ML20141B585

Forwards SER in Which Staff Accepts for Referencing Topical Rept EMF-1125(P) Submitted by Siemens Power Corp on 951130

ML20141B585
Person / Time
Issue date:	05/09/1997
From:	Holahan G NRC (Affiliation Not Assigned)
To:	Martin T NRC (Affiliation Not Assigned)
Shared Package
ML20141B591	List: ML20141B585 ML20141B596 ML20141B601
References
NUDOCS 9705150346
Download: ML20141B585 (4)

Text

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MEMORANDUM T0: Thomas T. Martin, Acting Associate Director for Technical Review

. Office of Nuclear Reactor Regulation FRON: Gary M. Holahan, Director / original signed by/

Division of Systems Safety and Analysis Office of Nuclear Reactor Regulation THROUGH: James E. Lyons, Acting Chief / original signed by/

Reactor Systems Branch Division of Systems Satety and Analysis Office of Nuclear Reactor Regulation

SUBJECT:

WAIVER OF CRGR REVIEW FOR FMF-1125(P), SUPPLEMENT 1 APPENDIX C, "ANFB CRITICAL POWER CORRELATION APPLICATION FOR CO-RESIDENT FUEL"

REFERENCES:

Memorandum from E. L. Jordan to T. E. Murley, "CRGR Consideration of Topical Report 4," September 29, 1989.

Attached L the safety evaluation s peri / G ) prepared by the Division of Systems Setetj and Analysis, in whi:h tha staff accepts for referencing the Topical Report EMF-ll25(P). This bpical report was submitted by the Siemens Power Corporation (SPC) in a letter dated November 30, 1995.

EMF-1125(P) describes the analyses conducted by the SPC pertaining to the use of additive constants to treat the changes in critical power performance due to changes in design features between assembly types. The additive constants for SPC fuel are determined based on test data according to the NRC approved procedures described in Reference 1. The additive cc.stants for the co-resident fuel are determined by a statistical method described in the attached SER.

The uncertainties associated with these additive constants are then used in the approved SPC safety limit methodology to assure that less than 0.1 percent i of the fuel rods are in boiling transition during steady state operation and anticipated operational occurrences.

According to its charter, CRGR should review each staff approval of topical i reports. However, the staff believes that CRGR review is not necessary l because EMF-1125(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

/ original signed by/ -

Thomas T. Martin yh ' f O b*

)

Approad: CRGR review is not necessary CONTACT: A. Attard, SRXB/DSSA l 415-2876 j u l l

DISTRIBUTION: File Center PDR SRXB R/F GHolahan JLyons j l MChatterton KBohrer JConran MRdriguez AAttard R/F AAttard 1 D CUMENT NAME: G:\SIEMSMXF. TOP 3 5004 3*See previous concurrences l i

SRXB:DSSA SRXB:DSSA SRXB:DSSA D:DSSA ADT:NRR  ;

AATTARD* MCHATTERTON* JELYONS* GHOLAHAN* TTMartin* I

., 2/5/97 2/6/97 2/13/97 5/8/97 5/9 /97 . - - .

97@5150346 970509 'FICIAL RECORD COPY my MC

-_--kiOkRE O )E 97Y7 b- ------ --- - _ - _

," MEMORANDUM T0: Thomas T. Martin, Acting Associate Director ,

for Technical Review i

- Office of Nuclear Reactor Regulation j l

FROM: Gary M. Holahan, Director .

Division of Systems Safety and Analysis l Office of Nuclear Reactor Regulation

^

THROUGH: James E. Lyons, Acting Chief Reactor Systems Branch ,

Division of Systems Safety and Analysis Office of Nuclear Reactor Regulation ~ l

\ z' i

SUBJECT:

WAIVER OF CRGR REVIEW FOR EMF-1125(P), SUPPLEMENT 1 APPENDIX C, "ANFB CRITICAL POWER CORRELATION APPLICATION FOR .

CO-RESIDENT FUEL" / l

/

REFERENCES:

Memorandum from E. L. Jordsn to T. E. Murley, "CRGR i Consideration of Topical _' Reports," September 29, 1989.

Attachedisthesafetyevaluationrehrt(SER)preparedbytheDivisionof Systems Safety and Analysis, in which the staff accepts for referencing the Topical Report EMF-ll25(P). 'This' topical report was submitted by the Siemens Power Corporation (SPC) in a letter dated November 30, 1995.

EMF-ll25(P) describes the anal'yses conducted by the SPC pertaining to the use of additive constants to treat the changes in critical power performance due to changes in design features between assembly types. These additive constants are determined based on test data according to the NRC approved procedures described in Reference 1.

The uncertainties associated with these. additive constants are then used in the approved SPC safety, limit methodology to assure that less than 0.1 percent of the fuel rods are in' boiling transition.during steady state operation and anticipated operational occurrences. \,

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-ll25(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.

E

Attachment:

As stated Ihgmas-T. Martin N Approved: CRGR review is not necessary <

s CONTACT: A. Attard, SRXB/DSSA 415-2876 \

DISTRIBUTION: File Center PDR SRXS R/F GHolahan s JLyons MChatterton KBohrer JConran MRdriguez AAttard R/F 4Attard

\

DOCUMENT NAME: G:\SIEMSMXF. TOP \ ,

• See previous concurrences \

SRXB:DSSA SRXB:DSSA SRXB:DSSA D:DSSA ADT NRR AATTARD* McHATTERTON* JELYONS* GHOLAHAN*

TT \

j'//97rtinh}jl)x 2/5/97 -

2/6/97 2/13/97 5/8/97 5/ ,(l N OFFICIAL RECORD COPY \x

~

MEMORANDUM TO: Thomas T. Martin, Acting Asscciate Director for Tcchnical Review

. Office of Nuclear Reactor Regulation FROM: Gary M. Holahan, Director i Division of Systems Safety and Analysis Office of Nuclear Reactor Regulation James E. Lyons, Acting Chief

/

THROUGH:

Reactor Systems Branch f ,

Division of Systems Safety and Analysis Officce of Nuclear Reactor Regulation

SUBJECT:

WAIVEROFCRGRREVIEWFOREMF-1125(P), SUPPLEMENT /1 APPENDIX C, "ANFB CRITICAL POWER CORRELATION APPLICATION FOR C0-RESIDENT FUEL"

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 the staff accepts for referencing the Topical Report EMF-ll25(P). This topical report was/ submitted by the Siemens  ;

Power Corporation (SPC) in a letter dated November,30,1995.

EMF-1125(P) describes the analyses conducted by t e SPC pertaining to the use of additive constants to treat the changes in cr'itical power performance due to changes in design features between assembly /types. These additive constants are determined based on test data according to the NRC approved procedures described in Reference 1. /

j The uncertainties associated with these a ditive constants are then used in I the approved SPC safety limit methodology to assure that less than 0.1 percent of the fuel rods are in boiling transition during steady state operation and anticipated operational occurrences./

/

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-1125(P) does not p'rssent 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  ;

l l Thomas T. Martin  !

Approved: CRGR review is not necessary CONTACT: A. Attard, SRXB/DSSA 415-2876 DISTRIBUTION: File Center PDR SRXB R/F GHolahan JLyons l MChatterton KBohrer- JConran MRdriguez AAttard R/F AAttard  !

DOCUMENT NAME: G:\SIEMSMXF. TOP

• See previous concurrences y SRXB:DSSA SRXB:DSSA SRXB:DSSA :DSSA4 ADT:NRR I AATTARD* MCHATTERTON* JELYONS* 0LAHA TTMartin

-2/5 /97 2/6/97 2/13/97 0FFICIAL RECORD COPY 5/ ,'%/97 5/ /97 i

MEMORANDUATO:y Brian W. Sheron, Acting Associate Director s for Technical Review ,

\

x Office of Nuclear Reactor Regulation /

\ ,

FROM- \ ary G M. Holahan, Director Division of Systems Safety and Analysis /

/

Office of Nuclear Reactor Regulation p

/

SUBJECT:

WAIVER OF CRGR REVIEW FOR EMF-ll25(P), SUPPLEMENT l' APPENDIX C, "ANFB Critical Power Correlation App /lication for Co-Resident Fuel". -

, /

REFERENCES:

Memorandhm from E. L. Jordan to T. E. Murley( "CRGR Consideration of Topical Reports", September 29, 1989.

Attached is the safety evaldation report (SER) prepared'by the Division of Safety and Analysis, in whichsthe staff accepts for referencing the Topical Report EMF 1125(P). This Topical Report was submitted by the Siemens Power Corporation (SPC) in a letter dated November 30, 1995.

> /

EMF-ll25(P) describes the analyse's conducted by/the Siemens Power Corporation (SPC) pertaining to the use of additive constants to treat the changes in critical power performance due to changes irVdesign features between assembly types. These additive constants are determined based on test data according to the NRC approved procedures described'in, Reference 1.

Theuncertaintiesassociatedwiththes[additiveconstantsarethenusedin the approved SPC safety limit methodology 1to assure that less than 0.1% of the fuel rods are in boiling transition'during' steady state operation and anticipated operational occurrences.  ;

x According to its charter, CRGRIhould review e~ach staff approval of topical reports. However, the staff, believes that CRGR' review is not necessary because EMF-ll25(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 '

Approved: CRGR review is not necessary i CONTACT: A. Attard, SRXB/DSSA N

.415-2876 DISTRIBUTION: File Center PDR SRXB R/F BSheron GHolafian JLyons MChatterton KBohrer JCor ran MRdriguez AAttard R/f

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