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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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Georga Pcwer Company 333 Piedmont Avrfnue ANnta Georgra 30303 TcMpnoco 404 526-7020 MaAng Actess Post Otf ze Bcx 4545 Abarta Gecga 30302 Georgia Power ~
J. T. Beckham, Jr.
va emsiaent and ocnerar ua,a;cr November 4, 1981 Nuc' ear Gwraicn f
h4 Director of Nuclear Reactor Regulation Mfh.I3 U. S. Nuclear Regulatory Commission
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OPERATING LICENSES DPR-57,JPE-5 EDWIN I. HATCH NUCLEAR PLANT UNii5 1, 2 NUREG-0737 ITEMS II.F.1.1 AND II.F.1.2 m
Gentlemen:
Yourf letter of October 5,1981 requested that any technicalMeviations from the stated positions of items II.F.1.1 and ID.T.l.2 pf NUREG-0737 be submitted for review.
Further, it was ' requested that sthe need ~ for any
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extensions be brought to the NRC's attention.
A request for extension of s
the implementation. schedule for these particular items was included among other NUREG-0737 items in a request dated November 4,1981.
This letter will not, therefore, further address a request for extension.
We have, however, determined a technical exception to the state'd "NUREG-0737 positions on these items.
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Item II.F.1.2 required provisions for effluent monitoring of radiciodines for the accident condition.
It was stated that the design of the systems for the sampling of particulates and iodines shoe'.d provide for sample nozzle entry velocities which are approximately isokinetic with expected induct or instack air velocities.
Georgia Power Company hereby
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- requestsexceptiontothisrequirementforthereasondescribed_herein.\\
The error associated with anisokinetic sampli6g is neglihible for small particulates.
Releases of radioactive iodines and/or particulates from the -
E. I. Hatch Plant take place through either the off-gas s' step stack or the a
j reactor building exhaust vent.
Before being released, theses effluents Dass through HEPA filters which trap large partic01ates.
Sampling will. take place downstream of these filters.
Although thetsample. will bestakerPat 'a constant flow rate irrespective of the flow through the duct or. stack, no significant error will result because of the particulate size. distribution resulting from HEPA filtration.
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