IA-87-706, Final Response to FOIA Request for Documents on Nrc/Idcor Meeting on 870910 Re Individual Plant Evaluation.Forwards Documents Listed in App B.Apps a & B Documents Available in Pdr.App C Documents Totally Withheld (Ref FOIA Exemption 5)

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Final Response to FOIA Request for Documents on Nrc/Idcor Meeting on 870910 Re Individual Plant Evaluation.Forwards Documents Listed in App B.Apps a & B Documents Available in Pdr.App C Documents Totally Withheld (Ref FOIA Exemption 5)
ML20148S507
Person / Time
Issue date: 04/13/1988
From: Grimsley D
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
To: Sholly S
MHB TECHNICAL ASSOCIATES
Shared Package
ML20148S510 List:
References
FOIA-87-706, RTR-NUREG-CR-4920 NUDOCS 8804190050
Download: ML20148S507 (11)


Text

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U.S. NUCLEAR REGU ORY COMM:SSION N~c Foia nouest westasi

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INFORMATION ACT (FOlA) REQUEST

%.ees[./ APR 131989 oocur wueia s, ur .,, .a.,i at0VESTER Mr. Steven C. Sholly PART l.-RECORDS RELEAJ'O OR NOT LOCATED (See checked bonest No agency records subrect to the roovest have been located.

No eMtional agency records subpect to the request have been located.

Agency records subrect to the request that are icenufed in Ama A ,,,,,,,,,,,,,,,,,,,,, pubi.c treo.et.on and copvmg in the NRC Pubhc Document Room, X irir w Streei. N w., washmaton oC.

Agency records subpoet to the reavest thet are identifed in Aopend+n B ,,,3,,ng m,oe ,,,4,s, ,o, puu.e esoecten and copymg m the NRC Pubhc Document X Room 1717 H St, set, N W., Washington. DC, in a folder under the FOI A number and requester name.

The nonproprotary vers.on of the proposattsi that you areed to accept e a teiephone conversation wth a member of my sta rt e now being nede avadable for pubhc inspection and Coymg at the NRC Pubhc Document Room.1717 H Street. N W . Washmgton, DC, m a folder under the FOIA number and roovester name.

Enciosed e informata on how you may cotain access to and the charges for copymg records placed m the NRC Public Document Room.1717 H S est N.W., WasNngton. OC.

Agency records subpect to the request are enclosed. Any apphcable charge for cepes gf the records prouded and payrmt.t procedures are noted m the corr,ments secton.

T.ecords subrect to the request have been referred to another Federal agencytest for revew and direct response te yos in vow of NRC's response to the request, no further acton e toeg taken or appeal letter dated PART ll.A-INFORMATION WITHHELD FROM PUBLIC DISCLOSURE Certam mformaton in the roovested records e bemg withhead from pubhc d.sclosure pursuant to the FOIA enemotons described in and for the reasons stated m Part li. .,ec.

a tions B, C, and D. Any reeased portions of the documents for whch only part of the record a beq withheid are being made avadatre for pubhc mspecten arw* copyeg in the NRC Pubhc Document Room 1717 H Street, N.W., Washegton, DC, m a folder under the FOIA number and requester name.

Comment 1

8804190050 080413 i PDR FFIA l SHOLLY87-706 PDR l

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. PREEDOt(DF INFORMATION ACT RESPONSE FOIA NUMBERIS): 87-706 OsE: APR 131988 PART ll.5- APPLICABLE FifA EXEMPTENS Recoeds subject to the request that are described in the enclosed Appendices C are being withheld in their entirety or in part under FOIA Esemptions and for the reasons set forth below pursuant to 5 U.S.C. 552(b) and 10 CFR 9.5(a) of NRC Regulations.

1. The withheld information a property clawfed pursuant to Executive Order 12356 IEXEMPTON 1)
2. The withheld informanon relates solely to tre intemal personned rules and procedures of NRC. (EXEMPTION 21
3. The withheld informaeon e spectrcsh exempted from pubhc deciosure by statute indicated. IEXEMPTION 31 Section 141145 of the Atomic Erugy Act which prohitxts the dsclosure of Restncted Data or Formetty Restncted Data 142 U.S C. 216121661.

Section 147 of the Atomic Energy Act which prohitxts the deciosure of Unclassefed Safeguards Intw.maton 142 U.S.C. 2167).

4. The wthhead asformanon e a trade secret or commercel or fmancial informaton that is being withheld for the reasorist ind.cated. lEXEMPTION 4)

The information is consdered to be confidentel buteess (proprietary) information.

The informaton is consadored to be proprietary informate pursuant to 10 CFR 2.790tdH1).

The informaton was submstted and received m confeence from a foregn source pumuant to 10 CFR 2.790(dlf25

5. The withbeid information conerbts of interagency or intraagency records that are not availaote through decovery dureg htigaton. Osclosure of predecsonal information would int., tendwem tweed to inhibit the openinfo,maton.

mofodecs.on.i and frank Th.re exchange ofno aiso .,e ideas essential r.a.onauy to the dehberatrve segreoave proc,ess f.ctu ponions b.caus. Where she ,s aserecords are wouid of me facts ethheld in ther pe,mn an entrety, the facts are ines indirect enquwy mto Ine predecisonal process of the egency. IExEMPTION 5)

XX

6. Th. wmneed intormation a ...mpi.d from puu.c d.csosure because ts d.ciowe wouid resuit in a cieriy unwananted inv. son of pmone on,acy. <ExtuPTiON 6>
7. The wthhe4d inr ormaton connets of investgatory records compeed for law enforcement purposes and a be ng mtmeld for the reasantsi indicated. IEXEMPTON 7)

Declosure wouid mterfere wm en enforcement proceedeg because et couid reveal the scope. detecton, erW focus of enforcement efforts. and thus could poss@fy allow them to take acton to thseid potental wrongdoeg or a volaton of NRC reguraments from mvestsgators. lEXEMPTION 7(A))

Deciosure wowid constituw an unwananted mveson of personal privacy (EXEMPTION 71CH The informatson consets of remes of indrviduals and other informaton the declosure of which wouid reveal ioentrnes of confidental sources IEXEMPTION 7(DH PART 11 C-DENylNG OFFICIALS Pursuant to 10 CFR 9 9 and/or 915 of the U.S. Nucinar Regulatory Commason regulatons, it has been determoed that the eformaton wthre6d a esempt from producten or declosure, and that rts producten or declosure a contrary to the pubhc etere*t The persons respoes.ble for the cenei are those orrices identifed below as denying offscels and the Drector.

Oms.on of Ruses and Records. Offce of Admmetration, for any deniais that may be appealed to the Enocuove Drector for Operationa itooi I DENYING OFFICIAL TITLE / OF FICE RECOROS DEN!EO APPELLATE OFFICIAL sECafT ARY (DO Eric S. Beckjord Director Office of s App. C A Ns. leer Reguidteri i Research l

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PART 110- APPEAL RIGHTS l The denial by each denying officialidentMed in Part II.C may be appealed to the Appenate Official ident&ed in that section. Any such appeal must be in wnting and must be made within 3G days of rece pt of this response. Appea!s must be addressed as appropnate to the Executive Dwector for Operstens or to the Secretary of the Commssion, U.S. Nuclest Regulatory Commission, Washington, DC 20555. and should clearty state on the envelope and in the letter that et is an "Appeal from an trutial FOtA Decnion."

nne pomu as4 trert si U.S. NUCLEAR REGULATORY COMMIS$lON is su FOIA RESPONSE CONTINUATION

Re: FOIA.87-706 APPENDIX A RECOROS MAINTAINED AMONG PDR Fil.ES NUMBER OATE DESCRIPTION

1. November 26, 1986 Ltr. Buhl to Speis, Subj:

Forwards Final Versions of Position Papers on NRC/IDCOR Technical Issues 4,9,10,12,138, 15 & 16. .

Topics include Fission Product

& Aerosol Deposition in Primary System & in Containment &

Retention nf Fission Products in the Ice Bed ACESSIO!I NO.: 8612040241

2. September 22, 1986 Ltr. Buhl to Speis, Subj: Forwards Final Versions of Position Papers on NRC/10COR Technical issues 1,2,3,5,6,11,13A & 17. Topics Include Fission Product Release Prior to Vessel Failure & Hydrogen Ignition & Burning ACCESSION NO : 8610100286
3. INDUSTRY REPORTS Date Accession No. Description April 30, 1987 8704300053 Westinghouse Electric Corp.-

"Individual Plant Evaluation Methodology for PWRs," Technical Rept. W/JR Siegel 870313 Release Memo.

March 31, 1987 8704290449 Fauske & Associates. Inc. -

"Technical Rept. 86.382 Source Tem Methodology for BWRs."

, W/JR Seigel 870313 Release ltr.

March 31, 1987 8704290340 Fauske & Associates Inc. -

"Technical Rept 86.3A2: IPE Source Tem Methodology for PWR."

W/870313 Release Ltr.

March 31, 1987 8706110080 System Energy Resources, Inc.

"IDCOPP Technical Rept 86.200 Verification of IPE for Grand Gulf." W/JR Siegel 870313 release memo.

Re: FOIA- 87-706 APPENDIX A RECORDS MAINTAINED AMONG PDR FILES NUMBER DATE DESCRIPTION INDUSTRY REPORTS Date Accession No. Description March 13, 1987 8703230059 Atomic Industrial Forum - Forwards 10COR "Technical Rept 3.2, Assess Dominant Sequences," for Oct.1988. NRC granted authority to duplicate copyrighted 10COR matis as necessary for use by NRC & NRC ,

contractor personnel in carrying out regulatory mission.

March 13, 1987 8706100235 Atomic Industrial Forum - Forwards IDCOR, "Technical Rept 12.1, Hydrogen Generation During Severe Core Damage Sequences," dtd June 1983. Authority granted to duplicate copyrighted IDCOR matis as necessary fo use by NRC in carrying out regulatory miss ,,

January 31, 1987 8706110091 Long Island Lighting Co./0elian Corp.

"Technical Rept 86.2SH Verification of IPE for Shoreham," with/870313 release memo.

November 30, 1986 8704160086 Duke Power Co. "Technical Rept 86.200:

Verification of IPE for Oconee." W/870313 release memo.

August 31, 1986 870a010500 Fauske & Associates, Inc. "Technical Rept 23.5 Evaluations of Containment Bypass & Failure to Isolate Sequences for 10COR Ref Plants." w/870313 release ltr.

August 31, 1986 8704160089 Stone & Webster, Inc. "Technical Rept 85.5B (5.9): Source Tenn & Emergency Planning."

W/870313 ltr.

August 31, 1986 8705150389 Atomic Industrial Forum "Technical Rept 17.5 Draf t Final of IDCOR-85 An Investigation of High-Temperature Accident Conditions for Mark-I Containment Yessels."

W/870313 release ltr.

August 31, 1986 8704010455 Stone & Webster Eng. Corp. "Technical Rept 85.5A (5.5) Revised Source Tems."

W/870313 release ltr.

February 28, 1986 8704010472 Stone & Webster Eng. Corp. "Technical Rept 65.4 (5.3), Reassessrrent of Errergency Planning Requirements W/Present Scurce Terms." W/870313 release ltr.

w - +

Re: FOIA.87-706 APPENDIX A RECORDS MAINTAINED AMONG POR FILES NUMBER DATE DESCRIPTION Date Accession No. Description July 31, 1985 8705150359 Atomic Industrial Forum /Fauske & Associates, Inc "Technical Rept 85.2 Technical Support for i

Issue Resolution." W/870313 release ltr encl.

June 30, 1985 8705150210 Energy, Inc. "Technical Rept 21.1 Risk Reduction Pot ntial." W/870313 release memo.

. lune 30, 1985 8705180003 Connonwealth Edison Co. "Technical Rept 23.1Z Zion Nuclear Generating Station -

Integrated Containment Analysis."

W/870313 release memo.

May 31, 1985 8704160329 Fauske & Associates, Inc. "Technical Rept 23.4 MAAP Uncertainty Analysis."

May 31, 1985 8704010542 Affiliation not assigned "IDCOR-85 Program Plan." W/870313 release memo.

May 31, 1985 8704020157 Tennessee Valley Authority "Technical Reot 23.15 Sequcyah huclear Plant Integrated Containment Analysis." W/870313 release 1tr.

March 31,1985 8706100288 Fausko & Associates Inc. "Technical kept 11.7.FAI Aerosol Correlation."

W/870313 release memo.

March 31,1985 8705150276 Atomic Industrial Fonn/ Philadelphia Electric Co. "Technical Rept 23.1PB Peach Bottom Atomic Power Station - Integrated Containment Analysis." W/870313 release ltr enci March 31, 1985 8704010611 Mississippi Power & Light Co. "Technical Rept 23.1GG Grand Gulf Nuclear Station-Integrated Containment Analysis."

JR Siegel 870313 release ltr encl.

January 31, 1985 8704160088 Jaycor "Technical Rept 16.4 Analysis to Support MAAP Phenomenological Models."

10COR program rept. W/870407 release ltr.

December 31, 1984 8705180033 LN Technologies Corp. (formerly NUS Corp)

"Technical Rept 18.1, Evaluate Atinospheric

& Liquid Pathway Dose," program rept.

W/870313 release 1tr.

Decertber 31, 1984 8704010494 Technology for Energy Corp. "Technical Rept 24.4 Operator Response to Severe Accidents." W/870313 release 1tr.

Re: FOIA.87-706 APPENDIX A RECORDS MAINTAINED AMONG POR FILES NUMBER DATE DESCRIPTION Date Accession No. Description November 30, 1984 8703160228 Technology for Energy Corp. - Errata to 10COR technical sumary rept. "Nuclear Power Plant Response to Severe Accidents."

September 30, 1984 870'4160188 LN Technologies Corp. (formerly NUS Corp)

"Technical Rept 9,1R Preventive Methods to Arrest Sequences of Events Prior to Core Damage Rev 1." program rept.

August 31, 1984 8703200383 Technology for Energy Corp. "Technical Rept 1.1 Safety Goal Evaluation:

Implications for IDCOR." W/870313 release 1tr.

August 31, 1984 8706100486 Fauske & Associates. Inc. Technical Rept 11.6, Resuspension of Deposited Aerosols Following Primary Sys or Containment Failure." W/870313 release memo.

June 30, 1984 8705180014 Fauske & Associates, Inc. "Technical Rept 22.1, Safe Stable States." W/870313 release memo.

February 28, 1984 8706110353 S. Levy, Inc. "Technical Rept 13.2-3 Evaluation of Means to Prevent, Suppress, or Control Hydrogen Burning in Reactor Containments," W/870313 release 1tr.

January 31, 1984 8706110018 Impe11 Corp. "!DCOR Technical Rept 11.2 Identifying Pathways on Fission Product Transport." W/JR Siegel 870313 release 1tr.

December J1,1983 8706110174 Impe11 Corp. "Technical Rept 11.3 Fission Product Transport in Degraded Core Accidents."

W/870313 release memo.

December 31, 1983 8704170037 Jaycor "Technical Report 16.1A, Review of Modular Accident Analysis Program of BWR and PWR Codes." W/870407 release memo.

November 30, 1983 8704160339 Energy, Inc. "Technical Rept 6.1: Risk Significance Profile for ESF & Other Equipment." W/870407 release 1tr.

October 31, 1983 8507130018 Electric Power Research Institute -

Technical Repts. 11.1.11.4 & 11.5 "Estimation of Fission Product & Core.

Matl Characteristics." W/870313 release 1tr.

Re: FOIA.87-706 APPENDIX A RECORDS MAINTAINED AMONG POR FILES NUMBER DATE DESCRIPTION Date Accession No. Description October 31, 1983 8704160294 Science Applications Internationao Corp.

(Fonnerly Science Industry) "Technical Rept. 4.1, Containment Event Trees,"

10COR program rept. W/870313 release ltr.

September 30, 1983 8705150340 Atomic Industrial Forum / Electric Power Research Institute "Technical Pept 15.18, Analysis of In-Yessel Core Melt Progression." W/870313 release ltr.

September 30, 1983 8706110106 Electric Power Research Institute -

"Technical Rept 12.2: Hydrogen Combustion in Reactor Containment Bldgs." W/870313 release ltr.

l September 30, 1983 8706110042 Electric Power Research Institute -

"Technical Rept.12.1 Hydrogen Distribution in Reactor Containment Bldgs." W/870313 release memo.

September 30, 1983 8704160093 Fauske & Associates, Inc. "Technical Rept. 15.3: Core-Concrete Intcractions."

W/870313 release memo.

August 31, 1983 8704160083 Industry Degraded Core Rulemaking Program -

"Technical Rept 15.2B Debris Coolability, Vessel Penetration & Debris Dispersal."

W/870313 release 1tr.

July 31, 1983 8705150238 Industry Degraded Core Rulemaking Program -

"Technical Rept 20.1 Core Retention Devices."

l l July 31, 1983 8703200350 "Technical Rept 3.3: Selection of Dominant Sequences-Update." W/870313 release ltr.

July 31, 1983 8706110025 Bechtel Corp. "IDCOR Technical Rept.19.1,

, Alternate Containment Concepts."

l W/JR Siegel 870313 release ltr.

l July 31, 1983 8706110385 Technology for Energy Corp. "Technical Rept 10.1 Containment Structural Capability of light Water Nuclear Power Plants." .

W/870313 release memo.

July 31, 1983 8702130103 Fauske & Associates, Inc. - Technical Rept.15.1A, "In-Vessel Core Melt Progression Phenomena." W/870313 release ltr.

Re: FOIA- 87-706 APPENDIX A RECORDS MAINTAINED AMONG POR FILES NUMBER DATE DESCRIPTION Date Assession-No. Description June 30, 1983 8402130060 Fauske & Associates. Inc'. - Technical Report 14.1B, "Key Phenomenological Models for Assessing Nonexplosive Steam Generation Rates."

June 30, 1983 8402130109 Electric Power Research Institute -

Technical Rept. 15.2A, "Effects of Hypothetical Core Melt Accident on PWR Vessel W/ Top-Entry Instruments."

W/870313 release ltr.

April 30, 1983 8507130169 Jaycor - Technical Rept. 16.1, "Access Available Codes, Define Use & Follow &

Support Ongoing Activities."

March 31, 1983 8704160350 Technology for Energy Corp. "Technical Rept 5.1 Human Error: Effects on Dominant Accident Sequences."

August 31, 1982 8703200339 Technology for Energy Corp. "Mgt Pept 3:

Survey of Research Programs Related to Degraded Core issues." W/870313 release 1tr.

June 30, 1982 8402130080 Technology for Energy Corp. - Technical Rept. 3.1, "Define Initial likely Sequences."

April 30, 1982 8402130077 Technology for Energy Corp. - Technical Rept No. 2.1, "Ground Rules for Industry Degraded Core Rulemaking Program."

November 30, 1981 8206150191 Technology for Energy Corp. -

"lDCOR Program Plan."

l

Re: FOIA- 87-706 APPENDIX B RECORDS MAINTAINED IN THE POR UNDER THE ABOVE REQUEST NUMBER NUMBER DATE DESCRIPTION

1. November 1987 NUREG/CR-4920 Assessment of Severe Accident Prevention BNL-NUREG-52070 and Mitigation Features: BWR, Mark 1 Volume 1 Containment Design, prepared by W. T. Pratt, et al (Draft) (82 pages;
2. November 1987 'NUREG/CR-4920 Assessment of Severe Accident Prevention BNL-NUREG-52070 and Mitigation Features: BWR, Mark 11 Volume 2 Containment (Oraf t) (96 pages Desig)n, by C. J. Hsu, et al
3. November f(UREG/CR-4920 Assessment of Severe Accident Prevention BNL-NUREG-52070 and Mitigation Features: BWR, Mark !!!

Volume 3 Containment Design, by R. G. Fitzpatrick, et al (Draft) (64 pages}

4. November 1987 NUREG/CR-4920 Assessment of Severe Accident Prevention CNL-NUREG-52070 and Mitigation Features: PWR, large Volume

( Volume 4 Containment Design, by W. J. Luckas, et al (Ora f t) (112 pages)

5. November 1987 NUREG/CR-4920 Assessment of Severe Accident Prevention BNL-NUREG-52070 and Mitigation Features: PWR, Ice-Condenser Volume 5 Containment Design, by K. R. Perkins, et al I

(1) mges)

6. October 14, 1987 Met iltawila to Sheron and Coffman, Subj : Minutes of the NRC/IDCOR Steering i

Comittee Meeting on September 10, 1987 l (15pages) i

7. October 2,1987 Ltr. Sheron to Buhl, Subj: Response to Ltr. Dated July 9,1987, fm Buhl to Beckjorc Response to Brookhaven National Laboratory's Comments on 10COR's Model of the Mark I Containment Response to Direct Contact with Molten Core Debris (4pages) i 8. July 9,1987 Ltr. Buhl to Beckjord, Subj: Response to Brookhaven National Laboratory's (BNL) l Coments on 10COR's Model of the Mark I l

Containment Response to Direct Contact with Molten Core Debris (8 pages)

9. March 11,1987 Ltr Speis to Buhl, Subj: Encl. Position Paper Re the issue of Direct Containment Heating (6 pages)
10. March 9,1987 Ltr. Buhl to Speis, Subj: Submittal of Revisions to the IDCOR Individual Plant Evaluation (IPE) Pressurized Water Reactor Systems Methodology (12 pages)

Re: FOIA- 87-706 APPENDIX g RECORDS MAINTAINED IN THE POR UNDER THE ABOVE REQUEST NUMBER HUMBER DATE DESCRIPTION

11. December 10, 1986 Ltr. Buhl to Speis, Subj: IDCOR Response to NRC Corynents on the Individual Plant Evaluation Methodology (46 pages)
12. September 9, 1986 Ltr Speis to Buhl, Subj: HRC Preliminary Review of the Draft Individual Plant Examination Methods (IPEM) Submitted by IDCOR on My 2,1986 (41 pages) l l

M Re: FOI A- 87-706 APPENDIX C RECORDS TOTALLY WITHHELD NUMBER DATE DESCRIPTION & EXEMPTION

1. 10/19/87 Draft Generic Letter Concerning Individual Plant Examinations for Severe Accident Vulnerabilities (Including Supporting Documents) - Exemption 5
2. Undated Draft Evaluation of IDCOR IPEM for PWR's (Including Supporting Documents) - Exemption 5
3. Undated Draft Evaluation of IDCOR IPEM for BWR's (Including Supporting Documents) _ Exemption 5 4

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