NOC-AE-07002196, CFR50.46 Annual Report of ECCS Model Revisions: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
 
(Created page by program invented by StriderTol)
 
Line 16: Line 16:


=Text=
=Text=
{{#Wiki_filter:Nuclear Operating Company South Texas Pro/ca Electric Generating Station PO. Bow 289 Wadsworth.
{{#Wiki_filter:Nuclear Operating Company South Texas Pro/ca Electric Generating Station PO.Bow 289 Wadsworth. Texas 77483 September 4, 2007 NOC-AE-07002196 10CFR50.46 U. S. Nuclear Regulatory Commission Attention: Document Control Desk One White Flint North 11555 Rockville Pike Rockville, MD 20852-2738 South Texas Project Units I & 2 Docket Nos. STN 50-498, STN 50-499 10CFR50.46 Annual Report of ECCS Model Revisions
Texas 77483 September 4, 2007 NOC-AE-07002196 1 OCFR50.46 U. S. Nuclear Regulatory Commission Attention:
Document Control Desk One White Flint North 11555 Rockville Pike Rockville, MD 20852-2738 South Texas Project Units I & 2 Docket Nos. STN 50-498, STN 50-499 10CFR50.46 Annual Report of ECCS Model Revisions  


==References:==
==References:==
: 1. Letter from D. A. Leazar to NRC Document Control Desk, "1 OCFR5 0.46 Annual Report of ECCS Model Revisions," dated February 11, 2003 (NOC-AE-03001464, ML030500320)
: 1. Letter from D. A. Leazar to NRC Document Control Desk, "1 OCFR5 0.46 Annual Report of ECCS Model Revisions," dated February 11, 2003 (NOC-AE-03001464, ML030500320)
: 2. Letter from D. A. Leazar to NRC Document Control Desk, "1 OCFR50.46 Annual Report of ECCS Model Revisions," dated September 18, 2006 (NOC-AE-06002064, ML062690497)
: 2. Letter from D. A. Leazar to NRC Document Control Desk, "10CFR50.46 Annual Report of ECCS Model Revisions," dated September 18, 2006 (NOC-AE-06002064, ML062690497)
Pursuant to I OCFR50.46(a)(3)(ii), STP Nuclear Operating Company (STPNOC) submits this report concerning revisions to the accepted Emergency Core Cooling System (ECCS) evaluation model at South Texas Project (STP) Units 1 and 2.The STP Unit I and Unit 2 Small Break LOCA peak clad temperatures (PCT) are unchanged from those reported in the previous report (Reference 2): 1612'F STPNOC has determined that the rebaseline described in Reference I was a reanalysis to establish a new Analysis of Record for Large Break LOCA with a PCT of 2136 'F. Corrections to the STP Unit 1 and Unit 2 Large Break LOCA analyses resulted in a PCT of 2112'F, as described in the attachment.
Pursuant to I OCFR50.46(a)(3)(ii), STP Nuclear Operating Company (STPNOC) submits this report concerning revisions to the accepted Emergency Core Cooling System (ECCS) evaluation model at South Texas Project (STP) Units 1 and 2.
The change is less than the 50'F criterion for reanalysis in I OCFR50.46(a)(3)(ii).
The STP Unit I and Unit 2 Small Break LOCA peak clad temperatures (PCT) are unchanged from those reported in the previous report (Reference 2): 1612'F STPNOC has determined that the rebaseline described in Reference I was a reanalysis to establish a new Analysis of Record for Large Break LOCA with a PCT of 2136 'F. Corrections to the STP Unit 1 and Unit 2 Large Break LOCA analyses resulted in a PCT of 2112'F, as described in the attachment. The change is less than the 50'F criterion for reanalysis in I OCFR50.46(a)(3)(ii).
There are no commitments in this submittal.
There are no commitments in this submittal.
STI: 32188233 NOC-AE-07002196 Page 2 of 3 If you should have any questions concerning this matter, please contact Mr. A. W. Harrison at (361) 972-7298 or me at (361) 972-7795.David A. L~ea Manager, Fuels & Analysis  
STI: 32188233
 
NOC-AE-07002196 Page 2 of 3 If you should have any questions concerning this matter, please contact Mr. A. W. Harrison at (361) 972-7298 or me at (361) 972-7795.
David A. L~ea Manager, Fuels & Analysis


==Attachment:==
==Attachment:==
Peak Clad Temperature Summary for Appendix K Large Break LOCA
NOC-AE-07002196 Page 3 of 3 cc:
(paper copy)                              (electronic copy)
Regional Administrator, Region IV        A. H. Gutterman, Esquire U. S. Nuclear Regulatory Commission      Morgan, Lewis & Bockius LLP 611 Ryan Plaza Drive, Suite 400 Arlington, Texas 76011-8064              Mohan C. Thadani U. S. Nuclear Regulatory Commission Mohan C. Thadani                          Thad Hill Senior Project Manager                    Eddy Daniels U.S. Nuclear Regulatory Commission        Marty Ryan One White Flint North (MS 7 Dl)          Harry Holloway 11555 Rockville Pike                      Steve Winn Rockville, MD 20852                      NRG South Texas LP Senior Resident Inspector                Ed Alarcon U. S. Nuclear Regulatory Commission      J. J. Nesrsta P. 0. Box 289, Mail Code: MN 16          R. K. Temple Wadsworth, TX 77483                      Kevin Pollo City Public Service C. M. Canady                              Jon C. Wood City of Austin                            Cox Smith Matthews Electric Utility Department 721 Barton Springs Road                  C. Kirksey Austin, TX 78704                          City of Austin Richard A. Ratliff Bureau of Radiation Control Texas Department of State Health Services 1100 West 49th Street Austin, TX 78756-3189


Peak Clad Temperature Summary for Appendix K Large Break LOCA NOC-AE-07002196 Page 3 of 3 cc: (paper copy)(electronic copy)Regional Administrator, Region IV U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 400 Arlington, Texas 76011-8064 Mohan C. Thadani Senior Project Manager U.S. Nuclear Regulatory Commission One White Flint North (MS 7 Dl)11555 Rockville Pike Rockville, MD 20852 Senior Resident Inspector U. S. Nuclear Regulatory Commission P. 0. Box 289, Mail Code: MN 16 Wadsworth, TX 77483 C. M. Canady City of Austin Electric Utility Department 721 Barton Springs Road Austin, TX 78704 Richard A. Ratliff Bureau of Radiation Control Texas Department of State Health Services 1100 West 49th Street Austin, TX 78756-3189 A. H. Gutterman, Esquire Morgan, Lewis & Bockius LLP Mohan C. Thadani U. S. Nuclear Regulatory Commission Thad Hill Eddy Daniels Marty Ryan Harry Holloway Steve Winn NRG South Texas LP Ed Alarcon J. J. Nesrsta R. K. Temple Kevin Pollo City Public Service Jon C. Wood Cox Smith Matthews C. Kirksey City of Austin NOC-AE-07002196 Page,1 of 1 Attachment Peak Clad Temperature Summary for Appendix K Large Break LOCA South Texas Units 1 & 2 Analysis Information:
NOC-AE-07002196 Page,1 of 1 Attachment Peak Clad Temperature Summary for Appendix K Large Break LOCA South Texas Units 1 & 2 Analysis Information:
Analysis Date: 12/17/2002 Evaluation Model: BASH Limiting Break Size: Cd=0.8, Min SI FQ: 2.55 FdH: 1.62 Fuel: RFA /Vantage 5H Steam Generator Tube Plugging (%): 10 Notes: RFA Re-analysis  
Analysis Date: 12/17/2002 Evaluation Model: BASH               Limiting Break Size: Cd=0.8, Min SI FQ: 2.55     FdH: 1.62 Fuel: RFA /Vantage 5H       Steam Generator Tube Plugging (%): 10 Notes: RFA Re-analysis - FdH = 1.55 for Once Burned Standard Fuel Licensing Basis Analysis-Of-Record (AOR) PCT*:                                       2136 OF PCT Assessments (Delta PCT)
-FdH = 1.55 for Once Burned Standard Fuel Licensing Basis Analysis-Of-Record (AOR) PCT*: 2136 OF PCT Assessments (Delta PCT)A. Prior ECCS Model Assessments I .IMP Database Error Corrections:
A. Prior ECCS Model Assessments I . IMP Database Error Corrections:                                   0
0 2. PAD Version 4.0 Implementation:  
: 2. PAD Version 4.0 Implementation:                                   -30°F B. Planned Plant Modification Evaluations I . None C. 2007 ECCS MODEL ASSESSMENTS I . LOCBART Pellet Volumetric Heat Generation Rate:                   6 OF Licensing Basis PCT + PCT Assessments PCT:                               2112 OF As noted in the cover letter, STPNOC has determined that the rebaseline performed in 2002 established a new AOR. The new AOR PCT of 2136 °F was calculated from 2090 °F (1998 AOR) + 46 °F (2002 Rebaseline).}}
-30°F B. Planned Plant Modification Evaluations I .None C. 2007 ECCS MODEL ASSESSMENTS I .LOCBART Pellet Volumetric Heat Generation Rate: 6 OF Licensing Basis PCT + PCT Assessments PCT: 2112 OF As noted in the cover letter, STPNOC has determined that the rebaseline performed in 2002 established a new AOR. The new AOR PCT of 2136 °F was calculated from 2090 °F (1998 AOR) + 46 °F (2002 Rebaseline).}}

Latest revision as of 03:41, 23 November 2019

CFR50.46 Annual Report of ECCS Model Revisions
ML072570097
Person / Time
Site: South Texas  STP Nuclear Operating Company icon.png
Issue date: 09/04/2007
From: Leazar D
South Texas
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
NOC-AE-07002196
Download: ML072570097 (4)
v • d • e


Text

Nuclear Operating Company South Texas Pro/ca Electric Generating Station PO.Bow 289 Wadsworth. Texas 77483 September 4, 2007 NOC-AE-07002196 10CFR50.46 U. S. Nuclear Regulatory Commission Attention: Document Control Desk One White Flint North 11555 Rockville Pike Rockville, MD 20852-2738 South Texas Project Units I & 2 Docket Nos. STN 50-498, STN 50-499 10CFR50.46 Annual Report of ECCS Model Revisions

References:

1. Letter from D. A. Leazar to NRC Document Control Desk, "1 OCFR5 0.46 Annual Report of ECCS Model Revisions," dated February 11, 2003 (NOC-AE-03001464, ML030500320)
2. Letter from D. A. Leazar to NRC Document Control Desk, "10CFR50.46 Annual Report of ECCS Model Revisions," dated September 18, 2006 (NOC-AE-06002064, ML062690497)

Pursuant to I OCFR50.46(a)(3)(ii), STP Nuclear Operating Company (STPNOC) submits this report concerning revisions to the accepted Emergency Core Cooling System (ECCS) evaluation model at South Texas Project (STP) Units 1 and 2.

The STP Unit I and Unit 2 Small Break LOCA peak clad temperatures (PCT) are unchanged from those reported in the previous report (Reference 2): 1612'F STPNOC has determined that the rebaseline described in Reference I was a reanalysis to establish a new Analysis of Record for Large Break LOCA with a PCT of 2136 'F. Corrections to the STP Unit 1 and Unit 2 Large Break LOCA analyses resulted in a PCT of 2112'F, as described in the attachment. The change is less than the 50'F criterion for reanalysis in I OCFR50.46(a)(3)(ii).

There are no commitments in this submittal.

STI: 32188233

NOC-AE-07002196 Page 2 of 3 If you should have any questions concerning this matter, please contact Mr. A. W. Harrison at (361) 972-7298 or me at (361) 972-7795.

David A. L~ea Manager, Fuels & Analysis

Attachment:

Peak Clad Temperature Summary for Appendix K Large Break LOCA

NOC-AE-07002196 Page 3 of 3 cc:

(paper copy) (electronic copy)

Regional Administrator, Region IV A. H. Gutterman, Esquire U. S. Nuclear Regulatory Commission Morgan, Lewis & Bockius LLP 611 Ryan Plaza Drive, Suite 400 Arlington, Texas 76011-8064 Mohan C. Thadani U. S. Nuclear Regulatory Commission Mohan C. Thadani Thad Hill Senior Project Manager Eddy Daniels U.S. Nuclear Regulatory Commission Marty Ryan One White Flint North (MS 7 Dl) Harry Holloway 11555 Rockville Pike Steve Winn Rockville, MD 20852 NRG South Texas LP Senior Resident Inspector Ed Alarcon U. S. Nuclear Regulatory Commission J. J. Nesrsta P. 0. Box 289, Mail Code: MN 16 R. K. Temple Wadsworth, TX 77483 Kevin Pollo City Public Service C. M. Canady Jon C. Wood City of Austin Cox Smith Matthews Electric Utility Department 721 Barton Springs Road C. Kirksey Austin, TX 78704 City of Austin Richard A. Ratliff Bureau of Radiation Control Texas Department of State Health Services 1100 West 49th Street Austin, TX 78756-3189

NOC-AE-07002196 Page,1 of 1 Attachment Peak Clad Temperature Summary for Appendix K Large Break LOCA South Texas Units 1 & 2 Analysis Information:

Analysis Date: 12/17/2002 Evaluation Model: BASH Limiting Break Size: Cd=0.8, Min SI FQ: 2.55 FdH: 1.62 Fuel: RFA /Vantage 5H Steam Generator Tube Plugging (%): 10 Notes: RFA Re-analysis - FdH = 1.55 for Once Burned Standard Fuel Licensing Basis Analysis-Of-Record (AOR) PCT*: 2136 OF PCT Assessments (Delta PCT)

A. Prior ECCS Model Assessments I . IMP Database Error Corrections: 0

2. PAD Version 4.0 Implementation: -30°F B. Planned Plant Modification Evaluations I . None C. 2007 ECCS MODEL ASSESSMENTS I . LOCBART Pellet Volumetric Heat Generation Rate: 6 OF Licensing Basis PCT + PCT Assessments PCT: 2112 OF As noted in the cover letter, STPNOC has determined that the rebaseline performed in 2002 established a new AOR. The new AOR PCT of 2136 °F was calculated from 2090 °F (1998 AOR) + 46 °F (2002 Rebaseline).
Retrieved from "https://kanterella.com/w/index.php?title=NOC-AE-07002196,_CFR50.46_Annual_Report_of_ECCS_Model_Revisions&oldid=2173345"