ML20236Q282
| ML20236Q282 | |
| Person / Time | |
|---|---|
| Issue date: | 07/13/1998 |
| From: | Essig T NRC (Affiliation Not Assigned) |
| To: | Curet H SIEMENS POWER CORP. (FORMERLY SIEMENS NUCLEAR POWER |
| Shared Package | |
| ML20236Q285 | List: |
| References | |
| PROJECT-702 TAC-M98478, NUDOCS 9807200141 | |
| Download: ML20236Q282 (4) | |
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," p guag g p t UNITED STATES j
- ! NUCLEAR REGULATORY COMMISSION g e WASHINGTON, D.C. 30666 0001
%, . . . . . p' July 13,1998 l
Mr. H. Donald Curet, Manager Product Licensing Siemens Power Corporation 2101 Hom Rapids Road P.O. Box 130 Richland, WA 99352-0130 J
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SUBJECT:
ACCEPTANCE FOR REFERENCING OF LICENSING TOPICAL REPORT ANF-1125(P), SUPPLEMENT 1, APPENDIX D, "ANFB CRITICAL POWER CORRELATION UNCERTAINTY FOR LIMITED DATA SETS" (TAC NO. 98478) i
Dear Mr. Curet:
The staff has reviewed the subject report submitted by Siemens Power Corporation (SPC) by letter of April 18,1997. This report provides the description of a statistical method to estimate the variance of a hypotheticallarger data set using the observed variance of the existing limited data set for the ATRIUM-9 fuel. Since the report was submitted, additional ATRIUM-98 test data has been acquired and analyzed. Based on this data, the staff determined that the methodology described in this topical report is not applicable to the ATRIUM-9B design.
Therefore, the staff reviewed the report for use for the ATRIUM-9X fuel only. The staff has found the report to be acceptable for referencing in license applications for ATRIUM-9X fuel only, to the extent specified and under the limitations stated in the U.S. Nuclear Regulatory Commission (NRC) safety evaluation. The evaluation defines the basis for acceptance of the report. For the ATRIUM-9B fuel, the interim Additive Constant Uncertainty value of 0.029 should continue to be used until a new value has been approved by the NRC staff.
The staff will not repeat its review of the matters described in the SPC Topical Report ANF-1125(P), Supplement 1 Appendix D, when the report appears as a reference in license applications, except to ensure that the material presented applies to the specific plant involved. I NRC acceptance applies only to the matters described in the SPC Topical Report ANF-1125(P), 1 Supplement 1, Appendix D. In accordance with procedures established in NUREG-0390, the NRC requests that SPC publish accepted versions of the submittal, proprietary and non-proprietary, within 3 months of receipt of this letter. The accepted versions shall incorporate this letter and the enclosed evaluation between the title page and the abstract and an -A I (designating accepted) following the report identification symbol.
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Mr. H. Donald Curet 2 July 13,1998 i
If the NRC's criteria or regulations change so that its conclusion that the submittal is acceptable are invalidated, SPC and/or the applicant referencing the topical report will be expected to revise and resubmit its respective documentation, or submit justification for the continued applicability of the topical report without revision of the respective documentation.
Sincerely, FrancisAkstulewizfor/
Thomas H. Essig, Acting Chief Generic issues and Environmental Branch Division of Reactor Program Management Office of Nuclear Reactor Regulation
Enclosures:
- 1. ANF-1125(P), Supplement, Appendix D, evaluation
- 2. Technical Evaluation Report from PNNL Project No. 702 Distribution:
Hard Coov E-Mail Central File B. Sheron E. Wang PUBLIC G. Holahan J. Birmingham PGEB r/f B. Boger SRXB r/f J. Roe T. Essig T. Collins T. Huang E. Weiss OGC M. Chatterton ACRS F. Akstulewicz DOCUMENT NAME: G:ULB\10179R2.SER d OFFICE PGEB/NRR n o SC:PG ,/h AC:htjR,[
l NAME JBirmingha[ FAksfuleNd TEssihh[ !
DATE 07// J /98 07/h /98 07/ [ /98 j t
2 ;
Mr. H. Donald Curet 2 July 13,1998 4
If the NRC's criteria or regulations change so that its conclusion that the submittal is acceptable are invalidated, SPC and/or the applicant referencing the topical report will be expected to revise and resubmit its respective documentation, or submit justification for the continued applicability of the topical report without revision of the respective documentation.
. Sincerely, 1 ) s7
&u.-v 'f l omas H. Essig, Acting Chief Generic issues and Environ $tal Branch Division of Reactor Program Management Office of Nuclear Reactor Regulation
Enclosures:
- 1. ANF-1125(P), Supplement, Appendix D, evaluation
- 2. Technical Evaluation Report from PNNL Project No. 702 l
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Mr. H. Donald Curet 2 July 13,1998 If the NRC's criteria or regulations change so that its conclusion that the submittal is acceptable are invalidated, SPC and/or the applicant referencing the topical report will be expected to revise and resubmit its respective documentation, or submit justification for the continued applicability of the topical report without revision of the respective documentation.
Sincerely, ;
FrancisAkstulewizfor/
1 Thomas H. Essig, Acting Chief )
Generic issues and Environmental Branch Division of Reactor Program Management Office of Nuclear Reactor Regulation
Enclosures:
- 1. ANF-1125(P), Supplement, Appendix D, evaluation
- 2. Technical Evaluation Report from PNNL 1 Project No. 702 !
Distribution:
Hard Copy E-Mail Central File B. Sheron E. Wang PUBLIC G. Holahan J. Birmingham PGEB r/f B. Boger SRXB r/f J. Roe T. Essig T. Collins T. Huang E. Weiss OGC M. Chatterton I ACRS F. Akstulewicz DOCUMENT NAME: G:\JLB\10179R2.SER s OFFICE PGEB/NRR , , ,, SC:PGFflM) AC: Mtyt[
NAME JBirmingha[ FAksfuIeNd TEssig/[b DATE 07// J /98 07//3 /98 07/h//98 2
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