View source for RA-14-0014, Duke Energy Carolinas, LLC (Duke Energy): 10 CFR 50.46 - Annual Report for 2013 for Oconee Nuclear Station, Units 1, 2 and 3

{{Adams
| number = ML14205A280
| issue date = 07/07/2014
| title = Duke Energy Carolinas, LLC (Duke Energy): 10 CFR 50.46 - Annual Report for 2013 for Oconee Nuclear Station, Units 1, 2 and 3
| author name = Waldrep B
| author affiliation = Duke Energy Carolinas, LLC
| addressee name = 
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000269, 05000270, 05000287
| license number = DPR-038, DPR-047, DPR-055
| contact person = 
| case reference number = RA-14-0014
| document type = Annual Report, Letter type:RA
| page count = 5
}}

=Text=
{{#Wiki_filter:DUK                                                     6wm0      C vkim PradchN Wakk
                                                                                 &operatwn suppad 520 8. Chuwh SOW Ohaftft, NC 28M1g MdkVg Aftsix*
EC07H / P.O. Sax 1008 ChwmoWe, NC 28201-1008
                             * .                                                 704-8248162 704-M8-4541 fax Serial: RA-14-0014                                                                10 CFR 50.46 July 7, 2014 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Oconee Nuclear Station, Units 1, 2, and 3 Docket Numbers; 0-269,50-270, and 50-287 Renewed Operating License No&. DPR-38, DPR-47, and DPR-55

==Subject:==
Duke Energy Carolinas, LLC (Duke Energy): 10 CFR 50.46 - Annual Report for 2013 for Oconee Nuclear Station, Units 1, 2, and 3

==Reference:==
: 1) Letter, G. D. Miller (Duke Energy) to USNRC, 30.Day Report Pursuantto 10 CFR 50.46, Changes to or Errorsin an EvaluationModel, December 16, 2013 (ADAMS Accession No. ML13353A137) 10 CFR 50.46 (a)(3)(H) requires the reporting of changes to or errors in Emergency Core Cooling System (ECCS) evaluation models (EMs). This report covers the time period from January 1, 2013 to December 31,2013 for the Oconee Nuclear Station (ONS). The most recent 10 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 model errors previously reported to the NRC. Attached are the LOCA PCT margin summary tables for Oconee 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)             MsueOuke- wgr.um).
(34S Sincerely, Benjamin C.Walr~
Vice PresidentNuclear CorporateGovernance &OperafonsSupport 013 Annual Report of Peak Cladding Temperature                                         L)
                                                                                                  /" tC---

U.S. Nuclear Regulatory Commission RA-14-0014 Page 2 xc (with attachment):
V.M.McCree Regional Administrator U.S. Nuclear Regulatory Commission -Region II Marquis One Tower 245 Peachtree Center Ave., NE Suite 1200 Atlanta, GA 30303-1257 J. R.Hall NRC Project Manager (ONS)                                             .4f U.S. Nuclear Regulatory Commission One White Flint North, Malt Stop 8G9A 11555 Rockville Pike                          . .' .. * . ,.,, , ., "
Rockville, MD 20852-2738 Eddy Crowe NRC Senior Resident Inspector Oconee Nucleai Station

U.S. Nuclear Regulatory Commission RA-14-0014 Attachment Page 1 of 3 Attachment Duke Energy Carolinas, LLC*
Oconee Nuclear Station, Unft 1, 2, and 3 10 CFR 60.46 Acceptance Crti for Emergency Core Cooling System for Ught-Water Nucer Power Reactors 2013 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 3 Table 1: LOCA Peak Cladding Temperature Margin Summary-Oconee Unite 1, 2, and 3 LSLOCA                            PnT(F)                           Commenf.
Evaluation model: RELAPS/MO2-B&W                          .___ -.               ___,..___._,_*
Analysis of record PCT                                        1852                           Reference F Prior 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
                                           "                    +2 degradation (considered a change In the application of the evaluation model)
Fial licensing basis PCT                                    -1854, SOLOCA Full Power .10%FP                       PCI(QF)                          Comments Evaluation 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)                                                          0
: 1. ECCS Bypass and Upper Plenum Column Weldment Modeling Current 10 CFR 50.48 Changes or Error Corrections (APCT)                                                          0
: i. None Final licensing basis PCT                                     15.8 SSLOCA Reduced Power [1l                      PCT(oF)                          CommeMts Analysis of record PCT                                         N/A              Wil be reported under a separate 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/A (A*P  T)                 . .. .     .. ...                           . .....                             .
Errors (APCT)                                                  NIA Final licensing basis PCT                                      N/A           Operation Not Justified [21 Notes
: 1. Partial power SBLOCA analysis with one HPI pump out of service, supports 30 day LCO for 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 3 References for Table 1:
A)   Letter, R. M. Glover (Duke Energy) to USNRC, 30-Day Report Pursuantto 10 CFR50.46, Changes to or Errorsin an EvaluationModel, December 8, 2011 (ADAMS MLI 347A1 93)
B) Letter, B. C. Walirep (Duke Energy) to USNRC, 30-Day andAnnual Report Pursuantto 10 CFR 50.46, Changes to or Errorsin an EvaluationModel, July 5, 2012 (ADAMS ML121910319)
C) Letter, B. C. Waldrep (Duke Energy) to USNRC, 30-Day Report Pursuantto 10 CFR 50.46, Changes to or ErrorsIn an EvaluationModex, December 20, 2012 D) Letter, G. J. St.Clair (AREVA) to S. Thomas (Duke Energy), 10 CFR 50.46 LOCA Report of Two EM ErrorCorrections(AREVA CR 2012-165: ECCS Bypass MathematicalErrorand AREVA CR 2012-757: UpperIPlenum Column Wedkpnt EM Change), Febnuq 23, 2012, AREVA Letter FAB12-120 E) Letter, D. C. Culp (Duke Energy) to USNRC, 30-Day Report Pursuantto 10 CFR 50.46, Changes to or Errorsin an EvaluationModel, March 9,2012 (ADAMS ML12073A354)
F) Letter, G. J. St.Clair (AREVA) to S. Thomas (Duke Energy), 10 CFR 50.46 LOCA Report of an EM ErrorCorrection(A RE VA CR 2013-5610)Related to an Error#ithe            fltered Flow Calculationof the FilterBreak Frequency,Noveme 14, 2013, AREVA Letter FABI3-00549 G) AREVA NP Document No. 86-92064-000, TCD TransentAssessment for SWPlants Summary Report,October 21, 2013 (AREVA Proprietary)
                                                                               ....}}