ML070670204
"Draft Meeting" is not in the list (Request, Draft Request, Supplement, Acceptance Review, Meeting, Withholding Request, Withholding Request Acceptance, RAI, Draft RAI, Draft Response to RAI, ...) of allowed values for the "Project stage" property.
| ML070670204 | |
| Person / Time | |
|---|---|
| Site: | Boiling Water Reactor Owners Group |
| Issue date: | 03/13/2007 |
| From: | Michelle Honcharik NRC/NRR/ADRA/DPR/PSPB |
| To: | Rosenberg S Office of Nuclear Reactor Regulation, NRC/NRR/ADRA/DPR/PSPB |
| Honcharik M, NRR/DPR/PSPB, 301-415-177 | |
| Shared Package | |
| ML0700670207 | List: |
| References | |
| TAC MD3430 | |
| Download: ML070670204 (7) | |
Text
March 13, 2007 MEMORANDUM TO: Stacey L. Rosenberg, Chief Special Projects Branch Division of Policy and Rulemaking Office of Nuclear Reactor Regulation FROM:
Michelle C. Honcharik, Project Manager
/RA/
Special Projects Branch Division of Policy and Rulemaking Office of Nuclear Reactor Regulation
SUBJECT:
SUMMARY
OF NOVEMBER 16, 2006, OPEN PRE-SUBMITTAL MEETING WITH THE BOILING WATER REACTOR OWNERS GROUP (BWROG) ON DRAFT LICENSING TOPICAL REPORT (LTR) BASED ON THE METHODOLOGY CONTAINED IN IEEE STANDARD 497-2002 (TAC NO. MD3430)
On November 16, 2006, a Category 2 public meeting was held between the U.S. Nuclear Regulatory Commission (NRC) staff and representatives of the BWROG at NRC Headquarters, Two White Flint North, 11545 Rockville Pike, Rockville, Maryland. The purpose of the meeting was to discuss a draft LTR which is based on the methodology contained in IEEE Standard 497-2002 for establishing accident monitoring instrumentation requirements. A list of attendees is provided as Enclosure 1.
The BWROG representatives presented an overview of the BWROG Regulatory Guide (RG) 1.97 Committee, including the purpose of the committee, the committees work scope, and future direction (see Enclosure 2). The BWROG representatives also presented an overview of the draft LTR of the BWR application to IEEE-497. This presentation included a discussion of the IEEE-497 requirements, the BWROG evaluation methodology, typical BWR variables, and application guidelines (see Enclosure 3). The BWROG representatives summarized the key results and findings from the BWROG RG 1.97 Committee activities (see ).
The NRC staff provided comments to the BWROG representatives to be addressed when preparing the LTR for submittal (see Enclosure 5). The BWROG representatives thanked the NRC staff for the feedback.
Members of the public were not in attendance.
Project No. 691
Enclosures:
- 1. List of Attendees
- 5. NRC Staff Comments cc w/encls: See next page
MEMORANDUM TO: Stacey L. Rosenberg, Chief March 13, 2007 Special Projects Branch Division of Policy and Rulemaking Office of Nuclear Reactor Regulation FROM:
Michelle C. Honcharik, Project Manager
/RA/
Special Projects Branch Division of Policy and Rulemaking Office of Nuclear Reactor Regulation
SUBJECT:
SUMMARY
OF NOVEMBER 16, 2006, OPEN PRE-SUBMITTAL MEETING WITH THE BOILING WATER REACTOR OWNERS GROUP (BWROG) ON DRAFT LICENSING TOPICAL REPORT (LTR) BASED ON THE METHODOLOGY CONTAINED IN IEEE STANDARD 497-2002 (TAC NO. MD3430)
On November 16, 2006, a Category 2 public meeting was held between the U.S. Nuclear Regulatory Commission (NRC) staff and representatives of the BWROG at NRC Headquarters, Two White Flint North, 11545 Rockville Pike, Rockville, Maryland. The purpose of the meeting was to discuss a draft LTR which is based on the methodology contained in IEEE Standard 497-2002 for establishing accident monitoring instrumentation requirements. A list of attendees is provided as Enclosure 1.
The BWROG representatives presented an overview of the BWROG Regulatory Guide (RG) 1.97 Committee, including the purpose of the committee, the committees work scope, and future direction (see Enclosure 2). The BWROG representatives also presented an overview of the draft LTR of the BWR application to IEEE-497. This presentation included a discussion of the IEEE-497 requirements, the BWROG evaluation methodology, typical BWR variables, and application guidelines (see Enclosure 3). The BWROG representatives summarized the key results and findings from the BWROG RG 1.97 Committee activities (see ).
The NRC staff provided comments to the BWROG representatives to be addressed when preparing the LTR for submittal (see Enclosure 5). The BWROG representatives thanked the NRC staff for the feedback.
Members of the public were not in attendance.
Project No. 691
Enclosures:
- 1. List of Attendees
- 5. NRC Staff Comments cc w/encls: See next page Package Accession No. ML070670207 Meeting Summary Accession No. ML070670204 Notice Accession No. ML063040048 Accession No. ML070640518 Accession No. ML070640519 Accession No. ML070640523 OFFICE PSPB/LA PSPB/PM EICB/BC PSPB/BC NAME DBaxley MHoncharik AHowe SRosenberg DATE 3/9/2007 3/9/2007 3/12/2007 3/13/2007 OFFICIAL RECORD COPY
DISTRIBUTION FOR
SUMMARY
OF MEETING ON NOVEMBER 16, 2006, WITH THE BWROG Dated: March 13, 2007 PUBLIC PSPB Reading File RidsNrrAdro RidsNrrDpr RidsNrrDprPspb RidsNrrPMMHoncharik RidsNrrLADBaxley RidsOpaMail Barry Marcus Roger Pedersen Timothy Frye George Thomas George Tartal Subinoy Mazumdar Amar Pal Gary Armstrong R. Brad Harvey Jerome Bettle Dinesh Taneja Kathryn Brock Nick Trikouros Timothy Kobetz RidsNrrDirsItsb Jim Kenney, jken@ptd.net A. Klemptner, klemptnera@dteenergy.com Wes Bowers, wesley.bowers@exeloncorp.com Ron Engel, rengel102@sbcglobal.net Robert Jasinski RidsOgcMailCenter RidsAcrsAcnwMailCenter
BWR Owners Group Project No. 691 Mr. Doug Coleman Vice Chair, BWR Owners Group Energy Northwest Columbia Generating Station Mail Drp PE20 P.O. Box 968 Richland, WA 99352-0968 DWCOLEMAN@energy-northwest.com Mr. Amir Shahkarami Executive Chair, BWR Owners Group Exelon Generation Co., LLC Cornerstone II at Cantera 4300 Winfield Road Warrenville, IL 60555 amir.shahkarami@exeloncorp.com Mr. Richard Libra Executive Vice Chair, BWR Owners Group DTE Energy - Fermi 2 M/C 280 OBA 6400 North Dixie Highway Newport, MI 48166 librar@dteenergy.com Mr. William A. Eaton Entergy Operations Inc.
P.O. Box 31995 Jackson, MS 39286 weaton@entergy.com Mr. Richard Anderson First Energy Nuclear Operating Co Perry Nuclear Power Plant 10 Center Road Perry, OH 44081 randerson@firstenergycorp.com Mr. Scott Oxenford Energy Northwest Columbia Generating Station Mail Drp PE04 P.O. Box 968 Richland, WA 99352-0968 wsoxenford@energy-northwest.com Mr. James F. Klapproth GE Energy M/C A-16 3901 Castle Hayne Road Wilmington, NC 28401 james.klapproth@gene.ge.com Mr. Joseph E. Conen Regulatory Response Group Chair BWR Owners Group DTE Energy-Fermi 2 200 TAC 6400 N. Dixie Highway Newport, MI 48166 conenj@dteenergy.com Mr. J. A. Gray, Jr.
Regulatory Response Group Vice-Chair BWR Owners Group Entergy Nuclear Northeast 440 Hamilton Avenue Mail Stop 12C White Plains, NY 10601-5029 JGray4@entergy.com Mr. Thomas G. Hurst GE Energy M/C A-16 3901 Castle Hayne Road Wilmington, NC 28401 thomas.hurst@ge.com Mr. Tim E. Abney GE Energy M/C A-16 3901 Castle Hayne Road Wilmington, NC 28401 tim.abney@ge.com Mr. Randy C. Bunt Chair, BWR Owners Group Southern Nuclear Operating Company 40 Inverness Center Parkway/Bin B057 Birmingham, AL 35242 RCBUNT@southernco.com 2/23/07
ENCLOSURE 1 Public Meeting with Boiling Water Reactor Owners Group (BWROG)
November 16, 2006 Meeting Attendees NAME ORGANIZATION Michelle Honcharik NRC Barry Marcus NRC Roger Pedersen NRC Timothy Frye NRC George Thomas NRC George Tartal NRC Subinoy Mazumdar NRC Amar Pal NRC Gary Armstrong NRC R. Brad Harvey NRC Jerome Bettle NRC Dinesh Taneja NRC Kathryn Brock NRC Nick Trikouros NRC Jim Kenney BWROG A. Klemptner DTE Enegery/BWROG Wes Bowers Exelon/BWROG Ron Engel GE/BWROG
ENCLOSURE 5 NRC Staff Comments Concerning the BWROG Pre-Submittal Meeting on the BWR Application of IEEE 497-2002 Draft Licensing Topical Report (LTR)
The draft LTR addresses IEEE 497-2002, IEEE Standard Criteria for Accident Monitoring Instrumentation for Nuclear Power Generating Stations. Since Regulatory Guide (RG) 1.97, Revision 4, Instrumentation for Light Water Cooled Nuclear Power Plants To Assess Plant and Environs Conditions During and Following and Accident, endorses, with exceptions, IEEE 497-2002, the LTR should address RG 1.97, Revision 4, and its regulatory positions.
Section 3.2, Type B Variables, of the draft LTR, addresses contingency actions. However, the only discussion of contingency actions in IEEE 497-2002 is in regard to Type A variables. This discussion of contingency actions in IEEE 497-2002 has been modified by Regulatory Position 4 of RG 1.97, Revision 4. The LTR should be revised to relocate this discussion and should take into consideration Regulatory Position 4.
The topic of compliance with industry standards that are referenced by IEEE 497-2002 is addressed generically in the draft LTR. The LTR should be revised to state that plant-specific applications that would reference this LTR should address any deviations from the referenced standards.
The draft LTR appears to only address complete conversions to IEEE 497-2002 and not modifications as described in Regulatory Position 1 of RG 1.97, Revision 4. The LTR should indicate that it is also applicable for modifications as described in Regulatory Position 1 of RG1.97, Revision 4. The LTR should also include clear descriptions of a complete conversion to RG 1.97, Revision 4, and a modification as allowed by Regulatory Position 1 of RG 1.97, Revision 4. It appears that what the BWROG representatives described during the meeting as a modification is actually a conversion with deviations from newer versions of industry standards.
Although during the meeting the BWROG representatives indicated that the LTR referenced NEDO-33160-A (relaxation of safety relief valve position indication), the NRC staff was unable to find this reference. A reference and appropriate discussion of NEDO-33160-A should be included in the LTR if appropriate.
Table A-1 in the draft LTR is hard to follow. The LTR should include information that clarifies that the column titled BWR/4" describes an example of the current type and category classifications of instrumentation currently installed at a typical BWR/4 plant. The LTR should include information to clarify that this table includes all BWR variables listed in RG 1.97, Revision 3. This table should include the purpose of each variable (the bold text in the variable column of RG 1.97, Revision 3) and the equivalent purpose of each variable under RG 1.97, Revision 4. During the meeting, it was stated that the order that the variables are listed in this table was the order that they appear in RG 1.97, Revisions 3. However, it does not appear that this is the case. The order that variables are listed in this table should be the order that they appear in RG 1.97, Revision 3.
The LTR should include (either in Table A-1 or in a separate table) the following for each variable: the variable name, Revision 3 type, Revision 3 category, Revision 3 purpose, Revision 4 type, Revision 4 purpose, and comments including information about change of type, purpose, deletion from the list of variables, or addition to the list of variables.
The LTR should include an additional table that shows variables that under RG 1.97, Revision 4, have different types, purposes, deletion from the list of variables, addition to the list of variables, and why the change is appropriate, from what was provided under RG 1.97, Revision 3.
The LTR should include more details concerning the proposed change in the primary containment radiation monitoring variables going from both Type C, Category 1, and Type E, Category 1, variables (with different ranges) under RG 1.97, Revision 3, to only a Type E variable under RG 1.97, Revision 4. It is not clear to the NRC staff how this variable would not be considered a Type C variable under RG 1.97, Revision 4. The purpose of this variable under RG 1.97, Revision 3, is for detection of a breach of the reactor coolant pressure boundary and the verification of the level of radiation in the containment. The LTR should include a discussion of how Type C variables in the LTR meet all of the criteria of Clause 4.3 of IEEE 497-2002 and if the purpose of the Type C variables has changed from Revision 3 to Revision 4 of RG 1.97.
The LTR should include more details for other variables that would change types from Revision 3 to Revision 4 of RG 1.97. One example is containment isolation valve indication which is a Type B, Category 1, variable under RG 1.97, Revision 3, and would become a Type D variable under RG 1.97, Revision 4.
Although not included in the LTR, technical specifications (TSs) were discussed at the meeting.
The BWROG would like to see changes to the Improved Standard TSs that would reflect the LTR. A discussion of this subject should be conducted with representatives of the TS Branch (ITSB) of the Division of Inspection and Regional Support.