ML070660151
| ML070660151 | |
| Person / Time | |
|---|---|
| Site: | Boiling Water Reactor Owners Group |
| Issue date: | 03/13/2007 |
| From: | Michelle Honcharik NRC/NRR/ADRA/DPR/PSPB |
| To: | Bunt R Southern Nuclear Operating Co |
| Honcharik M, NRR/DPR/PSPBPM, 415-1774 | |
| References | |
| TAC MD2917 | |
| Download: ML070660151 (5) | |
Text
March 13, 2007 Mr. Randy C. Bunt Chair, BWR Owners Group Southern Nuclear Operating Company 40 Inverness Center Parkway/Bin B057 Birmingham, AL 35242
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION RE: THE BOILING WATER REACTOR OWNERS GROUP (BWROG) TOPICAL REPORT (TR)
NEDO-33148, SEPARATION OF LOSS OF OFFSITE POWER FROM LARGE BREAK LOCA [LOSS-OF-COOLANT ACCIDENT], REVISION 2 (TAC NO. MD2917)
Dear Mr. Bunt:
By letter dated August 25, 2006 (Agencywide Documents Access and Management System Accession No. ML062480327), the BWROG submitted for U.S. Nuclear Regulatory Commission (NRC) staff review TR NEDO-33148, Separation of Loss of Offsite Power from Large Break LOCA." Upon review of the information provided, the NRC staff has determined that additional information is needed to complete the review. On March 7, 2007, Mr. Fred Emerson, BWROG Project Manager, and I agreed that the NRC staff will receive your response to the enclosed Request for Additional Information (RAI) questions by May 25, 2007.
The enclosed RAI questions reflect the additional information required by the BWR Systems Branch staff. Additional RAI questions may be issued under separate letter to request information required by the other reviewing branches. If you have any questions regarding the enclosed RAI questions, please contact me at 301-415-1774.
Sincerely,
/RA/
Michelle C. Honcharik, Project Manager Special Projects Branch Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Project No. 691
Enclosure:
RAI questions cc w/encl: See next page
March 13, 2007 Mr. Randy C. Bunt Chair, BWR Owners Group Southern Nuclear Operating Company 40 Inverness Center Parkway/Bin B057 Birmingham, AL 35242
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION RE: THE BOILING WATER REACTOR OWNERS GROUP (BWROG) TOPICAL REPORT (TR)
NEDO-33148, SEPARATION OF LOSS OF OFFSITE POWER FROM LARGE BREAK LOCA [LOSS-OF-COOLANT ACCIDENT], REVISION 2 (TAC NO. MD2917)
Dear Mr. Bunt:
By letter dated August 25, 2006 (Agencywide Documents Access and Management System Accession No. ML062480327), the BWROG submitted for U.S. Nuclear Regulatory Commission (NRC) staff review TR NEDO-33148, Separation of Loss of Offsite Power from Large Break LOCA." Upon review of the information provided, the NRC staff has determined that additional information is needed to complete the review. On March 7, 2007, Mr. Fred Emerson, BWROG Project Manager, and I agreed that the NRC staff will receive your response to the enclosed Request for Additional Information (RAI) questions by May 25, 2007.
The enclosed RAI questions reflect the additional information required by the BWR Systems Branch staff. Additional RAI questions may be issued under separate letter to request information required by the other reviewing branches. If you have any questions regarding the enclosed RAI questions, please contact me at 301-415-1774.
Sincerely,
/RA/
Michelle C. Honcharik, Project Manager Special Projects Branch Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Project No. 691
Enclosure:
RAI questions cc w/encl: See next page DISTRIBUTION:
PUBLIC RidsNrrDpr PSPB Reading File RidsNrrDprPspb RidsNrrLADBaxley RidsAcrsAcnwMailCenter RidsNrrPMMHoncharik RidsOgcMailCenter Benjamin Parks (BTP)
RidsNrrDssSbwb Steven Laur (SAL)
George Morris (GWM2)
Ralph Landry (RRL)
Vijay Goel (VKG)
Vanice Perin (VAP)
David Nold (DAN2)
ADAMS ACCESSION NO.: ML070660151 NRR-106 OFFICE PSPB/PM PSPB/LA SBWB/BC PSPB/BC NAME MHoncharik DBaxley GCranston SRosenberg DATE 03/13/07 03/09/07 2/22/07 03/13/07 OFFICIAL RECORD COPY
ENCLOSURE REQUEST FOR ADDITIONAL INFORMATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION TOPICAL REPORT (TR) NEDO-33148, SEPARATION OF LOSS OF OFFSITE POWER FROM LARGE BREAK LOCA [LOSS-OF-COOLANT ACCIDENT], REVISION 2" BOILING WATER REACTOR OWNERS' GROUP PROJECT NO. 691 All page numbers refer to TR NEDO-33148, Revision 2, unless specified otherwise.
1.
The third bullet on Page 4-10 states, "The changes "Eliminate LPCI [low pressure coolant injection] Loop-Select" and "One Loop of RHR [residual heat removal] in SPC
[suppression pool cooling] Mode" cannot both be implemented together." Discuss whether it is intended for licensees to be able to implement the RHR in SPC mode change that do not have or have previously eliminated LPCI loop select logic systems.
Also discuss how, if this change can be implemented in plants without the LPCI loop select logic system, licensees will continue to meet the single failure criterion assuming the availability of offsite power. Provide separate discussions for the following:
BWR/3 and BWR/4 that previously had and have eliminated the LPCI loop select logic system, BWR/3 and BWR/4 that were not designed with a LPCI loop select logic system (if any exist), and BWR/5 and BWR/6, which do not have a LPCI loop select logic system.
2.
TR NEDO-33148 suggests that some plants have already removed the LPCI loop select logic system and that previous modifications to accomplish this task were much more complicated. Discuss the previous process used to perform the LPCI loop select modifications. If any previously reviewed documents are referenced, please provide copies. The NRC staff has been unable to locate such documents in the Agencywide Document Access and Management System.
3.
The fifth paragraph on Page B.6-1 states:
Within a plant type there is variability in the RPV [reactor pressure vessel] size and total ECCS [emergency core cooling system] injection flow. A series of runs was performed using MAAP4 to evaluate the impact of a change in RPV liquid volume with the core power level at the 25% uprated condition and ECCS injection flow unchanged. The base cases for this series of runs were Cases A and D, discussed above. RPV liquid volume, which includes the shroud, lower plenum, shroud head, separators, and active core regions, was varied +/-20%.
The change in PCT [peak cladding temperature] for these cases was limited to approximately 100 EF for the BWR4 and approximately 200 EF for the BWR6.
The largest increase in PCT occurred at lower RPV volumes (refer to Figure B.6-1).
a.
From what was ECCS injection flow unchanged?
b.
Confirm that the range of liquid volumes analyzed will bound limiting initial conditions from the proposed maximum extended load line limit analysis plus operating state points.
4.
How does the thermal-hydraulic analysis account for different fuel designs?
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 2/23/07