ML20132E820

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Response to FOIA Request for Documents Used for NUREG-0999. App a Documents in Pdr.App B Documents Encl.App C & D Documents Copyrighted.App E Documents Withheld (Ref FOIA Exemption 4)
ML20132E820
Person / Time
Issue date: 06/06/1985
From: Felton J
NRC OFFICE OF ADMINISTRATION (ADM)
To: Sholly S
UNION OF CONCERNED SCIENTISTS
Shared Package
ML20132A685 List:
References
FOIA-83-619, RTR-NUREG-0999, RTR-NUREG-999 NUDOCS 8507180162
Download: ML20132E820 (9)
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NUCLEAR REGULATORY COMMISSION WASHINCTON, D. C. 20555 yh

%.,,.+ M 06 M Mr. Steven C. Sholly Technical Research Associate IN RESPONSE REFER Union of Concerned Scientists TO F01A-83-619 1346 Connecticut Avenue, NW Suite 1101 Washington, DC 20036

Dear Mr. Sholly:

This is in response to your letter dated October 20, 1983, in which you requested, pursuant to the Freedom of Information Act, documents concerning NUREG-0999, "Sizewell B--Analysis of British Application of U.S. PWR Technology."

The NRC has already made the five documents identified on the enclosed Appendix A available for public inspection and copying at the NRC Public Document Room (PDR), 1717 H Street, NW, Washington, DC.

The 26 documents listed on the enclosed Appendix B are being placed in the NRC PDR. You may,obtain access by presenting a copy of this letter or by requesting folder F01A-83-619 in your name.

The two documents listed on the enclosed Appendix C are copyrighted documents. In order to obtain copies of these documents, you may wish to communicate with the organizations listed on the appendix.

The three documents listed on the enclosed Appendix 0 are Crown copyrighted documents. In order to obtain copies of these documents, you may wish to communicate with the UKAEA Liaison Office, British Embassy, 3100 Massachusetts Avenue, NW, Washington, DC 20008.

The three documents listed on the enclosed Appen' dix E are being withheld in their entirety pursuant to Exemption (4) of the F0IA (5 U.S.C.

552(b)(4)) and 10 CFR 9.5(a)(4). These documents were submitted by and received in confidence from a foreign source. Under these conditions the documents are 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.

h$071$8jja050606 SHOLLYD3-619 pga

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Mr. Steven C. Sholly 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 public interest. The persons responsible for this denial are the undersigned and James R. Shea, Director, Office of International Programs.

This denial may be appealed to the Commission'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."

This completes NRC's action on your request.

Sinc ely, r

M J. . Felton, Director Division of Rules and Records Office of Administration

Enclosures:

As stated

e FOIA-83-619 APPENDIX A

1. Undated SNUPPS Final Safety Analysis Report Accession No. 7910120219
2. 3/79 Report: NUREG-0536, " Evaluation of Simulated - LOCA Tests that Produce Large Fuel Cladding Ballooning" Accession No. 7904270046
3. 11/16/79 Letter to D. G. Eisenhut f' rom T. M. Anderson Accession No. 7912040356
4. 4/80 Report: NUREG-0630, " Cladding Swelling and Rupture Models for LOCA Analysis" Accession No. 8005120229
5. 8/31/81 Letter to H. R. Denton from N. A. Petrick, "CPB Reactor Fuels Reviews" Accession No. 8109080028

l F0!A-83-619 i APPENDIX B

1. 7/13/77 Memo to P. S. Check from D. Ross,

Subject:

Meetings with UKAEA and UKNII Regarding Fuel Clad Ballooning with enclosures (12 pages)

2. 9/77 UKAEA Report ND-R-6(S), E. D. Hindle, "Zircaloy Fuel Clad Ballooning Tests at 900-1070K in Steam" (30 pages)
3. 3/31/78 Memo to File from M. L. Picklesheimer,

Subject:

Minutes of Workshop on Simulation of Nuclear Fuel Rods in LOCA, National Bureau of bandards, Gaithersburg, MD with enclosures (9pages) 4, 8/7/78 Memo to K. Kniel from D. A. Powers,

Subject:

Foreign Travel Trip Report w/ enclosures (23 pages)

5. 9/15/78 Letter to Delegates from J. Rixon (UKN!!) " Notes of a Meeting on Axially Extended Fuel Clad Ballooning Held at the UKAEA Springfields Nuclear Laboratories on 30th June 1978" w/ attachments (187 pages)
6. 4/79 " Safety Assessment Principles for Nuclear Power Reactors" HMNuclearInstallationsInspectorate(49pages)
7. 12/1/81 Letter to E. P. Rahe from J. R. Miller, " Acceptance for Referencing of the 1981 Version of the Westinghouse large Break ECCS Evaluation Model (32 pages)
8. 3/82 Design Safety Criteria for CEGB Nuclear Power Stations, Central Electricity Generating Board, Report HS/R167/81 (26pages)
9. 4/82 Central Electricity Generating Board's Statement of Case (563pages) 10, 4/82 Pressurised Water Reactor Design Safety Guidelines, Central Electricity Generating Board, DSG2 (155 pages)
11. 6/82 Report by A. T. Donaldson et al., " Pre-Test Prediction and Post-Test Analysis of PWR Fuel Rod Ballooning in the MT-3 In-Pile LOCA Simulation Experiment in the NRU Reactor,"CEGBReportTPRD/B/0101/N82,WR/F8WG/P(82)68 (34pages)

F01A-83-619 i APPENDIX B (Continued)

12. 7/82 An Assessment of the Radiological Consequences of Releases from Degraded Core Accidents for the Sizewell PWR, National Radiological Protection Board, NRPB-R 137 (133pages)
13. 7/2/82 Sizewell B, A review by HM Nuclear Installations Inspectorate of the Pre-Construction Safety Report with 8 supplements (262 pages)
14. 9/13-17/ IAEA-CN-42/126, International Conference on Nuclear Power 1982 Experience, " Current CEGB Safety Policy and Criteria," R.

R.Matthews(15pages)

15. 10/82 Degraded Core Accidents for the Sizewell PWR: A Sensitivity Analysis of the Radiological Consequences, National Radiological Protection Board, NRPB-R142 (133 Pages)
16. 10/29/82 Memo to J. Huang, et al., from T. P. Spets,

Subject:

DSI ReviewersofSizewell"B"(34pages)

17. 11/82 A Review by HM Nuclear Installations Inspectorate Supplement 1 Degraded Core Analysis (21 pages)
18. 11/24/82 Memo to T. M. Novak from L. S. Rubenstein,

Subject:

Design Comparison between SNUPPS ard Sizewell "B" Nuclear Plants w/ enclosure (22 pages)

19. 1/21/83 Memo to B. J. Youngblood from G. E. Edison, " Summary of Meeting with Westinghouse on Reactor Coolant Pump Seal Performance (generic)"(73pages) i
20. 2/8/83 Memo to B. J. Youngblood from F. J. Congel,

Subject:

Review of Draft 2 of Sizewell B Evaluation Report (1 page)

21. 2/23/83 Letter to R. Anthony From H. R. Denton,

Subject:

NRC SizewellEvaluationReport(1page)

22. 2/23/83 Letter to R. Matthews from H. R. Denton,

Subject:

NRC SizewellEvaluationReport(1page)

23. 5/27/83 Letter to R. Anthony from H. R. Denton,

Subject:

Transmittal of NRC Report on Sizewell "B" Evaluation (1page)

F0!A-83-619 APPENDIX B (Continued)

24. 5/27/83 Letter to R. R. Matthews from H. R. Denton,

Subject:

Transmittal of NRC Report on Sizewell "B" Evaluation

(1page)
25. 7/83 NII 01 (Supp. 12) Sizewell 8 - A Review by HM Nuclear Installations Inspectorate, Supplement 12, ALARP Strategy for Dose Reduction (45 pages)
26. 1/84 Causes of Larger Degraded Core Frequencies in Earlier Safety Studies Compared with Sizewell B by A. A. Debenham  ;

and P. G. Bonell, Safety and Reliability Directorate, l' SRD R 281, final version (23 pages) i i

F01A-83-619 i

i APPENDIX C

1. Undated EPRI-NP-2301, Loss of Offsite Power At Nuclear Power Plants: Data and Analysis -- A copy of this re can be requested from Research Reports Center RRC), (port Box 50490, Palo Alto, CA 94303
2. 5/8-10/78 Copyrighted Paper XII.3: by M. Llory and B. Gachot, "Probabilistic Analysis of Systems Related to PWR Safety-Synthesis of E.D.F. Studies," in Proceedings of the ENS /ANS Topical Meeting on Probabilistic Analysis of Nuclear Reactor Safety at Los Angeles California -- A copy of this report can be requested from ANS Publica-tions, 555 North Kensington Avenue, LaGrange Park, IL 63525

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F01A-83-619 i

APPENDIX D

1. 3/82 Report by W. Marshall "An Assessment of the Integrity of PWR Pressure Vessels," UKAEA (1,070 pages)
2. 4/82 Sizewell B PWR Pre-Construction Safety Report, CEGB 10
3. 9/3/82 Sizewell B Probabilistic Safety Study, WCAP-9991, Rev. 1

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! APPENDIX E f

1. 9/78 UKAEA Report by E. D. Hindle " Mechanisms of Interaction ;

of Zircaloy Cladding in Multi-Rod Array LOCA Swelling 7 Experiments,"ND-M-482(S)(26pages)  ;

2. 1/28/83 Letter to H. Denton from R. R. Matthews, "NRC Draft  :

Report - Sizewell B Analysis of British Application of U.S. PWR Technology" w/ attachment (13 pages) ,

! 3. 9/19/83 Causes of Larger Degraded Core Frequencies in Earlier l Safety Studies Compared with Sizewell B by A. A. t Debenham&P.G.Bonell,Draftversion,SRD/R281(54 l Pages) T l r l

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