ML20199A477

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Further Response to FOIA Request for All Documentation Re Comanche Peak Task Force & Alleger Info Provided in Sser 8. App M Documents Encl.Listed Documents Partially Withheld (Ref FOIA Exemption 5)
ML20199A477
Person / Time
Site: Palo Verde, Comanche Peak, 05000000
Issue date: 06/04/1986
From: Grimsley D
NRC OFFICE OF ADMINISTRATION (ADM)
To: Garde B
GOVERNMENT ACCOUNTABILITY PROJECT
Shared Package
ML17192A346 List:
References
FOIA-85-313, FOIA-85-59, FOIA-86-A-20, RTR-REGGD-01.010, RTR-REGGD-01.044, RTR-REGGD-1.010, RTR-REGGD-1.044 NUDOCS 8606120379
Download: ML20199A477 (37)
v • d • e


Text

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/ a ucg'e UNITED STATES i NUCLEAR REGULATORY COMMISSION WASHfNGTON, D. C. 20555 h h 9,

'% , , , , , #g M4 W Cocket Nos. 50-445/50-446 Ms. 8illie Pirner Garde Director, Environmental Whistleblower Clinic IN RESPONSE REFER Government Accountability Project TO FOIA-85-59 1555 Connecticut Avenue, NW, Suite 202 F01A-85-313, AND 86-A-20 Washington, DC 20036

Dear Ms. Garde:

This is in further response to your letter dated January 21, 1985, in which you requestad, pursuant to the Freedom of Information Act (F0IA), records related to the NRC Comanche Peak Task Force established in March 1984 (F01A-85-59) and your letter dated April 22, 1985, in which you requested, pursuant to the F0IA, all records related to all infomation provided by the alleger identified in the February 1985 SSEP. No. 8 (F01A-85-313).

Certain records subject to the two F0IA requests identified above are described below and on the enclosed Appendix M.

With regard to F01A-85-313, the staff identified Inspection Report 84-32/84-11 as being subject to your request. That record has already been made available for public inspection and copying at the NRC Public Document Room (PCR), 1717 H Street, NW, Washington, DC 20555, under PDR accession number 8502200334.

The remaining records subject to F01A-85-313 are also subject to F01A-85-59 and are being addressed under that F0IA request. Therefore, we are taking no further action on F01A-85-313 or your letter dated March 3,1986, appealing our lack of response to FOIA-85-313.

With regard to F01A-85-59, with the exception of the records which are undergoing further staff review and are identified by asterisks on the enclosed Appendix M, we are now placing the remaining box of records (box 4) in the mechanical / piping category, covering Appendix M records numbered I through 514, into the PDR in file F0!A-85-59 under your name.

Portions of the records identified at numbers 1, 49, 59, 60, 78, 95, 229, 230, 254, 255, 268, 281 through 284, and 340 are being withheld from public disclosure pursuant to Exemption (5) of the F0IA (5 U.S.C. 552(b)(5)) and 10 CFR 9.5(a)(5) of the Commission's regulations. The withheld portions contain the advice, 8606120379 860604 PDR FOIA GARDE 86-A-20 PDR

, , 1 m

Ms. Billie P. Garde  !

opinions, and recommendations of the staff concerning potential violations.

The nonexempt portions of the Appendix M records are being placed in PDR file FOIA-85-59 under your name.

1 Pursuant to 10 CFR 9.9 of the Commission's regulations, it hcs buen determined that the information is exempt from production of disclosure and that its production or disclosure is contrary to the public interest. The persons responsible for this denial are the undersigned and Mr. Harcld R. Denton, Director, Office of Nuclear Reactor Regulation.

This denial may be appealed to the Executive Director for Operations within 30 days from the receipt of this letter. Any such appeal must be in writing, addressed to the Executive Director for Operations, U. S. Nuclear Regulatory Commissien, Washington, DC 20555, and should clearly state on the envelc90 and in the letter that it is ao " Appeal from an Initial F0IA Decision."

Portions of the records identified at numbers 32, 63, 66 through 77, 88, 101, 112 through 114, 116, 201, 203 through 205, 242, 256, 258, 259, 269, 270, 280, 282, 284, 298, 299, 316 through 319, 338, 427 through 429, 455, 457, 466 through 458, and 490 contain deletions without invocation of-an FOIA exemption in accordance with the agreement reached between you and the NRC staff at a meeting held on May 8,1985. This agreement was sunnarized in a letter to you from Mr. Joseph M. Felton dated May 15, 1985. The information that has been deleted consists of names and identifying details of allegers and other individuals.

A separate set of the disclosed records is being made available for public l inspection and copying at the Local Public Document Room (LPDR) located at i the University of Texas Library, 701 South Cooper Street, Arlington, Texas.

l Additional boxes of records subject to F01A-85-59 are current.ly under review and will be placed in the PDR and LPCR in the coming weeks.

Sincerely, E E_Q M Donnie H. Grimsley, Director g Division of Rules and Records Office of Administrat. ion

Enclosure:

As stated i

{

l l

l

i

'Re: F0IA-85-59 APPENDIX M DOCUMENTS IN PDR FILE F01A-85-59 Mechanical / Piping Box 4 Pages

1. 11/19/84 SSER AW-34, 35, 38 12 Draft 6
2. 4/8/76 Gibbs & Hill 31 Specification 2323-MS-34 Revision 1 Section 3 (Technical specification Diesel-Generatorsets)
3. 12/29/76 Delaval Procedure 9 No. 100-W-la 4, 7/17/80 CPSES Nonconformance Report 3 N-80-00009, Rev. 6
5. 12/18/80 Transamer Delaval 3 Ltr to TUSI,

Subject:

Material Certifications for 02-717-01-JM Auxiliary Skids

6. 5/22/81 Delaval ltr to TUSI , 3

Subject:

Comanche Peak Steam Electric Station Purchase Order CP-0034 Standby Diesel Generator, S. O. 76001/4

7. 12/7/81 Transamerica Delaval 6 Addendum One to Piping Analysis Calculations Texas Utilities Services, Inc.

Units 1 & 2 Part 2 Analysis of Welded Channel Box Section CPSES Nonconformance Report '

8. 5/13/82 2 M-82-00581
9. 5/13/82 CPSES Nonconformance Report 2 M-82-00581 Rev. I
10. 7/8/82 CPSES Nonconformance Report 1 M-82-00902 Rev. 1 l

l 11, 7/8/82 CPSES Nonconformance Report 4 M-82-0902 1

Re: F01A-85-59 APPENDIX M (Continued)

12. 8/6/82 CPSES Noncot.formance Report 1 M-82-01207
13. 8/10/82 CPSES Inspection Report 1 No. IRDG-03688 14, 8/12/82 CPSES Inspection Report 1 No. IR-DG-03689
15. 8/18/82 CPSES Inspection Report 3 No. IRDG-03690
16. 8/24/82 Repair Process Sheet 3 WDC Serial No. 687310
17. 9/13/82 CPSES Inspection Report. 3 No. IROG-03757 18, 9/14/82 Repair Process Sheet 2 WDC Serial No. 687490
19. 9/15/82 Partial Statement of Alleger 1
20. 1/10/84 TUGC0 Itr TXX-4095 to NRC 9 Re: Comanche Peak Steam Electric Station Unit 2 Diesel Generator Auxiliary Skid QA file:

CP 82-06, SDAR -82 File No. 101100

21. 2/6/84 TUGC0 Instruction 10 CP-EI-4.0-50 Revision 0 (Control of Re-fabrication &

Installation of Diesel Generator Auxiliary Skid Base and Associated Structures - Unit 2)

22. 3/7/84 Partial Interview of Alleger 5

, 23. 7/19/84 TRT Reviewer Notes 3 l

24. 8/2/84 Coriversation Record 2

Subject:

Weld Filler Metal Control

25. No date Reactor Unit 2 - DeLaval Skid 10
26. No date Interim Records Vault 9 Documentation Package Inventory Card. Pkg. No.

MSB-2605-DG09-WJ

27. No date Brown & Root QA Dept. Visual 1 Examination Checklist 2

l - . .

Rs: F01A-85-59 e -

APPENDIX M (Continutd)

28. No date Comanche Peak Open Issue 3 Action Plan -
29. No date Comanche Peak Nuclear Power 2 Plant A'ilegations and/or Investigations Summary
30. 9/9/84 United States of America 2 NRC Before the Atomic Safety and Licensing Board (Case's Proposed findin Welding Issues)gs of fact on
31. No date Partial Interview of Alleger 4
32. No date TRT Review Notes 3
33. 6/7/77 Brown & Root 8 35-1195-PCP-1 Revision (Partial) 34 1/12/81 CPSES Inspection Report 1 No. IR-MH5-1352
35. 1/12/81 CPSES Inspection Report 1 Class 5 Pipe Support
36. 10/10/81 Component Modification 2 Card Serial No. 46762 Rev. 1
37. 10/20/81 Component Modification Card 1 Serial No. 34365 Rev. 1
38. 3/31/83 Brown & Root Ref: 1 Dwg. M1-1206-3
39. 3/31/83 Brown & Root Sketch 1
40. 3/31/83 Brown & Root Mark No. 1 CT-1-073-001-Y45R Rev. 2
41. 8/1/83 Brown & Root 1 Dwg. BRHL-CT-1YD-002 Rev. 3 42, 2/27/84 CPSES Inspection Report 1 No. MH5-1-0027548
43. 3/20/84 CPSES Nonconformance 1 Report (NCR) No, M-84-00754-5 4

3

-~.

Re: F01A-85-59 APPENDIX M (Continued) 44, 3/22/84 CPSES Inspection Report 1 No, MHS-1-0034702

45. 10/12/84 TRT Reviewer Ilotes 1
46. No date TRT Information 1
47. No date Weld Filler Material Log 10 Sheets
48. No date Component Modification Card 2 Serial No. 46762
49. 12/13/84 SSER AP-14, 9 and 13 14 Draft 3
50. 7/11/77 Brown & Root ltr. 9 BRF-6565 to TLSI Re: Process Pipe Installation
51. 2/26/79 Gibbs & Hill Specification 2 2323-MS-100 Rev. 5 (Partial)
52. 12/6/82 TUSI Instruction 4 CP-EI-4.0-30 Rev. 1 (Review of Pipe Support Required Prior to System Operation)
53. 5/14/84 Brown & Root Procedure 3 No. CP-CPM 6.9E Revision 7 Pages 25-27 of 27
54. 7/16/84 Conversation Record 2

& Summary

Subject:

Temporary Supports, the Fabrication, Installation and Removal of.

55. 7/16/84 TRT Reviewer notes 3
56. No date TRT Reviewer notes 3
58. No date Outline for Discussion 1 with QA/QC
59. 11/1/84 SSER AQW-28, 10, 30 14 AW-36, 54, 31 Draft 8 4

R2: FOIA-85-59 APPENDIX M

, . (Continuxd) l *60. 10/26/84 SSER AQW-28, 10, 30 13 AW-36, 54, 31 Draft 7 4 61. No date Comanche Peak Open Issue Plan 3

62. No date Draft

Subject:

2 Resolution of TRT QA/QC Consnents on Mechanical / Piping Category 2 SSER

63. No date Comanche Peak Nuclear Power 4 Plant. Allegation and/or Investigation Summary
64. 9/9/81 Comanche Peak Steam Electric 2 Nonconformance Report M-81-00191
65. 10/11/84 USNRC Before Administrative 2 Judges Memorandum (Telephone Conference)
66. No date Partial Testimony of A11eger 3
67. No Date Partial Testimony of Alleger 13 Pages 20,311 - 10,323
68. No date Partial Testimony of A11eger 9 Pages 10,589 - 10,597
69. No date Partial A11eger Affidavit 4 Pages 10705 - 10708
70. No date Partial A11eger Affidavit 9 Pages 10837 - 10845 71 No date Partial A11eger Affidavit 6 Pages 10898 - 10903
72. No date Partial A11eger Affidavit 2 Pages 10924 - 10925
73. No date Partial Alleger Affidavit 7 i Pages 4086 - 4092
74. No date Partial A11eger Affidavit 8 Pages 4147 - 4154
75. No date Partial A11eger Affidavit 12 Pages 4210 - 4221
76. No date Partial Alleger Affidavit 10 Pages 4356 - 4365 5

L

Re: F0IA-85-59 APPENDIX M (Continued)

77. No date CPSES Welding Issues 9 (Weave Welding)
78. No date SSER AW-54 8 Handwritten Draft
79. 4/4/79 Brown & Root ltr. 9 BRF-9265 to TUSI Re: Approval of Welding Procedure Specification
80. 4/16/82 U.S. Nuclear Regulatory 9 Commission Region IV Investigation No. 50-445/81-12; 50-446/81-12
  • 81 09/05/83 Partial Statement of Alleger 1
82. 11/7/83 Brown & Root ltr. 10 BRF-11286 to TUSI Re: Approval of Welding Procedure Specification
83. 2/7/84 Supports - Testimony 1
84. 3/7/84 Partial Interview of Alleger 1
85. 3/16/84 Letter to Bill Baker from 3 Gary Maedgen Re: Listing of Documentation Packages
86. 7/5/84 Gibbs & Hill, Inc. 1 Specification 2323-MS-100 Rev. 8 Page 4-57
87. 8/28/84 Reviewed Hanger Data Packages 1 with Impacts for WPS
88. 10/10/84 Weave Welding - CPSES Issues 5
89. No date AW-54. Item 14 13 Results of March 8, 1985 TRT Visual Inspection of Integral (Welded) Attachments for Pipe Supports on Main Steam and Feed-water Lines of Unit 1.
90. No date NC-2322.2-NC-2341 1 Section III, Division 1 Subsection NC
91. No date Component Support Identification 1
92. No date Listing of Hangers 17 6

Re: F0!A-85 59 l l

APPENDIX M ,

(Continued)

93. No date TRT Reviewer Notes 1
94. No date Gibbs and Hill Specification 6 2323-MS-43a Rev. 1 Appendix 1, Piping Specification Category 1303 (Partial)
95. No date SSER AW-36 6 (Handwritten draft)
96. 6/21/79 USNRC Report No. 9 50-445/79-15; 50-446/79-15
97. 7/2/79 NRC ltr to TUGC0 2 Re: The Investigation conducted by Messrs. R. G. Taylor and W. A.

Crossman of NRC staff on May 29 through June 4, 1979.

i

98. No date TRT Reviewer Notes 4
99. No date IR by Region IV, Page 65 1
  • 100. 3/7/84 Partial Interview of Alleger 1 101. No date Partial Interview of Alleger 4 102. 8/25/82 Component Modification Card 7 103. 9/29/82 Brown & Root, Inc. 1 CPSES,QI-QAP-11.1-28 Rev. 14 104. 12/3/82 USNRC Region IV Report 18 50-445/82-11; 50-446/82-10 105. 12/13/82 NRC ltr to TUGC0 Re: 5 Transmittal of Inspection Report 106. No date TRT Reviewer Notes 2 107. No date TRT Reviewer Notes 4 (Cat.2,AQW-10,AW-31) 108. No date NF-3000 Design 4 NR-3275-NF-3292.1(Partial) 1 109. No date Cases of ASME Boiler and 1 Pressure Vessel Code (Page729) 7

R2: F0!A-85-59 APPENDIX M (Continued) 110. 9/4/84 NRC Staff Proposed Findings of 17 Fact on Allegations of Intimidation, Threatening and Harassment of Quality Control Inspectors and Other Quality Control Personnel at the Comanche Peak Steam Electric Station ANO 8409130167 50-445G 111. 9/27/84 Applicants' Prehearing 23 Proposed Findings of Fact Concerning Allegations of Harassment, Intimidation and Threats of Quality Control Inspectors at the Comanche Peak Steam Electric Station AN0 8409050518 50-445G 112. 11/27/84 USNRC Allegation Interview 13 (Partial) 113. No date TRT Reviewer Notes 1 114. No date Partial Testimony of Alleger 10 115. No date Case's Preliminary Proposed 22 Findings of Fact on Harassment and Intimidation PDR ANO 8409070162 A00CK 50-445G 116. No date Section III.J NCR with 25 Inaccurate Dates (Partial) 117. 9/4/79 Brown & Root 1 Nonconformance Report NCR-M-1192-R.3 118. 12/27/79 Brown & Root 1 Nonconformance Report NCR M-1860 119. 1/9/80 Brown & Root memo to Distribution 1 Re: Minutes of ANI/QA Meeting of 1/9/80 120. 1/22/80 Letter from the Hartford Steam i Boiler Inspection and Insurance Co. to Brown & Root Inc. Re: Minutes of AN!/QA Meeting of 1/9/80 y

8

Ra: F0!A-85-59 APPENDIX M (Continuud) 121. 1/24/80 Letter from the Hartford Steam 1 Boiler Inspection and Insurance Company to Brown & Root Re:

Minutes of ANI/QA Meeting 1/9/80 My Letter 1/22/80 122. 2/15/80 Brown & Root Memo 1 Sub: Preliminary Review of CSTP.MRS & WOC 123. 3/4/80 Brown & Root, Inc. 2 Itr to The Hartford Steam Boiler Inspection & Ins. Co.

Re: Compliance of Weld Examination Program 124. 3/18/80 Brown & Root Nonconformance 1 Report (NCR) No. M-1931 R.1 Serial No. 6395298 125. 2/3/81 Weld Data Card WDC 3 Serial No. 6395298 126. 2/5/81 Weld Data Card WDC 1 Serial No. 6395340 127. 2/5/81 Weld Data Card WDC 1 2"-CS-1-546-601 R.2 128,2/5/81 Weld Data Card WDC 1 Serial No. 6395342 50-445/81-07; 50-446/81-07 129. 5/5/81 USNRC Inspection Report 2 50-445/81-07; 50-446/81-07 130. 1/8/82 Brown & Root. Inc. Quality 1 Assurance Dept. Nonconformance Report NCR No. M-3120 131. 3/4/82 Brown & Root Inspection Report 1 132. 5/17/82 Request for RT No. 53000 1 133. 6/9/82 Request for RT No. 4160 1 134. 6/14/82 Repair Process Sheet 1 WDC Serial No. 6395298 135,6/16/82 Brown & Root Visual 1 Examination Checklist 136. 6/17/82 Brown & Root Quality 1 Assurance Dept. MT/PT Report 9

R2: F01A-85-59 APPENDIX M (Continued) 137. 6/17/82 Brown & Root Inspection Report 1 1

138. 9/9/82 SIS Record for Monitoring 2 QA/QC Program #308 139. 4/15/83 Brown & Root Quality Insurance 17 Dept. NCR M-2690 R.6 140. 9/13/83 Brown & Root Message to Bill 1 Hartshern Re: ANI Request 141. 1/14/84 Weld Filler Material Log 1 WDC No. 40851 142. 1/17/84 Brown & Root Nondestructive 1 Test Inspection Request 143. 1/18/84 Repair Process Sheet WDC 1 Serial No-40851 144. 3/28/84 Weld Data Card WDC 1 Serial No. 40851 145. 5/25/84 Applicant Response 1 Allegation No. 21 146. 6/1/84 Applicant Response 1 Allegation No. 19 147. 7/25/84 Request for RT No. 62071 1 148. 7/25/84 Brown & Root 1 Quality Assurance Dept. NDE Radiographic Report 149. 7/25/84 Brown & Root 1 Quality Assurance Dept.

NDE Radiographic Report RT 30972 150. 7/25/84 Brown & Root 1 Quality Assurance Dept.

Nonconformance Report (NCR)M-12963 151. No date TestimonyofAlleger(Partial) 4 AQW-30 152. No date StatementofAlleger(Partial) 1 153. No date Statement of Alleger 2 154. No date Brown & Root. Inc. Dwg. No Number. 1 BRP-AF158-007 10

Re: F01A-85-59 APPENDIX M (Continued)

  • 155. 1/24/83 USNRC Office of Investigations 8 Field Office Region IV Assistance to Inspection Report

Subject:

Comanche Peak Alleged Defective Pipe Hangers 156, 5/8/78 Brown & Root 2 Weld Data Card Unit 1, System 4803, Line 10-CT-1-009-301 R-2 157. 5/8/78 Brown & Root 2 Weld Data Card Unit 1, System 4803, Line 10-CT-1-009-301 R-2 158. 1/27/79 Brown & Root, Inc. 1 Quality Assurance Dept.

Visual Examination Report 159. 1/29/79 Request for RT No. 22461 1 160. 1/30/79 Brown & Root Weld Data Card 1 Serial No. 00705 161. 2/5/79 Brown & Root 1 Quality Assurance Dept.

NDE Liquid Penetrant Report 162. 2/5/79 Brown & Root 1 Quality Assurance Dept.

Visual Examination Report 163. 2/26/79 Gibbs & Hill, Inc. 1 Specification 2323-MS-100 Rev. 5 164. 3/8/79 Weld Addition / Removal Card 1 Serial No. 001355 165. 3/8/79 Brown & Root 2 Weld Data Card Serial No. 10297 166. 6/13/79 Brown & Root, Inc. 2 Quality Assurance Dept.

NDE Radiographic Report RT 5566 167. 5/29/79 Brown & Root 1 Quality Assurance Dept.

Visual Examination Report 11

R2: F0!A-85-59 APPENDIX M

. (Continued) 168. 5/30/79 CPSES Weld Addition / Removal 1 Card Serial No. 001466 169. 6/2/79 Brown & Root, Inc. 2 Weld Data Card Serial No. 13264 170. 6/13/79 Brown & Root 1 Quality Assurance Dept.

NDE Radiographic Report RT 5829 171. 7/3/79 Brown & Root 1 Quality Assurance Dept.

NDE Radiographic Report RT 6113 172. 7/9/79 Weld Data Card 1 Numbers not Legible 173. 4/3/80 Brown & Root 1 Quality Assurance Dept NDE Report Serial No. 0797 174. 4/3/80 Repair Process Sheet R-1 1 Base Metal Repair 175. 4/10/80 Brown & Root 1 Quality Assurance Dept.

UT Thickness Report No. 767 176. 4/10/80 Brown & Root 2 Weld Data Card Dwg. No. BRP-CT-1-SB-017R3 177. 4/16/80 Request for RT No. 31812 1 178. 4/23/80 Brown & Root Quality Assurance Dept. 1 NDE Radiographic Report RT 12691 179. 2/18/82 Brown & Root, Inc. 6 Quality Assurance Report NCR No. M-3226 180. 5/6/82 TUSI Site Memo 2 GTT-8679

Subject:

Radial Weld Shrinkage 181. 5/18/82 Comanche Peak Steam Electric 1 Station Design Change Authorization DCA No. 13,335 12

R2: F01A-85-59 APPENDIX M (Continu;d) 182. 5/21/82 TUSI Memo CPPA# 19,384 1 to J. C. Keller Re: Class I Pipe Stress Analysis Weld Shrinkage 183. 5/25/82 Brown & Root, Inc. 3 Quality Assurance Dept.

Nonconformance Report NCR No. M-3220 184. 6/3/82 Brown & Root, Inc. 4 Quality Assurance Dept.

Nonconformance Report NCR No. M-3177 R.1 185, 1/27/83 Brown & Root, Inc. 1 Inspection Report 186. 3/9/83 Appendix B 9 U.S. Nuclear Regulatory Commission Region IV Reports 50-445/83-07; 50-446/83-04 187. 4/26/83 TUSI Dwg. No. 1 GHH-CT-1-SB-017 Rev. I 188. 8/31/83 Brown & Root, Inc. 1 Dwg. No. BRHL-CT-1-SB-017 Rev. 2 189. 3/7/84 Partial Interview of Alleger 1 190. 6/26/84 Brown & Root, Inc. 1 Dwg. No. BRP-CT-1-SB-017 Rev. 20 191. 9/13/84 TRT Reviewer Notes 2 Category 3 (AW-52, 59, 62) 192. 12/12/84 TRT Reviewer Notes 1 AW-52, 59, 62 193. 12/12/84 TRT Reviewer Notes 4

Subject:

Resolution of TRT QA/QC Comments on Mechanical

& Piping Category 3 SSER Item:

Radial Shrinkage of Welds 194. No date ITTG Piping Sketch 2 195 No date Component Modification 1 Card (CMC)No.30794 13

. . Re: FOIA-85-59 APPENDIX M (Continued) 196. No date Brown & Root, Inc. 1 Weld Data Card 197. No date TRT Reviewer Notes 3 (CT-1-SB-017, Spool ITTS, ContainmentSpray) 198. No date Comanche Peak Open Issue 3 Action Plan 199. No date Comanche Peak Nuclear Power 2 Plant Allegations and/or Investigations Sumary 200. No date Hand drawn Sketch 3 BRP-CT-1-SB-17 FW1 RT-4032 201. 4/27/84 NPC ltr to Division of 5 Engineering Architecture &

Technology Oklahoma State Univ. Stillwater Oklahoma Sub:

Texas Utilities Electric Company, et al. (Cornnche Peak Steam Electric 3YatTon, Units 1 and 2, Docket Nos. 50-445 and 50-446 202. 4/30/84 NRC ltr to TUSI 2 Re: Dockets 50-445; 50-446 203, 9/11/84 Record of Telephone 3 Conversation with Alleger 204. No date TRT Reviewer Notes 37 from Interview with Alleger 205. No date Listing of Issues 2

  • 206. No date Partial Statement of Alleger 3 207. 12/21/77 TUSI Dwg. 2323-S-0901 1 Rev. 2 208, 6/6/78 CPSES/ Design Change 1 Authorization No. 1828 209. 7/13/78 CPSES/ Design Change 1 Authorization No. 2087 210. 12/4/79 Brown and Root Dwg. 2 FSE-00159 Sheet 8057 14

Ra: F01A-85-59 APPENDIX M

, (Continued) 211, 1/31/80 TUSI Dwg. 2323-El-0712-01-S 1 Rev. 7 212. 4/20/81 1 TUSI Sheet Dwg(.

1 CableTNE-S2-0901 Tray Support) 213. 11/12/81 Brown & Root Dwg. 1 FSE-00159 Sheet 8073

  • 214, 4/16/82 US Nuclear Regulatory 9 Comission Inspection Repor.t (50-445/81-12, 50-446/81-12) 215. 5/29/84 TUGC0 ltr TXX-4183 1 to USNRC Regarding: Plug Welds in Unit 2 Spread Room 216. 7/3/84 CPSES/Nonconformance Report 3 NCR Na. M-84-01230 R.1 217. 7/3/84 CPSES/Nonconformance Report 3 NCR No. M-84-01231 R.1 218. 7/3/84 CPSES/Nonconformance Report 3 NCR No. M-84-01232 R.1 219. 8/1/84 TRT Notes Re: Drawing 2 Review 220. 8/13/84 TUGC0 ltr. TXX-4259 to 5 NRC Re: Plug Welds in Unit 2 Spread Room Additional Response File No. 903.9 221. 8/31/84 TRT Reviewer Notes 1 (Re: Plug Welds) 222. 9/5/84 TRT Reviewer Notes 5 Re: Welding Allegations 223. 10/13/84 M&PC AW-49-AW AW-55 1 Reviewer Note to Author 224. No date Appendix A: Plug and Slot Welds 1 225. No date Figure 1, Subsection NF 1 Component Supports Design Stress Intensities & Allowable Stresses (KSI) 226. No date Comanche Peak Open Issue 3 Action Plan Task: Plug Welds 15

. . Re: F0IA-85-59 APPENDIX M (Continued) 227. No date Partial Statement of A11eger 1 228. No date Comanche Peak Nuclear Power 2 Plant Allegations and/or Investigations Sunnary 229. 10/22/84 SSER AW-44, Draft 2 4 230. 1/16/85 SSER AW-44, Draft 4 4 231, 8/7/75 TUSI Dwg. 2323-S1-0513 1 R.B. Containment Liner Details SH. No. 3 232. 3/4/76 Chicago Bridge & Iron Company 1 Dwg. No. 382 74-2427u Rev. 2 233. 3/4/76 Chicago Bridge & Iron Company 1 Dwg. No. 381 74-2427u Rev. 2 234. 4/7/76 Chicago Bridge & Iron Company 1 Dwg. 32 Rev. 5 235. 6/9/76 CBI Shop Check List 2 Contract No. 74-2427 236. 6/26/76 TUSI Dwg. 2323-SI-0506 Rev. 5 1 237. 7/30/76 CBI Shop Release for Shipment 1 Check Dist. Contract No.

74-2427 238. 11/9/76 Gibbs & Hill Memo GHF-1025 9 Re: B&R Welding Procedure WPS-10038 Rev. 3 Ref: BRF-3802 239. 2/2/79 EPG Engineered Systems 1 Division Dwg. 802252 Item 1 240. 7/8/81 NRC ltr to Regulatory Guide 2 Distribution List (Division 1)

Sub: Withdrawal of Six Division 1 Regulatory Guides 241, 8/19/81 TUSI Dwg. (Reactor Containment 1 Penetration & Details) 242. 1/26/84 TRT Reviewer Notes 2 16

R2: F0IA-85-59 APPENDIX M (Centinu;d) 243, 5/31/84 Comanche Peak Allegation 1 Work Package " Mechanical &

Piping Category 5 - Weld Designs" 244. 8/6/84 Conversation Record 1

Subject:

Welding of Cadweld Sleeves to Main Steam Penetration Sleeves and Attaching Rebar to Same 245. 8/6/84 Conversation Record 1

Subject:

Welding of Cadweld Sleeves to Main Steam Penetra-tion Sheeve and Attaching Rebar to Same.

246. No date Comanche Peak Open Issue 2 Action Plan Task: Improper Weld Design 247. No date CBI Repair Check List 1 248. No date TRT Reviewer Notes 8 AW-44 Cadweld Welded to Penetration Sleeves 249. No date Reviewers notes to Author 2 250. No date Mechanical and Piping 1 Allegation Review Categories 251. No date Comanche Peak h elear Power 1 Plant Allegations and/or Investigations Summary 252. 1/2/73 U.S. Atomic Energy Connission 3 Regulatory Guide -

Directorate of Regulatory Standards

  • 253. 8/29/83 Statement of Alleger 4 254. 10/19/84 SSER AW-45, AW-46, AW-61, AW-66 7 Oraft 4 255, 1/31/85 SSER AW-45, AW-46, AW-61/ AW-66 7 Draft 6 17

Re: F0IA-85-59 APPENDIX M (Ccntinu:d) 256. No date Partial List and Description 3 of Allegations AW-61

  • 257. No date Field Walkdown with A11eger 1 258. No date Response for Allegations 1 of A11eger in Mechanical /

Piping Area 259. No date Allegation Sumary 1

  • 260. No date Investigative Findings 2 Regarding the Allegation of Intimidation by Threat of Termination
  • 261. 5/20/83 Partial Testimony of A11eger 2 AW-45 262. 3/5/84 Brown & Root CPSES Procedure 1 CP-CPM 14.1 Rev. 2 Page 4 of 4
  • 263. 3/7/84 Partial Testimony of A11eger 2 AW-61
  • 264. 3/7/84 Partial Testimony of A11eger 1 AW-46 265. No date Comanche Peak Nuclear Power 3 Plant Allegations and/or Investigations Sumary 266. No date PaymentReceipt(NRC) 1
  • 267, 11/5/82 USNRC Report of Inquiry 2

Subject:

Alleged Irregularities in Comanche Peak Radiographic Operations Report Number Q4-82-025 268. 1/31/85 SSER AW-48, AQW-20, AQW-21, 6 and AQW-23 Draft with Comments 269. No date TRT Reviewer Note 1 Re: Telephone Call J. Zudans to R. Masterson 270. No date Record of Telephone Conversation 1 with A11eger 271. 10/6/77 Brown & Root Quality Assurance Dept. 13 Welder Documentation Surveillance Checklist 18

Re: FOTA-85-59 APPENDIX M l (Continued) 272. 1/4/78 Gibbs & Hill ltr 41 i GHF-2305 to TUSI Re: B&R Welding Procedure Specification (w/ attachment) 273. 9/29/S2 NRC Memorandum for: Gagliardo 1 from: R.G. Taylor Re: Allegation Regarding Irregularities in Comanche Peak Radiographic Operations 274. 5/24/83 Brown & Root Memo IM-25594 32 to: Documentation Center from: W. E. Baker

Subject:

Recall of Welding Construction Procedure 275. 2/8/84 TUGC0 Procedure CP-QP-2.4 1 Rev. 4 Nondestructive Examination Personnel Training, Qualification and Certification Page 1 of 27

  • 276. 3/7/84 Partial Interview of Alleger 1 277. No date Comanche Peak Nuclear Power 1 Plant Allegations and/or Investigations Summary 278. No date Partial of Investigation of 5 Allegations in Regard to Piping Activities AQ0-23
  • 279. 3/7/84 Partial Testimony of Alleger 3 280. 8/1/84 Partial Testimony of Alleger 6 281. 9/18/84 SSER AW-63 Draft 5 6 282. 10/9/84 Category 8 TRT Reviewer Notes 14 283, 1/29/85 SSER AW-63, AW-67 Draft 10 5 284. 2/28/85 SSER AW-63, AW-67 Draft 11 14 285. 2/25/80 Brown & Root Dwg. 1 BRP-MS-2-RB-018 Rev. 1 286. 2/25/80 Brown & Root Dwg. 1 BRP-MS-2-RB-019 Rev. 1 287. 8/26/80 Brown & Root 8 Weld Data Card With Attachments 19

. Re: F0!A-85-59 APPENDIX M (Continued) 288. 4/15/82 Component Modification Card 4 (CMC) Serial No. 57616 Rev. 2 289. 2/1/83 Brown & Root 30 Quality Assurance Dept.

Nonconformance Report (NCR) No. M-3425 Rev. 2 290. 3/1/84 Brown & Root Quality 10 Assurance Dept.

Nonconformance Report No. M-14560 291. 9/18/84 M&PC 8 AW-63, AW-67 2 Review with no comment 292. No date TRT Reviewer Outline 2 Category 8 Weld Repairs 293. No date Comanche Peak Open Issue 3 Action Plan 294. No date Rewrite of Assessment 9 l Only of Category 8 Mechanical /

Piping Group 295. No date TRT Reviewer Notes Item 4 2 296. No date Comanche Peak Nuclear Power 1 Plant Allegations and/or Investigations Sumary

  • 297. 3/7/84 Interview of Alleger 1 298. No date NRC Staff Testimony on Welding 40 Fabrication 299. No date Sumation of Weld Rod Control 8 300. 4/4/78 Arizona Public Service ltr to 98 NRC

Subject:

Control of Low Hydrogen, Covered, Arc Welding Electrodes at Palo Verde Units 1, 2, and 3 (with attachments) 301. 1978 Weldability of steels by: 2 Welding Research Council 302. 12/11/81 Alloy Rods Division 4 ATOM ARC 7018 Moisture Resistant Low Hydrogen Electrodes 20

R2: F01A-85-59 APPENDIX M (Continu;d) 303. 2/24/82 Alloy Rods Division 4 ATOM ARC 7018-1 Moisture Resistant Low Hydrogen Electrodes 304. 4/16/82 U.S. Nuclear Regulatory Commission 9 Region IV Investigation No.

50-445/81-12; 50-446/81-12 305. 7/11/84 CPSES Design Change Authorization 1 DCA No. 15,295, Rev. 1 306. 8/2/84 Conversation Record

Subject:

1 Weld Filler Metal Control 307. 9/17/84 TRT Reviewer Notes 13 308. 1984 Structural Welding Code 8 (American Welding Society) 309. No date A Study of Hydrogen Cracking 7 in Underwater Steel Welds (WeldingResearchSupplement) 310. No date TRT Reviewer Notes 2 311. No date Comanche Peak Open Issue 2 Action Plan 312. No date Part C - Welding Rods, 2 Electrodes and Filler Metals Page 63 and 64 313. No date Report on Overexposed 13 E7018 Electrode 314. No date Comanche Peak Nuclear Power 2 Plant Alle0ations

  • 315, 9/15/83 Partial Statement of Alleger 1 316. 3/19/84 Partial Testimony of Alleger 19 317, 3/20/84 Partial Testimony of Alleger 7 318. No date Partial Testimony of Alleger 9 319. No date Partial Testimony of A11eger 12 320. 2/26/79 Gibbs & Hill 2 Specification 2323-MS-100 Rev. 5 (Partial) 21

R2: F0!A-85-59 APPENDIX M (Continued) 321. 9/28/79 Comanche Peak Electric 4 Station Design Change Authorization 5503 Rev. 1 322. 10/18/79 Comanche Peak Electric Station 4 Design Change Authorization 5551 Rev. 2 323. 1/3/80 Brown & Root, Inc. 7 QI-QAP-11.1-26 Rev. O ASME Piping & Welding Inspections 324. 2/6/80 Brown & Root, Inc. 4 CP-CPM 6.90 (Appendix D)

Welding & Related Processes 325. 7/10/81 Brown & Root Quality Assurance 4 Dept. NDE Report 326. 1/19/81 Brown & Root 39 CP-CPM-6.9G Rev. 2 CP-CPM 6.9 (Appendix G)

Documentation for ASME Welding Fabrication, and Installation Activities 327. 2/26/81 CPSES Design Change 2 Authorization DCA No. 9716 328. 4/29/81 Brown & Root 3 QI-QAP 11.1-26 Rev. 5 (Supplement 6.90-11)

ASME Piping Weld Inspections 329. 6/12/81 Brown & Root CP-CPM-6.90 10 Rev. 2 Appendix 0 Welding and Related Processes 330, 5/20/82 Brown & Root QI-QAP-16.1-2 31 Rev. 4 (Documenting Base Metal Repairs, Minimum Wall Violation and ARC Strike Repairs) 331. 5/25/82 Attachment 10 4 Documentation Check List Pkg. No. CC-1-SB-038 7Q3 RPS 332. 7/26/83 Attachment 1 9 Documentation Check List Pkg. No. H-CC-1-SB-038-010-3 Rev. 1 22

, Re: F01A-85-59 APPENDIX M

, (Continued) 333. 1/12/84 Brown & Root 4 CP-CPM 6.9D Rev. 6

  • 334. 3/7/84 Partial Interview of Alleger 1 335. 6/11/84 Brown & Root 3 QI-QAP-11.1-26 Rev. 16 336. 6/11/84 Brown & Root 6 CP-QAP-16.1 Rev. 21 Control of Nonconforming Items 337. No date Category 10, AP5, Item 14 1 338. No date Partial Statement of Alleger 2
  • 339. No date Partial Statement of Alleger 1 340. 4/2/85 SSER AQ-77, AQ-79 and AQ-138 20 Revision 1 341. 9/19/78 NRC ltr to TUGC0 2 Re: Inspection Activities During August 1-31, 1978 Rpt. 78-13 342, 2/27/79 NRC ltr to TUGC0 3 Re: Inspection Activities February 5-8, 1979 343. 5/14/79 NRC ltr to TUGC0 15 Re: Inspection Activities April 2-3 and April 13-23, 1979(withReport)(79-11) 344. 7/21/80 Brown & Root 13 CP-CPM 6.9C Appendix C Material Identification 345. 2/2/83 Brown & Root 17 CP-QAP-14.1 Rev. 1 Inspection of Storage and Maintenance of Mechanical Equipment 346. 5/31/83 NRC ltr to TUGC0 5 Re: Construction Appraisal Inspection January 24 -

February 4, 1983 and Februar March 3, 1983 (83-18; 83-12)y 14 -

23

Re: F0!A-85-59 APPENDIX M

, (Continued) 347. 7/11/83 NRC ltr to TUGC0 11 Re: Acknowledgement of Response to Notice of Violations (83-18; 83-12) 348. 8/24/83 NRC ltr to TUGC0 16 Transmittal of Inspection Report (83-24;83-25) 349. 6/11/84 Brown & Root 41 QI-QAP-11.1-39 Rev. 4 (Mechanical Equipment InstallationInspection) 350. 6/11/84 Brown & Root CP-QAP-11.1 3 Rev, 5 (Fabrication and Installation Inspection of Components, Component Supports, and Piping) 351. 7/23/84 NRC ltr to TUGC0 Re: 20 Inspection Conducted Under the Resident Inspection Program March 20, 1984 through May 18, 1984 352. 7/26/84 NRC ltr to TUGC0 16 Re: Inspection Activities Novembe'r 14, 1983 through March 31, 1984 353. S/1/84 Brown & Root 12 Procedure MCP-1, Rev. 4 354. 8/8/84 Brown & Root 9 Procedure CP-CPM 6.3 Rev. 11 355. 9/25/84 Brown & Root 12 Procedure CP-CPM 8.1 Rev. 2 356. 2/1/85 Brown & Root 25 Procedure MCP-10 Rev. 8 357. 3/6/85 Brown & Root 1 Material Return to Warehouse No. W-19816 358. 3/7/85 Brown & Root, Inc. 1 CPSES Material Requisition 24

Re: F01A-85-59 APPENDIX M (Continued) 359. No date Sketch 2 (Pipe Fab Shop) 360. No date Appendix B 5 Potential Enforcement Findings

  • 361. 3/7/84 Partial Testimony of Alleger 2 362. 3/1/76 Gibbs & Hill, Inc. 2 Specification 2323-MS-100 363. 5/26/77 Westinghouse Process Specification 6 Cover Sheet PSPAS-01, Rev. 0 364. 6/28/78 Traveler ME78-014-5505 13 365. 9/16/78 Traveler ME78-007-5505 6 366. 12/7/78 Traveler WE78-026-5505 5 367. 2/1/79 Traveler WE-79-035-5505 2 368. 2/19/79 Traveler WE-79-035-5505 3 369. 2/19/79 Traveler WE-79-036-5505 3 370. 2/19/79 Traveler WE-79-037-5505 10 371. 2/27/79 Brown & Root ltr BRF-9181 3 to TUSI Re: Reactor Coolant Pipe 372. 3/12/79 Brown & Root ltr BRF-9207 2 to TUSI Re: Reactor Coolant Pipe Field Measurements 373. 3/i3/79 Brown & Root ltr BRF-9211 2 to TUSI Re: Reactor Coolant Pipe Field Measurements 374. 3/19/79 Westinghouse Dwg. 1 2323-MI-0520 375. 5/4/79 Brown & Root ltr BRF-9348 P.

to TUSl Re: Reactor Coolant Pipe Field Measurements 376. 1/3/80 Brown & Root QI-QAP-11.1-26 1 Rev. 0 (ASME Piping & Welding Inspections) 377. 2/6/80 Brown & Root QI-QAP-11.1-26 2 Ru. 1 25

. . Re: FOIA-85-59

^

APPENDIX M

. (Continued) 378. 5/23/80 Brown & Root CP-CPM 6.9E 2 Rev. 1 379. 6/26/80 Brown & Root QI-QAP-11.1-26 1 J Rev. 2 i

380. 7/16/80 Brown & Root Quality Assurance 8 i Dept. Nonconformance Report M-2305 381. 7/22/80 Brown & Root QI-QAP-11.1-26 2 Rev. 3 382. 8/22/80 Brown & Root QI-QAP-11.1-26 2 Rev. 4 383. 2/25/81 Brown & Root QI-QAP-11.1-31 1

Rev. 0 384. 4/29/81 Brown & Root QI-QAP-11.1-26 2 Rev. 5 3 385. 9/28/81 Brown & Root QI-QAP-11.1-31 1 Rev. 1 386. 1/12/82 Brown & Root QI-QAP-11.1-31 7 Rev. 2 387. 1/25/82 Brown & Root QI=QAP-11.1-31 9 4 Rev. 3 388. 1/27/82 Brown & Root QI-QAP-11.1-31 13
Rev. 3 1

! 389. 3/12/82 Brown & Root QI-QAP-11.1-26 2 Rev. 7 j

390. 4/15/82 Brown & Root QI-QAP 11.1-26 4

Rev. 8 391. 6/11/82 Texas Utilities Services, Inc. 3 4

CP-EP-4.0 Rev. 3

392. 12/16/82 Brown & Root QI-QAP 11.1-26 4 l Rev. 9 393. 2/2/83 Brown & Root QI-QAP 11.1-26 5 i Rev. 10 i 394. 3/18/83 Brown & Root QI-QAP 11.1-26 5

] Rev. 11 i

l

, 26

Ra: F01A-85-59 APPENDIX M (Continued) 395. 9/12/83 Comanche Peak SES Reactor 1 ,

CoolantLoop#1(sketch) 396. 5/14/84 Brown & Root CP-CPM-6.9E 3 Rev. 7 397. 6/11/84 Brown & Root QI-QAP-11.1-26 2 Rev. 16 398. 6/25/84 Brown & Root CP-QAP-6.1 8 Rev. 6 399. 7/3/84 Attachment 1 Documentation 15 Check List Pkg. No, ME-78-009-5505 400. 7/3/84 Attachment 1 Documentation 10 Check List Fkg. No.

ME-78-019-5505 401. 7/3/84 Attachment 1 Documentation 29 Check List Pkg. No.

ME-78-010-5505 402. 7/3/84 Attachment 1 DocumentatiGn 17 Check List Pkg. No.

ME-78-013-5505 403, 7/3/84 Attachment 1 Documentation 10 Check List Pkg. No, ME-78-021-5505 404. 7/3/84 Attachment 1 Documentation 62 Check List Pkg. No.

ME-78-008-5505 405. 7/3/84 Attachment 1 Documentation 15 Check List Pkg. No.

ME-78-020-5505 406. 7/3/84 Attachment 1 Documentation 3 Check List Pkg. No.

ME-78-007-5505 407. 7/3/84 Attachment 1 Documentation 30 Check List Pkg. No.

ME-78-015-5505 408. 7/3/84 Attar.hment 1 Documentation 15 Check List Pkg. Ko.

ME-18-022-5505 27

Re: F01A-85-59 APPENDIX M

{Eontinued) 409. 7/5/84 Gibbs and Hill 6 ,

Specification 2323-MS-100 1 Revision 8 410. 7/6/84 Brown & Root DWG. 1 BRP-RC-1-520-001 Rev. 10 411. 7/6/84 Brown & Root DWG. 2 BRP-RC-1-520-001 Rev. 10 Sh. 2 and 3 of 3 412. 9/3/84 Attachment 1 Documentation 7 Check List Pkg. No.

WE-78-006-5505 413. 9/3/84 Attachment 1 Documentation 14 Check List Pkg. No.

WE-78-028-5505 414. 9/3/84 Attachment 1 Documentation 12 Check List Pkg. No.

WE-78-025-55C5 415. 9/3/84 Attachment 1 Doucmentation 5 Check List Pkg. No.

WE-78-016-5505 416. 9/3/84 Attachment 1 Documentation 10 Check List Pkg. No.

WE-78-024-5505 417. 9/3/84 Attachment 1 Documentation 14 Check List Pkg. No.

WE-78-029-5505 418, 9/3/84 Attachment 1 Documentation 5 Check List Pkg. No.

WE-78-030-5505 419. 9/3/84 Attachment 1 Documentation 9 Check List Pkg. No.

WE-78-019-5505 420. 9/10/84 Brown & Root Dwg. 1 BRP-RC-520-001 Rev. 10 Sheet 1 of 3 421. No date Specification No. 10466-M204 14 Appendix D Compensation Allowances for Piping Misalignment 28

Re: F0IA-85-59 APPENDIX M (Continued) 422. No date Sketches (Comanche Peak) 10 Typical Reactor Vessel Supports 423. No date N B-3000 - Design 4 424. No date N B-4000 - Fabrication 2 and Installation Requirements 425. No date Attachment to TRT Report 2 Category 42 Field Weld Repairs, RCS Unit #1 426. No date Hot Leg -Cold Leg -Crossover 4 427. 7/12/84 Partial Testimony of Alleger 17 428. 7/12/84 Partial Testimony of Alleger 48 429. 8/1/84 Conversation Record 1 430. 5/1/73 U.S. Atomic Energy Commission 3 Regulatory Guide Control of the Use of Sensitized Stainless Stell 431, 3/1/76 Gibbs & Hill 1 Specification 2323-MS-100 432. 5/10/79 NRC Inspection Report 8 (79-06) 433, 5/23/80 Brown & Root 2 CP-CPM 6.9E Rev. 1 434. 9/23/80 Brown & Root 3 CP-CPM 6.90 Rev. 1 435, 5/7/81 CPSES Flow Diagram 1 Containment Spray System 436. 6/8/81 Brown & Root Message 3 With Sketches 437. 6/12/81 Brown & Root 1 CP-CPM 6.9D Rev. 2 438. 7/27/81 Weld Filler Material 6 Log Dwg. No. BRP-MS-1-TB-02 439. 8/21/81 Brown & Root Message 2 With Sketches 29

Re: F0IA-85-59 APPENDIX M

, (Continued) 440. 10/13/81 Brown & Root Message 2 With Sketches 441. 12/2/81 Brown & Root Message 2 With Sketch 442. 1/11/82 Brown & Root Message 2 With Sketch 443. 6/30/82 Brown & Root Message 2 With Sketch 444. 7/20/82 Brown & Root Message 2 (Sketch) 445. 3/14/83 Brown & Root Interoffice 7 Memo IM#25214

Subject:

Recall of Welding Procedure Specifications 446. 3/30/83 Brown & Root Procedure 1 No. CP-CPM-6.9D Rev. 5 447. 4/28/83 Brown & Root Message 3 With Sketch 448. 1/12/84 Brown & Root 7 CP-CPM 6.9D Rev. 6

  • 449. 3/7/84 Partial Testimony of Alleger 3 450. 5/14/85 Brown & Root 3 CP-CPM-6.9E Rev. 7 451. 7/5/84 Gibbs & Hill, Inc. 2 Specification 2323-MS-100 Revision 8 452. 8/2/84 CPSES Piping-Nuclear 4 Specification 2323-MS-43A 453. No date TRT Reviewer Notes 3 454. No cate Article NC-2000 3 Materials 455. 2/3/83 Case ltr to NRC 9 i

Re: Affidavit of Alleger

  • 456. 5/6/83 Statement of Alleger 2
  • 457. 5/20/83 Partial Testimony of Alleger 3 l

30

Re: F01A-85-59 APPENDIX M (Continued)

  • 458. 5/23/83 NRC-Assistance to Inspection 3 Report A4-83-005
  • 459. 6/6/83 NRC Memorandum to: 8 William J. Ward From:

Richard K. Herr

Subject:

Assistance To Inspection Report No. A4-83-005 460. 9/29/83 NRC ltr to TUGC0 29 Re: Transmittal of Inspection Report During Periods May 10 - July 1 and September 9-22, 1983 PDR ANO 8310180214 ADOCK 50-445Q 461. 11/28/83 Case ltr to NRC 7 Sub: In the Matter of Application of Texas Utilities Generating Company et al. for an Operating License for Comanche Peak Steam Electric Stations Units #1 and #2 (CPSES) Dockets Nos. 50-445 and 50-446 Affidavits Attached to CASE'S 11/28/83 Answer to Board's 10/25/83 Memorandum (Procedure Concerning Quality Assurance) PDR ANO 8312010094 ADock 50-445G

  • 462. 11/30/83 NRC Assistance to Inspection 6 Report " Supplemental"

Subject:

Comanche Peak Steam Electric Station: Alleged Improper Construction Practices Report Number: A4-83-005

  • 463. 2/9/84 Report of Inquiry

Subject:

4 Comanche Peak Steam Electric Station Alleged Procedural Violations of Construction Practices 464. 3/15/84 USNRC Memorandum (Clarification 21 of Open Issues) PDR AN0 8403190002 AD0CK 50-445G

  • 465. 5/20/84 Results of Interview with Alleger 2 466. 9/19/84 Technical Interview of Alleger 28 467. 9/19/84 Notes Related to Alleger 11 Interview 468. No date Results of Interview with Alleger 3 31 I

. . Re: F0!A-85-59 APPENDIX M (Continued) 469. 3/1/76 Gibbs & Hill Specification 7 2323-MS-100 (Partial) 470. 7/9/76 Gibbs & Hill Specification 3 2323-MS-100, Revision 2 (Partial) 471. 3/9/77 Gibbs & Hill Specification 4 2323-MS-100 Rev. 3 (Partial) 472. 4/30/77 Gibbs & Hill Specification 4 l 2323-MS-100 Rev. 4 (Partial) 473. 7/11/77 Brown & Root ltr BRF-6565 9 to TUGC0 Re: Transmittal of Procedure 474. 2/26/79 Gibbs & Hill Specification 4 2323-MS-100 Rev. 5 (Partial) 475. 6/16/80 US Nuclear Regulatory 10 Commission Office of Inspection and Enforcement Report No. 50-445/80-11; 50-446/80-11 476. 1/13/81 Brown & Root Dwg. 2 MS-1-01-007-C72K Rev. 0 477. 1/13/81 Brown & Root Dwg. 1 MS-1-01-001-E725 478. 1/13/81 Brown & Root Dwg. 2 MS-1-01-007-072K Rev. O i

479. 5/15/81 Texas Utilities Generating 3 l Company Procedure:

( CP-QP-19.3, Rev. 0 l (Surveillance of Piping

! Erection) 480. 7/24/81 Brown & Root Dwg. T l MS-1-001-002-6725 Rev. 4 481. 11/17/81 Brown & Root Dwg. 1 MS-1-001-006-C72K Rev. 1 32

Re: F01A-85-59 APPENDIX M (Continued) 482. 3/15/82 Gibbs & Hill Specification 14 2323-MS-100 Rev. 6 Section 7 483. 4/21/82 Brown & Root, Inc. 1 Message to Weld Eng.

(Request for Temp.

Data Cards) 484. 6/4/82 TUSI Instruction 4 CP-EI-4.0 Rev 0 (Review of Pipe Support Required Prior to System Operation) 485. 6/5/82 Attachment 10 10 Documentation Pkg. No.

MS-1-RB-001 486. 6/15/82 Attachment 10 18 Documentation Check List Pkg. No.

MS-1-RB-002 487. 12/6/82 TUSI Instruction 4 CP-EI-4.0-30 Rev. 1 (Review of Pipe Support Required Prior to System Operation) 488. 1/26/83 Brown & Root Dwg. 1 BRHL-MS-1RB-002 Rev. 3 Y

l 489. 2/4/83 Tl!31 Office Memorandum 2

Subject:

Comanche Peak Steam Electric Station 490. 2/15/83 Notes & Sketch 2 491. 2/24/83 Computer Lising of Class 2 56 Summary of 10 Highest Stresses for Each Equation 492. 9/22/83 Brown & Root Dwg. 8 Pkg. BRHL-FW-1-RB-004 Rev. 3 493. 10/20/83 Brown & Root Dwg. 1 Steam Generator Feedwater

  • f I

33

, Re: F01A-85-59 APPENDIX M (Continued) 494. 11/2/83 Brown & Root Dwg. 1 i MS-1-01-001-C72S {

Rev. 4 l 495. 11/6/83 Brown & Root Dwg. 1 MS-1-01-001-C72S Rev. 5 496. 12/2/83 Gibbs & Hill 3 Specification 2323-MS-100 Rev. 7 497. 3/5/84 Brown & Root 15 Procedure CP-CPM 14.1 Rev. 2 498. 6/11/84 Brown & Root 1 CP-QAP-12.1 Rev. 11 (Partial) 499. 6/11/84 Brown & Root 1 CP-QAP-12.2 Rev. 8 500. 6/11/84 Brown & Root 2 QI-QAP-11.1-28 Rev. 25 501. 6/11/84 Brown & Root 2 QI-QAP-11.1-26 Rev. 16 502. 7/10/84 Brown & Root Dwg. 1 BRP-MS-1-RB-002 Rev. 13 503. 7/30/84 Brown & Root Dwg. 8 BRP-FW-1-RB-003 Rev. 14 504. 8/24/84 Computer Listing Job Log 127

  • 505. No date Partial Statement of Alleger 6 506. No date Brown & Root Dwg. 9 Pkg. FSM-00165 Rev. 1 Containment 4 507. No date Brown & Root Dwg. 9 Pkg. FSM-00165 Rev. 1 Containment 2 508. No date Cat. 11 AP-13 6 (Sketches and Notes) 509. No date TRT Reviewer Notes AP-13 14 34

, Re: F01A-85-59 l'

APPENDIX M

- (Continued) 510. No date TRT Reviewer Notes 6 511. No date Component Modification Card 4 No. 61306 512. No date TUSI Sketch 1 Sub: Hanger MS-1-001-005-072K 513. No date Brown & Root Sketch 1 514. No date Sketch Coordinates 1 From Cont. Bldg.

i l

35

f

,q',. .], . n .. ..

. __ c .

t .

,' \ .' . . _ .

. 1 bOVERNMENT ACCOUNTADILITY PROJECT 45SS Connecikut Avenue. N.W Suite 202 WosNngton, D.C. 20036 I (202)232-8550 G:85:104 January 21,1985 i

_ FREEDOM OF INFORMATION ACT REQUEST FREEDOM OF INFORMATION ACI REQUEST.

Director Fo2'A -/5-sy Office of Administration Nuclear Regulatory Commission kd4 h/-g-g Washington, D.C. 20555 To Whom It May Concern:

Acccuntability Project (" GAP") requests copies of any and all a information, including but not limited to notes, letters, memoranda, drafts, sinutes, diaries, logs, calendars, tapes, transcripts, summaries, interview re- i charts, maps, photographs, agreementsports, procedures, instructicns, enginee handwritten notes, studies, data sheets, notebooks, books, telephone messages,, computations, voice recordings, computer runoffs, any other data compilations, interim and/or final reports, status re-ports, and any and all other records relevant to and/or generated in connection by any person, branch, or department of 18, the 1985. NRC since Janu This the NRC request Manual,includes Appendix all 0211 agency records as defined in 10 C.F.R. 5 9.3a(b) d ari Parts 1.A.2 and A.3 (approved October 8,1980) whether they currently exist in the NRC official, " working," investigative or other files, or at any other location, including private residences.

l If any records as defined in 10 C.F.R. 5 9.3a(b) and the NRC Manual, supra, and j covered by this request have been destroyed and/or removed after this request, please provide all surrounding records, including but not limited to a list of all records which have been or are destroyed and/or removed, a description of the

. to action (s) taken

' implement therelevant to, generated in connection with, and/or issued in order action (s).

GAP requests that fees be waived, because " finding the information can be con-sidered as primarily benefitting the general public," 5 U.S.C. 5 552(a)(4)(a).

GAP is a non-profit, non-partisan public interest organization concerned with honest and open government.

whistleblowers as agents of government accountability.Through Through its Citizens public outreach, the i Clinic, GAP offers assistance to local public interest and citizens groups steking to ensure the health and safety of their communities. The Citizens Clinic is currently assisting several citizens groups, local governments and '

intervenors in the central Texas area concerning the construction of the l

Comanche Peak nuclear power plant. .

u9 % ,',2I/

>>>s-.

.)c..

/ ~.~

~

6frector.

Office of Administration .

Page Two W2 are requesting the above information as part of an ongoing monitoring project on the adequacy of the NRC's efforts to protect public safety and health at .

nuclear power plants.

For any documents or portions that you deny due to a specific FOIA exemption, please provide an index itemizing and describing the documents or portions of dccuments withheld. The index should provide a detailed jusitfication of your grounds for claiming each exemption, explaining why each exemption is relevant to the document or portion of the document. withheld. This index is required under Vaughn v. Rosen (I), 484 F.2d 820 (D.C. Cir.1973), cert. denied, 415 U.S. .

977 (1974).

We look forward to your response to this request within ten days.

Sincerely, iW Billie Pirner Garde Citizens Clinic Director 9

4 l

- - - - - -- ,..-._ - .._ _. _ _. - . . - _ , . . - - . - , m ,,, . --.- - - - --- . - - - - . . - , .

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