ML20212M207
| ML20212M207 | |
| Person / Time | |
|---|---|
| Issue date: | 10/05/1999 |
| From: | Holahan G NRC (Affiliation Not Assigned) |
| To: | Sheronm B NRC (Affiliation Not Assigned) |
| Shared Package | |
| ML20212M211 | List: |
| References | |
| NUDOCS 9910080227 | |
| Download: ML20212M207 (3) | |
Text
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MEMORANDUM TO: Briin W. Sheron, Associata Dirzctor Octobar 5, 1999 for Proh:ct Licensing end Tcchnical Anilysis Office of Nuclar R: actor 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 EMF-2158(P), REVISION 0, "SIEMENS POWER CORPORATION METHODOLOGY FOR BOILING WATER REACTORS: EVALUATION AND VALIDATION OF CASMO-4/MICROBURN-B2"
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 Report EMF-2158(P),
Revision 0, "Siemena Power Corporation Boiling Water Reactors: Evaluation and Validation of CASMO4/MICROBURN-B2." The Siemens Power Corporation (SPC) submitted this topical report by letter dated December 30,1998.
This repod describes the SPC upgraded boiling water reactor (BWR) neutronics design code system. The new code system consists of the CASMO-4 lattice spectrum / depletion code and the MICROBURN-B2 core simulator code. CASMO-4 is an improved version of CASMO-3 and MICROBURN-B2 is an improved version of MICROBURN. The new code system replaces the existing neutronics codes used for the approved SPC boiling-water reactor (BWR) neutronic design and safety methodology.-
SPC's new code system incorporates many advanced model features, such as an improved pin I
power reconstruction method. This report establishes a set of methodology evaluation and f
validation criteria, by which a new neutronics design code, or code system would be assessed i
for application to BWR neutronics design.
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-2158(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 Brian W. Sheron
/8/
g,. g Approved: CRGR review is not necessary CONTACT: A. Attard, SRXB/DSSA. 415-2876 DISTRIBUTION:
1 File Center.
PDR SRXB R/F GHolahan DLurie f
JConran MRdriguez AAttard R/F AAttard tJ DOCUMENT NAME: G:SRXB\\CASMO4-MICROBURN-82. TOP.WPD N.6b I
OFFICE:
SRXB:DSSA SRXB:DSSA SRXB:DSSA D:DSSA AD T. RR NAME:
AATTARD*
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JWERMIEL* GHOLAHAN* BSHHWDN C4 M
/*// 'f/99 Y, g(ga DATE:
9/14/99 9/20/99 9/21/99 9/30/99
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WASHINGTON, D.C. enmaa aaa1 october 5, 1999 MEMORANDUM TO: Brian W. Sheron, Associate Director for Project Licensing and Technical Analysis Office of Nuclear Reactor Regulation
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FROM:
Gary M. Holahan, Director Division of Systems Safety and Analysi Office of Nuclear Reactor Regulation
SUBJECT:
WAIVER OF CRGR REVIEW FOR EMF-2158(P), REVISION 0, "SIEMENS POWER CORPORATION METHODOLOGY FOR BOILING WATER REACTORS: EVALUATION AND VALIDATION OF CASMO-4/MICROBURN-B2"
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 referencine *- Topical Report EMF-2158(P),
Revision 0, "Siemens Power Corporation Boiling
'eactors: Evaluation and Validation of CASMO4/MICROBURN-B2." The Siemens Power Corporation (SPC) submitted this topical report by letter dated December 30,1998.
This report describes the SPC upgraded boiling water reactor (BWR) neutronics design code system. The new code system consists of the CASMO-4 lattice spectrum / depletion code and the MICROBURN-B2 core simulator code. CASMO-4 is an improved version of CASMO-3 and MICROBURN-B2 is an improved version of MICROBURN. The new code system replaces the existing neutronics codes used for the approved SPC boiling-water reactor (BWR) neutronic design and safety methodology.
SPC's new code system incorporates many advanced model features, such as an improved pin power reconstruction method. This report establishes a set of methodology evaluation and validation criteria, by which a new neutronics design code, or code system would be assessed for application to BWR neutronics design.
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-2158(P) does not present a new stafi 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.
Attacnment: As st
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Brian W. Sheron Md
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Approved: CRGR review is not necessary CONTACT: A. Attard, SRXB/DSSA,415-2876
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WASHINGTON, D.C. 30656-0001
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' Mr. H. D. Curet, Manager Siemens Power Corporation Nuclear Division Engineering and Manufacturing Facility 2101 Horn Rapids Road Post Office Box 130 Richland, Washington 99352-0130
SUBJECT:
ACCEPTANCE FOR REFERENCING OF LICENSING TOPICAL REPORT EMF-2158(P), REVISION 0, "SlEMENS POWER CORPORATION METHODOLOGY FOR BOILING WATER REACTORS: EVALUATION AND VALIDATION OF CASMO-4/MICROBURN-82"
Dear Mr. Curet:
We have completed our review of the subject topical report the Siemens Power Corporation (SPC) submitted by letter dated December 30,1998. The 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 is enclosed. The safety evaluation defines the basis for NRC acceptance of the report.
We do not intend to repeat our review of the matters described in the report, and found acceptable when the report appears as a reference in license applications, except to ensure that the material presented is applicable to the specific plant involved. Our acceptance applies only to the matters described in the report.
In accordance with procedures established in NUREG-0390, we request that SPC publish accepted versions of this report, 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. The accepted versions shallinclude an "A" (designating accepted) following the report identification symbol.
Should our criteria or regulations change so that our conclusions about acceptability of the report are invalidated, SPC and the licensees referencing the topical report will be expected to revise and resubmit their respective documentation, or to submit justification for the continued effective applicability of the topical reports without revision of their respective documentation.
Sincerely, Stuart A. Richards, Director Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation
Enclosure:
As stated
-.