ML20206K757
| ML20206K757 | |
| Person / Time | |
|---|---|
| Issue date: | 05/08/1999 |
| From: | Holahan G NRC (Affiliation Not Assigned) |
| To: | Sheron B NRC (Affiliation Not Assigned) |
| Shared Package | |
| ML20206K759 | List: |
| References | |
| NUDOCS 9905130275 | |
| Download: ML20206K757 (2) | |
Text
May 8, 1999 MEMORANDUM TO: Bri:n W. Sharon, Assoclita Director
! for Pro #ct Lic:nsing and Technic:1 Analysis Office of Nuclear Reactor Regulation FROM: Gary M. Holahan, Director / original signed by T. Collins for/
Division of Systems Safety and Analysis Office of Nuclear Reactor Regulation-
SUBJECT:
WAIVER OF CRGR REVIEW FOR CENPD-389-P, "10X10 SVEA FUEL CRITICAL POWER EXPERIMENTS AND CPR CORRELATIONS:
SVEA-96+"
REFERENCES:
Memorandum from E. L. Jordan to T. E. Murley, "CRGR Consideration of Topical Reports," September 29,1989 Attached is the safety evaluation report (SER) prenared by the Division of Systems Safety and Analysis, in which the staff accepts for referencing the Topical Report CENPD-389-P, "10X10 SVEA FUEL CRITICAL POWER EXPERIMENTS AND CPR CORRELATIONS: SVEA-96+."
This topical report was submitted by ABB Combustion Engineering (ABB-CE) Nuclear Power Corporation by letter dated June 9,1998.
This report describes the analyses conducted by ABB-CE pertaining to the application of the critical power correlation to the SVEA-96+ fuel design. The critical power ratio (CPR) correlation for the ABB SVEA-96+ fuel is referred to as ABBD2.0. The SVEA-96+ fuel assembly design is very similar to the NRC approved SVEA-96 fuel assembly design, and each consist of four sub-bundles in a 5x5 lattice configuration with one fuel rod missing. The only difference between the SVtEA-96 and the SVEA-96+ assemblies is in the design, number, and location of the spacers.
The ABBD2.0 correlation was developed by ABB-CE for application to design and licensing -l calculations for the SVEA-96+ water cross fuel assemblies over the range of steady state and
. operational transient conditions for boiling-water reactor (BWR) plants. The ABBD2.0 correlation for the SVEA-96+ fuel is very similar to the NRC approved XL-S96 correlation for the SVEA-96 fuel.
According to its charter, CRGR should review each staff approval of topical reports. However, the staff believes that CRGR review is not necessary because the approval of CENPD-389-P ,
does 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 m /s/
Brian W. Sheron u Approved: CRGR review is not necessary h CONTACT:' A. Attard, SRXB/DSSA .
Q 415-2876 Q hi F ~M f
<fpg7 h DISTRIBUTION: File Center PDR CRXB R/F GHolahan JWermiel EWeiss
.CCarpenter AAttard *See previous concurrence DOCUMENT NAME: G:%BBCE96P. TOP -
y RD+ & A *
' J 4 (1- 7 c. R(n f(
I
- SRXB:DSSA SRXB:DSSA SRXB:DSSA D:DSSA Up A T: DRGEB: DRIP AATTARD* EWEISS* JWERMIEL* GHOLAHAN BW RON CCARPENTER
- " 5/3 /99 5/3/99 5/3/99 5/ 6/99 5/j /99 5/
/ g /99 i
} y)g Q { OFFICIAL RECORD COPY-W 4y
MEMORANDUM TO: Brirn W. Shsron, Associats Dircctor for Proj::ct Lic:;nsing & Technical Antlysis
. - Office of Nucitar Rsactor R:gul tion
\; FROM: Gary M. Holahan, Director
\ Division of Systems Safety and Analysis N-\ Office of Nucle,ar Reactor Regulation
SUBJECT:
WAIVER OF CRGR REVIEW FOR CENPD-389-P, "10X10 SVEA FUEL
\ CRITICAL POWER EXPERIMENTS AND CPR CORRELATIONS:
~\ SVEA-96+".
N REFERENCES- 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 ttle staff accepts for referencing the Topica: Report CENPD-389-P, "10X10 SVEA FUEL CRITICA.L POWER EXPERIMENTS AND CPR CORRELATIONS: SVEA-96+",
This topical report was' submitted by ABB Combustion Engineering (ABB-CE) Nuclear Power Corporation by letter dat'e d June 9,1998.
This report describes the an\alyses conducted by ABB-CE pertaining to the application of the
. critical power correlation to the SVEA-96+ fuel design. The critical power ratio (CPR) correlation for the ABB SVEA-96+sfuelis referred to as ABBD2.0. The SVEA-96+ fuel assembly design is very similar to the NRC a'pproved SVEA-96 fuel assembly design, and each consist of four sub-bundles in a 5x5 lattice configuration with one fuel rod missing. The only difference between the SVEA-96 and the SVEA-96+ assemblies is in the design, number, and location of the spacers.
The ABBD2.0 correlation was developed by ABB-CE for application to design ar'd licensing
- calculations for the SVEA-96+ water cross fuel' assemblies over the range of steady state and operational transient conditions for boiling water re, actor (BWR) plants. The ABBD2.0 correlation for the SVEA-96+ fuel is very similar to the NRC approved XL-S96 correlation for the SVEA-96 fuel.
\\
According to its charter, CRGR should review each staff a' pproval of topical reports. However, the staff believes that CRGR review is not necessary becaus,e the approval of CENPD-389-P
' does not present a new staff position. If you agree that a CRG,R review is not necessary, please
.so indicate by signing below. Otherwise, the staff will prepare ar(appropriate CRGR package.
Attachment:
As stated \
\
Brian W. - Sheron N Approved: CRGR review is not necessary K
CONTACT: A. Attard, SRXB/DSSA 4
\
415-2876 ,
4 DISTRIBUTION File Center PDR SRXB R/F GHolahan JWermiel EWeisd CCarpenter. AAttard DOCUMENT NAM - BCE
-S SA SRX D:DSSA ' ADT:NRR DRGEB:DRIPx D E JSS JWE lEL GHOLAHAN BWSHERON CCARPENTERN J /99- J/99 MJ/99 y /99 S ' /99 S /99 \
OFFICIAL RECORD COPY. N
\ n,