-TM GL-82-05, GL-82-10, GL-82-5, NED-83-152, TAC-48451, TAC-48452, TAC-48505, TAC-48506, NUDOCS 8303170300 |
| Download: ML20069B852 (2) |
|
Similar Documents at Hatch |
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Text
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' Georgia Power Comparty
?
333 Piedmont Avenuo Atlanta, Georgia 30308 Telephone 404 526 7020 Mailing Address:
Post Office Box 4545 Atlanta, Georgia 30302 Georgia Power the southem electnc system J. T. Beckham, Jr.
Vice President and General Manager i
Nuclear Generation ED-83-152 March 11, 1983 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.
4 EDWIN I. HATCH NUCLEAR PLANT UNITS 1, 2 NUREG-0737 ITEM II.B.3 IWLEENTATION SCHEDULE Gentlemen:
In Georgia Power Company's letters of June 7, 1982. and December 20, 1982, schedules for implementation of NUREG-0737 Item II.B.3, Post-Accident '
Sampling Capability, were proposed for Hatch Unit 2
and Unit 1,
respectively.
It was estimated that implementation of Item II.B.3 would be completed by April.1,1983 for Unit 1 and by the end of the outage following Cycle 3 for Unit 2.
GPC hereby revises ' the estimated completion dates for Its II.B.3 to
+
July 1,1983 for both Unit 1 and Unit 2.
As discussed with Mr. George L
Rivenoark on March 4,1983, several recently identified factors contribute r
to this delay.
[
The vendor of the on-line chloride analysis portion of the Post-Accident Sample Systs (PASS) has recently recommended that their equipment not be
- installed as delivered.
They have indicated that. the lifetime. of the chloride electrode' in a simulated post-accident environment is unacceptably short, but-that several' promising approaches to increasing its lifetime are
- currently under investigation.
Recognizing that on-line chloride analysis of post-accident reactor coolant samples is a state of the art technology, i
GPC feels that a three-month schedule allowance would be prudent.
In the event that on-line chloride analysis is not ~ available, grab sample analysis I
will be used.
Furthermore, we are concerned that other electronic components may require replacement.
This presents a potential delay of up to two months.
The need will not be known until system testing has been j_
conducted.
!j' Considering the aforementioned factors and the availability of interim
' measures for post-accident sampling, GPC considers the July 1,
1983 imp 1 mentation date for the Plant Hatch PASS to be justified.
!!!158!!o!888 sit ik/
I P
PDR
-. _ _. _.... _,, _ _ _... _ _ _. _ _ _ _ _ _ _ _ _ _ _.. ~. _ _ _ _ _ _ _ _
Georgia Power d Director of Nuclear Reactor Regulation Attention: Mr. John F. Stolz, Chief Operating Reactors Branch No. 4 March 11, 1983 Page Two Please contact this office if there are any questions.
Very truly yours, k
AA o_(
J. T. Beckham, Jr.
JH/mb' xc:
H. C. Nix, Jr.
J. P. O'Reilly (NRC-Region II) 1 Senior Resident Inspector 4
i 700775
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