ML20040C985

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Affidavit of WR Spezialetti Re Contention 2 on Verification & Acceptance of Computer Codes.Discusses Topical Repts Relevant to Contention 2.Prof Qualifications Encl
ML20040C985
Person / Time
Site: Comanche Peak  Luminant icon.png
Issue date: 01/19/1982
From: Spezialetti W
TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC), WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
To:
Shared Package
ML20040C961 List:
References
NUDOCS 8201290440
Download: ML20040C985 (6)
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Text

UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of )

Docket Nos. 50-445 and TEXAS UTILITIES GENERATING 50-446 COMPANY, et al.

(Application for (Comanche Peak Steam Electric ) Operating Licenses)

Station, Units 1 and 2) )

AFFIDAVIT OF WILLIAM R. SPEZIALETTI REGARDING CONTENTION 2 (VERIFICATION AND ACCEPTANCE OF COMPUTER CODES)

William R. Spezialetti, being first duly sworn, deposes and states:

I am employed by Westinghouse Electric Corporation (Westinghouse) in the position of Manager, Domestic Licensing Technology. I have knowledge of the Westinghouse technical reports relied on in performing the safety analyses of the Nuclear Steam Supply Systen of Comanche Peak and of their verification by Westinghouse and acceptance by the NRC Regulatory Staff.

A statement of my education and professional qualifications is attached to this affidavit, and is incorporated herein by reference.

I will list the various Westinghouse Topical Reports which have been identified by Citizens for Fair Utility Regulation (CFUR) as being the subject of Contention 2 in the above-captioned proceeding. I will also 8201290440 820126 PDR ADOCK 05000445 0 PDR

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identify those Topical Reports that were not relied upon in safety analyses for Comanche Peak, and identify those Topical Reports that do not introduce new computer codes for NRC review or present justification for the validity of any particular code.

Reports and Codes The topical reports to which this affidavit appliesE are, as follows:

1. An Evaluatior, of Solid State Logic Reactor Protection in Anticipated Transients, WCAP-7706 (Non-Proprietary), February 1973
2. Overpressure Protection for Westinghouse Pressurized Water Reactors, WCAP-7769, October 1971
3. Overpressure Protection for Westinghouse Pressurized Water Reactors, WCAP-7769, Revision 1, June 1972
4. Evaluation of Steam Generator Tube, Tubesheet and Divider Plate Under Combined LOCA Plus SSE Conditions, WCAP-7832, December 1973
5. LOFTRAN Code Description, WCAP-7907, June 1972
6. FACTRAN - A FORTRAN-IV Code for Thermal Transients in a U02 Fuel Rod, WCAP-7908, June 1972
7. MARVEL, A Digital Computer Code for Transient Analysis of r. Multi-loop PWR System. WCAP-7909, June 1972
8. Fuel Assembly Safety Analysis for Combined Seismic and Loss of Coolant Accident, WCAP-7950, July 1972
9. Reactor Coolant Pump Integrity in LOCA, WCAP-8163, September 1973 If The reports are as listed by Intervenor CFUR and use the numbers assigned in the Applicants' Motion for Summary Disposition of Contention 2. Report Numbers 19-21 are not Westinghouse reports and are not subjects of this affidavit.
10. Safety Analysis of the 17x17 Fuel Assembly for Combined Seismic and Loss of Coolant Accident, WCAP-8288 (Non-Proprietary), January 1974
11. Documentation of Selected Westinghouse Structural Analysis Computer Codes, WCAP-8252, Revision 1, July 1977
12. Hydraulic Flow Test of the 17x17 Fuel Assembly, WCAP-8279 (Non-Proprietary), February 1974
13. Westinghouse Anticipated Transients Without Trip Analysis, WCAP-8330, August 1974
14. An Evaluation of Loss of Flow Accidents Caused by Power Systems Frequency Transients in Westinghouse PWRs, WCAP-8424, Revision 1, June 1975
15. Fuel Rod Bowing, WCAP-8692 (Non-Proprietary), December 1975
16. Improved Analytical Models Used in Westinghouse Fuel Rod Design Computations, WCAP-8785 (Non-Proprietary), October 1976
17. Westinghouse Emergency Core Cooling System Evaluation Model -

Modified October 1975 Version, WCAP-9169 (Non-Proprietary),

September 1977 ,

18. Properties of Fuel and Core Component Materials, WCAP-9224 (Non-Proprietary), September 1977
19. MRI/STARDYNE, Static and Dynamic Structural Analysis System, User's Information Manual, developed by and proprietary to Mechanics Research, Inc., employed by Gibbs & Hill
20. SCONV, Gibbs & Hill 21 . SPECTRA, Gibbs & Hill
22. Safety-Related Research and Development for Westinghouse Pressurized Water Reactors, Program Summaries, WCAP-8768, latest revision
23. THINC-IV, An Improved Program for Thermal-Hydraulic Analysis of Rod Bundle Cores, WCAP-7956, June 1973
24. Calculational Model for Core Reflooding After a Loss of Coolant Accident (WREFLOOD Code), WCAP-8171 (Non-Proprietary), June 1974
25. WFLASH, A FORTRAN-IV Computer Program for Simulation of Transients in a Multi-Loop PWR, WCAP-8261, Revision 1 (Non-Proprietary), July 1974
26. LOCTA-IV Program: Loss of Coolant Transient Analysis, WCAP-8305 (Non-Proprietary), June 1974
27. SATAN-IV Program: Comprehensive Space-Time Dependent Analysis of Loss of Coolant, WCAP-8306 (Non-Proprietary), June 1974
28. Containment Pressure Analysis Code (C0C0), WCAP-8326 (Non-Proprietary),

June 1974

29. Westinghouse ECCS Evaluation Model-A Summary, WCAP-8339, July 1974
30. Westinghouse ECCS Plant Sensitivity Studies, WCAP-8356 (Non-Proprietcry), July 1974
31. Westinghouse ECCS Evaluation Model Sensitivity Studies, WCAP-8342 (Non-Proprietary), July 1974
32. Westinghouse ECCS Evaluation Model -- Supplementary Information, WCAP-8472 (Non-Propriet6ry), April 1975 Topical Report Acceptance-Of the above reports, Numbers 2, 17 and 22 were not relied upon in performing safety analyses of systems important to safety at Comanche Peak. Number 2 is an earlier version of Number 3. Only Number 3 was used at Comanche Peak. Number 17 was previously used in safety analyses for Comanche Peak but is no longer relied on for performing such analyses and is no longer referenced in the Comanche Peak FSAR. Number 22 is merely an informational report submitted to the NRC for that purpose only.

Topical Report Numbers 3, 9,13,14,15 and 18 do not introduce new computer codes for NRC review and do not present justification for the validity of any particular code. These topical reports present infor-

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mation, provide bases or describe analyses which have been accepted by the NRC Staff. The uses for which Topical Report Numbers 3, 9, 13, 14, 15 and 18 were employed in the Comanche Peak FSAR are described in FSAR Sections 5.2, 5.4,15.2,15.3, 4.2 and 4.2, respectively.

Further, Number 7 was employed to generate the mass / energy data present in FSAR Section 6.2.1.

9 w, William R. Spezialetti i

Subscribed and sworn to before me this 19th day of January 1982.

l i j A l_ Notary P0bT1 4

Educational and Professional Qualifications WILLIAM R. SPEZIALETTI MANAGER - DOMESTIC LICENSING TECHNOLOGY NUCLEAR TECHNOLOGY DIVISION My name is William R. Spezialetti. My business address is Westinghouse Electric Corporation, P. O. Box 355, Pittsburgh, Pennsylvania 15230. I am employed as Manager, Domestic Licensing Technology at the Nuclear Technology Division for Westinghouse Elec-tric Corporation and I have served in this capacity since December 1979. I am one of the individuals responsible for directing the development of technical information for nuclear power plant docu-mentation and interfacing with utilities during the plant licensing process.

I was graduated from the Pennsylvania State University in 1966 with a B.S. Degree in Mechanical Engineering. I have also received a M.S. Degree in Mechanical Engineering from Rensselaer Polytechnic Institute in 1970.

Since 1973 I have been with Westinghouse Electric Corporation, where I have been involved directly in the field of nuclear power plant licensing and project management functions.

I am a member of the Atomic Industrial Forum Subcommittee on Standardization.

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