ML20216J324

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Appeals Denial of FOIA Request for Documents Re Comanche Peak Task Force Established in Mar 1984 & Documents Requested on 870422 Re Info Provided by Alleger Identified in Sser 8
ML20216J324
Person / Time
Site: Comanche Peak  Luminant icon.png
Issue date: 07/08/1986
From: Garde B
GOVERNMENT ACCOUNTABILITY PROJECT
To: Stello V
NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO)
References
FOIA-85-59, FOIA-86-A-106 NUDOCS 8707020357
Download: ML20216J324 (2)
v • d • e


Text

. . .

GOVfRNMENT ACCOUNTADIUTY PROJECT

, 1555 Connecticut Avenue, N.W., Suite 202 )

j Washington, D.C. 20036 (202)232-8550 1

July 8, 1986

{

Victor Stell Executive Director for Operations APPEAL OF INITML rDA DECSON i i

U.S. Nuclear Regulatory Commission h-[-/Cg g'[ h Washington, I;.C. 20555 jq Re: Appeal of FOIA 85-59 and 85-313

Dear Mr. Stello:

h This is an appeal pursuant to subsection a(6) of the Freedom  !

of Information Act as amended (5 U.S.C. 522), of the actual l denial of the Commission to release documents requested on January 21, 1985 by the Government Accountability Project (GAP) regarding the Comanche Peak Task Force established in March 1984, and documents requested on April 22, 1985 regarding records  !

related to information provided by the alleger identified in SSER I No. 8.

By letter dated June 4, 1986, Mr. Donnie Grimsley, Director of the Division of Rules and Records advised us that records subject to the two requests were designated as Appendix M. He advised that of the 514 documents contained in Appendix M, portions of 16 were being withheld pursuant to FOIA Exemption 5 because they contain the advice, opinions and recommendations of the staf f concerning potential violations. . Mr. Grimsley also advised that portions of 49 documents were being withheld pursuant to an agreement reached between the staff and myself at a May 8, 1985 meeting, that the names and identifying details of allegers and other individuals would be protected.

Please be advised that the agreement reached at the May 8, 1985 meeting was that the confidentiality of allegers would be protected from disclosure 'and at 'no time was it meant to extend to "other individuals" as your letter states. To the extent the documents withheld pursuant to the May 8, 1985 relate to anyone but "allegers" we appeal their denied release.

We believe we are entitled to release of the portions of documents being withheld.

We expect your. response to this appeal within 20 working days of your receipt so that we can determine whether to pursue this matter further in the courts.

8707020357 070708 O DE A-106 PDR

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1 Thank you for your consideration of this appeal. I l

Sincerely,

& LA+-M hwb-Billie Pirner Garde  ;

Director, Environmental ]

Whistleblower Clinic

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- n NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555

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Docket Nos. 50-445/50-446 l

Ms. Billie Pirner Garde Director, Environmental Whistleblower Clinic IN RESPONSE REFER Government Accountability Project TO F01A-85-59 1555 Connecticut Avenue, NW, Suite 202 F01 A-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 requested, pursuant to the Freedom of Information Act (FOIA), records related to the NRC Comanche Peak Task Force established in March 1984 (F0IA-85-59) and your letter dated April 22, 1985, in which you requested, pursuant to the F0IA, all records related to all information provided by the alleger identified in the February 1985 SSER 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 (PDR),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 F0IA-85-313 or your letter dated March 3,1986, appealing our lack of ,

response to F01A-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 1 through.514, into the PDR in file F01A-85-59 under your name. '

Portions of the records identified at numbers 1, 49, 59, 60, 78, 95, 229, 230, l 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, 1

1&5 M M S M Mev ,

a

o l Ms. Billie P. Garde -2

.o opinions, and recommendations of the staff concerning potential violations.

The nonexempt portions of the Appendix M records are being placed in pDR file F01A-85-59 under your name.

Pursuant to 10 CFR 9.9 of the Commission's regulations, it has been 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. Harold R. Denton, 1 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 Commission, Washington, DC 20555, and should clearly state on the envelope and in the letter that it is an " 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 468, 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 sumarized in a letter to you from Mr. Joseph M. Felton dated May 15, 1985. The infonnation 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 inspection and copying at the Local Public Document Room (LPDR) located at the University of Texas Library, 701 South Cooper Street, Arlington, Texas.

Additional boxes of records subject to F01A-85-59 are currently under review and will be placed in the PDR and LPDR in the coming weeks.

Sincerely,

{

I M Donnie H. Grimsley, Director g Division of Rules and Records Office of Administration 4

Enclosure:

As stated l

l I

l l

)

e Re: F0!A-85 I APPENDIX M '

DOCUMENTS IN PDR FILE-F01A-85-59 Mechanical / Piping Box 4 Pages

1. 11/19/84 SSER AW-34, 35,'381 12 Draft 6.
2. 4/8/76 Gibbs &. Hill. 31-

. Specification 2323-MS-34 .g

]

Revision 1 Section 3 i (Technical specification i Diesel-Generator. sets)

3. .12/29/76 'Delaval Procedure 9 a No. 100-W-la 1
4. 7/17/80 CPSES Nonconformance Report 3 M-80-00009, Rev. 6

'5. 12/18/80 Transamer Delaval 3 l Ltr' to TUSI,

Subject:

Material l 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 4

7. 12/7/81 Transamerica Delaval 6 Addendum One to Piping {

j Analysis Calculations (

Texas Utilities Services, Inc. .i Units 1 8'2 Part 2 Analysis of-. '

Welded Channel Box Section

8. 5/13/82 CPSES Nonconformance Report 2 M-82-00581 ,
9. 5/13/82 CPSES Nonconformance Report 2 M-82-00581 Rev. 1
10. 17/8/82' CPSES Nonconformance_ Report: 1 I

~M-82-00902 Rev. I

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

1

l l , APPENDIX M (Continued) i

12. 8/6/82 CPSES Nonconformance Report 1 1 M-82-01207 1
13. 8/10/82 CPSES Inspection Report 1 l

No IRDG-03688 '

14 8/12/82 CPSES Inspection Report 1 i 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 j No. IRDG-03757 l
18. 9/14/82 Repair Process Sheet 2 WDC Serial No. 687490
19. 9/15/82 Partial Statement of Alleger 1 I
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 l l

21. 2/6/84 TUGC0 Instruction- 10 J

CP-El-4.0-50 Revision 0 (Control of Re-fabrication &

Installation of Diesel Generator Auxiliary Skid Base and i Associated Structures - Unit 2) l 22, 3/7/84 Partial Interview of Alleger 5

23. 7/19/84 TRT Reviewer Notes 3
24. 8/2/84 Conversation Record 2

Subject:

Weld Filler Metal Control

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

MSB-2605-DG09-WJ

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

. ,u . .. van-oa-as:

APPENDIX M J (Continued)

28. No date . Comanche Peak Open Issue -3 l Action Plan
29. No date Comanche Peak Nuclear Power 2' Plant Allegations 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 l

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 No. IR-MHS-1352 1-

)

35. 1/12/81 CPSES Inspection Report 1 Class S. 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 Reff 1 Dwg. M1-1206-3
39. 3/31/83 Brown & Root Sketch 'l
40. 3/31/83 Brown & Root Mark No. 1 4 CT-1-073-001-Y45R Rev. 2
41. 8/1/83 Brown & Root 1 Owg. BRHL-CT-1Y0-002 Rev. 3 42, 2/27/84 .CPSES Inspection' Report ,1 No. MH5-1-0027548 i i
43. 3/20/84 CPSES Nonconformance 1 1 Report (NCR) No.-..M-84-00754-S i j

J j

3 14

. - . .....wu

,- s APPENDIX M-l' -

(Continued) l

44. 3/22/84 CPSES Inspection Report 1 No. MHS-1-0034702 4
45. 10/12/84- TRT Reviewer Notes 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 8RF-6565 to TUSI Re: Process i Pipe Installation '
51. 2/26/79 Gibbs & Hill Specification 2 l 2323-MS-100 Rev. 5 (Partial)
52. 12/6/82 TUSI Instruction 4 H 1

CP-EI-4.0-30 Rev. I j (Review of Pipe. Support '

Required Prior to System Operation)

53. 5/14/84- Brown & Root Procedure 3 No. CP-CPM 6.9E Revision 7 q Pages 25-27 of 27 j

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 4

with QA/QC

59. -11/1/84 SSER AQW-28, 10, 30 14 AW-36, 54, 31. Draft 8 4

1 l

, APPENDIX M I (Continued) l

  • 60, 10/26/84 SSER AQW-28, 10, 30 13 AW-36, 54, 31 Draft 7 l
61. No date  !

Comanche Peak Open Issue Plan 3

{

62. No date Draft

Subject:

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

63. No date Comanche Peak Nuclear Power 4 Plant Allegation and/or Investigation Summary

)

64. l 9/9/81 Conanche Peak Steam Electric 2 1 Nonconformance Report M-81-00191
65. 10/11/84 USNRC Before Administrative 2 Judges Memorandum 1

(Telephone Conference)

66. No date Partial Testimony of A11eger 3
67. No Date Partial Testimony of A11eger 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 l l
71. No date Partial A11eger Affidavit _6 Pages 10898 - 10903
72. No date Partial A11eger Affidavit 2 Pages 10924 - 10925
73. No date Partial A11eger Affidavit 7 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 A11eger Affidavit 10.

Pages 4356 - 4365 5

APPENDIX M j

TContinued)

77. No date CPSES Welding Issues 9 (Weave Welding)
78. No date SSER AW-54 .

8 Handwritten Draft '

i

79. 4/4/79 Brown & Root ltr. 9 BRF-9265 to TUSI Re: Approval-of Welding Procedure Specificetion
80. 4/16/82 U.S. Nuclear Regulatory 9 Commission Region IV l Investigation No. 50-445/81-12; I 50-446/81-12 l
  • 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, i

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 Weiding - 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 l' Subsection NC

91. No date Component Support Identification- 1
92. No date Listing of Hangers 17' 6

' APPENDI): M

'(Continued) 4

93. No date TRT Reviewer Notes 1 94 No date Gibbs and Hill Specification 6 l 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 i 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.

98. No date TRT Reviewer Notes 4 4

'9. No date IR by Region IV, Page 65 1 l

  • 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 i

105. 12/13/82 NRC ltr to TUGC0 Re: 5  !

Transmittal of Inspection  !

Report j

106. No date TRT Feviewer Notes 2 107. No date TRT Reviewer Notes 4 (Cat. 2, AQW-10, AW-31)  !

l 108. No date NF-3000 Design 4 NR-3275-NF-3292.1 (Partial) 109. No date Cases of ASME Boiler and 1 Pressure Vessel Code (Page 729) 7 l  :

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.0ther_ Quality Control Personnel at the Comanche Peak Steam Electric Station AND 8409130167 50-445G 111. 9/27/84 Applicants' Prehearing 23 Proposed Findings of Fact Concerning Allegations of Harassment, Intiniidation 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 I

and Intimidation PDR AN0 8409070162 ADOCK 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 1 Boiler Inspection and Insurance Co. to Brown & Root Inc. Re: Minutes of ANI/QA Meeting of 1/9/80 8

. . . . ... u .

~

APPENDIX M Itontinued) l 121. 1/24/80 Letter from the' Hartford Steam -I Boiler Inspection and Insurar.ce.

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 I CSTP.MRS & WOC  !

123. 3/4/80 Brown & Root, Inc.

2 ltr to The Hartford Steam

-Boiler' Inspection & Ins. Co.

Re: Compliance of Weld i Examination Program 4

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 J 128. 2/5/81 Weld Data Card WDC 1 Serial rio. 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 l, 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'

ne: rum-on-os APPENDIX'M TContinued) 137. 6/17/82 Brown & Root Inspection Report 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 Pe: 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 j 1

144, 3/28/84 Weld Data Card WDC 1- I 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 l

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 J

151. No date Testimony of Alleger (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

. APPENDIX M (Continued)

  • 155. 1/24/83 USNRC Office of Investigations 8 Field Office Region IV- ,

Assistance to Inspection Report j

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 l

)

157. 5/8/78 Brown & Root 2 Weld Data Card Unit 1, System 4803, )

j Line 10-CT-1-009-301 1 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 I l Serial No. 00705 161. 2/5/79 Brown & Root 1 Quality Assurance Dept. ,

NDE Liquid Penetrant Report l 162. 2/5/79 Brown & Root .

1 Quality Assurance Dept.

Visual Examination Report 163. 2/26/79 Gibbs & Hill, Inc. 1 Speci fica tion - 2323-MS-100 Rev. 5 164. 3/8/79 Weld Addition / Removal Card 1 Serial No. 001355 4 165. 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

I APPENDIX M' l TContinued) 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 Conanche Peak Steam Electric 1 Station Design Change Authorization DCA No. 13,335

~12

APPENDIX M TContinued) 182. 5/21/82 TUS! Memo CPPA# 19,384 1 to J. C. Keller Re: Class I 1 Pipe Stress Analysis Weld i Shrinkage Brown & Root, Inc.

183. 5/25/82 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. P-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 l

190. 6/26/84 Brown & Root, Inc. 1 l Dwg. No. BRP-CT-1-SB-017 Rev. 20 1

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

. . . . . . . . . . . . , 1 i i

, ' 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, Containment Spray) 198. No date Comanche Peak Open Issue 3 Action Plan 199. No date Comanche Peak Nuclear. Power 2 Plant Allegations and/or 3

Investigations Summary (

200. No date Hand drawn $ ketch 3 ,

BRP-CT-1-SB-17 FW1 RT-4032 1

(

201. 4/27/84 NRC ltr to Division.of 5' 'i Engineering Architecture & l Technology Oklahoma State 1 Univ. Stillwater Oklahoma Sub:

Texas Utilities' Electric Company, et al. Comanche Peak Steam Electric HaRon(, Units.I and 2, Docket a 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 1

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 Authorization No. 1828 1

)

209. 7/13/78 CPSES/ Design Change -1  !

Authorization No. 2087 j 210. 12/4/79 Brown and Root Dwg. 2 FSE-00159 Sheet 8057 l

14

.,u. . v n u s s .,

, APPENDIX M (Continued) .;

211. 1/31/80 TUSI Dwg. 2323-El-0712-01'-S 1 Rev. 7 212. 4/20/81 TUSI Dwg. TNE-S2-0901 1 Sheet 1 (Cable Tray Support) 213. 11/12/81 Brown & Root Dwg. 1.

FSE-00159 Sheet 8013

. *214. 4/16/82 US Nuclear Regulatory 9 Commission Inspection Report.(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 No. 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 I40tes Re: Drawing 2 Review ,

)

220. 8/13/84 TUGC0 ltr. TXX-4259 to 5. 1 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. l' 225. No date ' Figure 1, Subsection NF 1 i Component Supports Design- .

Stress Intensities & Allowable.

Stresses'(KSI).

226. No date Comanche Peak Open Issue . 3 Action Plan ~ Task: Plug Welds 15

.w . i u m-os- a :, . R

, APPENDIX M (Continued) 227. No date Partial Statement of A11eger 1 i

?28. No date Comanche Peak Nuclear Power 2 Plant Allegations and/or

. Investigations Summary 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-SI-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-S1-0506 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 suioe 2 Distribution List (Division 1)-

Sub: .W ithdrawal of Six Division 1, Regulatory Guides 241. 8/19/81' , TUSl>Dwg.(ReactorContaknment 1

' Penetration & Details)  ;

ii i 242. 1/26/84' TRT Reviewer Notes 2' U. . s i ' c  ;

4

(:

16 .

APPENDIX M (Continued) 243. 5/31/84 Comanche Peak Allegation 1 Work Package " Mechanical &

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

Subject:

Welding of Cadweld- '

Sleeves to Main Steam Penetration Sleeves and Attaching Rebar to )

Sane 245. 8/6/84 Conversation Record 1

Subject:

Welding of Cadweld l Sleeves to Main Stean Penetra-tion Sheeve and Attaching l i

Rebar to Same.

246. No date Comanche Peak Open Issue 2 Action Plan Task: Improper Weld Design 24/ 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 Nuclear Power 1 I Plant Allegations and/or Investigations Summary 252. 1/2/73 U.S. Atomic Energy Commission 3 Regulatcry 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 Draft 4 255. 1/31/85 SSER AW-45, AW-46, AW-61/ AW-66 7 Draft 6 17

-'-7,/'

256, No date APPENDIX M o ...

Partial of TrontT61Ted) . .... - ~

  • 257. No da te Allegations AWList and Descript

-61 ion 258. No date Field Walkdown with 3 Response for AllAlleger of 259. No date Piping AreaAlleger n in Mecha iegations 1 cal /

  • 260. No date Allegation Summa 1 Inv ry Regarding thes Allestigative Finding
  • 261 5/20/83 Termina Intimidation bytion ega tion reat of of Th 1 Partia l 2 262 3/5/84 AW-45 Testimony of Alleger Brown &
  • 263 3/7/84 CP-CPM Partial Root 14.1 CPSES Rev. 2 Page ure 4 of Proced 2 4
  • 264 3/7/84 AW-61 Testimony of 1 Alleger Partial AW-46 265. No date Testimony ofeger All 2

\

\

Comanche Plant Inv Allegati Peak 266. No date estigations Summa Nuclear ons and Power

/or 1

  • 2 ry 67 11/5/82 Payment Receip 3 USNRC t (NRC)

SubjectReport of k68 1/31/85 Operations Q4-82-025 a Reporin Irregulari ties Coman:che Pe kAlle 1

t NumberRadiographic 2 SSER 269. No date and AQW-23AW-48, AQW-20 TRT Draft with, AQW-21, Re:

Reviewer Note Comments 270. No date Telephone Call 6 to R. Masterso n J. Zudans Record of with 271 10/6/77 AllegerTelephone Conv 1

Brown ersation Welder &

Root Quality Ass Docum I Surveillan eni.= tion urance Dept.

ce Checklist 13 18

-/' -7' ,/'

..u. svan-us-ss

. APPENDIX M-(Continued) 272. 1/4/78 Gibbs & Hill ltr. -41 GHF-2305 to TUSI Re: B&R Welding Procedure Specification j (w/ attachment) -

273. 9/29/82 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 A11eger 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 19-4

7- -- -----.

APPENDIX M (Continued) 288. 4/15/82 Component Modification Card 4 (CMC) Serial No. 57616 Rev. 2 289. 2/1/83 Brown & Root 30 Ouality Assurance Dept.  ;

Nonconformance Report (NCR) No. M-3425 Rev. 2 290. 3/1/84 Brown & Root Quality 10 Assurance Dept. j 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 f 294. No date Rewrite of Assessment 9 Only of Category 8 Mechanical /

j Piping Group -

295. No date TRT Reviewer Notes Item 4 2 l

296. No date Comanche Peak Nuclear Power 1 i Plant Allegations and/or I Investigations Summary

  • 297. 3/7/84 Interview of Alleger 1 i 298. No date NRC Staff Testimony on Welding 40 Fabrication 299. No date Summation of Weld Rod Control 8 300. 4/4/78 Arizona Public Service 1tr 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 Moistur': Resistant Low Hydrocan Electrodes 20

  • ' APPENDIX M-TContinued)-

-303, 2/24/82 Alloy Rods Division '4 ATOM ARC 7018-1 Moisture Resistant Low Hydrogen ,,

Electrodes  !

s 204. 4/16/82 U.S. Nuclear Regulatory Commission f 9 (

Region IV Investigation No. l 50-445/81-12; 50-446/81-12 j

305. 7/11/84 CPSES Design Change Authorization l' DCA No. 15,295, Rev. 1 i'

306. 8/2/84 Conversation Record

Subject:

1.

Weld Filler Metal Control j 307. 9/17/84 TRT Reviewer Notes 13 j

308. 1984 Structural Welding Code 8- .!

(American Welding Society) j!

309. No date A Study of Hydrogen Cracking 7  !

in Underwater Steel Welds ,

(Welding Research Supplement) '

310. No'date TRT Reviewer Notes 2 1 l

311. No date Comanche Peak Open Issue 2 Action Plan 312. No date Part C - Welding Rods, 2 i Electrodes and Filler Metals j Page 63 and 64 l

313. No date Report on Overexposed ) '

13 E7018 Electrode 314. No date Comanche Peak Nuclear Power 2 Plant Allegations 3 1

  • 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 Alleger '12 320.' 2/26/79 Gibbs & Hill 2 Specification 2323-MS-100 Rev. 5.(Partial) 21

. ~ . . . ~ , n u ., n

, APPENDIX M (Continued), i i

321, 9/28/79 Comanche Peak Electric 4'

Station Design Change Authorization 5503  !

Rev. 1 l

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 6.9D (Appendix D)

Welding & Related Processes 325. 7/10/81 Brown & Root Quality Assurance 4 Dept. NDE Report'

~

3 i

326. 1/19/81 Brown & Root 39 CP-CPM-6.9G Rev. 2 )

CP-CPM 6.9 (Appendix G)

Documentation for ASME Welding 1 Fabrication, and. Installation Activities- i I

327. 2/26/81 CPSES Design Change 2 )

' Authorization-DCA No.'9716 1 328. 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-6.9D 10 )

Rev. 2 Appendix D Welding l and Related Processes. 4 330. 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 l Pkg. No. CC-1-SB-038 7Q3 RP5 332. 7/26/83 . Attachment.1 . 4 '

Documentation Check List Pkg. No. H-CC-1-SB-038-010 Rev. 1 22

uv. rusn-ou-on APPENDIX M (Continued) 333. 1/12/84 Brown & Root 4  !

CP-CPM 6.90 Rev. 6 '

  • 334. 3/7/84 Partial Interview of Alleger 1 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 la 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 i 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 1tr to TUGC0 15 Re: Inspection Activities April 2-3 and April 13-23, 1979 (with Report) (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 I

i' 346. 5/31/83 NRC ltr to TUGC0 5 Re: Construction Appraisal Inspection January 24 -

February 4,1983 and February 14 - {

March 3, 1983 (83-18; 83-12) 23 l

1

. . . . ...,,u.,-o.

, APPENDIX M (Continued) 347. 7/11/83. NRC ltr.to TUGCO. .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 i InstallationInspection) ,l l

350. 6/11/84 Brown & Root CP-QAP-11.1 3 1 Rev. 5 (Fabrication and.

Installation Inspection'of Components, Component Supports, and Piping) 351. 7/23/84 NRC ltr to TUGC0 Re: 20 l Inspection Conducted Under the Resident Inspection -

Program March'20, 1984 through May-18, 1984 352. 7/26/84. NRC'1tr to TUGC0 16 Re: Inspection Activities I November 14, 1983 through March 31, 1984 353. 8/1/84 Brown & Root 12.

Procedure MCP-1, Rev. 4 354. 8/8/84 Brown & Root 9' )

Procedure CP-CPM 6.3 Rev. 11  !

i

-1 355, 9/25/84 Brown & Root 12 Procedure CP-CPM 8.1 Rev. 2 l

356, 2/1/85 Brown & Root 25  !

Procedure MCP-10 i Rev. 8 i

357. 3/6/85 Brown & Root 1~

Material Return to Warehouse No. W-19816 l 358. 3/7/85 Brown & Root, Inc. . 1 CPSES Material Requisition-a i

24 i

APPENDIX M (Continued) {

359. No date Sketch 2 l (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 i

367. 2/1/79 Traveler WE-79-035-5505 2 l

368. 2/19/79 Traveler WE-79-035-5505 3

{

l 369. 2/19/79 Traveler WE-79-036-5505 3 l 370. 2/19/79 l Traveler WE-79-037-5505 10 q

\

371. 2/27/79 Brown & Root ltr BRF-9181 3 to TUSI Re: Reactor Coolant Pipe l

372. 3/12/79 l Brown & Root ltr BRF-9207 2 l to TUSI Re: Reactor Coolant Pipe Field Measurements 1 373. 3/13/79 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 2 to TUSI Re: Reactor Coolant Pipe Field Measurements 376. 1/3/80 Brown & Root QI-QAP-11.1-26 1 l Rev. 0 (ASME Piping 8 Welding i Inspections) 377. 2/6/80 Brown & Root QI-QAP-11.1-26 2 Rev. i 25 l

APPENDIX M (Continued) , I 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 Rev. 2 4

380. 7/16/80 Brown & Root Quality Assurance 8 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 Ql-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 '

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 Rev. 3 388. 1/27/82 Brown & Root QI-QAP-11.1-31 13 Rev. 3 f 1

389. 3/12/82 Brown & Root QI-QAP-11.1-26 2 {

Rev. 7 390. 4/15/82 Brown & Root QI-QAP 11.1-26 4 l Rev. 8 391. 6/11/82 Texas Utilities Services, Inc. 3 CP-EP-4.0 Rev. 3 392. 12/16/82 Brown & Root QI-QAP 11.1-26 4 Rev 9 393. 2/2/83 Brown & Root QI-QAP 11.1-26 5  :

Rev. 10 l 394. 3/18/83 Brown & Root QI-QAP 11.1-26 5 Rev. 11 1 26

. APPENDIX M (Continued) 395. 9/12/83 Comanche Peak SES Reactor 1 Coolant Loop #1 (sketch) I 396. 5/14/84 Brown & Root CP-CPM-6.9E 3 Rev. 7 397. 6/11/84 Brcwn & 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 l

Check List Pkg. No.

ME-78-009-5505 400. 7/3/84 Attachment 1 Documentation 10 Check List Pkg. 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 Documentation 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 l Check List Pkg. No. l ME-78-008-5505 1 405. 7/3/84 Attachment 1 Documentation 15 Check List Pkg. No.  !

ME-78-020-5505 I i

406. 7/3/84 Attachment 1 Documentation 3 Check List Pkg. No.

3 ME-78-007-5505 l

407. 7/3/84 Attachment 1 Documentation 30 f Check List Pkg. No.

ME-78-015-5505 3

408. 7/3/84 Attachment 1 Documentation 15 j Check List Pkg. No. l ME-78-022-5505 1

-l I

\

i 27

APPENDIX M (Continued)' i i

409, 7/5'/84- Gibbs and Hill 6 -

Specification 2323-MS-100 -

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

WE-78-025-5505 415. 9/3/84 Attachment 1 Doucmentation I

.5 l Check List Pkg. No.

WE-78-016-5505 (

j 416. 9/3/84 Attachment 1 Documentation 10 Check List Pkg. No. 'j WE-78-024-5505 l 417. 9/3/84 Attachment 1 Documentation 14 Check List Pkg. No.

WE-78-029-5505 418. 9/3/84 't Attachment 1 Documentation 5 l Check List Pkg. No.

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

WE-78-019-5505~

i 420. 9/10/84 Brown & Root Dwg. 1 l BRP-RC-520-001 Rev. 10 Sheet 1 of 3 1 421.'No date Specification No. 10466-M204 14'-

Appendix 0 Compensation  ;

.. Allowances for Piping Misalignment- '

t I

28

.,u. . i vin us-n APPENDIX M

-(Continued) 422. No-date Sketches'(Comanche Peak) 10 l

Typical . Reactor Vessel Supports 423. No date N B-3000 - Design 4'  !

l 424. No date N B-4000 - Fabrication 2-and Installation Requirements 425. No date Attachment to TRT Report.- .2 .j Category'42 Field Weld 1 Repairs, RCS Unit #1  !

426. No date Hot Leg -Cold Leg -Crossover- 4 3 q

427. 7/12/84 Partial. Testimony of, Alleger 17 l

428.'7/12/84 Partial Testimony of A11eger 48 1

429. 8/1/84 Conversation Record 1 430. 5/1/73 U.S. Atomic Energy Commission 3 i Regulatory Guide Control of the 1 Use of Sensitized: Stainless  !

Stell j 431. 3/1/76 Gibbs & Hill 1 Specification 2323-MS-100-432. 5/10/79 NRC Inspection Report (79-06) 8

])

433. 5/23/80 Brown & Root 2 CP-CPM 6.9E Rev. 1 'l 434. 9/23/80 Brown & Root 3 CP-CPM 6.9D Rev. 1 435. 5/7/81 CPSES Flow Diagram 1-Containment Spray Sfstem 436. 6/8/81 Brown & Root Message 3 With Sketches 437. 6/12/81 Brown"& Root 1  ;

CP-CPM 6.9D Rev. 2- 1 438. 7/27/81 Weld Filler Material .

6- ,

Log Dwg. No. BRP-MS-1-TB-02 l 439. 8/21/81 Brown'& Root Message 2 i With Sketches e

.29

o.e . susn-us-up APPENDIX M (Continued) 440. 10/13/81 Brown & Root Message 2 With Sketches 441. 12/2/81 Brown & Root Messace 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 l Procedure Specifications 446. 3/30/83 Brown & Root Procedure 1 No. CP-CPM-6.9D Rev. 5 j

(

447. 4/28/83 Brown & Poot 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 date Article NC-2000 3 Materials 455, 2/3/83 Case ltr to NRC 9 l

j Re: Affidavit of Alleger  ;

j

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

l 30 1

4

. APPENDIX M (Continued)

  • 458.-5/23/83 NRC- As'si' stance 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 AN0 8310180214 ADOCK 50-4450 461. 11/28/83 Case 1tr to NRC 7-Sub: In the Matter of .

Application of Texas Utilities .I 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) PDRfANO 8403190002 A00CK 50-445G

  • 465. 5/20/84. Results of Inte.rview with Alleger 2 466. 9/19/84 Technical Interview of Alleger 28 i 467. 9/19/84 Notes Related to Alleger 11 Interview 468. No date- Results of Interview with A11eger 3.

31

APPENDIX M i (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 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 i'

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. 0 479. 5/15/81 Texas Utilities Generating 3 Company Procedure:

CP-QP-19.3, Rev. 0 (Surveillance of Piping Erection) 480. 7/24/81 Brown & Root Dwg. 2 MS-1-001-002-6725 Rev. 4 481. 11/17/81 Brown & Root Owg. 1 MS-1-001-006-C72K Rev. 1 32

ne: russ-co-ov.

' APPENDIX M

]

-(Continued) i l

482. 3/15/82 Gibbs & Hill. Specification 14 2323-MS-100 Rev 6 ]

l Section 7 l

483. 4/21/82 Brown & Root, Inc. I l Message to Weld Eng. 1 (Request for Temp.

l Data Cards) 484. 6/4/82 TUSI Instruction 4 CP-EI-4.0 Rev. 0 .

1' (Review of Pipe Support Required Prior to System Operation) 485. 6/5/82 Attachment 10 10 Documentation Pkg. No. 1 MS-1-R8-001 486. 6/15/82 Attachment 10 18 i Documentation. Check 1 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. 3 489. 2/4/83 TUSI Office Memorandum 2

Subject:

Comanche Peak Stean Electric' Station 490. 2/15/83 Notes & Sketch 2 i

491. 2/24/83 Computer Lising of Class 2 56 Summary of 10 Highest Stresses for Each Equation 4 492. 9/22/83' Brown & Root Dwg. 8 i Pkg. BRHL-FW-1-RB-004 Rev. 3 493. 10/20/83 Brown & Root Dwg. I Steam Generator Feedwater 33

'P.e:

F01A-85-59 ,

-APPENDIX M-(Continued)- i 494. 11/2/83

\

Brown-& Root Dwg. 1 i

MS-1-01-001-C72S '

Rev. 4  ;

495. 11/6/83 Brown 8. Root Dwg. 1 MS-1-01-001-C72S Rev. 5.

-l 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 i QI-QAP-11.1-28 Rev. 25 501.-6/11/84 Brown & Root 2 QI-QAP-11.1-26 Rev. 16 i

502. 7/10/84 Brown & Root Dwg. 1 BRP-MS-1-RB-002 Rev. 13 a

503. 7/30/84 Brown & Root Dwg. 8 j 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. I 'i Containment 2 J 508. No date Cat. 11'AP-13' 6 (Sketches and Notes)' i s

509. No date: TRT Reviewer Notes AP-13 14' 1

34  ;,

1 c

.,s. .v.,,-us-a3 APPENDIX M TContinued) 510. No da:e 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 5'13. No date Brown & Root Sketch 1 514. No date Sketch Coordinates 1 From Cont. Bldg.

I 1

s 35

p, ., . . . .

- .\

i CVERNMENT ACCOUNTADIUTY PROJEG l$$5 Conrdcticut Avenue. N.W.. Soire 202 Washingtc>n. D.C. 20036 i

(202)232-8550 i G:85:104 Janua ry 21, 1985 i

l FREEDOM OF INFORMATION ACT REQUEST FREEDOM OF INFORMATION ACI REQUESI D

Director ,

Office of Administration Nuclear Regulatory Commission J

kg,,4,g8/ g-g A -/59 Washington, D.C. 20555 To Whom It May Concern:

Pursuant to the Accountability Freedom Project (" GAP")ofrequests Information copiesAct of any("FOI and,A") 5 U.S.C. S 552, th information, including but not limited to notes all agency records and minutes, diaries,instructions ports, procedures, logs, calendars, tapes, transcripts, letters, memoranda, drafts,

, summaries, interview re-charts, maps, photographs, agree,mentsengineering analyses, drawings, files, graphs, i.

runoffs, any other data compilations, '

interim and/or ngs, computer orts, status re-ports, with the and overvany and all other records relevant to and/or generated i n connection by any person,iew, ragulation and investigation branch, or department of the NRC since January of the 18 Comanche P

, 1985

' This request includes all agencyc orecords .

er 8, 1980 as define whether they currently exist in the NRC official, " working " i other files, or at any other location, including private residencesnvestigativ covered by this request have been destroyed anual, supraand/orIf and any re records which have been or are destroyed m e to a list and/or of all removed

, to action (s) taken implement the action relevant (s). to, generated in connection with, a description of the

, and/or issued in order GAP requests that fees be waived, because " finding the inf sidered GAP as primarily benefitting the general public,"

is a non-profit ormation5can

. . . S 552 U be S con-C honest and open gove,rnment.non-partisan public interest organization concer(a)(4)(a).

ned with whistleblowers Clinic ~ as agents of government accountabilityThrough public outrea Through its Citizens seeking to ensure the health and safety of their communities, Clinic is currently assisting several citizens, local groups .

The Citizens intervenors in the Comanche Peak nuclear power plant.

central Texas area concerning the governinents and ,

construction of the

1

. ,\ s . . .. ,

/. J )~

Director. i Office of Administration- . I Page Two We 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 de.ny due to a specific FOIA exemption,  !

p ease provide, an index itemizing and describing the documents or portions of d cuments 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 I under Vaughn v. Rosen (I), .484 F.2d 820. (D.C. Cir.1973), cert. denied, 415 U.S. .

977 (1974). l We look forward to your response to this request within ten days.  !

1 Sincerely, iW 5 Billie Pirner Garde U Citizens Clinic Director 8

h

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