ML20117P784
Text
e O 1 2 1987 MEMORANDUM FOR:
Robert A. Capra, Project Director Project Directorate I-1 Division of Reactor Projects - I/II FROM:
M. W. Hodges, Chief Reac'/.r Systems Branch Division of Engineering & Systems Technology
SUBJECT:
SAFETY EVALUATION REPORT ON THE BG&E TOPICAL REPORT A-Sb-11 "RETRAN COMPUTER CODE REACTOR SYSTEM TRANSIENT ANALYSIS MODEL QUALIFICATION", JANUARY 31, 1986 Plant Name:
Calvert Cliffs, Units 1 and 2 Docket Nos.:
50-317 and 50-318 TAC Nos.:
60647 and 60648 Project Directorate:
Project Directorate I-1 Project Manager:
S. McNeil l
Review Branch:
SRX8/ DEST Review Status:
Complete The Reactor Systems Branch (SRXB), with aid from its technical assistance contractors at the International Technical Service, Inc. (ITS), has completed its review of the Baltimore Gas and Electric Company (BG&E) Topical Report A-85-11, "P?TRAN Computer Code Peactor System Transient Analysis Model
- i Qualification". Supplemental information was submitted by BG&E in letters dated February 24, 1987 and June 9, 1987.
We have concluded that BG&E has demonstrated in the above stated submittals, the capability to properly develop RETRAN models for Calvert Cliffs and perform best-estimate simulation of reactor system non-LOCA transients using these models. BG&E indicated in its letter dated January 31, 1986 that this analytical capability will primarily be used to support the evaluation of proposed changes and revisions to operating procedures.
It is noted that BG&E used RETRAN 02/M00 03 which was developed as a result of making corrections necessitated after the NRC staff review of the RETRAN U2/M00 02 computer code. This corrected version of the code has not been approved by the staff. Nevertheless, we believe that there is reasonable assurance that this version of the code is adequate for use in this topical report and we accept its use in the BG&E's best-estimate model.
Contact:
C. Liang, SRXB, x29459
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l Robert A. Capra BG&E should be clearly informed that its Topical Report A-8511 has been approved only for use in preforming best-estimate transient analyses for the Calvert Cliffs Nuclear Power Plant as requested by BG&E. For future licensing analyses, BG&E should submit sufficient infomation to demonstrate that the licensing calculations are performed using a plant model incorporated with appropriate conservatism to assure that uncertainties in both plant operating conditions (dealt with by modifying code input) and phenomenological models (usually dealt with by use of more conservative models in the code) are treated in each analysis in a conservative manner.
The staff's safety evaluation report for this subject review is provided in, the technical evaluation report performed by ITS is provided in, and the SRXB input for a SALP evaluation is provided in Enclosure 3.
This completes the SRXB effort under TAC Nos. 60647 and 60648.
&W%
Mpule HadIN M. W. Hodges, Chief Reactor Systems Branch Division of Engineering & Systems Technology ll
Enclosures:
As stated cc: A6 S. Varga
- 8. Boger S. McNeil H. Komoriya (ITS)
SRXB Members DISTRIBUTION N
SRXB R/F M. W. Hodges R. Jones C. Liang C. Liang R/F Calvert Cliffs P/F C :SRXB: DEST SR t
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- 8/l$/87 0FFICIAL RECORD COPY
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