ML20217K046
| ML20217K046 | |
| Person / Time | |
|---|---|
| Issue date: | 10/15/1999 |
| From: | Stewart Bailey NRC (Affiliation Not Assigned) |
| To: | Joseph Kelly BABCOCK & WILCOX CO., FRAMATOME |
| Shared Package | |
| ML20217K053 | List: |
| References | |
| PROJECT-693 TAC-M93346, NUDOCS 9910260034 | |
| Download: ML20217K046 (2) | |
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NUCLEAR REGULATORY-COMMISSION
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.-October 15, 1999 N Mri J. J. Kelly, Manager' [
' P. O, Box 10935 f
- Lynchburg, VA124506-0935
SUBJECT:
SAFETY EVALUATION OF TOPICAL REPORT BAW-10193P, "RELAP5/ MOD 2-B&W FOR SAFETY ANALYSIS OF B&W-DESIGNED
- PWRS" (TAC NO. M93346)
Dear Mr. Kell'y:
The U.S. Nuclear Regulatory Commission (NRC) has completed its raview of the subject topical report that was submitted by Framatome Technologies, formerly B&W Nuclear Technologies, 1
7
- by letter dated August 14,1995. The intent of the submittal was to use the RELAP5/ MOD 2-B&W computer code to perform future non-loss-of-coolant accident (non-LOCA) safety -
analyses on B&W-designed pressurized-water reactors (PWRs), replacing two previously
. approved non-LOCA codes,- CADDS and TRAP 2.L The topical report presented benchmarks of RELAP5/ MOD 2-B&W calculations to data from test facilities and plant transients, as well as.
, comparisons to CADDS and TRAP 2 predictions, to demonstrate that RELAP5/ MOD 2-B&W properly predicts the phenomena exhibited by B&W-designed PWRs during non-LOCA events.
- The staff finds that the subject topical report is acceptable for referencing in licensing
- applications to the extent specified and under the limitations delineated in the report and in the associated NRC safety evaluation. The safety evaluation, which is enclosed, defines the basis
< for acceptance of the topical report. This closes the staff's efforts on TAC No. M93346.
The staff will not repeat its review of the matters described in the subject report, when the report bppears as a reference in license applications, except to ensure that the material
- presented applies to the' specific plant involved. In accordance with the procedures established
- in _NUREG-0390, the NRC requests that Framatome Technologies publish' accepted versions of
- the' submittal, proprietary and non-proprietry, within 3 months of receipt of this letter.' The i accepted versions'shall incorporate (1) this letter and the enclosed safety evaluation between l
- the title page and the abstract, and (2) an."A".(designating " accepted") following the report -
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. lf'the NRC's criteria or regulations change so that its conclusions about the acceptability of the report are :.walidated, Framatome Technologies or the applicant refe b, 9 or f
will be expected to revise and resubmit its respective documentation, or su P
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. J. J. Kelly F-the continued effective applicability of the report without revision of the respective documentation.
Sincerely, Stewart N. Bailey, P anager, Section 2 Project Directorate 111 Division of Licensing Project Management Office of Nuclear Reactor Regu;: tion Project No. 693
Enclosure:
Safety Evaluation cc w/ encl:
Mr. Michael Schoppman Licensing Manager Framatome Technologies, Inc.
1700 Rockville Pike, Suite 525 Rockville, MD 20852-1631
.