ML082210454

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Additional Request for Additional Information BWROG Licensing Topical Report (LTR) NEDO-33349, Revision 1, BWR Application to Regulatory Guide 1.97 Revision 4
ML082210454
Person / Time
Site: Boiling Water Reactor Owners Group
Issue date: 08/19/2008
From: Michelle Honcharik
NRC/NRR/ADRA/DPR/PSPB
To: Coleman D
BWR Owners Group, Energy Northwest
Honcharik M, NRR/DPR/PSPBPM, 415-1774
References
NEDO-33349, Rev 1, RG-1.097, Rev. 4, TAC MD6697
Download: ML082210454 (6)


Text

August 19, 2008 Mr. Doug Coleman Chair, BWROG Energy Northwest Columbia Generating Station Mail Drop PE20 P.O. Box 968 Richland, WA 99352-0968

SUBJECT:

ADDITIONAL REQUEST FOR ADDITIONAL INFORMATION RE: BOILING WATER REACTOR (BWR) OWNERS= GROUP (BWROG) LICENSING TOPICAL REPORT (LTR) NEDO-33349, REVISION 1, BWR APPLICATION TO REGULATORY GUIDE 1.97 REVISION 4 (TAC NO. MD6697)

Dear Mr. Coleman:

By letter dated August 31, 2007, the BWROG submitted for U.S. Nuclear Regulatory Commission (NRC) staff review LTR NEDO-33349, Revision 1, BWR Application to Regulatory Guide 1.97 Revision 4. The NRC staff transmitted a request for additional information (RAI) by letter dated August 4, 2008. Based on discussions at a recent IEEE Accident Monitoring Instrumentation Working Group meeting, the NRC staff has identified one additional area where additional information is needed to complete the review. The additional RAI question is provided below. On August 12, 2008, Mr. Mike Iannantuono, Project Manager, and I agreed that the NRC staff will receive your response to the August 4, 2008, RAI questions and the additional RAI question by October 31, 2008. If you have any questions regarding the RAI question, please contact me at 301-415-1774.

1. Page 4-7 of LTR NEDO-33349, Section 4.2.2 includes a discussion of critical safety functions. Subclause 3.7 of IEEE standard 497-2002 defines five critical safety functions.

These five IEEE standard 497-2002 critical safety functions are: reactivity control, reactor core cooling, reactor coolant system integrity, primary reactor containment integrity, and radioactive effluent control. However, Section 4.2.2 only identifies four critical safety functions and these are different from the five critical safety functions that are defined in IEEE standard 497-2002.

Section 4.2.2 should be modified to address each of the five IEEE standard 497-2002 critical safety functions. The Type B key variables that provide information about each of the five IEEE standard 497-2002 critical safety functions should be clearly identified.

Sincerely,

/RA/

Michelle C. Honcharik, Senior Project Manager Special Projects Branch Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Project No. 691 cc: See next page

August 19, 2008 Mr. Doug Coleman Chair, BWROG Energy Northwest Columbia Generating Station Mail Drop PE20 P.O. Box 968 Richland, WA 99352-0968

SUBJECT:

ADDITIONAL REQUEST FOR ADDITIONAL INFORMATION RE: BOILING WATER REACTOR (BWR) OWNERS= GROUP (BWROG) LICENSING TOPICAL REPORT (LTR) NEDO-33349, REVISION 1, BWR APPLICATION TO REGULATORY GUIDE 1.97 REVISION 4 (TAC NO. MD6697)

Dear Mr. Coleman:

By letter dated August 31, 2007, the BWROG submitted for U.S. Nuclear Regulatory Commission (NRC) staff review LTR NEDO-33349, Revision 1, BWR Application to Regulatory Guide 1.97 Revision 4. The NRC staff transmitted a request for additional information (RAI) by letter dated August 4, 2008. Based on discussions at a recent IEEE Accident Monitoring Instrumentation Working Group meeting, the NRC staff has identified one additional area where additional information is needed to complete the review. The additional RAI question is provided below. On August 12, 2008, Mr. Mike Iannantuono, Project Manager, and I agreed that the NRC staff will receive your response to the August 4, 2008, RAI questions and the additional RAI question by October 31, 2008. If you have any questions regarding the RAI question, please contact me at 301-415-1774.

1. Page 4-7 of LTR NEDO-33349, Section 4.2.2 includes a discussion of critical safety functions. Subclause 3.7 of IEEE standard 497-2002 defines five critical safety functions.

These five IEEE standard 497-2002 critical safety functions are: reactivity control, reactor core cooling, reactor coolant system integrity, primary reactor containment integrity, and radioactive effluent control. However, Section 4.2.2 only identifies four critical safety functions and these are different from the five critical safety functions that are defined in IEEE standard 497-2002.

Section 4.2.2 should be modified to address each of the five IEEE standard 497-2002 critical safety functions. The Type B key variables that provide information about each of the five IEEE standard 497-2002 critical safety functions should be clearly identified.

Sincerely,

/RA/

Michelle C. Honcharik, Senior Project Manager Special Projects Branch Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Project No. 691 cc: See next page DISTRIBUTION:

PUBLIC RidsNrrDpr PSPB Reading File RidsNrrDprPspb RidsNrrLADBaxley RidsAcrsAcnwMailCenter RidsNrrPMMHoncharik RidsOgcMailCenter RidsNrrDeEicb RidsNrrDssSrxb Kevin Williams, NSIR Kathryn Brock, NSIR Barry Marcus Steve LaVie, NSIR Tai Huang Aron Lewin RidsNrrDirsItsb ADAMS ACCESSION NO.: ML082210454 *No major changes from input.

NRR-106 OFFICE PSPB/PM PSPB/LA EICB/BC PSPB/BC NAME MHoncharik DBaxley WKemper*

SRosenberg DATE 8/19/08 8/18/08 7/31/08 8/19/08 OFFICIAL RECORD COPY

BWR Owners= Group Project No. 691 Mr. Richard Libra Executive Vice Chair, BWR Owners= Group Exelon Generation Co, LLC 200 Exelon Way Mail Code KSA 2-N Kennett Square, PA 19348 Rick.libra@exeloncorp.com Mr. Richard Anderson BWROG, Executive Chair FPL Energy (DAEC)

Duane Arnold Energy Center 3277 DAEC Road Palo, IA 52324 richard_l_anderson@fpl.com Mr. James F. Klapproth GE-Hitachi Nuclear Energy M/C A50 3901 Castle Hayne Road Wilmington, NC 28401 james.klapproth@ge.com Mr. Joseph E. Conen, Vice Chair Regulatory Response Group BWR Owners= Group DTE Energy-Fermi 2 200 TAC 6400 N. Dixie Highway Newport, MI 48166 conenj@dteenergy.com Dennis Madison, Hatch Vice President Southern Nuclear Operating Co.

11028 Hatch Parkway North Baxley, GA 31515-2010 drmadiso@southernco.com Frederick Emerson BWROG, Project Manager Frederick.emerson@ge.com Mr. Ken A. McCall, Program Manager GE-Hitachi Nuclear Energy M/C F12 3901 Castle Hayne Road Wilmington, NC 28401 kenneth.mccall@ge.com Oscar Limpias Entergy Nuclear Northeast 1340 Echelon Parkway.

Jackson, MS 39213-8202 olimpia@entergy.com Joe Donahue Progress Energy Inc.

410 S. Wilmington St.

PEB 6A Raleigh, NC 27601-1849 joe.w.donahue@pgnmail.com Paul J. Davison Hope Creek Generating Station P.O. Box 236 Hancocks Bridge, NJ 08038 paul.davison@pseg.com Mr. Ted Schiffley Vice Chairman, BWROG Exelon Generation Co., LLC.

Cornerstone II at Cantera 4300 Winfield Road Warrenville, IL 60555 frederick.schiffley@exeloncorp.com Mr. Randy C. Bunt, Chair Regulatory Response Group Southern Nuclear Operating Company 40 Inverness Center Parkway/Bin B057 Birmingham, AL 35242 rcbunt@southernco.com 8/6/08