ML20209E565
| ML20209E565 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 09/04/1986 |
| From: | Grimsley D NRC OFFICE OF ADMINISTRATION (ADM) |
| To: | Garde B GOVERNMENT ACCOUNTABILITY PROJECT |
| Shared Package | |
| ML20209E569 | List: |
| References | |
| FOIA-86-272, FOIA-86-454 NUDOCS 8609110225 | |
| Download: ML20209E565 (6) | |
Text
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UNITED STATES
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i NUCLEAR REGULATORY COMMISSION t
y WASHINGTON, D. C. 20555
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SEP 4 1996 Ms. Billie Pirner Garde Government Accountability Project IN RESPONSE REFER 1555 Connecticut Avenue, NW, Suite 202 TO F01A-86-272 AND
- 3 Washington, DC 20036 F01A-86-454
Dear Ms. Garde:
This is the second partial response to your letters dated April 9, 1986, and June 16, 1986, in which you requested, pursuant to the Freedom of Information Act (FOIA), copies of records related to the evaluation of ISAP's regarding the Comanche Peak plant.
The records identified on the enclosed Appendix B are already available for public inspection and copying at the NRC Public Document Room (PDR). The PDR accession numbers are identified beside the record descriptions.
The records identified on the enclosed Appendix C are being placed in the PDR. You may obtain access to these records by referring to PDR folder 86-272 under your name.
The records identified on the enclosed Appendix D are being withheld 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. These' records contain predecisional information consisting of advice, opinions, and recommendations of the staff.
Release of these records would tend to inhibit the open and frank exchange of ideas essential to the deliberative process. There are no reasonably segregable factual portions because release of the facts would permit an indirect inquiry into the predecisional process of the agency.
Pursuant to 10 CFR 9.9 of the Commission's' regulations, it has been determined that the information withheld is exempt from production or disclosure, and that its production or disclosure is contrary to the pubMc interest. The persons responsible for denial of the information are the undersigned and Mr. Robert D.' Martin, Regional Administrator, Region IV.
8609110225 860904 PDR FOIA GARDE 86-272 PDR
..e Ms. Garde t This denial may be appealed to the NRC's Executive Director for Operations within 30 days from the receipt of this letter. As-provided in 10 CFR 9.11, 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."
We will communicate with you further with regard to additional records which are subject to your requests.
i Sincerely, 4v /!
d l-47,
/
Donnie H. Grimsley, Director Division of Rules and Records Office of Administration
Enclosures:
As stated E
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Appendix B FOIA 86-272 and 86-454
( second partial)
Documents in PDR Accession No.
5/23/86 Letter, W. G. Counsil CPSES, to Vincent S. Noonan, 8605280142 1
Comanche Peak Project, Response to NRC Questions Transmitted By Letter Dated May 15, 1986.
i w attachment, 5RC Comments / Responses (2 pages) 1-i 4/28/86 Letter, Vincent S. Noonan to W. G. Counsil, CPRT 8605020347 Results Reports dtd April 4, 1986.
w attachment, a
I' Request for Additional Information (6 pages) 1 i
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F01A-86-272 and F01A-86-454 4
(Second Partial)-
APPENDIX C Released Records FOIA 86-454 1.
Undated Question / Response on VII.b.2 Valve Disassembly (10 pages) s 2.
7/22/83 Documentation Review, Table 1, Specification Revision / Addendum Report (6 pages) s e
3.
3/20/85 Interoffice Memo, Brown & Root, G. R. Purdy to Distribution, CPSES, 35-1195, Reinspection Program Implementation (2'pages)
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4.
4/8/85 Office Memorandum, Evaluation Research Corporation, Valve Disassembly Issue VII.b.2 Generic Valve Evaluation (4 pages) 5.
5/2/85 Office Memorandum, ERC, Valve Disassembly, Issue VII.b.2 Additional Generic Valve Evaluation (3 pages) 6.
5/20/85 Office Memorandum, ERC, Valve Disassembly, Issue VII.b.2, Generic Safety Consequences Analysis
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(7 pages) 2 a
l 7.
5/23/85 Table 4. Generic Safety Consequences Analysis 4
l (4 pages) i 4
i
o APPENDIX C F01A-86-272 AND 86-454 age 2 Released Records I
I 8.
6/19/85.
ERC Memo, Valve Disassembly', Issue VII b.2, Dis / Reassembly Procedural Control (2 pages) 9.
7/22/85 Texas Utilities Generating Company Office Memo, to Distribution, Unit 2 ASME Startup Activities I
(1 page) 10, 8/14/85 Valve Reinspection Checklist, Issue VII.b.2, Item No. 464 (8 pages) 11.
10/2/85 ERC Memo, Review of Procedures Pertinent to Valve Disassembly (1 page) 12.
11/25/85 Generic Safety Consequences Analysis, Item No.
VII.b.2, Revision 1 (6 pages)
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t 13.
3/13/86 ERCI letter w telecon, Obert to Milliken (2 pages) 14, 3/20/86
- a. Comanche Peak Response Team Results Report, ISAP VII.b.2, Valve Disassembly, Rev 1, w/ attachment: b. Action Plan (30 pages) i
F01A-86-272 and 86-454 (Second Partial Response)
Appendix D Records Denied in Entirety - Exemption (5) 1.
4/24/86 Memorandum from L. E. Ellershaw to T. F. Westerman, Review of Results Reports VIIb.2 and II.b (2 pages) 2.
5/12/86 Memorandum from L. E. Ellershaw to T. F. Westerman, Review of Results Reports VIIb.2 and II.b (2 pages) 3.
5/13/86 Memorandum from E. H. Johnson to V. S. Noonan, Staff Questions Regarding ISAP No. VII.b.2 Results Reports (1 page) 4.
5/16/86 Memo from Johnson to Noonan, re:
Evaluation Report (1 page) w/ attachment a.
Evaluation Report (ISAP III.d) (4 pages)