ML20237D127

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Final Response to FOIA Request for Documents.App a Documents Re Assessment of Accident Risks in Us Commercial Nuclear Power Plants & Severe Core Damage Accidents Already Available in PDR
ML20237D127
Person / Time
Issue date: 12/18/1987
From: Grimsley D
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
To: Martin T
GRATERFORD INMATES
References
FOIA-87-763 NUDOCS 8712230061
Download: ML20237D127 (3)
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S. NUCLEAR REoVLAToRY COMMISSloN Nac soi4 enutsi N.vue s gf. e.eq?e, F01A-87-763 i f I RESPONSE TO EbO OF f'

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// INFORMATION ACT (FOlA) REQUEST

DEC 181987 I"*

DOCKt1 NvustR.ss orenm ese a43stst'ER Mr. Thomas Martin PART t.-RECORDS RELEASED OR NOT LOCATED (See checked bones)

No agency records subrect to the request have been located No additional egency records subsect to the request have been located Agency records subsect to the request that are identif ed in Appendia A a,e ai,eady avasiabie for pumic inspect,on and copying e im NRC Public Document Room, y 1717 H Street, N W., Washington, DC Agency records subsect to the request that are identified in Appendts are being made available for public inspection and copving in the NRC Public Document Room,1717 H Street. N W., Washington, DC, in a folder under this FotA number and requester name.

The nonpropnetary version of the proposalts) that you agreed to accept in a teiephone conversation with a member of my staff a now being maoe avadable for pubhc inspe and coying at the NRC Publec Document Room.1717 H Street. % W WasNngton. DC , in a folder under this FOIA number anc sequester c'me y Enclosed e information on how you may obtam access to and the chaqpes for copying records placed in the NRC Public Documem Room.1717 H S**eet. N W., Washing Agency records subsect to the request are enclosed Any apphcat)ev chrge for copies of the records provided and payment procedur es are noted e the comments section.

Records subsect to the request have been referred to another Feoeral agencybes; for review and derect response to you In view of NRC's response to this request, no further action es being tm.en on appeal letter dated PART 11 A-INFORMATION WITHHELD FROM PUBLIC OISCLOSURE Certain information in the requested records sa beiry withheld from pubs < deciosu r e pursuant to the FOIA enemptions descnbod e and for the reasons stated in Part ti. sec-tions B, C. and D Any re6 eased portions of *he documents for w5ch only part of the record is being withheid are being made e.adable for publee inspection and co the NRC Public Document Room,1717 H Street. N W, Washington. OC. en a folder under this FOIA number and requester na e Canis Note:

Appendix A is a partial listing of significant records responsive to your request for which the fees exceed the $35.00 limit stated in your request.

Instructions are enclosed to assist you in obtaining copies of those records for which you are interested. Should you have further interest in this subject area following your review of the listed records, you may submit another FOIA request.

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Re: FOIA 87-763 A

APPENDIX RECORDS MAINTAINED AMONG DDR FILES

~ NUMBER DATE DESCR'PTION q

1. 10/31/75 WASH-1400 - Reactor Safety Study: Assessment of Accident Risks in U.S. Commercial Muclear Power Plants, Acc. No- .

8202220493

2. 11/30/81 NUREG/CR-1659 - Reactor Safety Study Methodology Applications Program: Grand Gulf No.18WR Power Plant Acc. No. 8201060015 I
3. 6/30/82 NUREG/CR-2497 - Precursors to Potential. Severe Core "

Damage Accidents 1969-197., Acc. No. 8207220676

4. 8/31/82 NUREG/CR-2802 - Interim Reliability Evaluation Program:

Analysis of the Browns Ferry, Unit 1, Nuclear Plant, Acc. No. 8209270137

.5. 12/31/82 NUREG/CR-2239 '- Technical Guidance for Siting Criteria Development, Acc. No. 830112 3023 6, 2/28/83 NUREG/CR-2800 - Guidelines for Nuclear Power Plant Safety Issue Prioritization Development, Acc. 'No. 8303150680

7. 4/30/83 NUREG/CR-3085 - Interim Reliability Evaluation Program: 4 Analysis of the Millstone Point Unit 1 Nuclear Power Plant, Acc. No. 8305310226 8, 12/31/83 NUREG-0933 ' A Prioritizaticn of Generic Safety . Issues, .

Acc. No. 8401230657

9. 8/31/84 NUREG-1068 - Review Insights on the Probabilistic Risk Assessments for The Limerick Generating Station, Acc. No. 8408290158
10. 9/84 NUREG/CR-3988 - MARCH 2 (Meltdown Accident Response Characteristics) Code Description and User's Manual, Acc. No. 8410170214
11. 4/85 ORNL/TM-8842, Review of the Status of Validation of the .

Computer Codes Used in the Severe Accident Source Term l Reassessment Study-(BMI-2104), Acc. No. 8508090668

12. 5/85 NUREG/CR-4085 - User's Maroal for CONTAIN 1.0, A Computer Codo for Severe Nuclear Reactor Accident Containment Analysis, Acc. No. 8508090656 l 13, 5/31/85 NUREG-1032 - Evaluation of Station Blackout Accidents at Nuclear Power Plants, Acc. No. 8506250217

1 Re: F0IA.87-763 4 APPENDIX A REC: CS MAINTAINED AMONG POR FILES i l

l NUMBER DATE DESCRIPTION

14. 7/86 NUREG/CR-4587 - Source Term Code Package A User's Guide (Mod.1), Acc. No. 8608180483
15. 10/31/86 NUREG/CR-4550 - Analysis of Core Damage Frecuency from Intemal Events: Peach Bottom Unit 2, Acc. 8703090175
16. 7/86 NUREG-0956 - Reassessment of the Technical Bases for Esticating Source Terms, Acc. No. 7911200319
17. 7/86 NUREG/CR-406 - Verification Test Calculations for the Source Term Code Package, Acc. No. 8608070351
18. 2/28/87 NUREG-1150 - Reactor Risk Reference Document, Acc. 'lo. 8703100040
19. 3/31/87 NUREG/CR-4448 - Shutdown Decay Heat Removal Analysis of a General Electric BWR3/ MARK 1, Acc. No. 8734060465
20. 4/30/87 NUREG'CR-4550 - Analysis of Core Damage Frecuency from Internal Events: Grand Gulf, Unit 1, Acc. No. 8707080284
21. 7/15/87 Letter to the Honorable Lando W. Zech, Jr. , from William Kerr, subject: "ACRS Comments on Draf t NUREG-il50,

' Reactor Risk Reference Document,' Acc. No. 8707230436

22. 10/31/78 NED0-24154, Vols.1 and 2, One-Dimensional Core Transient Model, Acc. No. 7902130235
23. 8/31/79 NED0-24708A, Additional Information Required for NRC Staff Generic Report on Boiling Water Reactors, Acc. No. 7909130304
24. 1/31/80 NUREG-0626 - Generic Evaluation of Feedwater Transients l and Snall Break Loss-of-Coolant Accidents in GE-Designed Operating Plants and Near-Term Operating License 1 Applications, Acc. No. 8003110304
25. 8/31/81 NUREG-0803 - Generic Safety Evaluation Report Regarding Integrity of BWR Scram System Piping, Acc. No. 8109220816
26. 2/28/87 NUREG/CR-4696 - Containment Venting Analysis for the Peach Bottom Atomic Power Station, Acc. No. 8704070476
27. 3/31/87 NED0-31331 - BWR Owner's Group Emergency Procedure Guidelines, Rev. 4 - Acc. No. 8705060276
28. Undated Browns Ferry Nuclear Plant Unit 1 Probabilistic Risk Assessment, Acc. No. 8611260176

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