ML20210C676

Affidavit of J Guttmann Re Contention Utah K & Confederated Tribes Contention B.* Affidavit Addresses Issues Pertaining to Wildfires as Admitted by Board with Respect to Contention

ML20210C676
Person / Time
Site:	07200022
Issue date:	07/22/1999
From:	Guttmann J NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20210C667	List: ML20210C660 ML20210C670 ML20210C676 ML20210C680
References
ISFSI, NUDOCS 9907270007
Download: ML20210C676 (4)

Text

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July 22,1999 UNITED STATES OF AMERICA '

NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of )

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

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(Independent Spent )

Fuel Storage Installation) )

AFFIDAVIT OF JACK GUTTMANN CONCERNING CONTENTION UTAH K AND CONFEDERATED TRIBES CONTENTION B I, Jack Guttmann, having first been duly sworn, do hereby state as follows:

1. My name is Jack Guttmann. I am employed as a Senior Nuclear Engineer in the 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 " Applicant's Motion for Panial Summary Disposition of Utah Contention K and Confederated Tribes Contention B" (Motion), filed on H 1

- June 7,1999 by Private Fuel Storage L.L.C. (Applicant or PFS), and the " Statement of Material Facts" attached thereto. In panicular, this Affidavit addresses issues penaining to wildfires as j admitted by the Board with respect to this' contention. l

3. As pan of my official responsibilities, I reviewed the adequacy of the thermal-hydraulic analysis for the Holtec International HI STORM-100 cask system, as described 9907270007 990722 PDR ADOCK 07200022 C , pm -

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2-in the HI-STORM 100 Safety Analysis Report, and I am involved in preparing the related section a

e ' of the NRC Staff's Safety Evaluation Report (SER) for the HI-STORM 100 cask system.

4. Also as pan of my official responsibilities, I have reviewed that portion of the

- Applicant's Motion which penains to wildfires (Motion at 18-20) and the Affidavits of Carlton Britton (and his February 8,1999 report), Jerry Cooper, Krishna Singh, and Ram Srinivasan, attached to the Applicant's Motion. In addition, I am familiar with the 'NRC Staff's Statement of Its Position Concerning Group I Contentions," dated June 15, 1999, with respect to fires external to the facility (Id. at 16), M the Affidavit of Paul Lain, attached hereto.

5. I have reviewed a portion of the Applicant's Statement of Material Facts which pertains to wildfires (Material Facts iT E6-E8). Based on my review of the Holtec thermal-hydraulic analysis and the documents attached to the Applicant's Motion, I am satisfied that paragraphs E6-E8 of the Applicant's Statement of Material Facts is correct, insofar as they relate to the HI-STORM'100 cask system. No opinion is expressed herein with respect to the TranStor cask system, which I did not review; however, the TranStor cask system would be required to meet the design basis for fires set fonh in i 8.2.5 of the PFS Safety Analysis Report (SAR), in i

order for PFS to utilize the casks at its site. Funher, inasmuch as the design basis fire set forth in the PFS SAR bounds the fire hazard posed by wildfires (see Affidavit of Paul Lain, attached l J

hereto), I am satisfied that PFS need not include wildfires in its design basis for its facility.

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

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Subscribcd and sworn to before me this 22nd day of July,1999. 0 4 NOTARY -

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Notary Public.'

My commission expires: M4vclt/,, ((l I

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

U. S. Nuclear Regulatory Commission 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. 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 ,

I computer codes used by the nuclear industry for transient and accident analysis. He was the Office ofNuclear 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 of Piping, and was on the task force for developing Risk-Informed regulatory guidance documents.

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- i 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 inspections.

Mr. Guttmann is currently performing thermal and containment evaluations of spent nuclear fuel transportation and storage casks. His work includes the evaluation of normal, off-normal and j accident dose analyses, and the adequacy of the thermal design of spent nuclear fuel casks. l 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, 1985-1990; Technical Assistant, Office of the Commission, NRC,1990- )

1994; Sr. Reliability and Risk Assessment Engineer, Office of Nuclear Regulatory Research, NRC, 1994-1999; Sr. Nuclear Engineer, Office of Nuclear Material Safety and Safeguards, NRC,1999-present.