ML20140F369
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UNITED STATES i
NUCLEAR REGULATORY COMMISSION g
-,, p WASHINGTON, D. C. 20555 i
%l y N6 so Mr. Edward A. Firestone Counsel-Litigation General Electric Company 175 Curtner Avenue IN RESPONSE REFER San Jose, CA 95125 TO F01A-85-665
Dear Mr. Firestone:
This is in further response to your letters dated September 27 and November 6, 1985, in which you requested, pursuant to the Freedom of Information Act (F0IA), several categories of documents regarding pressure suppression containment. During the course of numerous telephone conversations between yourself; Edward Shomaker, Office of Executive Legal Director; and Carol Ann Reed of my staff, the scope of this request was clarified to only include 1) the Humboldt Bay docket file up to December 31, 1976; 2) the Bodega Bay docket file; 3) information on the 4 x 4 tests; and 4) information concerning the 1972 incident at the Wuergassen plant in Germany.
The Final Safety Analysis Report and the Safety Evaluation Report for the Limerick plant contain the only information that could be located regarding item three of your request.
The documents listed on the enclosed Appendices D, E, F, and G are responsive to item four of your request. The documents listed on the enclosed Appendix D are being placed in the NRC Public Document Room (PDR),1717 H Street, NW, Washington, DC. The three reports listed on the enclosed Appendix E are already available in the PDR.
Portions of the documents listed on the enclosed Appendix F and the entire documents listed on the enclosed Appendix G are outside the scope of your request since they contain information which the General Electric Company considered proprietary at the time the documents were submitted to the NRC.
The releasable portions of the Appendix F documents are being placed in the PDR.
The review of additional documents subject to item four of your request is ccntinuing. As soon as our review is completed, we will notify you.
Sincerely, Y~cf fe,.,, // A Donnie H. Grimsley, Director Division of Rules and Records Office of Administration Cnclosures: As stated 8604010016 860114 PDR FOIA FIRESTOB5-665 PDR
850n 40692S$376 SJ 9.27.1965 13e36 P.
2 s.
GENERAL h ELECTRIC NUCLEAR ENERGY 805tNESS OPERATIONS GENERAL ELECIAIC COWANY
- 175 CURINtt AVENUE
- SAN JOSt. CAUFOMA 95125 i
l September 27, 1985 FREEseOg OF MFORMAIION ACT REQUEST Fom -M-W Mr. Joseph Felton
- d b~
Director Division of Rules and Recorde U.S. Nuclear Regulatory Cow.ionion Washington, D.C.
20555
Dear Mc. Felton:
Pursuant to the Freedom of Information Act (5 USC 552) and 10 CFR Part 9 on behalf of the General Electric Company I hereby request information pertaining to Pressure Suppression Containments of the type associated with boiling water reactors (BWRs).
I recognize that a large amount of technical and licene';.g information is available in NRC concerning these containments and that much'of the material is readily obtainab3e from the NRC Public Document Rocc.
Nevertheless, it is possible that there is other information concerning pressure suppression containments that for one reason or another may not have reached the Public Document Room.
Some, for et:6mple, may deal with 1
early license applications for the first plants which used pressure suppression containment concepts or came in draft form from NRC or AEC contractors, was the subject of internal NRC or AEC discussions, or may have been obtained from international sources. Therefore, General Electric Company requests the following information about pressure suppression containment that may not be in the Public Document Room for the time petiod 1955-present:
1.
All files of the NRC or AEC that pcrtain to pressure suppression containment, including, but not limited to: a) all general files and all files of all current and forcer personnel, eembers, managers and employees of the Containment Systems. Branch and its predecessors created while they were employed in that branch; b) all general files and all files of all current and former personnel, task managers.
membero and employees of the Generic Issues Branch and its predecessors pertaining to generic or unresolved safety issues relating to pressure suppression containments created while they were employed by that W3pp.
FEON 40t925$374 SJ 0.8F.0009 08e80 p.
8 a
CENER AL h ELECTRIC Mr. Joseph Folton September 27, 1985 branch. The above request encompacoes all information received by the NRC or AEC from any source, including, but not limited to licensees, applicants, contractore, vendors and other domestic or international l
sources.
2.
All communicatione, including contracts and draft and final reports, between the NRC or AEC (and any branch of the NRC or AEC including the Office of Research and its predecessors) and its contractors, including technical assistance contractors, concerning preosure suppression containments.
3.
All ERC or AEC files, including personal filco, of the following NPC or AEC enployece, past and present, pertaining to prcosure suppression containment:
a.
Robert Tedesco b.
Darrell Eisenhut c.
Victor Stello d.
Morris Rosen e.
Stephen Hanauer f.
Roger Mattson g.
Joseph Hendrie h.
Edson Case i.
Harold Price J.
Peter Morris k.
Saul Levine 1.
Herschel Specter c.
Robert Lorenstein 4.
All communications by and between the NRC or AEC and the Advisory Committee on Reactor Safeguards (ACRS), including material or.iginating with the ACRS or its consultants on the subject of pressure euppression containment.
\\
5.
All filco of the ACRS, including the files of ACRS members, j
consultante, employees and personnel on the subject of pressure euppression containment.
Please note that General Electric is defining files and communications to include records as defined in 10 CFR 9.3a and, in addition, all data, including published and unpublished nemoranda, personal notes, notes of telephone conversations, films, photographs, microfiche, microfilm, tapes and other electronic neans of recording data, published and unpublished repotts and any other material in the possession of the Agency from whatever source on the subject of pressure suppression containment.
1
rnon 4089255376 SJ 9.27.1985 13:39 P.
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CENER AL h ELECTRIC Hr. Joseph Felton September 27, 19R5 As noted earlier, we understand that much material is already in the NRC's Public Document Room.
This request is not intended to encompass meterial already available in the Public Document Room.
It has come to our ottention that KRR is about to be reorganized and that the Containment Systems Branch will soon be dissolved.
Therefore, vc would appreciate your making every effort to preserve all the filee of that branch and files of employees of the branch (including personal files).
Please do not hesitate to contact ne regarding any question you may have concerning this request.
Very truly yours, a
Edward A. Firestone Counsel-Litigation i
i i
Re:
F01A-85-665 APPENDIX D t
DATE TO FROM SUBJECT l
1.
1972 Abstract of Events from Nucleonics Week - page 4, dated 4/20/72
- 2. 11/27/74 Directorate of Regulatory Operations Notification of an Incident of Occurence
- 3. 12/27/74 Dr. Ivan Stuart Draft Safety & Licensing Nuclear Energy Div.
G.E. Company.
- 4. 02-04-75 R. Goller B. Grier
- 5. 1975 Hand-Outs Safety Relief Valve Phenomena
- 6. 1975 Hand-Outs Test Conclusions Series 5806
- 7. 02-21-75 R. Fraley R. Tedesco Transmitted for Inform.
of the Committee
- 8. 1975 E. G. Case G. Lear Mark I Containment Suppression J
Pool Temperature Limits
- 9. 02-25-75 R. C. DeYoung R. T. Tedesco Stand. Letter to Applicant V. A. Moore Mark III Pool Dynamic Load and Analytical Meth. Develop.
- 10. 03-10-75 R. L. Tedesco I. Stuart/ G.E.
Relief Valve Vent Clear and Steam Quenching Vibrations
- 11. 03-19-75 U.S. AEC Tech. Assis.
Request Control Form
- 12. 04-10-75 R. C. DeYoung R. L. Tedesco Stand. Letter to Applicant V. A. Moore System Pressure Relief Valve loads for plants w/ Mark II Type Containment s
Re:
F01A-85-665 APPENDIX D (CONINTUED)
FROM SUBJECT i
DATE To_
13; 04-10-75 R. C. DeYoung R. L. Tedesco Stand. Letter to Applicant V. A. Moore Concern. Primary System Pressure Relief Valve loads' for plants w/ Mark III Type Containment
- 14. 04-11-75 R. C. DeYoung R. L. Tedesco Stand. Letter to Applicant V. A. Moore
& Licensee c6ncerning Pool K. R. Goller dynamic loads.for plants w/ Mark I & II Type Contain.
- 15. 04-15-75 E. G. Case A. P. Bray Documentation of communications G.E. Company
- 16. 04-16-75 G. Lainas R. L. Cudlin Meeting with GE - Pool Dynamic & Relief Valve loads on Mark I & II Containment i 17. 04-17-75 R. C. DeYoung R. L. Tedesco Proposed Method for Review V. A. Moore R. R. Maccary of Mark I, II & III Pool K. R. Goller Dynamic Loads jg 04-18-75 DRAFT-Pool Dynamic Loads
- 19. 04-29-75 F. Schroeder G. Lainas Pool Dynamic Loads on Mark I Containments
- 20. 05-01-/5 R. L. Tedesco G. L. Gyorey Small-Scale Safety / Relief GE Valve Loads Test at Moss Landing a.l. 05-19-75 F. Schroeder G. Lainas Proposed Positions on GE
~
Pool Dynamic Test Programs
- 22. 06-11-75 R. C. DeYot.ng R. L. Tedesco BWR Pool Dynamic Concerns V. A. Moore
, 23. 06-12-75 I. Stuart R. L. Tedesco Pressure Suppression Contain.
- 24. 06-16-75 R. C. DeYoung R. R. Maccary Allens Creek 1 & 2 Pool Dynamic Loads (TAR 1634)
- 25. 06-20-75 Note to File J. Kudrick Mark III Pool Swell Impact Load Profile for Small Structures
Re.
F0lA-85-665 APPENDIX D (CONINTUED)
DATE To FROM SUBJECT _
- 26. )7-15-75 Power Autority New York K. Goller Steam /ent Clearing Phenomenon
- 27. 07-22-75 Note to K. Goller R. L. Todesco BWR Relief Valve Discharge Piping Inspection
- 28. 07-28-75 J. H. Ramstahler L. L. Wheat BWR Mark I Owners Meet Trip Report & Comments LLW-39-75 Tech. Assistance MK I & II Pool Dynamic Loads
' 29. No Date
- 30. 09-26-75 B. C. Rusche I. F. Stuart Containment & Bypass Leakage Docket No. STN 50-447
- 31. 10-06-75 R. F. Fraley R. L. Tedesco Transmitted Infor. of Committee
- 32. No Date U.S. AEC Tech. Assistance Request Control Form
, 33. 10-08-75 J. H. Ramsthaler L. L. Wheats Transmittal of Trip Request LLW-59-75
- 34. 10-14-75 I. Stuart R. E. Heineman Review & Audit Certain Infor. Design Relief Valve 35, 10-16-75 I. F. Stuart W. R. Butler Topical Report NEDE-20942-P
- 36. No Date GE Topical Reports Related to Ramshead
- 37. No Date Consultant's Report (Proprietary Information)
- 38. 11-14-75 W. R. Butler J. L. Embley GE Licensing Topical Request NEDE-21078-P " Test Resul ts Employed by GE for BWR Con-tainment and Vertical Vent i
loads" 39.
09-02-75 RRStiger B. A. Bush Tiip Report BWR Mark I Containment loads Meeting BAB-3-75
Re:
FOIA-85-665 4
APPENDIX D (CONINTUED)
DATE To FROM SUBJECT 40L 01-06-76 R. S. Boyd I. F. Stuart Mark I Containment Evaluation Program-In-Plant Safety / Relief Valve Test
- 41. 04-02-76 V. Stello B. II. Grier Inservice Inspection of Containment Strcctures I 42. No Date Note to Files Mark I Break Opening Time Study l
Design pressure of plants utlizing 43* No Date Mark I Containment
- 44. 05-11-76 L. L. Wheat Idaho National Engineering Laboratory Memo of Conversation
- 45. 05-28-76 J. H. Ramsthaler L. L. Wheut BWR Pool Penetrations and Scaling Study SRD-77-76
- 46. 06-28-76 G. C. Lainas T. M. Su Trip Report-Monticello Relief Valve Tests 47.' No Date Test Results 1
- 48. No Date G.E.
Monticello Test Plan
~
- 43. 10-04-76 G. C. Lainas T. M. Su Sumary of Heeting w/
GE on the Safety Relief Valve (Ramshead) analytical Model (TAR-1720)
- 50. 12-28-76 D. B. Vassallo R. L. Tedesco Draft Supple. 2 to the GESSAR Safety Evaluation Report
- 51. 01-18-77 S. A. Varga J. F. Quirk Loading Cri'.eria for Submerged Structures
- 52. 02-18-77 D. G. Eisenhut R. L. Tedesco Evaluation of Oyster Creek Modified Pressure Set-Point For Safety / Relief Valve (TAC-2285)
Re:
FOIA-85-665 APPENDIX D (CONINTUED)
DATE To FROM Sl6 JECT, 53; 03-02-77 S. A. Varga L. J. Sobon loading Criteria for Submerged Structures
- 54. 03-03-77 G. C. Lainas T. M. Su SRV Discussion w/ Mark II Owners Group
- 55. 05-07-77 PB Unit 2 66.
No Date Mark III 238-732 Standard Plant 57.
No Date Hand-outs Submerged Structure Loads Generic Program
- 58. 06-10-77 G. G. Sherwood
- 0. D. Parr GE Topical Report NEDE-21078-P Results Employed by GE for BWR Containment and Vetrical Vent Loads
- 59. 06-01-77 Draft Formal Questions to be Submitted to GE on "Caorso Relief Valve loads Tests-Test Plan"
- 60. '06-06-77 L. J. Sobon R. L. Tedesco Quencher Loads on Containment Structures
- 61. 06-14-77 G. Lainas J. Guibert
" Task Action Plan"
, 62. 06-20-77 R. L. Tedesco G. Maise "Caorso Relief" S3. 06-20-77 Distribution R. L. Tedesco Category "A" Task Action Plan 64.~06-23-77 R. E. Heineman R. L. Tedesco Establishing a Category "A" Technical Activity Seperate from Three other Authorized i
Category "A" Activities j
i
- 66. 06-29-77 S. Miner G. Lainas Review of GE Topi;al Report NEDM-20988, "Caorso Relief Valve Loads Tests-Test Plan" (TAC-2285)
- 67. 08-29-77 W. Minners J. Kudrick Rev'sion to TASK Action Plan A-39 i
b Re: F01A-85-665 APPENDIX 0 (CONINTUED)
FROM SUBJECT DATE T_o_
68.10-28-77 Note To Task Managers M. Aycock Task Action Plans
- 69. No Date Office of NRR Request for Generic Schedule Change
- 70. No Date Test Matrix Monticello
- 71. 11-08-77 R. L. Tedesco D. G. Eisenhut 10 CFR Part 21 Notification by GE Regarding Safety-Relief Valve Discharge Loads
- 72. 11-18-77 R. Mattson R. Tedesco Proposed Revisions to TASK Action Plan A-39, " Determination of Safety Relief Valve (SRV)
Pool Dynamic Loads and Temperature Limits for BWR Containment" Hand-Out MARK I Hydrodynamic /
- 73. 11/15/77 LLL Structural Interaction
- 74. 11-16-77 V. Stello E. W. McCauley Final Draft Report - Hydro-dynamic / Structural Interaction in the MARK I BWR Supperssion System
- 75. 11-75-77 A. S. Rosenthal Atomic Safety & Licensing Appeal Board
- 76. 12-02-77 R. Boyd E. G. Case Procedures & Responsibilities for Scheduling of Generic Tech. Activites and Revising Task Action Plan
- 77. (2-07-77 R. S. Boyd E. G. Case Generic Technical Activities
- 78. '2-09-77 T. Ippolito R. L. Tedesco Task Action Plan Schedule and Scope Changes
- 79. 12-09-77 G. C. Lainas T. M. Novak Task Action Plan A-39 on BWR Relief Valve Loads
- 80. 12-09-77 T. M. Su R. J. Bosnak Task Manager TAP A-39
- 81. No Date Change of Man Power
- 82. 12-13-77 T. M. Su W. R. Butler Comments on Revision 1 to Task A-39
I i
Re:
l APPENDIX D 1
l (CONINTUED)
DATE To FROM SUBJECT
- 83. 12-19-77 M. Aycock T. M. Su Generic Technial Activities
- 84. 12-19-77 E. G. Case R. J. Mattson Draft Status Summary Report for NRR Generic Technical Activities
- 85. 12-22-77 R. Mattson T. Su Proposed Revisions to Task Action Plan A-39 " Determination of Safety Relief Valve (SRV)
Pool Dynamic Loads and Temp.
Limits for BWR Containment 86* 12-27-77 T. M. Su L. C. Shao Comments on Revision 1 to Task A-39
- 87. 01-09-78 Multiple Addressess M. B. Aycock Meeting with Task Managers
- 88. 01-19-78 Hand-Out Zimmer Containment Design Assessment for SRV Load 89, 01-27-78 H. Kuo C. Anderson Fluid Structure Inter-
)
A. Hafi T. Su action for Mark II Pool l
Dynamic Laods
- 90. 01-78 Hand-Out Monticello &
Mark II Fluid Structure Interaction
- 91. No Date Hand-Out Engineering of Mechanics 92, 02-09-78 G. Lainas T. Su Summar of Meeting w/
Mark II Owners Group to discuss status of SRV related loads on containment
- 93. No Date Hand-Out Mark II Pressure Suppression Containment Systens
- 94. No Date Hand-Out Ramshead Condensation Instability
- 95. No Date Hand-Out Mark II Pressure Suppression Containement System l
Re:
F01A-85-665 APPENDIX D (CONINTUED)
DATE To E
Hand-Out Mark II Pressure
- 96. No Date Suppression Systems
- 97. D2-09-78 G. C. Lainas T. M. Su Summary of Meeting w/ Mark II Owners Group to Discuss Status of SRV related loads on Containment
- 98. 03-02-78 K. R. Goller D. G. Eisenhut Staff Position on Multi-Subsequent Actuations of Safety-Relief Valves in Mark I Plants
! 99. 03-21-78 Distribution L. C. Shao Engineering Branch Technical Assistance Programs for Category A Technical Act. FY78
'100. 03-21-78 R. Bosnak T. Su Review of Forces in Safety /
Relief Valve Discharge Line 101. 04-06-78 Hand-Outs Monticello SRV FSI
'102.04-10-78 F. Schroeder R. L. Tedesco ALAB-444 Writeups for Category A Task Action 103.04-27-78 R. Tedesco T. M. Su Report on BWC Experience
- 104. 04-27-78 Distribution D. Eisenhut Report on BWR Blowdown Exper.
105. 06-15-78 R. Tedesco T. Su SRV Actuation following DBA 106.10-30-78 L. S. Tong T. Sarpkaya Inquire thoughts and to seek your assistance regarding informal proposal l 107.12-18-78 H. R. Denton G. G. Sherwood Comments on 5 BWR-related items
-106. 03-01-79 Docket Nos.
T. M. Su Summary meeting held on 2-13-79 w/ representatives on Mark I owners group
'109. 07-16-79 S. H. Hanauer T. M. Su Summary meeting held on 4/4/79 w/ represtatives of GE comp.
to discuss methodology 110.08-08-79 A. Thadani T. M. Su Preliminary Question List for GE Report on ATWS
Re:
F01A-85-665 APPENDIX E t
1.
NUREG-0661 Safety Evaluation Report for the Merk I Containment Long-Term Program.
1 2.
NUREG-0487 Mark II Containment Lead Plant Program Load Evaluation and Acceptance Criteria.
3.
NUREG-0802 Safety / Relief Valve Quencher Loads Evaluation for BWR Mark II and III Containment.
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d F01A-85-665 9"e:
r APPENDIX i 4
DATE TO FROM SUBJECT 1.
1975 Hand-outs Tests Conclusions Series 5806 j
2.
09/24/75 R. L. Tedesco G. L. Gyorey Visual Aids 3.
10/10/75 J. H. Ramsthaler L. L. Wheat BWR Dynamics Position Letter !.LW-61-75 4
4.
04/19/76 J. H. Ramsthaler L. L. Wheat Critique of GE Safety-Relief Valve Analytical Models-LLW-18-76
}
5.
06/30/76 P. E. Litteneker J. H. Ramsthaler BWR Pool Swell Model Comparison RAM-374-76 i
6.
11/24/76 P. E. Littenker R. R. Stiger Peview of GE Safety-i Relief Valve Models-Stig-91-76 7.
05/26/77 W. Pike G. Lainas-Request for Additional Information for GE Topical Report NEDE-21078-P(TAC-3619) 4 i
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t
- 1 a
i
Re:
{
APPENDIX G DATE TO FROM SUBJECT 1.
10/08/75 L. L. Wheat B. A. Bush Trip Report - General BWR Containment Loads Meeting BAB-4-75 2.
04/76 Idaho National Analysis of the General i
Engineering Electric Safety-Relief Laboratory Valve Discharge Analytical 1
Models, SRD-71-76 i
3.
10/76 Idaho National Review of Safety-Relief Engineering Valve Analytical Models, Laboratory RE-S-76-6 1
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