ML20248L703

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Summary of 980311 Meeting W/Siemens Power Corp in Rockville, MD to Present to Staff New Additive Constants for Use W/Advanced Nuclear Fuel for Boiling Water Reactors to Operate Unit 2 Cycle 16 W/Atrium 9B Fuel
ML20248L703
Person / Time
Issue date: 03/18/1998
From: Wang E
NRC (Affiliation Not Assigned)
To: Essig T
NRC (Affiliation Not Assigned)
References
PROJECT-702 NUDOCS 9803240090
Download: ML20248L703 (109)


Text

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UNITED STATES 3

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NUCLEAR REGULATORY COMMISSION -

2 WASHINGTON, D.C. 20066 4 001

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March 18, 1998 MEMORANDUM TO:

Thomas H. Essig, Acting Chief 3

Generic issues and Environmental Projects Branch j

Division of Reactor Program Management l

Office of Nuclear Reactor Regulation j

FROM:

Egan Wang, Reactor Engineer Generic issues and Regulatory improvements Section Generic issues and Environmental Projects Branch Division of Reactor Program Management Office of Nuclear Reactor Regulation

SUBJECT:

SUMMARY

OF MEETING HELD ON MARCH 11,1998 WITH SIEMENS TO DISCUSS ISSUES RELATED TO ANFB APPLICATION TO D2C16 WITH ATRIUM -98 On March 11,1998, the staff held a public meeting with Siemens Power Corporation (SPC) at NRC headquarters in Rockville, Maryland. The purpose of this meeting was to present to the staff new additive constants for use with advanced nuclear fuel for boiling water reactors (ANFB) to operate Dresden Unit 2 Cycle 16 (D2C16) with Atrium -9B fuel. Most material presented during this meeting was proprietary. Attachment i lists meeting participants. provides a set of ncn-proprietary slides presented by SPC daring the meeting.

During an NRC inspection conducted in February and March of 1997, the NRC inspectors identified a nonconformance condition because of insufficient number of testing points and inadequate range of conditions, and concluded that SPC had failed to justify the uncertainty values for the additive constants used in Atrium 5-9B fuel (Inspection Report 99900081/97-01).

The SPC representatives also stated that SPC was committed to additional Atrium -9B tests including a complete range of independent variables and axial effects testing (cosine, upskew, and downskew). These testing are scheduled to be completed this month. The SPC representatives stated that the current data set contained five times more data points (mostly upskew and cosine data) than the original data set.

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SPC completed upskew tests on February 23,1998. The preliminary data and analysis showed the results were nonconservative with current additive constants. A revised additive constant uncertainy has been established for Atrium 5-9B designs. Cosine testing has also been completed, which covered complete range of independent variables. Based on the results SPC indicated that the code's predictions were acceptable. SPC's operational assessment recommended administrative plant actions that address minimum critical power ratio (MCPR) ' @t/

operating margins on Atrium *-9B fuels while results are further evaluated, q

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l.T T. Essig ' March 18, 1998 The SPC representatives also discussed D2C16 licensing approaches. SPC has submitted ANFB-1125, Supplement 1 Appendix D,"ANFB Critical Power Correlation Uncertainty for

Limited Data Sets," to be reviewed by the NRC staff. The planned approach was to use new additive constants based on all Atrium -9B test data and ANFB-1125, Supplement 1, l

Appendix D methodology for uncertainty. As a contingency approach, Commonwealth Edison Company (Comed) would submit a Technical Specifications amendment iequest by March 13, 1998, in support of D2C16.

The NRC staff commented that the schedule for safety evaluation report (SER) approval of l

ANFB-1125, Supplement 1, Appendix D methodology for uncertainty is still uncertain. This SER will have to be approved by NRC management and obtain a waiver from a review by the Committee to Review Generic Requirements (CRGR). The staff did not see any technical problem with ANFB-1125, Appendix D methodology for uncertainty; however, the staff indicated that SPC and Comed may consider both licensing approaches for D2C16.

Attachments: As stated Project No. 702 cc:

Mr. H. Don Curet Product Licensing

- Siemens Power Corporation j

2101 Horn Rapid Road P.O. Box 130 Richland, Wash ngton 99352-0130 l

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i-

T. Essig 2

March,18, 1998 I

The SPC representatives a'so discussed D2C16 licensing approaches. SPC has submitted ANFB-1125, Supplement 1 Appendix D, "ANFB Critical Power Correlation Uncertainty for Limited Data Sets," to be reviewed by the NRC staff. The planned approach was to use new additive constants based on all Atrium -9B test data and ANFB-1125, Supplement 1 Appendix D methodology for uncertainty. As a contingency approach, Commonwealth Edison Company (Comed) would submit a Technical Specifications amendment request by March 13, 1998, in support of D2C16.-

l The NRC staff commented that the schedule for safety evaluation report (SER) approval of ANFB-1125, Supplement 1, Appendix D methodology for uncertainty is still uncertain. This SER will have to be approved by.NRC management and obtain a waiver from a review by the Committee to Review Generic Requirements (CRGR). The staff did not see any technical problem with ANFB-1125, Appendix D methodology for uncertainty; however, the staff indicated that SPC and Comed may consider both licensing approaches for D2C16.

i l

Attachments: As stated Project No. 702 i

cc:

Mr. H. Don Curet Product Licensing Siemens Power Corporation 2101 Hom Rapid Road 3

P.O. Box 130 Richland, Washington 99352-0130 l

Attachments: As stated l

Project No. 702 cc:

Mr. Don Curet Product Licensing Siemens Power Corporation 2101 Hom Rapid Road l

P.O. Box 130 Richland, Washington 99352-0130 DISTRIBUTION: See attach page Document name: G:\\980311MT. SUM

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List of Attendees Name Organization Phone Number 1

Egan Wang USNRC 301-415-1076 Tony Ulses USNRC 301-415-1194 i

Edward Kendrick USNRC 301-415-2891 Michael Garret SPC 509-375-8294 Adelmu Pallotta Com Ed 630-663-3021 l

Larry Rossbach USNRC 301-415-2863 l

Bob Pulsifer USNRC 301-415-3016 P,obin Feuerbacher SPC 509-375-8267 James Mallay SPC 509-375-8757 Vern Hodge USNRC 301-415-1861 Daniel Denver SPC 509-375-8395 Richard Collingham SPC 509-375-8392 l

Tai Huang USNRC 301-415-2867 Tony Futis Comed-630-663-7292 Terrance Rieck Comed 630-663-7687 Tom Keheley SPC 509-375-8702 Bob Rybak Comed 630-663-7286 l

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WASHINGTON, D.C. 30eeHoot s

March 18. 1998 MEMORANDUM TO:

Thomas H. Essig, Acting Chief Generic Issues and Environmental Projects Branch Division of Reactor Program Management Office of Nuclear Reactor Regulation FROM:

Egan Wang, Reactor Engineer Generic issues and Regulatory improvements section i

Generic issues and Environmental Projects Branch

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Division of Reactor Program Management j

Office of Nuclear Reactor Regulation j

SUBJECT:

SUMMARY

OF MEETING HELD ON MARCH 11,1998 WITH SIEMENS TO DISCUSS ISSUES RELATED TO ANFB APPLICATION TO D2C16 WITH ATRIUM *-9B On March 11,1998, the staff held a public meeting with Siemens Power Corporation (SPC) at NRC headquarters in Rockville, Maryland. The purpose of this meeting was to present to the staff new additive constants for use with advanced nuclear fuel for boiling water reactors (ANFB) to operate Dresden Unit 2 Cycle 16 (D2C16) with Atrium -9B fuel. Most material presented during this meeting was proprietary. Attachment i lists meeting participants. provides a set of non-proprietary slides presented by SPC during the meeting.

During an NRC inspection conducted in February and March of 1997, the NRC inspectors identified a nonconformance condition because of insufficient number of testing points and inadequate range of conditions, and concluded that SPC had failed to justify the uncertainty values for the additive constants used in Atrium -9B fuel (Inspection Report 99900081/97-01).

The SPC representatives also stated that SPC was committed to additional Atrium -9B tests including a complete range of independent variables and axial effects testing (cosine, upskew, and downskew). These testing are scheduled to be completed this month. The SPC representatives stated that the current data set contained five times more data points (mostly upskew and cosine data) than the original data set.

SPC completed upskew tests on February 23,1998. The preliminary data and analysis showed the results were nonconservative with current additive constants. A revised additive constant uncertainty has been established for Atrium -98 designs. Cosir's testing has also been completed, which covered complete range of independent variables. Based on the results SPC indicated that the code's predictions were acceptable. SPC's operational assessment recommended administrative plant actions that address minimum critical power ratio (MCPR) operating margins on Atrium -98 fuels while results are further evaluated.

{

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a T. Essig March 18, 1998 l

The SPC representatives also discussed D2C16 licensing approaches. SPC has submitted ANFB-1125, Supplement 1 Appendix D, *ANFB Critical Power Correlation Uncertainty for Limited Data Sets," to be reviewed by the NRC staff. The planned approach was to use new additive constants based on all Atrium -98 test data and ANFB-1125, Supplement 1, Appendix D methodology for uncertainty. As a contingency approach, Commonwealth Edison Company (Comed) would submit a Technical Specifications amendment request by March 13, 1998, in support of D2C16.

1 The NRC staff commented that the schedule for safety evaluation report (SER) approval of ANFB-1125, Supplement 1, Appendix D methodology for uncertainty is still uncertain. This SER will have to be approved by NRC management and obtain a waiver from a review by the Committee to Review Generic Requirements (CRGR). The staff did not see any technical problem with ANFB-1125, Appendix D methodology for uncertainty; however, the staff indicated that SPC and Comed may consider both licensing approaches for D2C16.

Attachments: As stated Project No. 702 cc:

Mr. H. Don Curet l

Product Licensing l

Siemens Power Corporation i

2101 Horn Rapid Road P.O. Box 130 Richland, Washington 99352-0130 l

I I

l l

l l

t

T T. Essi9

-2 Match 18, 1998 The SPC representatives also discussed D2C16 licensing approaches. SPC has submitted ANFB-1125, Supplement 1 Appendix D, "ANFB Critical Power Correlation Uncertainty for Limited Data Sets," to be reviewed by the NRC staff. The planned approach was to use new additive constants based on all Atrium"-9B test data and ANFB-1125, Supplement 1 Appendix D methodology for uncertainty. As a conthigency approach, Commonwealth Edisor:

Company (Comed) would submit a Technical Specifications amendment request by March 13, 1998,in support of D2C16.

The NRC staff commented that the schedule for safety evaluaticn report (SER) approval of ANFB-1125, Supplement 1, Appendix D methodology for uncertainty is still uncertain. This SER will have to be approved by NRC management and obtain a waiver from a review by the Committee to Review Generic Requirements (CRGR). The staff did not see any technical problem with ANFB-1125, Appendix D methodology for uncertainty; however, the staff indicated that SPC and Comed may consider both licensing approaches for D2C16.

Attachments: As stated Project No. 702 cc:

Mr. H. Don Curet Product Licensing Siemens Power Corporation 2101 Hom Rapid Road P.O. Box 130 l

Richland, Washington 99352-0130 Attachments: As stated' Project No. 702 cc:

Mr. Don Curet Product Licensing Siemens Power Corporation 2101 Hom Rapid Road P.O. Box 130 Richland, Washington 99352-0130 DISTRIBUTION: See attach page Document name: G:\\980311MT. SUM j

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l List of Attendees Name Organization Phone Number Egan Wang USNRC 301-415-1076 Tony Ulses USNRC 301-415-1194 Edward Kendrick USNRC 301-415-2891 Michael Garret SPC 509-375-8294 Adelmu Pallotta Com Ed 630-663-3021 Larry Rossbach USNRC 301-415-2863 Bob Pulsifer USNRC 301-415-3016 Robin Feuerbacher SPC 509-375-8267 James Mallay SPC 509-375-8757

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USNRC 301-415-2867 Tony Futis Comed 630-663-7292 Terrance Rieck Comed 630-663-7687 Tom Keheley SPC 509-375-8702 Bob Rybak Comed 630-663-7286

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