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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Text
Georgia Power Company 333 Piedmont Avenue Atlanta. Georgia 30308 Telaphone 404 526 6526 Ma; ling Address:
Post Office Box 4545 Atlanta. Georgia 30302 Georgia Power L. T. Gucwa t%+ southem e'ectnc system Chief Nuclear Engineer Power Generation Department ED-83-331 June 2, 1983 Director of NJclear 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 m C DOCKET 50-366 OPERATING LICENSE NPF-5 EDWIN I. HATCH NUCLEAR PLANT UNIT 2 MODIFICATION OF SUPPLEMENT TO UNIT 2 PLANT UNIQUE ANALYSIS REPORT Gentlemen:
Our letter dated February 28, 1983, transmitted the " Supplement to the Edwin I.
Hatch Nuclear Plant - Unit 1 and Unit 2 Plant l#11gue Analysis Reports (PUAR)" pursuant to your " Order for Modification and Grant of Extension" dated January 19, 1982.
It was noted in the Unit 2 report that fourteen valves and two pumps were under evaluation at the time of submittal of that supplement.
Those evaluations have been completed, and the attached revised two pages reflect the satisfactory results of that evaluation.
Please insert the attached pages into the February 28, 1983 supplement to the PUAR for lkilt 2.
Yours very truly, 00 L. T. Gucwa WEBAt e
Attachment xc:
J. T. Beckham, Jr.
H. C. Nix, Jr.
J. P. O'Reilly (NRC-Region II)
Senior Resident Inspector
'I Il 8306160397 830602 PDR ADOCK 05000366 P
pm
PLANT UNIQUE ANALYSIS REPORT - RESOLUTION O
0F TORUS-ATTACHED P1 PING PUMP AND VALVE EVALUATION r
FOR E. I. HATCH NUCLEAR PLANT UNIT 2 INSERTION INSTRUCTIONS i
Remove and insert the PUAR pages listed below.
REMOVE INSERT 6.4-15/6.5-1 6.4-15/6.5-1 There are three pages in Appendix C.
Please remove the last page from the book and insert the revised page.
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6.4.4.5 ' Summary of Results
{,m)
V' The valves and pumps evaluated in the torus-attached piping analyses are those up to the first rigid anchor or up to the point where the effect of torus motion has been considered insignificant.
The piping systems considered for analyses are listed in Table 2.5.1-1.
o Valves A total of 52 valve assemblies considered in the analyses have been evaluated for operability and functionality.
All valve assemblies
- were found to be acceptable based on criteria cited in subsection 6.4.4.4.
o Pumps A total of eight pump assemblies considered in the analyses have been evaluated for operability and functionality.
All pump assemblies
- were found to be acceptable based on criteria cited in subsection 6.4.4.4.
- A more realistic torus analysis was performed considering " dry" structure techniques for the S/RV load.
The results were used to evaluate 14 valve assemblies and two pump assemblies.
v 6.4-15
6.5 REFERENCES
6-1 G. Everstine, "Ccupled Vibrations of a Structure in a Compressible Fluid."
6-2
" Mark I Containment Program Structural Acceptance Criteria Plant Unique Analysis Application Guide," General Electric Company, Report No. NEDO-24583-1, October 1979.
6-3 F. A. Leckie and R. K. Penny, "(1) A Critical Study of the Solutions for Asymmetric Bending of Spherical Shells, (2) Solutions for the Stresses in Nozzles in Pressure Vessels, (3) Stress Concentration Factors for the Stresses at Nozzle Intersections in Pressure Vessels," Welding Research Council Bulletin No. 90 (September 1963).
6-4 K. R. Wichman, A. G. Hopper, and J. L. Mershon, " Local Stresses in Spherical and Cylindrical Shells due to External Loadings," Welding Research Council Bulletin No. 107 (August 1965, revised March 1979).
6-5
" Standards of the Expansion Joint Manufacturers Association, Inc.,"
lxpansion Joint Manufacturers Association, Inc., Fifth Edition, 1980.
6-6 S. S. Manson, " Thermal Stress and Low Cycle Fatigue," McGraw-Hill, 1966.
O O
6.5-1 J
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O APPENDIX C (Continued)
I p
COMPONENT CATEGORY MODIFICATION DESCRIPTION DESIGN DRAWING /AE FABRICATION / ERECTION DRAWING CB&I l
t Torus-Attached Piping 1.
Addition of elbows S-2-22-79/SCS Drawing 25 and Supports Inside to the RHR test the Torus lines i
2.
Modification to return H-25083/Bechtel Drawing 29 line restraints H-25087/Bechtel Drawing 30 H-25119/Bechtel Drawing 31 i
Drawing 32 j
Drawing 33 Drawing 74 i
4 3.
Removal of spare DCR 82-76/Bechtel N/A piping - X227A i
Torus-Attached Piping 1.
Addition of flexible N/A N/A and Supports Outside metal hose to small l
the Torus bore piping, conduit, i
and instrumentation lines l
2.
Addition / modification DCR 82-76/Bechtel N/A l
of piping supports
]
l 3.
Modification of TAP DCR 82-76/Bechtel N/A valve components l
l 4.
Modification of TAP N/A N/A pump components i
i
}
i
APPENDIX C (Continued)
COMPONENT CATEGORY MODIFICATION DESCRIPTION DESIGN DRAWING /AE FABRICATION / ERECTION DRAWING - CB&I Suppression Fool 1.
Addition of thermo-H-25066 Drawing 23 Temperature wells and half H-25067 Monitoring couplings H-25068 S/RV Logic Change 1.
MSIV isolation N/A N/A level logic change 2.
SRV low-low set N/A N/A logic 9-O O
O
-