ML20127F101

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Further Response to FOIA Request for Five Categories of Documents Re Severe Accident Studies,Including NUREG/CR-3025,NUREG/CR-3440,issue Papers & Ltr Repts. Forwards App C Documents.App B Documents in PDR
ML20127F101
Person / Time
Issue date: 03/14/1985
From: Felton J
NRC OFFICE OF ADMINISTRATION (ADM)
To: Sholly S
UNION OF CONCERNED SCIENTISTS
Shared Package
ML20127C753 List:
References
FOIA-84-928, RTR-NUREG-CR-3025, RTR-NUREG-CR-3440 NUDOCS 8506250029
Download: ML20127F101 (7)
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%, UNITED STATES (DV oI v o o NUCLEAR REGULATORY COMMISSION 3 ;j WASHINGTON, D. C. 20555

%...../ eau am Mr. Steven C. Sholly Technical Research Associate Union of Concerned Scientists 1346 Connecticut Avenue, NW IN RESPONSE REFER Suite 1101 TO F0IA-84-928 Washington, DC 20036 P

Dear Mr. Sholly:

This is in further response to your letter of December 17, 1984, in which ,

you requested, pursuant to the Freedom of Information Act (F0IA), documents in five categories relating to severe accident studies. j The record identified on the enclosed Appendix B is subject to your request and has already been made available in the NRC Public Document Room (PDR).

The records identifjed on the enclosed Appendix C are now available for public inspection arid copying in the PDR in folder F01A-84-928.

The staff is continuing to search for additional records subject to your request. We will notify you upon completion of this search. ,

Sin erely, _

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

Enclosures:

As stated l

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APPENDIX B RECORDS SUBJECT TO F01A-84-928 ALREADY IN THE PDR Category 2

1. 09/84 NUREG/CR-3440, " Identification of Severe Accident Uncertainties" by J. B. Rivard, et al., Sandia National Laboratories, Albuquerque, NM. ' Friiduced under NRC FIN Nos. A-1228, A-1246, A-1258, A-1322, A-1339, and A-1342 (Acc. No. 8501030262 PDR/NUREG/CR-3440R) (307 pages).

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APPENDIX C RECORDS'IN PDR' FILE FOIA-84-928 Category 3 1, Issue Number 1.1.1 " Reactor Coolant System Themal and Hydraulic Behavior"(02/16/84)(8pages).

2. Issue Number 1.1.2 "Eate and Magnitude of Hydrogen Production in the Vessel and Release from the Reactor Coolant System" (02/16/84) (7 pages).
3. Issue Number 1.1.3/1.1.4 " Core Debris Interaction with Lower Plenum Structures, Reactor Vessel' Penetrations" (02/16/84)

(5 pages).

4 Issue Number 1.1.5 "In-Vessel Steam Explosions" (01/22/84) (17 pages).

5. Issue Number 1.1.6 " Recovery Potential Prior to Vessel Failure" (01/27/84) (12 pages).

6 Issue Number 1.1.7 " Primary System Failure from Overpressure" (01/30/84) (12 pages).

7 Issue Number 1.2.1 " Containment Themal and Hydraulic Behavior" (11/09/84)(7pages).

8 Issue Number 1.2.2 " Rate and Magnitude and Combustible Gas Production Ex-vessel" (04/02/84) (7 pages).

9. Issue Number 1.2.3 " Distribution of Combustible Gases, the Likelihood and Consequences of Flame Acceleration and Detonations" (01/27/84) (10 pages).

10 Issue Number 1.2.4 " Conditions Leading to and Resulting from Deflagration and Diffusion Flames" (04/02/84) (9 pages).

11 Issue Number 1.2.5 " Likelihood and Magnitude of Ex-vessel Steam Explosions

orSteamSpikes"(11/09/84)(8pages).

i 12. Issue Number 1.2.5 " Likelihood and Magnitude of Ex-vessel Steam Explosions orSteamSpikes"(09/28/83)(8pages).

13. Issue Number 1.2.6 " Debris Coolability in Ex-Vessel Locations" (02/16/84) j (8pages).

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14. Issue Number 1.2.7 " Debris Relocation Following Vessel Failure" (02/16/84) (6 pages).
15. Issue Number 1.2.8 " Fuel Debris-Containment Shell, Floor and Internal Structure Interactions" (02/16/84)

(7 pages).

16 Issue Number 1.2.9 " Rate and Magnitude of Noncondensible Gas Production Ex-Vessel" (01/30/84) (12 pages).

17. Issue Number 1.3.1 " Characteristics and Likelihood of Containment Leakage from Shock Loads" (undated) (3 pages).
18. Issue Number 1.3.2 " Characteristics and Likelihood of Containment Leakage Resulting from Steam Spikes and/or Hydrogen Burning" (undated) (6 pages).

19 Issue Number 1.3.3 " Characteristics and Likelihood of Containment Leakage Resulting from Slow Pressurization" (undated) (5 pages).

20. Issue Number 1.3.4 " Characteristics and Likelihood of Leakage Resulting from External Events" (undated) (4 pages).

21 Issue Number 1.3.5 " Characteristics and Likelihood of Containment Leakage Resulting from Thermal Loadina" (undated) (3 pages).

22 Issue Number 1.3.6 " Characteristics and Likelihood of Leakage Resulting from Internal Missiles" (undated)

(3 pages).

,, 23 Issue Number 1.3.7 " Potential for Basemat Penetrations" (undated)

(4 pages).

24 Issue Number 1.3.8 " Reliability of Early Containment Isolation" (undated) (4 pages).

25 Issue Number 1.3.9 " Equipment and Instrumentation Survivability"

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(undated) (4 pages),

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26. Issue Number 1.4.1 " Rate and Magnitude of Release of Fission Products From Fuel (In-Vessel)" (undated) (13 pages).
27. Issue Number 1.4.2 " Retention of Fission Products During In-Vessel Transport" (undated) (7 pages).

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28. Issue Number 1.4.3 " Rate and Magnitude of Release of Radionuclides

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from Fuel (Ex-Vessel) (undated) (8 pages).

29, Issue Number 1.4.4 " Deposition of Fission Products in Containment Due to Natural Processes" (undated) (8 pages).

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Re:- FOIA-84-928 30 Issue Number 1.4.5 "Effect of Engineered Safety Features on Fission Product Retention" (undated) (6 pages).

31. Issue Number 1.4.6 " Deposition of Fission Products in Other Plant Structures" (undated) (7 pages).
32. Issue Number 1.5.2 " Food Chain Transport" (09/29/83) (1 page).
33. Issue Number 1.5.2 " Food Chain Transport" (09/20/83) (3 pages).

34 Issue Number 1.5.3 " Dosimetry and Health Effects" (09/20/83) (2 pages).

35. Issue Number 1.5.3 " Dosimetry and Health Effects" (09/29/83) (2 pages).
36. Issue Number 1.5.4 "Modeling)of (09/29/83 (2 pages). (Offsite) Emergency Response"
37. Issue Number 2.1.1 " Plant Categorization" (undated) (7 pages).
38. Issue Number 2.1.2 " Identification of Accident Sequences" (10/04/83) (3 pages).
39. Issue Number 2.1.2 " Identification of Accident Sequences" (11/15/83) (4 pages).
40. Issue Number 2.1.3 "Quantification of Sequence Likelihood" (undated) (6 pages).
41. Issue Number 2.1.4 " Equipment Performance and Success Criteria" (10/04/83)(5pages).

42 Issue Number 2.1.4 " Equipment Performance and Success Criteria" (11/15/83) (3 pages).

43. Issue Number 2.1.5 " Influence of Operator Action on Accident Sequence" i

(undated) (4 pages).

l 1 44. Issue Number 2.2.1 " Response of Reference Plants to Selected Severe j Accidents" (10/04/83) (4 pages).

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45. Issue Number 2.2.1 " Response of Reference Plants to Selected Severe Accidents" (11/16/83) (7 pages).
46. Issue Number 2.2.2 " Qualitative Assessment of Severe Accident Likelihood (Insights)" (undated) (4 pages).

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47. Issue Number 2.2.3 " Integrated Probabilistic Risk Assessment for Reference Plants" (undated) (7 pages).
48. Issue Number 2.2.7 " Effects of Uncertainties on Estimates of Severe Accident Likelihood" (undated) (5 pages).

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49. Issue Number 2.3.1 " Design and Operation Changes to Prevent Severe Accidents Including Sabotage Protection" (undated)

(3pages). .

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50. Issue Number 2.3.2 " Improvement in Severe Accident Management Capability" (undated) (5 pages).
51. Issue Number 2.3.4 " Changes in Emergency Response Capability" (10/04/83) (6 pages).

52 Issue Number 3.1.1 " Selection of Decision Techniques" (undated)

(3 pages).

53. Issue Number 3.1.2/3.1.3 "Use of Cost-Benefit Analysis" (10/04/83)

(2pages).

54 Issue Number 3.1.2 " Selection of Attributes to be Used in Cost-BenefitAnalysts"(10/04/83)(4pages).

55 Issue Number 3.1.3 " Selection of Weights for Cost-Benefit Analysis" (10/04/83) (3 pages).

56. Issue Number 3.1.4 " Role of Safety Goals" (09/30/83) (4 pages).
57. Issue Number 3.1.5 " Balance of Approaches to Answering the Regulatory Questions" (undated) (4 pages).

58 Issue Number 3.1.6 " Balance of Preventive and Mitigative Measures" (10/04/83) (2 pages) with attached note to James C. Malaro, RES, from Mort Fleishman, RES, dated 09/26/83 regarding Design Basis Accident considerations-for the- Clinch River Breeder Reactor (1page).

59. 01/20/84 Note to Harold Denton, NRR, et al., from Miller B. Spangler, i NRR, entitled " Handout MaterTil FRelating to Severe Accident Program and Final Policy Statement" (112 page.s).

60 01/30/84 Note to Harold Denton, NRR, et al., from Miller B. Spangler, NRR, entitled " Handout MaterTal FRelating to Severe Accident

! Program and Final Policy Statement, ACRS Subcommittee Meeting" i

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i 61 01/11/85 Memorandum for Denwood F. Ross, RES, from Themis P. Spets, NRR, entitled " Severe Accident Issue Papers 1.2.1 and 1.2.5" (1page).

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i i 62. 04/17/84 Containment Systems Research Branch Weekly Report (1 page).

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63. 04-05/84 Technical Highlights / Administrative Report for the NRC Reactor Safety Research Program (A-1016, A-1030, A-1181, A-1218, A-1227, A-1246, A-1247, A-1263, A-1264, A-1335, A-1340, A-1342, A-1383), Sandia National Laboratories, Albuquerque, NM.(60 pages).
64. 06-07/84 Technical Highlights / Administrative Report for the NRC Reactor Safety Research Program (A-1016. A-1030, A-1181, A-1218, A-1227, A-1246, A-1247, A-1263, A-1264, A-1335, A-1340, A-1342, A-1383), Sandia National Laboratories, Albuquerque, NM (62 pages).
65. 08/20/84 Letter to Robert Minogue, RES, from Jack V. Walker, Sandia National Laboratories, enclosing April-May,1984 Bi-Monthly Report of SNL-managed work of the Reactor Safety Research Department (2 pages).
66. 10/30/84 Containment Systems Research Branch Weekly Report (1 page).
67. undated Containment Systems Research Branch Weekly Report (1 page).
68. undated Containment Systems Research Branch Weekly Report (1 page).
69. undated Report entitled " Behavior of Core Debris Ejected From a Pressurized Vessel into Scaled Reactor Cavities" by William W. Tarbell, Martin Pilch, and John E. Brockmann, Sandia National Laboratories, Albuquerque, NM (18 pages).

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