ML20196F148

Affidavit of J Guttmann Re Contention UT H (Inadequate Thermal Design).* Affidavit Prepared in Response to Applicant Motion for Partial Summary Disposition of UT Contention H.With Certificate of Svc

ML20196F148
Person / Time
Site:	07200022
Issue date:	06/25/1999
From:	Guttmann J NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS), NRC OFFICE OF THE GENERAL COUNSEL (OGC)
To:
Shared Package
ML20196F143	List: ML20196F137 ML20196F148
References
ISFSI, NUDOCS 9906290149
Download: ML20196F148 (5)

Text

,

j .

June 25,1999 UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of. .)

)

PRIVATE FUEL STORAGE, L.L.C. ) . Docket No. 72-22-ISFSI

)

(Independent Spent Fuel )

Storage Installation) )

AFFIDAVIT OF JACK GUTTMANN l CONCERNING CONTENTION UTAH H

GNADEOUATE THERMAL DESIGN) i I, Jack Guttmann, having first been duly sworn, do here'oy state as follows

l l

. 1. My name is Jack Guttmann. I am employed as a Senior Nuclear Engineer in the l

Spent Fuel Project Office (SFPO), Office of Nuclear Materials Safety and Safeguards, U.S.

Nuclear Regulatory Commission (NRC), in Washington, D.C. A statement of my professional qualifications is attached hereto.

2. This Affidavit is prepared in response to the " Applicant's Motion for Partial.-

Summary Disposition of Utah Contention H - Inadequate Thermal Design" (Motion), filed on May 19,1999, by Private Fuel Storage L.L.C. (Applicant or PFS), and the " Statement of Material Facts on Which No Genuine Dispute Exists" (Statement of Material Facts) attached thereto.

l r

i

3. As part of my official responsibilities, I reviewed the adequacy of the thermal- l hydraulic analysis for the Holtec International HI STORM-100 cask system, as described in the 1

HI-STORM 100 Safety Analysis Report, and am involved in preparing the related section of the NRC Staff's Safety Evaluation Report (SER) for the HI-STORM 100 cask system. In addition,  ;

9906290149 990625  ;

< PDR ADOCK 07200022 C PDR j

)

I have reviewed Holtec's thermal-hydraulic analysis for 125" F ambient temperature conditions, i

submitted by PFS in its February 10,1999 response to the NRC Staff's Requests for Additional  !

1 Information (specifically, RAI 4-2). I have also read and am familiar with the PFS Safety l Analysis Report, as revised on May 19,1999.

l

4. Also as part of my official responsibilities, I have reviewed the Applicant's Motion l l

and the attachments thereto, in which PFS seeks summary disposition of subparts 3,4 and 5 of i Utah Contention H. On the basis of my review of the Holtec thermal-hydraulic analysis, and the Applicant's SAR and its responses to the Staff's RAls, I am satisfied that the Statement of Material Facts attached to the Applicant's Motion is correct, except for the third and fourth sentences of Material Fact. No. 4, in which PFS states as follows: -

A fully loaded HI STORM 100 cask will experience higher temperatures, all other conditions being equal, than a fully loaded TranStor cask. Therefore, the revised thermal calculation for the HI STORM 100 cask is bounding.

With respect to the cited portions of Material Fact No. 4, no opinion is expressed herein.

5. I hereby certify that the foregoing is true and correct to the best of my knowledge, information and belief.

2d YL.&xw Jack Guttmann Subscribed and sworn to before me this 25th day of June,1999, c,6 E44 NOTARY RL M W

~

Notary Public My commission expires:2/AW[ [ JOO.3

m Jack Guttmann Senior Nuclear Engineer Spent Fuel Project Office Office of Nuclear Material Safety and Safeguards (NMSS)

' U. S. Nuclear Regulatory Conunission B.S. in Mechanical Engineering, Michigan Technological University,1973 M.S. Nuclear Engineering, University of Michigan,1974 Mr. Guttmann has experience in nuclear engineering related to thermal-hydraulic and mechanical engineering analysis.1 Mr. Guttmann worked at the Idaho National Engineering Laboratory as a contractor to the NRC in the area of thermal hydraulic computer code validation and analysis. He performed analyses that quantified the conservatism between the accident analysis requirements for licensing nuclear power plants

( 10 C.F.R. Part 50, Appendix K), validated the computer code RELAP for regulatory application by the NRC, and performed independent confirmatory transient and accident analyses of operating reactor events and safety issues defined by the NRC.

While working at the NRC, Mr. Guttmann was responsible for reviewing and approving the computer codes used by the nuclear industry for transient and accident analysis. He was the Office of Nuclear Reactor Regulation (NRR) representative on the Advanced Code Review Committee,the Loss of Fluid Test Facility, and the Semiscale Test Facility. Mr. Guttmann performed independent analyses of plant operating events, including regulatory responses to the TMI event. He was a member of the BWR Bulletins and Orders Task Force that reviewed the ramifications of the TMI-2 events for boiling water reactors. He reviewed and approved emergency operator procedures for PWR designs and performed quality assurance inspections.

Mr. Guttmann developed standard review plans for analyzing reactor transient and accident events, developed regulatory guidance and NUREG documents for implementing Risk-Informed in-Service Testing ofPiping, and was on the task force for developing Risk-Informed regulatory guidance documents.

With respect to policy development, Mr. Guttmann served as a technical assistant to Commissioner Forrest J.

Remick. He advised Commissioner Remick on policy development of advanced nuclear power plants, ,

operating reactor issues, research needs, and represented the Commission as an observer on INPO l inspections.

1 Mr. Guttmann is currently performing thermal and containment evaluations of spent nuclear fuel  ;

. transportation and storage casks. His work includes the evaluation ofnormal, off-normal and accident dose l

. analyses, and the adequacy of the thermal design of spent nuclear fuel casks.

PROFESSIONAL CHRONOLOGY:-Jr.. Engineer, Detroit Edison Co., Enrico Fermi Atomic Power Plant-1,

~

1972-73; Research Engineer, Idaho National Engineering Laboratory,1975-1976; Nuclear Engineer, Office of Nuclear Reactor Regulation, NRC, 1976-1985; Technical Coordinator, Office of the Secretary, NRC, l 1985-1990; Technical Assistant, Office of the Commission, NRC, 1990-1994; Sr. Reliability and Risk L Assessment Engineer, Office of Nuclear Regulatory Research, NRC, 1994-1999; Sr. Nuclear Engineer, l Of11ce of Nuclear Material Safety and Safeguards, NRC,1999-present.

I  !

4 i

i^ l L i 4

y  :

00CKETED

. UNITED STATES OF AMEIUCA tjsHRC NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD 9 M In the Matter of. ) OFFL '

) Ru :F !

PRIVATE FUEL STORAGE L.L.C. ) Docket No. 72-22-Ikkb #

)

(Independent Spent )

Fuel Storage Installation) )

CERTIFICATE OF SERVICE I hereby certify that copies of "NRC STAFF'S RESPONSE TO APPLICANT'S MOTION FOR PARTIAL

SUMMARY

DISPOSITION OF UTAH CONTENTION H (INADEQUATE THERMAL DESIGN)" in the above captioned proceeding have been served on the following through deposit in the Nuclear Regulatory Commission's internal mail system, or by deposit in  !

the United States mail, first class, as indicated,by an asterisk, with copies by electronic mail as indicated, this 25th day of June,1999:

G. Paul Bollwerk, III, Chairman Atomic Safety and Licensing Board Panel Administrative Judge U.S. Nuclear Regulatory Commission Atomic Safety and Licensing Board Washington, DC 20555 U.S. Nuclear Regulatory Commission Washington, DC 20555 Office of the Secretary

.(E-mail copy to GPB@NRC. GOV) ATTN: Rulemakings and Adjudications Staff U.S. Nuclear Regulatory Commission Dr. Jerry R. Kline Washington, DC 20555 Administrative Judge - (E-mail copy to:

Atomic Safety and Licensing Board HEARINGDOCKET@NRC. GOV)

U.S. Nuclear Regulatory Commission Washington, DC 20555 Office of the Commission Appellate (E-mail copy to JRK2@NRC. GOV) Adjudication Mail Stop: 16-C-1 OWFN Dr. Peter S. Lam U.S. Nuclear Regulatory Commission Administrative Judge Washington, DC 20555 Atomic Safety and Licensing Board i U.S. Nuclear Regulatory Commission James M. Cutchin, V Washington, DC 20555 Atomic Safety and Licensing Board I (E-mail copy to PSL@NRC. GOV) U.S. Nuclear Regulatory Commission Washington, DC 20555 l (by E-mail to JMC3@NRC. GOV)

I l

werepu & .

> _.-.nua4,

~ . _ . . ..

Danny Quintana, Esq.* Diane Curran, Esq.*

Danny Quintana & Associates, P.C. Harmon, Curran, Spielberg 50 West Broadway, Fourth Floor & Eisenberg, L.L. P.

Salt Lake City, UT 84101 1726 M. Street N.W., Suite 600 (E-mail copy to quintana @Xmission.com) Washington, D.C. 20036 (E-mail copy to i Jay E. Silberg, Esq.* dcurran@harmoncurran.com) l Ernest Blake, Esq.*  !

Paul A. Gaukler, Esq.* John Paul Kennedy, Sr., Esq.* l SHAW, PITTMAN, POTTS & 1385 Yale Ave. i TROWBRIDGE Salt Lake City, UT 84105 2300 N Street,' N.W. (E-mail copy to john @kennedys.org) ,

Washington, DC 20037-8007 I (E-mail copies to jay _silberg, Joro Walker, Esq.*

paul _gaukler, and ernest _blake Land and Water Fund of the Rockies

@shawpittman.com) 2056 East 3300 South, Suite 1 Salt Lake City, UT 84109 i Denise Chancellor, Esq.* (E-mail copy to joro61@inconnect.com)  ;

Fred G. Nelson, Esq.

l Utah Attorney General's Office

~

Richard E. Condit, Esq.

160 Ea'st 300 South,5th Floor Land and Water Fund of the Rockies  !

P.O. Box 140873 - 2260 Baseline Road, Suite 200 4 Salt Lake City, UT 84114-0873 Boulder, CO 80302 l (E-mail copy to dchancel@ State.UT.US) _(E-mail copy to rcondit@lawfund.org)

L ,

. Connie Nakahara, Esq.* i Utah Dept. of Environmental Quality 168 North 1950 West j i . P.' O. Box 144810

~ Salt Lake City, UT 84114-4810 (E-mail copy to enakahar@ state.UT.US)

L

)

Sherwin E. Turk I Counsel for NRC Staff l