ML20236S035
| ML20236S035 | |
| Person / Time | |
|---|---|
| Issue date: | 07/17/1998 |
| From: | Holahan G NRC (Affiliation Not Assigned) |
| To: | Sheron B NRC (Affiliation Not Assigned) |
| Shared Package | |
| ML20236S037 | List: |
| References | |
| NUDOCS 9807240094 | |
| Download: ML20236S035 (2) | |
Text
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WASHINGTON, D.C. 20M1 July 17, 1998 MEMORANDUM TO: Brian W. Sheren, Acting Associate Director for Technical Review Office of Nuclear Reactor Regulation FROM:
Gary M. Holahan, Director Division of Systems Safety and Analysis Office of Nuclear Reactor Regulation
SUBJECT:
WAIVER OF CRGR REVIEW FOR EMF-1997(P), REVISION 0, "ANFB-10 CRITICAL POWER CORRELATION," AND EMF-1997(P) SUPPLEMENT 1, REVISION 0, "ANFB-10 CRITICAL POWER CORRELATION: HIGH LOCAL PEAKING RESULTS"
Reference:
Memorandum from E.L. Jordan to T.E. Murley, "CRGR Consideration of Topical Reports," September 29,1989 Attached is the safety evaluation report (SER) prepared by the Division of Systems Safety and Analysis, in which the staff accepts for referencing the Topical Reports EMF-1997(P), Revision 0, "ANFB-10 CRITICAL POWER CORRELATION," and EMF-1997(P) Supplement 1, Revision 0, "ANFB-10 CRITICAL POWER CORRELATION:
HIGH LOCAL PEAKING RESULTS." These topical reports were submitted by the Siemens Power Corporation (SPC) by letters dated October 30,1997, and January 29, 1998.
r These reports describe the analyses conducted by SPC pertaining to the application of the ANFB-10 critical power correlation to the ATRIUM-10 fuel design. The ATRIUM-10 fuel design consists of a 10x10 square array fixed at axial locations by ULTRAFLOW spacers and using an internal square water canister, replacing a 3x3 array of rods. The 10x10 array contains 83 full-length rods and 8 part-length rods.
The ANFB-10 correlation is very similar to the original ANFB correlation that is also used to predict critical heat flux for assemblies with only full-length rods. The ANFB-10 correlation uses enthalpy, pressure, and planar average values of coolant mass velocity, to predict planar average critical heat flux.
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CONTACT:
A. Attard, SRXB/DSSA 4o) 415-2876 I
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Brian W. Sheron 2
' According to its charter, CRGR should review each staff approval of topical reports.
However, the staff believes that CRGR review is not necessary because EMF-1997(P) and its supplement do not present a new staff position if you agree that a CRGR review is not necessary, please so indicate by signing below. Otherwise, the staff will prepare an appropriate CRGR package.
Attachment:
As stated
/ original signed by Brian Sheron/
Brian W. Sheron Approved: CRGR review is not necessary DISTRIBUTION: FildCenter PDR SRXB R/F GHolahan JLyons MChatterton TCarter JCONRAN MRodriguez AAttard R/F AATTARD DLurie DOCUMENT NAME: G:\\ANFB-10. top
- See previous concurrence SRXB:DSSA OCFO:DBA SRXB:DSSA SRXB:DSSA D: DSS AATTARD*
DLURIE*
MCHATTERTON TCOLLINS*
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BWS RON 7/l(p /98 OFFICIAL RECORD COPY ky n(D 1
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