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{{#Wiki_filter:DUK 6wm0 C Wakkvkim PradchN& operatwn su ppad520 8. Chuwh SOWOhaftft, NC 28M1gMdkVg EC07H / P.O. Sax 1008ChwmoWe, NC 28201-1008* .704-8248162704-M8-4541 faxSerial: RA-14-0014 10 CFR 50.46July 7, 2014U. S. Nuclear Regulatory CommissionAttn: Document Control DeskWashington, DC 20555-0001Oconee Nuclear Station, Units 1, 2, and 3Docket Numbers; 0-269,50-270, and 50-287Renewed Operating License No&. DPR-38, DPR-47, and DPR-55
{{#Wiki_filter:DUK 6wm0 C Wakkvkim PradchN& operatwn su ppad520 8. Chuwh SOWOhaftft, NC 28M1gMdkVg EC07H / P.O. Sax 1008ChwmoWe, NC 28201-1008
* .704-8248162 704-M8-4541 faxSerial: RA-14-0014 10 CFR 50.46July 7, 2014U. S. Nuclear Regulatory Commission Attn: Document Control DeskWashington, DC 20555-0001 Oconee Nuclear Station, Units 1, 2, and 3Docket Numbers; 0-269,50-270, and 50-287Renewed Operating License No&. DPR-38, DPR-47, and DPR-55


==Subject:==
==Subject:==
Duke Energy Carolinas, LLC (Duke Energy): 10 CFR 50.46 -Annual Report for2013 for Oconee Nuclear Station, Units 1, 2, and 3
 
Duke Energy Carolinas, LLC (Duke Energy):
10 CFR 50.46 -Annual Report for2013 for Oconee Nuclear Station, Units 1, 2, and 3


==Reference:==
==Reference:==
: 1) Letter, G. D. Miller (Duke Energy) to USNRC, 30.Day Report Pursuant to 10 CFR 50.46,Changes to or Errors in an Evaluation Model, December 16, 2013 (ADAMS Accession No.ML13353A137)10 CFR 50.46 (a)(3)(H) requires the reporting of changes to or errors in Emergency CoreCooling System (ECCS) evaluation models (EMs). This report covers the time period fromJanuary 1, 2013 to December 31,2013 for the Oconee Nuclear Station (ONS). The most recent10 CFR 50.46 report for ONS (Reference 1) provided the Peak Cladding Temperature (PCT)results of a Large Break Loss of Coolant Accident (LOCA) reanalysis to correct ECCS modelerrors previously reported to the NRC. Attached are the LOCA PCT margin summary tables forOconee Units 1, 2, and 3. There are no new regulatory commitments contained in this letter.Please address any comments or questions regarding this matter to WNlWt K Wwr dt(010) (34S MsueOuke- wgr.um).Sincerely,Benjamin C. Walr~Vice President NuclearCorporate Governance & Operafons SupportAttachment 2013 Annual Report of Peak Cladding Temperature L)/" tC---
: 1) Letter, G. D. Miller (Duke Energy) to USNRC, 30.Day Report Pursuant to 10 CFR 50.46,Changes to or Errors in an Evaluation Model, December 16, 2013 (ADAMS Accession No.ML13353A137) 10 CFR 50.46 (a)(3)(H) requires the reporting of changes to or errors in Emergency CoreCooling System (ECCS) evaluation models (EMs). This report covers the time period fromJanuary 1, 2013 to December 31,2013 for the Oconee Nuclear Station (ONS). The most recent10 CFR 50.46 report for ONS (Reference  
U.S. Nuclear Regulatory CommissionRA-14-0014Page 2xc (with attachment):V. M. McCreeRegional AdministratorU.S. Nuclear Regulatory Commission -Region IIMarquis One Tower245 Peachtree Center Ave., NE Suite 1200Atlanta, GA 30303-1257J. R. HallNRC Project Manager (ONS)U.S. Nuclear Regulatory CommissionOne White Flint North, Malt Stop 8G9A11555 Rockville PikeRockville, MD 20852-2738Eddy CroweNRC Senior Resident InspectorOconee Nucleai Station.4f..' ..* .,.,, , ., "
: 1) provided the Peak Cladding Temperature (PCT)results of a Large Break Loss of Coolant Accident (LOCA) reanalysis to correct ECCS modelerrors previously reported to the NRC. Attached are the LOCA PCT margin summary tables forOconee Units 1, 2, and 3. There are no new regulatory commitments contained in this letter.Please address any comments or questions regarding this matter to WNlWt K Wwr dt(010) (34S MsueOuke-wgr.um).Sincerely, Benjamin C. Walr~Vice President NuclearCorporate Governance  
U.S. Nuclear Regulatory CommissionRA-14-0014AttachmentPage 1 of 3AttachmentDuke Energy Carolinas, LLC*Oconee Nuclear Station, Unft 1, 2, and 310 CFR 60.46Acceptance Crti for Emergency CoreCooling System for Ught-Water Nucer Power Reactors2013 Annual Report of Peek Cladding TemperaureTable 1: LOCA Peak Cladding Temperature Margin,11mnary -Oconee Unts 1, 2, and 3 U.S. Nuclear Regulatory CommissionRA-14-0014AttachmentPage 2 of 3Table 1: LOCA Peak Cladding Temperature Margin Summary-Oconee Unite 1, 2, and 3LSLOCA PnT(F) Commenf.Evaluation model: RELAPS/MO2-B&W .___ -. ___,..___._,_*Analysis of record PCT 1852 Reference FPrior 10 CFR 50.46 Changes or Error Corrections(APCT)1. None _. __. _ .....Current 10 CFR 50.46 Changes or Error Corrections.' Reference G(APCT)1. Transient fuel pellet thermal conductivity " +2degradation (considered a change In theapplication of the evaluation model)Fial licensing basis PCT -1854,SOLOCA Full Power .10% FP PCI(QF) CommentsEvaluation model: RELAPWiMOD2-B&W _. _ _.......Analysis of record PCT 1598 References A B C____ysi__ofreordPCT._______,_,_,___ 15(2HPiCase)q.15WbreakPrior 10 CFR 50.46 Changes or Error Correctior.s References D, E(&PCT) 01. ECCS Bypass and Upper Plenum ColumnWeldment ModelingCurrent 10 CFR 50.48 Changes or Error Corrections(APCT) 0i. NoneFinal licensing basis PCT 15.8SSLOCA Reduced Power [1l PCT(oF) CommeMtsAnalysis of record PCT N/A Wil be reported under aseparate LAR(References A, B. C)Prior 10 CFR 50.46 Changes or Error Corrections N/A(APCT)Current 10 CFR 50.46 Changes or Error Corrections N/AT) ... ... ... ...... .Errors (APCT) NIAFinal licensing basis PCT N/A Operation Not Justified [21Notes1. Partial power SBLOCA analysis with one HPI pump out of service, supports 30 day LCOfor TS 3.5.2 Condition B. Also supports TS 3.5.2 Condition CI and C2.2. Pending review and approval of separate LAR. Refer to Reference A for additionaldetails.
& Operafons SupportAttachment 2013 Annual Report of Peak Cladding Temperature L)/" tC---
U.S. Nuclearj'#Igulatory Commission ..RA-14-0014'Attachment :, ,Page 3 of 3References for Table 1:A) Letter, R. M. Glover (Duke Energy) to USNRC, 30-Day Report Pursuant to 10 CFR 50.46,Changes to or Errors in an Evaluation Model, December 8, 2011 (ADAMS MLI 347A1 93)B) Letter, B. C. Walirep (Duke Energy) to USNRC, 30-Day and Annual Report Pursuant to10 CFR 50.46, Changes to or Errors in an Evaluation Model, July 5, 2012 (ADAMSML121910319)C) Letter, B. C. Waldrep (Duke Energy) to USNRC, 30-Day Report Pursuant to 10 CFR 50.46,Changes to or Errors In an Evaluation Modex, December 20, 2012D) Letter, G. J. St.Clair (AREVA) to S. Thomas (Duke Energy), 10 CFR 50.46 LOCA Report ofTwo EM Error Corrections (AREVA CR 2012-165: ECCS Bypass Mathematical Error andAREVA CR 2012-757: Upper Plenum Column Wedkpnt EM Change), Febnuq 23, 2012,AREVA Letter FAB12-120 IE) Letter, D. C. Culp (Duke Energy) to USNRC, 30-Day Report Pursuant to 10 CFR 50.46,Changes to or Errors in an Evaluation Model, March 9,2012 (ADAMS ML12073A354)F) Letter, G. J. St.Clair (AREVA) to S. Thomas (Duke Energy), 10 CFR 50.46 LOCA Report ofan EM Error Correction (A RE VA CR 2013-5610) Related to an Error #ithe fltered FlowCalculation of the Filter Break Frequency, Noveme 14, 2013, AREVA Letter FABI3-00549G) AREVA NP Document No. 86-92064-000, TCD Transent Assessment for SWPlantsSummary Report, October 21, 2013 (AREVA Proprietary)................. ....'...}}
U.S. Nuclear Regulatory Commission RA-14-0014 Page 2xc (with attachment):
V. M. McCreeRegional Administrator U.S. Nuclear Regulatory Commission  
-Region IIMarquis One Tower245 Peachtree Center Ave., NE Suite 1200Atlanta, GA 30303-1257 J. R. HallNRC Project Manager (ONS)U.S. Nuclear Regulatory Commission One White Flint North, Malt Stop 8G9A11555 Rockville PikeRockville, MD 20852-2738 Eddy CroweNRC Senior Resident Inspector Oconee Nucleai Station.4f..' ..* .,.,, , ., "
U.S. Nuclear Regulatory Commission RA-14-0014 Attachment Page 1 of 3Attachment Duke Energy Carolinas, LLC*Oconee Nuclear Station, Unft 1, 2, and 310 CFR 60.46Acceptance Crti for Emergency CoreCooling System for Ught-Water Nucer Power Reactors2013 Annual Report of Peek Cladding Temperaure Table 1: LOCA Peak Cladding Temperature Margin,11mnary  
-Oconee Unts 1, 2, and 3 U.S. Nuclear Regulatory Commission RA-14-0014 Attachment Page 2 of 3Table 1: LOCA Peak Cladding Temperature Margin Summary-Oconee Unite 1, 2, and 3LSLOCA PnT(F) Commenf.Evaluation model: RELAPS/MO2-B&W  
.___ -. ___,..___._,_*
Analysis of record PCT 1852 Reference FPrior 10 CFR 50.46 Changes or Error Corrections (APCT)1. None _. __. _ .....Current 10 CFR 50.46 Changes or Error Corrections.'
Reference G(APCT)1. Transient fuel pellet thermal conductivity  
" +2degradation (considered a change In theapplication of the evaluation model)Fial licensing basis PCT -1854,SOLOCA Full Power .10% FP PCI(QF) CommentsEvaluation model: RELAPWiMOD2-B&W
_. _ _.......Analysis of record PCT 1598 References A B C____ysi__ofreordPCT._______,_,_,___
15(2HPiCase)q.15Wbreak Prior 10 CFR 50.46 Changes or Error Correctior.s References D, E(&PCT) 01. ECCS Bypass and Upper Plenum ColumnWeldment ModelingCurrent 10 CFR 50.48 Changes or Error Corrections (APCT) 0i. NoneFinal licensing basis PCT 15.8SSLOCA Reduced Power [1l PCT(oF) CommeMtsAnalysis of record PCT N/A Wil be reported under aseparate LAR(References A, B. C)Prior 10 CFR 50.46 Changes or Error Corrections N/A(APCT)Current 10 CFR 50.46 Changes or Error Corrections N/AT) ... ... ... ...... .Errors (APCT) NIAFinal licensing basis PCT N/A Operation Not Justified  
[21Notes1. Partial power SBLOCA analysis with one HPI pump out of service, supports 30 day LCOfor TS 3.5.2 Condition B. Also supports TS 3.5.2 Condition CI and C2.2. Pending review and approval of separate LAR. Refer to Reference A for additional details.
U.S. Nuclearj'#Igulatory Commission  
..RA-14-0014' Attachment  
:, ,Page 3 of 3References for Table 1:A) Letter, R. M. Glover (Duke Energy) to USNRC, 30-Day Report Pursuant to 10 CFR 50.46,Changes to or Errors in an Evaluation Model, December 8, 2011 (ADAMS MLI 347A1 93)B) Letter, B. C. Walirep (Duke Energy) to USNRC, 30-Day and Annual Report Pursuant to10 CFR 50.46, Changes to or Errors in an Evaluation Model, July 5, 2012 (ADAMSML121910319)
C) Letter, B. C. Waldrep (Duke Energy) to USNRC, 30-Day Report Pursuant to 10 CFR 50.46,Changes to or Errors In an Evaluation Modex, December 20, 2012D) Letter, G. J. St.Clair (AREVA) to S. Thomas (Duke Energy),
10 CFR 50.46 LOCA Report ofTwo EM Error Corrections (AREVA CR 2012-165:
ECCS Bypass Mathematical Error andAREVA CR 2012-757:
Upper Plenum Column Wedkpnt EM Change),
Febnuq 23, 2012,AREVA Letter FAB12-120 IE) Letter, D. C. Culp (Duke Energy) to USNRC, 30-Day Report Pursuant to 10 CFR 50.46,Changes to or Errors in an Evaluation Model, March 9,2012 (ADAMS ML12073A354)
F) Letter, G. J. St.Clair (AREVA) to S. Thomas (Duke Energy),
10 CFR 50.46 LOCA Report ofan EM Error Correction (A RE VA CR 2013-5610)
Related to an Error #ithe fltered FlowCalculation of the Filter Break Frequency, Noveme 14, 2013, AREVA Letter FABI3-00549 G) AREVA NP Document No. 86-92064-000, TCD Transent Assessment for SWPlantsSummary Report, October 21, 2013 (AREVA Proprietary)
.................  
....'...}}

Revision as of 13:02, 1 July 2018

Duke Energy Carolinas, LLC (Duke Energy): 10 CFR 50.46 - Annual Report for 2013 for Oconee Nuclear Station, Units 1, 2 and 3
ML14205A280
Person / Time
Site: Oconee  Duke Energy icon.png
Issue date: 07/07/2014
From: Waldrep B C
Duke Energy Carolinas
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
RA-14-0014
Download: ML14205A280 (5)


Text

DUK 6wm0 C Wakkvkim PradchN& operatwn su ppad520 8. Chuwh SOWOhaftft, NC 28M1gMdkVg EC07H / P.O. Sax 1008ChwmoWe, NC 28201-1008

  • .704-8248162 704-M8-4541 faxSerial: RA-14-0014 10 CFR 50.46July 7, 2014U. S. Nuclear Regulatory Commission Attn: Document Control DeskWashington, DC 20555-0001 Oconee Nuclear Station, Units 1, 2, and 3Docket Numbers; 0-269,50-270, and 50-287Renewed Operating License No&. DPR-38, DPR-47, and DPR-55

Subject:

Duke Energy Carolinas, LLC (Duke Energy):

10 CFR 50.46 -Annual Report for2013 for Oconee Nuclear Station, Units 1, 2, and 3

Reference:

1) Letter, G. D. Miller (Duke Energy) to USNRC, 30.Day Report Pursuant to 10 CFR 50.46,Changes to or Errors in an Evaluation Model, December 16, 2013 (ADAMS Accession No.ML13353A137) 10 CFR 50.46 (a)(3)(H) requires the reporting of changes to or errors in Emergency CoreCooling System (ECCS) evaluation models (EMs). This report covers the time period fromJanuary 1, 2013 to December 31,2013 for the Oconee Nuclear Station (ONS). The most recent10 CFR 50.46 report for ONS (Reference
1) provided the Peak Cladding Temperature (PCT)results of a Large Break Loss of Coolant Accident (LOCA) reanalysis to correct ECCS modelerrors previously reported to the NRC. Attached are the LOCA PCT margin summary tables forOconee Units 1, 2, and 3. There are no new regulatory commitments contained in this letter.Please address any comments or questions regarding this matter to WNlWt K Wwr dt(010) (34S MsueOuke-wgr.um).Sincerely, Benjamin C. Walr~Vice President NuclearCorporate Governance

& Operafons SupportAttachment 2013 Annual Report of Peak Cladding Temperature L)/" tC---

U.S. Nuclear Regulatory Commission RA-14-0014 Page 2xc (with attachment):

V. M. McCreeRegional Administrator U.S. Nuclear Regulatory Commission

-Region IIMarquis One Tower245 Peachtree Center Ave., NE Suite 1200Atlanta, GA 30303-1257 J. R. HallNRC Project Manager (ONS)U.S. Nuclear Regulatory Commission One White Flint North, Malt Stop 8G9A11555 Rockville PikeRockville, MD 20852-2738 Eddy CroweNRC Senior Resident Inspector Oconee Nucleai Station.4f..' ..* .,.,, , ., "

U.S. Nuclear Regulatory Commission RA-14-0014 Attachment Page 1 of 3Attachment Duke Energy Carolinas, LLC*Oconee Nuclear Station, Unft 1, 2, and 310 CFR 60.46Acceptance Crti for Emergency CoreCooling System for Ught-Water Nucer Power Reactors2013 Annual Report of Peek Cladding Temperaure Table 1: LOCA Peak Cladding Temperature Margin,11mnary

-Oconee Unts 1, 2, and 3 U.S. Nuclear Regulatory Commission RA-14-0014 Attachment Page 2 of 3Table 1: LOCA Peak Cladding Temperature Margin Summary-Oconee Unite 1, 2, and 3LSLOCA PnT(F) Commenf.Evaluation model: RELAPS/MO2-B&W

.___ -. ___,..___._,_*

Analysis of record PCT 1852 Reference FPrior 10 CFR 50.46 Changes or Error Corrections (APCT)1. None _. __. _ .....Current 10 CFR 50.46 Changes or Error Corrections.'

Reference G(APCT)1. Transient fuel pellet thermal conductivity

" +2degradation (considered a change In theapplication of the evaluation model)Fial licensing basis PCT -1854,SOLOCA Full Power .10% FP PCI(QF) CommentsEvaluation model: RELAPWiMOD2-B&W

_. _ _.......Analysis of record PCT 1598 References A B C____ysi__ofreordPCT._______,_,_,___

15(2HPiCase)q.15Wbreak Prior 10 CFR 50.46 Changes or Error Correctior.s References D, E(&PCT) 01. ECCS Bypass and Upper Plenum ColumnWeldment ModelingCurrent 10 CFR 50.48 Changes or Error Corrections (APCT) 0i. NoneFinal licensing basis PCT 15.8SSLOCA Reduced Power [1l PCT(oF) CommeMtsAnalysis of record PCT N/A Wil be reported under aseparate LAR(References A, B. C)Prior 10 CFR 50.46 Changes or Error Corrections N/A(APCT)Current 10 CFR 50.46 Changes or Error Corrections N/AT) ... ... ... ...... .Errors (APCT) NIAFinal licensing basis PCT N/A Operation Not Justified

[21Notes1. Partial power SBLOCA analysis with one HPI pump out of service, supports 30 day LCOfor TS 3.5.2 Condition B. Also supports TS 3.5.2 Condition CI and C2.2. Pending review and approval of separate LAR. Refer to Reference A for additional details.

U.S. Nuclearj'#Igulatory Commission

..RA-14-0014' Attachment

, ,Page 3 of 3References for Table 1:A) Letter, R. M. Glover (Duke Energy) to USNRC, 30-Day Report Pursuant to 10 CFR 50.46,Changes to or Errors in an Evaluation Model, December 8, 2011 (ADAMS MLI 347A1 93)B) Letter, B. C. Walirep (Duke Energy) to USNRC, 30-Day and Annual Report Pursuant to10 CFR 50.46, Changes to or Errors in an Evaluation Model, July 5, 2012 (ADAMSML121910319)

C) Letter, B. C. Waldrep (Duke Energy) to USNRC, 30-Day Report Pursuant to 10 CFR 50.46,Changes to or Errors In an Evaluation Modex, December 20, 2012D) Letter, G. J. St.Clair (AREVA) to S. Thomas (Duke Energy),

10 CFR 50.46 LOCA Report ofTwo EM Error Corrections (AREVA CR 2012-165:

ECCS Bypass Mathematical Error andAREVA CR 2012-757:

Upper Plenum Column Wedkpnt EM Change),

Febnuq 23, 2012,AREVA Letter FAB12-120 IE) Letter, D. C. Culp (Duke Energy) to USNRC, 30-Day Report Pursuant to 10 CFR 50.46,Changes to or Errors in an Evaluation Model, March 9,2012 (ADAMS ML12073A354)

F) Letter, G. J. St.Clair (AREVA) to S. Thomas (Duke Energy),

10 CFR 50.46 LOCA Report ofan EM Error Correction (A RE VA CR 2013-5610)

Related to an Error #ithe fltered FlowCalculation of the Filter Break Frequency, Noveme 14, 2013, AREVA Letter FABI3-00549 G) AREVA NP Document No. 86-92064-000, TCD Transent Assessment for SWPlantsSummary Report, October 21, 2013 (AREVA Proprietary)

.................

....'...