ML20062B309

Responds to NRC 780927 Ltr Re Benchmarking PTSBWR/2 Code Against Present Data & Verifying Transient & Stability Tests.Data to Be Supplied in Oct 1979 Will Satisfy Requests. GE Proprietary Info Must Be Provided

ML20062B309
Person / Time
Site:	Peach Bottom
Issue date:	10/19/1978
From:	Owsley G SIEMENS POWER CORP. (FORMERLY SIEMENS NUCLEAR POWER
To:	Eisenhut D Office of Nuclear Reactor Regulation
References
NUDOCS 7810270108
Download: ML20062B309 (2)

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E(ON NUCLEAR COMPANY,Inc. 1 l

2101 Horn Rapids Road P. O. Box 130. Richland. Washington 99352

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S50 October 19, 1978 Mr. Darrell G. Eisenhut Assistant Director for - Systems and Projects Division of Operating Reactors

            .                 Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission
 '         ( ""             ._1,42.0 Norfolk Avenue s -            Tethesda, Maryland 20014

Reference:

" Transient and Stability Tests at Peach Bottom Atomic Power Station Unit 2 at End of Cycle             2," EPRI NP-564, Research Project 1020-1, Topical Report, June 1978

Dear Mr. Eisenhut:

In your letter to our Warren Nechodom dated September 27, 1978, you stated your belief that ENC's PTSBWR/2 code must be benchmarked against presently available data. In particular, you referred to the Peach Bottom Atomic Power Station Unit 2 transient and stability tests reported in the reference report. In our meeting with the Staff in June 1978 to discuss j Exxon Nuclear's jet pump BWR licensing program, members of the Staff stated that verification of the PTS code used for these analyses should be based z,gn_cxperimental rather than the G.E. REDY code results. Your September 27,

          ]. _-,           ' 31bs.lstter is in substantive agreement with your recommendations at the meeting.

The PTSBWR/2 code has been used to date for external recirculation plants (nonjet-pump) only. The modeling of these plants differs in some specific aspects from the Peach Bottom plant. However, we believe that the verification with the Peach Bottom data will be equally a m licable to both the nonjet-pump and jet-pump models as the analytical tre.aent of many .

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aspects is the same for both models. Following our meeting in June, 1978, Exxon Nuclear formulated plans for completing the development, benchmark calculations, and documentation of its PTSBWR code for application to the jet pump BWRs by October 1979. In response to your recommendations in this meeting, benchmark calculations would include analysis of the Peach Bottom transient results. We believe that the information which we will submit in October 1979 will fulfill your requirements for incorporating the Peach Bottom data into the ENC PTSBhR qualification program for pressurization transients, k 7 g,p r AN AFIILIATE OF EXXON CORPORATION

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                        ,   Mr. D. G. Eisenhut (USNRC)                                     October 19, 1978                      .

We have reviewed the reference report and have found that necessary data germane to this benchmark effort have been withheld as proprietary by the General Electric Company. The missing information is the controller setpoints and gains for the following controllers: (1) feedwater flow, (2) pressure control (including steam dump), and (3) recirculating flow. In absence of this information, the scope of *he benchmark calculations to fully simulate the transient tests performed at the Peach Bottom plant will be restricted. To perform the benchmark work which you request, we will need information regarding the controller setpoints and gains. In this respect, we will be please to discuss our specific information needs with you at your convenience. If you have further comments or questions regarding this matter, please contact me directly (509-943-8241). i ' l

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