ML20126E146
| ML20126E146 | |
| Person / Time | |
|---|---|
| Issue date: | 04/04/1985 |
| From: | Felton J NRC OFFICE OF ADMINISTRATION (ADM) |
| To: | Flora J FLORA, J.W. |
| Shared Package | |
| ML20126E150 | List: |
| References | |
| FOIA-84-907 NUDOCS 8506150306 | |
| Download: ML20126E146 (4) | |
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o o NUCLEAR REGULATORY COMMISSION UNITED STATES .
2 E WASHING TON, D. C. 20555
\...../ 0N APR o 41985 Mr. John W. Flora 3076 South High Street IN RESPONSE REFER Denver, CO 80210 TO F01A-84-907
Dear Mr. Flora:
This is in further response to your letter dated December 3,1984, in which you requested, pursuant to the Freedom of Information Act (F0IA), documents which relate to the mode of failure of RCP seals, the probable causes of failures of the seals, and possible remedies for failure of the seals.
The document identified or, enclosed Appendix C is being placed in the NRC Public Document Room (PDR) located at 1717 H Street, NW, Washington, DC 20555, in file folder F01A-84-907 in your name.
The three documents identified on enclosed Appendix D are subject to your request. Pursuant to Exemption 4 of the F0IA (5 U.S.C. 552(b)(4)) and 10 CFR 9.5 (a)(4) of the Connission's regulations, the three documents are being withheld in their entirety. Document 1 contains infonnation received in confidence from foreign sources. Under these conditions, the document is protected from mandatory public disclosure under the alternative test set out in National Parks and Conservation Association v. Morton, 498 F.2d 765 (D.C.Cir. 1974). Under that test, a record can be withheld because disclosure would impair the Government's ability to obtain necessary information in the future. It is our view that a breach of understanding between the NRC and a foreign source could in the future inhibit the free flow of information to the NRC and could interfere with our mission.
The portions of document 2 that are relevant to your request, and document 3 contain information which the Westinghouse Electric Corporation considers confidential business (proprietary) information. We are consulting with Westinghcuse to review that firm's proprietary claim, and we will let you know as soon as possible if the documents, or any portion thereof, may be disclosed to the public.
Pursuant to 10 CFR 9.9 of the NRC'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 public interest. The persons responsible for the denial of document 1 are the undersigned and James R.
Shea, Director, Office of International Programs. The persons responsible for the denial of document 2 are the undersigned and Harold R. Denton, Director, Office of Nuclear Reactor Regulation. The person responsible for the denial of document 3 is the undersigned.
8506150306 850404 PDR FDIA FLORAS 4-907 PDR l
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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 Comission, Washington, DC 20555, and should clearly state on the envelope and in the letter that it is an " Appeal from an Initial FOIA Decision."
Please accept our apologies for the delay in our response to your request.
Sir rely, J. M. Felton, Director Division of Rules and Records Office of Administration
Enclosures:
As stated
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f Re: FOIA-84-907 f
APPENDIX C
- 1. 10/29/84 Letter from Armand Onesto, Rockwell International, to Gerry"Weidenhamer re: Westinghouse Reactor Coolant Pump (RCP) Seal Leakage Analysis.
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Re: FOIA-84-907 APPENDIX D
- 1. 6/6/83 Memo from R. W. Houston to Roger J. Mattson re: Station Blackout - French, British, German and American Approaches.
- 2. Response to Question I re: Reactor Coolant Pump Seals, attachment to 1/10/84 letter from W. G. Counsil to B. J. Youngblood. (Note: The 1/10/84 cover letter is already available in the Public Document Room,
- Acc. #8401130364.- Only Question 1 is relevant to j this request.)
- 3. 12/84 Draft NUREG/CR-4077 Reactor Coolant Pump Shaft Seal Behavior
! During Station Blackout.
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