ML20237J214

FOIA Request for Listed Documents Ref in NUREG-1150 & Related Contractor Repts

ML20237J214
Person / Time
Site:	Peach Bottom, Grand Gulf, Sequoyah, Zion, 05000000
Issue date:	07/02/1987
From:	Sholly S MHB TECHNICAL ASSOCIATES
To:	Grimsley D NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
FOIA-87-416, RTR-NUREG-1150, RTR-NUREG-CR-4165, RTR-NUREG-CR-4550, RTR-NUREG-CR-4551, RTR-NUREG-CR-4772 NUDOCS 8708180029
Download: ML20237J214 (5)

Text

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j GAB Q TECHNICAL CONSULTANTS ON wgw l Dale G Bricentaugh 1723 Harnetton Avenue-Sute K Richard B Hubbard San Jose Caldornia 95125 )

Gregory C Minor Pt.one:(408) 266 2716 EREEDOM OF INFORMATION 2 July 1987 M T M EST R9/ A. / 7- W6 Mr. Donnie H. Grimsley, Director g}T

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7/f//7 Division of Rules and Records Office of Administration and Resources Management

, U.S. Nuclear Regulatory Commission l

Washington, D.C. 20555 RE: Request for Certain Documents Referenced in NUREG-1150 and Related ContractorReports

Dear Mr. Grimsley:

)

Pursuant to the Freedom of Information Act and 10 CFR Part 9, Subpart A, j

' Freedom of information Act Regulations", please make available at the Commission's l Washington, D.C., Public Document Room single copies of the following records: 1/ j i

A. Sandia National Laboratories memorandum dated 2/25/86 from D.A. Powers and D. Williams to Source Term Peer Review

Team, " Radionuclides Release and Aerosol Generation During

Ejection of Core Debris from a Pressurized Reactor Vessel".

[ Reference #20 in NUREG/CR-4551, Vol. 5, Evaluatlon of Sg;'ere Accident Risks and Potential for Risk Reduction: Zion  !

Power Pla.nf, Brookhaven National Laboratory, Draft for Comment, February 1987)

B. Sandia National Laboratories, " Instructions for Programs EVNTREISS and LAHRS", February 1986. [ Reference #15 in NUREG and *Po/CR-4551, tential for.Vol.

Risk5,Reduction:

Evaluation ofZion Severe Accident Power Plant,Risks Brookhaven National Laboratory, Draft for Comment, February 1987)

C. NRC memorandum dated 8/1/85 from T.P. Spels to H.R.

Denton,

Subject:

" Recommendations Resulting from Zion Risk inquiry". [ Reference #5 in NUREG/CR-4550, Vol. 7, AnalvsLt 1/ As used here, " records" has the definition provided in 10 CFR 9.3(b) of the Commission's regulations. Furthermore, " records" are considered to be those in the possession of the NRC, its contractors, its subcontractors, or others as provided for in 10 CFR 9.4.

87oB1 Boo 29 870702 PDR FoIA SHOLLYB7-416 PDR

I 1 I Il 2-of Core Damage Frecuency From Intemal Events: Zion Unit 1.

Sandia National Laboratories, October 1986]

D. F.T. Harper, et al., Analysis of Core Damaae Frecuency From Intemal Events: Methodology Guidelines, Sandia National Laboratories, NUREG/CR-4550, SAND 86-2084, Vol. 1.

' Reference #3 in NUREG/CR-4550, Vol. 4, enalysis of Core Damage Freauency From Intemal Events: Peach Bottom. Unit l 2, Sandia National Laboratories, October 1986]

E. J. Minarick, "BWR Event V " Presentation at ASEP SCG/0956 -  !

l NRC Meeting,5/22/85. [ Reference #12 in NUREG/CR-4550, Vol. 4, Analysis of Core Damaae Freauency From Internal Events: Peach Bottom. Unit 2, Sandia National Laboratories, October 1986]

l F. A.J. Call, et al., "LaSalle Comty Station Probabilistic Safety l Analysis," General Electric Company, NEDO-31085, Class I, l November 1985. [ Reference #16 in NUREG/CR-4550, Vol. 4, i Analysis of Core Damaae Freauencv From Internal Events:

Peach Bottom. Unit 2. Sandia National Laboratories, October 1986]

G. Letter dated 6/18/85 from G.J. Bo Optimization Services, Inc.) to F.T.yd Harper(Safety (Sandia and Reliability National i Laboratories). [ Reference #21 in NUREG/CR-4550, Vol. 4, i l Analvsis of Core Damaae Freauencv From Internal Events:

l Peach Bottom. Un/t 2. Sandia National Laboratories, October l 1986]

H. Letter dated 7/2/85 from F.T. Harper and G.J. Kolb (Sandia National Laboratories) to "PRA Experts",

Subject:

" Subtle '

i interactions Found in Past PRAs and PRA Related Studies".

' Reference #22 in NUREG/CR-4550, Vol. 4, Analvsis of Corg Damaae Freauencv From Internal Events: Peach Bottom. Unit 2, Sandia National Laboratories, October 1986]

l. A.D. Swain, Accident Secuence Evaluation Proaram Human l

• Reliability Analysis'Procycty.rg, Sandia National Laboratories, 1 NUREG/CR-4772, SAND 86-1996. [ References #25 and #26 in NUREG/CR-4550, Vol. 4, Analvsis of Core Damaae Frecuencv From Internal Events: Peach Bottom. Unit 2. Sandia National Laboratories, October 1986]

l J. H.R. Denton memorandum dated 10/30 , "NRR Office

Letter No.16, Revision 2-Regulatory An sis Guidelines,"

U.S. NRC. [Section 3, Reference #6 in NUR /CR-4551, Vol.

4, Evaluation of Severe Accident Risks and the Potential for Risk Redyction: Grand Gulf. Unit 1. Sandia National Laboratories, April 1987]

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3-  ;

K. 'W.J. Lukas, et al., A Human Reliability Analvsis'for the ATWS ll

. Accident Seauence with MSIV Closure at the Peach Bottom 1

- Atomic Power Station. Brookhaven National Laboratory, May .i 1986. [ Reference #29 in NUREG/CR-4550, Vol. 4, Analvsis of .;

Core Damaae Freauency From Internal Events: Peach Bottom. i Unit 2, Sandia National Laboratories, October 1986]

L R.J. Dallman,' et' al., Severe Accident Seouence Analvsis Proaram - Anticipated Transient Without Scram Simulations for ' ,

Browns Ferry Nuclear Plant Unit 1. Idaho National Engineering -

~

Laboratory- (EG&G Idaho), NUREG/CR-4165, EGG 2379, ]

February 1985. [ Reference #34 in NUREG/CR4550, Vol. 4, l Analvsis of Core Damaae Freauencv From Internal Events: }

P_ each Bottom. Unit 2. Sandia National Laboratories October .

1986]

M. hia Electric Company . comments on Draft Philadelp/CR-4550, Vol. 4. -(Seg, Appendix C in NUREG/CR-NUREG _

4550, Vol. 4,' Analvsis of Core Damaae Freauencv From Internal Events: Peach Bottom. Unit - 2. ' Sandia . National Laboratories, October 1986] j

.s N. M.T. Drouin, et al., Analvs;a of Core Damaoe Freauencv from . }

Internal Events: Grand ' Gulf. Unit- 1, Sandia' National y Laboratories, NUREG/CR-4550, .Vol. ' 6,' November 1986. l

'Section 1, Reference #4, in NUREG/CR-4551, .: Vol. 4, i'

$ valuation of Severe Accident Risks and the Potential for Risk . .

Reduction: Grand Gulf. Unit 1. Sandia Natonal Laboratories, . ,

April 1987)

O. J.M. Griesmeyer, User's Guide for the EVNTRE Comouter Section 2, Reference #5 i Code, Sandia National in NUREG/CR-4551, Laboratories.

Vol. 4, Evaluat [ ion of Severe Accident ^

Risks and the Potential for Risk Reduction: Grand Gulf. Unit 1. l l Sandia National Laboratories, April 1987)

P. M.L Corradini, " Additional Comments on the Peach' Bottom )

and Grand. Gulf Containment Event Trees," letter. report to i Mark Cunningham, U.S. NRC, .10/13/66. [Section 2,  !

i Reference #7 in ~ NUREG/CR-4551, Vol. 4, Evaluation of t Severe Accident Risks and the Potential for Risk Reductlam .)

Grand Gulf. Unit 1, Sandia National Laboratories, April 1987) . d l.

O. Brookhaven National Laboratories, Review of the Source-Term ~  !

Code Packsos.- [Section 2, Reference #10 in NUREG/CR .  !

4551, Vol 4', Evaluation of Severe Accident Risks and the Potential for Risk Reduction: Grand Gulf. Unit 1. Sandia '~

National Laboratories, April 1987) l l

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- R. ' Sandia National Laboratories, Probabilistic Risk 'Uncertiantv d Evaluation Prooram fPREUP). (Section 2, Reference #12 in .

NUREGlCR-4551, VOL 4, Evaluation of Severe Accident Risks .

and the Potential for Risk Reduction: Grand Gulf. Unit 1.

Sandia National Laboratories, April 1987]

S. F.T. Harper, 'ASEP ' Data' Reevaluation," : memorandum ~ .to i Senior Consultant Group, et al., Sandia Natonal Laboratories, 1 3/15/85.] {

4, Evalua tion of Severe Accident Risks and the Potential fo,Section 2, Refe j Risk Reduction: Grand - Gulf. Un/t 1. Sandia National 1

. Laboratories, April 1987]. j 1 T. A.S. Benjamin and F.T. Harper, Value Imoact Investlaation of

~

l

. Filtered-Vented Containment Svstems and Other Safetv j Ootions for a BWR Mark I Containment. Sandia National Laboratories, NUREG/CR 4065 (Draft), Septebmer 1984.

'Section '3, Reference #5 in NUREG/CR-4551, Vol. 4, I Evaluation of Severe Accident Risks and the Potential for Risk i.

Reduction: Grand Gulf. Unit 1. Sandia National Laboratories,  ;

April 1987] [

l U. J.L Dooley, et al., Mitlantion Svstems for Mark ll Reactors, (

AppendM R&D Associates, F, Reference RDA-TR-127303-001,

1. 12,'in NUREG/CR-4551, Vol. May 1984. [luation of 4, Eva 4 Severe Accident Risks and the Potential for Risk Reduction:

Grand Gulf. Unit 1. Sandia National Laboratories, April 1987] .!

l' V. Letter dated 6/4 86 from. K.D. Ber ron '(Sandia National l Laboratories) to M. Lee (NRC). '[Se on 4, Reference #4 in -

NUREGlCR-4551, Vol. 2, Evaluation of Seve e Accident Risks' i at the Potential for Risk Reduction: Seouovah Power Station. i Unit 1. Sandia National Laboratories, February 1987]

l

~

W. Letter dated 3/19/86 from G. Greene (Brookhaven? National' q Laboratories) to A.S. Benjamin (Sandia National Laboratories),

ix B, Referenoe #20 in NUREG/CR-4551, Vol. 2, av uation of Severe Accident Risks at the Potential tbr Risk i Reduction: Seouovan Power Station. Unit 1, Sandia National  ;

Laboratones, February 1987] j X. .W.J. Camp, et al.,'A Mechanistic Code kx Analvs/s of Reactor '

~

Core Melt Progression and -Vessel Attack Under Severe i

, Accident Condiflons. Sandia National Laboratories, SAND 85- l

' 0237, draft. [ Appendix J.2, Reference J.2.12 in NUREG-1150, Vol. 3, Reactor Risk Reference Docurrigat, ' February 1987] .

In each case above, the requested documents are' references' in other published NRC reports (references are provided). If there is a more recent version of the . J

. document than listedin the reports, please provide the most recent version rather than l the one listed in the referenced reports.

i 1

1

, . . . j if you or any members of your ~ staff have any questions concerning this request, please contact the undersigned directly by telephone at (408) 266-27.16. Partial responses would be appreciated as documents become available. Your_ prompt attention to this request will be appreciated.

l SincereY, l

\ Steven C. Sholly /

l l Associate Consultant l

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