Letter Sequence Other |
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Results
Other: ML19209B217, ML19210E687, ML19250C166, ML19261C487, ML19270F761, ML19338C686, ML19341C283, ML19344D978, ML20039B447, ML20070S058, ML20071C377, ML20076C882, ML20076H077, ML20080K634, ML20082N526, ML20082N549, ML20244A626
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MONTHYEARML19261C4871979-02-27027 February 1979 SER of Interim Assessments of MSIV Actuations in Mark I Containment Plants Project stage: Other ML19270F7611979-03-12012 March 1979 Discusses Status of Mark I Containment long-term Program. Requests Schedule Showing Time Periods for Installation of Specific Plant Mods.Discusses Safety Relief Valve Discharge Device Installation & Forwards Staff Evaluation Project stage: Other ML20244A6261979-05-14014 May 1979 Forwards Schedule for Implementation & Resolution of Mark I Containment long-term Program.Only Vent Header Deflectors Are Necessary as Major Mod for Conformance to long-term Program Acceptance Criteria Project stage: Other ML19209B2171979-10-0202 October 1979 Forwards Proposed Amend to License NPF-5,changing Tech Specs,App a Project stage: Other ML19250C1661979-10-31031 October 1979 Forwards Rept, NRC Acceptance Criteria for Mark I Containment Long-Term Program. Requests Schedule for Submittal of long-term Program plant-unique Analysis Project stage: Other ML19210E6871979-11-30030 November 1979 Commits to Addl Confirmatory Condensation Oscillation Tests in full-scale Test Facility,Outlined in GE Re Mark I Containment Program.Schedule for Submittal of Plant Unique Analysis Will Be Provided Following NRC Resolution Project stage: Other ML19320B1581980-06-26026 June 1980 Notification of 800703 Meeting W/Util in Bethesda,Md to Discuss Util Basis for Delayed Schedule for Installing T-quenchers Project stage: Meeting ML19338C6861980-08-0707 August 1980 Submits Documentation Re Previous Mod,Future Installations & Completion Schedule Per Ongoing Mark I long-term Program. Mods Performed to Strengthen Torus Shell & Related Structures Project stage: Other ML19344D9781980-08-14014 August 1980 Provides Clarification Re Util Outlining Schedule for Resolution of Mark I Program Concerns.Recent Tests Indicated That Submerged Structure Loads Caused by SRV Actuation Are Negligible Project stage: Other ML20003A6761981-01-13013 January 1981 Order Granting Extension of Exemption from General Design Criteria 50 & Requiring Licensee to Reassess Containment Design for Suppression Pool Hydrodynamic Loading Project stage: Approval ML20037C3601981-01-13013 January 1981 Order Granting Extension of Exemption from General Design Criteria 50 & Requiring Licensee to Reassess Containment Design for Suppression Pool Hydrodynamic Loading Project stage: Approval ML19345F7441981-02-13013 February 1981 Summary of 810210 Meeting W/Util Re Impact of Mark I Containment Orders on long-term Program for Facilities. Attendance List Encl Project stage: Meeting ML19341C2831981-02-24024 February 1981 Requests Mod of Schedules for Completion of Mark I Program Per NRC 810113 Orders.Completion Is Tied w/1982 Refueling Outage for Each Unit.Requests Hearing in Event NRC Does Not Approve or Act Upon Request Project stage: Other ML20039B4471981-12-14014 December 1981 Commits to Complete BWR Mark I Containment long-term Program Prior to Startup for Fuel Cycle 7 (Unit 1) & Fuel Cycle 4 (Unit 2) Project stage: Other ML20070S0581983-01-26026 January 1983 Forwards, Mark I Containment Long-Term Program Plant Unique Analysis Rept. Suppls Re Safety/Relief Valve Discharge Line Drywell Supports & Torus Attached Piping & Supports Scheduled for 830228 Submittal Project stage: Other ML20071C3771983-02-28028 February 1983 Forwards, Mark I Containment Long-Term Program Plant Unique Analysis Rept-Suppl. Rept Addresses safety-relief Valve Discharge Line Drywell Supports,Torus Attached Piping & Supports,Valves,Pumps & Torus Shell Nozzles Project stage: Other ML20069G1691983-02-28028 February 1983 Public Version of Rev 15 to Emergency Plan Implementing Procedure HNP-8008, Radiation Work Permit Project stage: Request ML20076C8821983-05-16016 May 1983 Commits to Submit Results of plant-unique Calculations Re Acceptability of Mod to Torus Vacuum Breakers by 830615, in Response to Generic Ltr 83-08 Project stage: Other ML20076H0771983-06-0202 June 1983 Forwards Revised Pages to Plant Unique Analysis Rept Re Resolution of torus-attached Piping Pump & Valve Evaluation. Pages Reflect Satisfactory Results of Evaluation of 14 Valves & Two Pumps Project stage: Other ML20024E0591983-08-0101 August 1983 Forwards Request for Addl Info Re Mark I Containment long- Term Program plant-unique Analysis Rept on Loads & Structural Evaluations.Meeting at Contractors Ofc to Resolve Issues Suggested Project stage: RAI ML20080J4881983-09-16016 September 1983 Forwards Explanation of Use of Srss in Lieu of Absolute Sum in Calculations Involving Certain Multiple Valve Actuations, Per 830831 Meeting.Replacement Pages in Response to Questions Raised in Also Encl Project stage: Meeting ML20080K6341983-09-27027 September 1983 Audit for Mark I Containment Long-Term Program - Structural Analysis for Operating Reactors,Ei Hatch Nuclear Plant Units 1 & 2, Technical Evaluation Rept Project stage: Other ML17194B7301983-09-30030 September 1983 Forwards Proprietary Dresden 2/3 Nuclear Generating Plant Suppression Pool Temp Response, Ei Hatch Nuclear Power Station Units 1 & 2 Suppression Pool Temp Response & Mark I 830825 Meeting Viewgraphs.Repts Withheld (Ref 10CFR2.790) Project stage: Meeting ML20082N5261983-12-0505 December 1983 Forwards Revised Pages to plant-unique Analysis Rept, Reflecting 10 Valve Evaluations Unavailable in 830228 Rept Project stage: Other ML20082N5491983-12-31031 December 1983 Rev 2 to Plant-Unique Analysis Rept for Ei Hatch Nuclear Plant Unit 1,Mark 1 Containment Long-Term Program Project stage: Other 1981-02-13
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8 lo,'n UNITED STATES NUCLEAR REGULATORY COMMISSION
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WASHINGTON, D. C. 20555
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OCTOBER 3 1 1979 Docket Nos. 50-321 and 50-366 Mr. Charles F. Whitmer Vice President - Engineering Georgia Power Company P. O. Box 4545 Atlanta, Georgia 30302
Dear Mr. Whitmer:
RE:
ACCEPTANCE CRITERIA FOR THE MARK I CONTAINMENT LONG TERM PROGRAM The staff has completed its review of the generic aspects of the Mark I Containment L6ng Term Program (LTP).
The results of this review are reflected in the enclosed acceptance criteria, which are intended to be used to perfonn individual plant-unique analyses for each Mark I facility.
These criteria have been developed from the staff,'.s evaluation of the Mark I LTP Load Definition Report, Plant Unique Analysis Appli-cations Guide, and related suppression pool hydrodynamic experimental and analytical programs, which have been submitted by the Mark I Owners Group.
In developing these criteria, we have considered verbal comments provided by representatives of the Mark I Owners Group on a draft of the criteria issued August 2, 1979.
These comments were presented to the staff during a meeting held on August 15,1979, and supplemented by additional information provided in a letter from General Electric dated September 7, 1979. This information and internal comments by the staff and our consultants have resulted in some modifications to the draft criteria.
However, others of the Owners Group recommendations were not adopted for the NRC criteria, based on the staffss judgment relative to the interpretation of specific cata or analyses.
In certain cases, the staffss generic criteria identify specific hydro-dynamic load assessment techniques that will have to be evaluated on a plant-specific basis. However, deviations from any other generic criteria should be avoided.
The criteria also identify additional experimental verification that must be obtained for " condensation oscillation" load uncertainty. This requirement was communicated to you earlier in our letter dated October 2, 1979.
7911080 3 7 3
!?75 202
Mr. Charles F. Whitmer.
Within 30 days'of your receipt of this letter, we request that you provide the schedule for submittal of the LTP plant-unique analysis for your facility.
In developing this schedule, you should consid6r that we are continuing to target the completion of this program and the tennination of the exemption issued for your facility for December 1980.
The staff presently expects to issue the generic Safety Evaluation Report supporting these criteria in December 1979.
Should you have any questions reg.ar ing this action contact C. Grimes (301-492-8204).
t i
Wst) arrell G. Ei enh t Ac ti Directo,r Division of Operating Reactors
Enclosure:
As stated cc w/ enclosure:
See next page
!?75 203 e
Mr. Charles F. Whitmer
' Georgia Power Company cc:
G. F. Trowbridge, Esquire Shaw, Pittman, Potts and Trowbridge 1800 M Street, N. W.
Washington, D. C.
20036
' Ruble A. Thomas
' Vice President P. O. Box 2625 Southern Services, Inc.
Binningham, Alabama 35202 Ozen Batum P. O. Box 2625 Southern Services, Inc.
Birmingham, Alabama 35202 Mr. W1111a, Widner.
Georgia Power Company Power Generation Department P. O. Box 4545 Atlanta, Georgia 30302 Mr. L. T. Gucwa Georgia Power Company Engineering Department P. O. Box 4545 Atlanta, Georgia 30302 Appling County Public Library Parker Street Baxley, Georgia 31413 Mr. R. F. Rogers U. S. Nuclear Regulatory Commission P. O. Box 710 Baxley, Georgia 31513 1775 204
.