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MONTHYEARML20003F5031981-04-0202 April 1981 Proposed Changes to Tech Spec Page 3.9-6 Project stage: Request ML20003F4831981-04-0202 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 ML19350D4171981-04-0808 April 1981 Notice of Issuance & Availability of Amend 82 to License DPR-57 Project stage: Other 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 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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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| ML20077J689 |
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| Site: |
Hatch  |
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| Issue date: |
08/15/1983 |
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| From: |
Gucwa L 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.F.1, TASK-TM NED-83-417, TAC-47604, TAC-47605, TAC-47746, TAC-47747, NUDOCS 8308180163 |
| Download: ML20077J689 (2) |
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Text
Georg:a Power Company 333 P edmont Avenue Atlanta. Georg:a 30308 Telephone 404 526 6526 Mamnq Address Post Omce Box 4545 Atlanta Georg a 30302 b
Georgia Power L T. Gucwa r e san >wn eMuc sywm Ch.ef Nuclea' Engineer Power Generation Department NED-83-417 August 15, 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 EDWIN I. HATCH NUCLEAR PLANT UNITS 1, 2 NUREG-0737 ITEM II.F.l(2), SAMPLING AND ANALYSIS OF PLANT EFFLUENTS Gentlemen:
Our letter of February 11, 1983 addressed the schedule for implementation of NUREG-0737 Items II.F.l(l), Noble Gas Effluent Monitor, and II.F.l(2),
Samplir.g and Analysis of Plant Effluents, at Plant Hatch Unit 1.
Recent discussions with Mr.
George Rivenbark have indicated the need for clarification of a portion of that letter.
In that letter it was stated that implementation of Items II.F.1(1) and II.F.l(2) involved the installation of high-range gaseous effluent monitors at the Main Stack and Reactor Building Vent Plenum.
It was further stated that each high-range monitor utilized five Geiger-Muller (GM) detectors, two for noble gas monitoring and three for the monitoring of iodine and particulate collectors. The latter statement could be construed to mean that GM detectors are used to determine particulate and iodine releases, but such is not the case.
The quantification of releases is done by sampling with separate laboratory analysis. The purpose of the GM detectors is as follows:
When the high-range monitor automatically starts, the sample flow is directed through one of three parallel filter /adsorbers.
A GM detector monitors the buildup of radioactive iodine and particulates and, when a predetermined radiation level is detected, causes the flow to be diverted to another filter /adsorber and actuates an alarm to alert plant personnel.
The first filter /adsorber can then be removed and transported to the laboratory for analysis and a " clean" one installed in its place.
All three filter /adsorbers function in a similar manner.
0 9308180163 830815 PDR ADOCK 05000321 P
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a GeorgiaPower b 4
Director of Nuclear Reactor Regulation Attention: Mr. John F. Stolz, Chief Operating Reactors Branch No. 4 August 15, 1983 Page Two Georgia Power Company considers this arrangement to be in compliance with the criteria of NUREG-0737 Item II.F.l(2).
We also note that a third high-range monitor has been installed at the Unit 2 Reactor Building Vent Plenum, thus completing the implementation of Items II.F.l(l) and II.F.l(2) at i
both Hatch units.
Please contact this office if there are any further questions.
Very truly yours, b
L. T. Gucwa JH/mb xc:
J. T. Beckham, Jr.
H. C. Nix, Jr.
J. P. O'Reilly (PflC-Region II)
Senior Resident Inspector i
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i 4
700715
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