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| {{#Wiki_filter:}} | | {{#Wiki_filter:ENERGY June 6, 2013 Serial: HNP-13-050 ATTN: Document Control Desk U.S. Nuclear Regulatory Commiss i on Washington , DC 20555-0001 Shearon Harris Nuclear Power Plant , Unit 1 Docket No. 50-400 |
| | |
| | ==Subject:== |
| | Annual Report of Changes Pursuant to 1 0 CFR 50.46 Ladies and Gentlemen: David H. Corlett Manager , Regulatory Affa i rs Harris Nuc l ear Pl ant 5413 Shearon Harris Road New Hill NC 27562-9300 919.362.3137 10 CFR 50.46 Pursuant to 10 CFR 50.46(a)(3)(ii), Duke Energy Progress , Inc., formerly known as Carol i na Power & Light Company , hereby submits the enclosed annual report of changes to and errors discovered in the loss of coolant accident analyses for the Shearon Harris Nuclear Power Plant , Unit 1, for the period May 23 , 2012, through April 23 , 2013. This document contains no regulatory commitments. Please refer any questions regarding this submittal to John Caves at (919) 362-2406. |
| | Sincerely , David H. Corlett DHC/jrc |
| | |
| | ==Enclosure:== |
| | Annual Report of Changes Pursuant to 1 0 CFR 50.46 cc: Mr. J. D. Austin , NRC Sr. Resident Inspector , HNP Ms. A T. Billoch Colon , NRC Projec t Manager , HNP Mr. V. M. McCree , NRC Regional Adm i nistrator , Region II U.S. Nuclear Regulatory Commission Page 1 of 2 Enclosure to HNP-13-050 Shearon Harris Nuclear Power Plant, Unit 1 Annual Report of Changes Pursuant to 10 CFR 50.46 Reporting Period May 23, 2012, through April 23, 2013 Small Break Loss of Coolant Accident (SBLOCA) Analysis Evaluation Model: |
| | AREVA EMF-2328(P)(A) |
| | , PWR Small Break LOCA Evaluation Model, S-RELAP5 Based , Revision 0, March 2001 |
| | . The previous SBLOCA analysis of record was superseded using AREVA's EMF |
| | -2 328, PWR Small Break LOCA Evaluation Model, S |
| | -RELAP5 Based |
| | . This result ed in a change to the peak clad temperature (PCT) of +33 |
| | °F. The base analysis of record PCT is 1627 |
| | °F. |
| | The SBLOCA analysis is impacted by one error discovered during this reporting period |
| | . The Sleicher-Rouse correlation for heat transfer is used by the S |
| | -RELAP5 code. |
| | One of the equations was initially not programmed in a form consistent with other heat transfer correlations and expected physical trends, which resulted in an impact of +4 |
| | °F. Summary of Changes |
| | (°F) Resultant PCT (°F) SBLOCA PCT effective May 22, 2012 1594 Changes during reporting period Revised analysis of record |
| | +33 1627 Errors during reporting period Sleicher-Rouse correlation |
| | +4 1631 SBLOCA PCT effective April 23, 2013 1631 Sum of absolute values of PCT changes during this reporting period 37 The resultant predicted fuel element PCT, accounting for changes and errors in the evaluation model, is within the 2200 |
| | °F acceptance criteria in 10 CFR 50.46(b)(1). |
| | |
| | U.S. Nuclear Regulatory Commission Page 2 of 2 Enclosure to HNP-13-050 Large Break Loss of Coolant Accident (LBLOCA) Analysis Evaluation Model: |
| | AREVA ANP-3011(P), Harris Nuclear Plant Unit 1 Realistic Large Break LOCA Analysis , Revision 1, as approved by NRC Safety Evaluation dated May 30, 2012. This evaluation model is a plant specific implementation of AREVA EMF-2103(P)(A), Realistic Large Break LOCA Methodology, Revision 0 , April 2003. |
| | The previous LBLOCA analysis of record was superseded using ANP-3011 , Harris Nuclear Plant Unit 1 Realistic Large Break LOCA Analysis |
| | . The NRC safety evaluation documenting approval of ANP |
| | -3011 require s that an adder of 138 |
| | °F be applied to calculated peak cladding temperatures to address concerns related to droplet shattering and fuel relocation. |
| | In addition, the base analysis also includes a +14 |
| | °F impact for the Sleicher |
| | -Rouse error, as discussed above related to SBLOCA. The base analysis of record PCT is 2071 |
| | °F. |
| | The LBLOCA analysis is impacted by one error discovered during this reporting period. There was an error in the calculation of uncertainty for one parameter of the Cathcart |
| | -Pawel oxide growth correlation used to calculate energy released from oxidation of cladding. |
| | This results in a 0 °F impact on PCT. |
| | Summary of Changes |
| | (°F) Resultant PCT (°F) LBLOCA PCT effective May 22, 2012 2081 Changes during reporting period Revised analysis of record Calculated PCT: 1919 |
| | °F Conservative adder to account for uncertainties related to droplet shattering and fuel relocation: +138 |
| | °F Sleicher-Rouse correlation: +14 °F -10 2071 Errors during reporting period Cathcart-Pawel correlation 0 2071 LBLOCA PCT effective April 23, 2013 2071 Sum of absolute values of PCT changes during this reporting period 10 The resultant predicted fuel element PCT, accounting for changes and errors in the evaluation model, is within the 2200 |
| | °F acceptance criteria in 10 CFR 50.46(b)(1).}} |
|
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Category:Letter
MONTHYEARIR 05000400/20240112024-09-10010 September 2024 NRC Inspection Report 05000400/2024011 IR 05000400/20240052024-08-26026 August 2024 Updated Inspection Plan for Shearon Harris Nuclear Power Plant, Unit 1 (Report 05000400-2024005) Rev 1 ML24059A4252024-08-14014 August 2024 Issuance of Amendment No. 202 Regarding Alignment of Certain Technical Specifications with Improved Standard Technical Specifications ML24213A0522024-08-0202 August 2024 Issuance of Amendment No. 201 to Extend Completion Time of Inoperable Reactor Coolant System Accumulator Using Consolidated Line Item Improvement Process ML24212A3412024-07-31031 July 2024 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection IR 05000400/20240022024-07-29029 July 2024 – Integrated Inspection Report 05000400/2024002 ML24170A7312024-07-29029 July 2024 – Exemption from the Requirements of 10 CFR 50.55a(H)(2) Using the Risk-Informed Process for Evaluations Letter ML24183A0972024-07-12012 July 2024 ISFSI; Catawba 1, 2 & ISFSI; McGuire 1, 2 & ISFSI; Oconee 1, 2, 3 & ISFSI; Shearon Harris 1; H. B. Robinson 2 & ISFSI; and Radioactive Package Shipping Under 10 CFR 71 (71-266 & 71-345) – Review of QA Program Changes EPID L-2024-LLQ-0002 IR 05000400/20243022024-06-27027 June 2024 – NRC Operator Licensing Examination Approval 05000400/2024302 IR 05000400/20244012024-06-25025 June 2024 – Security Baseline Inspection Report05000400/2024401 ML24162A1372024-06-24024 June 2024 – Regulatory Audit Summary Related to the Review of Exemption Request from Certain Requirements in 10 CFR 50.55a(h)(2)(EPID L-2024-LLE-00040) ML24136A1382024-05-20020 May 2024 – Notification of an NRC Fire Protection Team Inspection (FPTI) (NRC Inspection Report 05000400/2024011) and Request for Information (RFI) ML24116A2592024-05-14014 May 2024 Staff Evaluation Related to Aging Management Plan and Inspection Plan for Reactor Vessel Internals ML24127A1592024-05-0808 May 2024 – Notification of Licensed Operator Initial Examination 05000400/2024302 IR 05000400/20240012024-05-0505 May 2024 Integrated Inspection Report 05000400/2024001 ML24100A0912024-04-10010 April 2024 Operator License Examination Report ML24058A2462024-03-18018 March 2024 – Supplemental Information Needed for Using the Risk-Informed Process for Evaluations for the Request for Exemption from Certain Requirements in 10 CFR 50.55a(h)(2) IR 05000400/20230062024-02-28028 February 2024 Annual Assessment Letter for Shearon Harris Nuclear Power Plant - NRC Inspection Report 05000400/2023006 ML24032A2632024-02-23023 February 2024 – Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0044 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) IR 05000400/20243012024-02-21021 February 2024 – NRC Operator Licensing Examination Approval 05000400/2024301 IR 05000400/20230042024-01-30030 January 2024 Integrated Inspection Report 05000400/2023004 ML23317A3462023-11-14014 November 2023 Duke Fleet - Correction Letter to License Amendment Nos. 312 & 340 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 IR 05000400/20230032023-11-0909 November 2023 Integrated Inspection Report 05000400/2023003 ML23346A1322023-10-0606 October 2023 Communication from C-10 Research & Education Foundation Regarding NextEra Common Emergency Fleet Plan License Amendment Request and Related Documents Subsequently Published ML23234A1702023-10-0303 October 2023 Issuance of Amendment No. 199 Regarding Administrative Changes to the Renewed Facility Operating License and Technical Specifications ML23256A0882023-09-25025 September 2023 Issuance of Alternative to Steam Generator Welds ML23195A0782023-08-29029 August 2023 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 IR 05000400/20230052023-08-23023 August 2023 Updated Inspection Plan for Shearon Harris Nuclear Power Plant, Unit 1 (Report 05000400/2023005) ML23234A2542023-08-22022 August 2023 RQ Inspection Notification Letter IR 05000400/20234022023-07-26026 July 2023 Security Baseline Inspection Report 05000400/2023402 IR 05000400/20230022023-07-24024 July 2023 Integrated Inspection Report 05000400/2023002 IR 05000400/20234402023-07-17017 July 2023 Special Inspection Report 05000400/2023440 and Preliminary Greater than Green Finding and Apparent Violation Cover Letter IR 05000400/20230012023-05-10010 May 2023 Integrated Inspection Report 05000400 2023001 IR 05000400/20234042023-05-0404 May 2023 Cyber Security Inspection Report 05000400/2023404 ML23118A0762023-05-0101 May 2023 Approval for Use of Specific Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML23118A1392023-04-28028 April 2023 Submittal of Updated Final Safety Analysis Report (Amendment 65), Technical Specification Bases Revision, Report of Changes Pursuant to 10 CFR 50.59 and Summary of Commitment Changes IR 05000400/20234032023-04-0505 April 2023 Security Baseline Inspection Report 05000400/2023403 IR 05000400/20230102023-03-15015 March 2023 Comprehensive Engineering Team Inspection (CETI) Inspection Report 05000400/2023010 ML22332A4932023-03-10010 March 2023 William States Lee III 1 and 2 - Issuance of Amendments Regarding the Relocation of the Emergency Operations Facility IR 05000400/20220062023-03-0101 March 2023 Annual Assessment Letter for Shearon Harris Nuclear Power Plant - NRC Inspection Report 05000400/2022006 ML23033A5272023-02-0808 February 2023 Correction of Typographical Errors Incurred During Issuance of License Amendment No. 196 IR 05000400/20220042023-02-0707 February 2023 Integrated Inspection Report 05000400/2022004 ML23020A1252023-01-23023 January 2023 Notification of Target Set Inspection and Request for Information (NRC Inspection Report 05000400/2023403) ML22096A0032022-11-18018 November 2022 McGuire Nuclear Station and Shearon Harris Nuclear Power Plant Authorization of RA-19-0352 Regarding Use of Alternative for RPV Head Closure Stud Examinations ML22256A2532022-11-14014 November 2022 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-541, Rev. 2 IR 05000400/20220032022-11-10010 November 2022 Integrated Inspection Report 05000400/2022003 IR 05000400/20223012022-11-0202 November 2022 NRC Operator License Examination Report 05000400/2022301 ML22271A6202022-09-29029 September 2022 Notification of Shearon Harris Nuclear Power Plant Comprehensive Engineering Team Inspection - U.S. Nuclear Regulatory Commission Inspection Report 05000400/2023010 ML22258A1262022-09-14014 September 2022 NRC Operator Licensing Examination Approval 05000400/2022301 ML22242A0022022-09-12012 September 2022 Issuance of Amendments to Adopt TSTF 569, Revision 2, Revise Response Time Testing Definition 2024-09-10
[Table view] Category:Annual Operating Report
MONTHYEARRA-24-0083, Annual Report of Changes Pursuant to 10 CFR 50.462024-04-25025 April 2024 Annual Report of Changes Pursuant to 10 CFR 50.46 RA-23-0044, Aduke Energy Annual Report of Changes Pursuant to 10 CFR 50.462023-04-26026 April 2023 Aduke Energy Annual Report of Changes Pursuant to 10 CFR 50.46 RA-23-0046, Annual Radioactive Effluent Release Report - 20222023-04-24024 April 2023 Annual Radioactive Effluent Release Report - 2022 RA-22-0028, Annual Report of Changes Pursuant to 10 CFR 50.462022-04-27027 April 2022 Annual Report of Changes Pursuant to 10 CFR 50.46 RA-21-0131, Annual Environmental (Non-radiological) Operating Report2021-04-27027 April 2021 Annual Environmental (Non-radiological) Operating Report RA-21-0051, Shearon Harris Nuclear Power Plant, McGuire Nuclear Station, Oconee Nuclear Station, and H. B. Robinson Steam Electric Plant - Annual Report of Changes Pursuant to 10 CFR 50.462021-04-0505 April 2021 Shearon Harris Nuclear Power Plant, McGuire Nuclear Station, Oconee Nuclear Station, and H. B. Robinson Steam Electric Plant - Annual Report of Changes Pursuant to 10 CFR 50.46 RA-20-0126, Annual Report of Changes Pursuant to 10 CFR 50.462020-05-27027 May 2020 Annual Report of Changes Pursuant to 10 CFR 50.46 RA-18-0022, Carolinas, LLC (Duke Energy) - Annual Report of Changes Pursuant to 10 CFR 50.462018-05-24024 May 2018 Carolinas, LLC (Duke Energy) - Annual Report of Changes Pursuant to 10 CFR 50.46 HNP-18-021, Annual Report in Accordance with Technical Specification 6.9.1.22018-02-19019 February 2018 Annual Report in Accordance with Technical Specification 6.9.1.2 RA-17-0027, Duke Energy Carolinas, LLC - Annual Report of Changes Pursuant to 10 CFR 50.462017-05-25025 May 2017 Duke Energy Carolinas, LLC - Annual Report of Changes Pursuant to 10 CFR 50.46 RA-16-0025, Duke Energy Annual Report of Changes Pursuant to 10 CFR 50.462016-05-31031 May 2016 Duke Energy Annual Report of Changes Pursuant to 10 CFR 50.46 HNP-15-031, Annual Environmental (Nonradiological) Operating Report for 20142015-04-27027 April 2015 Annual Environmental (Nonradiological) Operating Report for 2014 HNP-13-050, Annual Report of Changes Pursuant to 10 CFR 50.46 for May 23, 2012 Through April 23, 20132013-06-0606 June 2013 Annual Report of Changes Pursuant to 10 CFR 50.46 for May 23, 2012 Through April 23, 2013 HNP-13-030, Annual Radiological Environmental Operating Report for 20122013-04-19019 April 2013 Annual Radiological Environmental Operating Report for 2012 HNP-13-039, Annual Environmental (Non-Radiological) Operating Report, January 1, 2012 Through December 31, 2012, Appendix B2013-04-19019 April 2013 Annual Environmental (Non-Radiological) Operating Report, January 1, 2012 Through December 31, 2012, Appendix B HNP-12-035, Submittal of Annual Radioactive Effluent Release Report2012-04-16016 April 2012 Submittal of Annual Radioactive Effluent Release Report HNP-11-046, Emergency Core Cooling System Evaluation Changes Annual Report2011-05-23023 May 2011 Emergency Core Cooling System Evaluation Changes Annual Report ML11123A2592011-04-27027 April 2011 Submittal of Annual Radiological Environmental Operating Report for 2010 HNP-11-031, Annual Environmental (Nonradiological) Operating Report2011-04-27027 April 2011 Annual Environmental (Nonradiological) Operating Report HNP-11-032, Annual Radioactive Effluent Release Report for 20102011-04-25025 April 2011 Annual Radioactive Effluent Release Report for 2010 HNP-11-011, Annual Report in Accordance with Technical Specification 6.9.1.22011-02-0202 February 2011 Annual Report in Accordance with Technical Specification 6.9.1.2 HNP-10-043, Submittal of Annual Radiological Environmental Operating Report2010-04-27027 April 2010 Submittal of Annual Radiological Environmental Operating Report HNP-10-041, Annual Radioactive Effluent Release Report for 20092010-04-16016 April 2010 Annual Radioactive Effluent Release Report for 2009 HNP-09-040, Annual Radiological Environmental Operating Report for 20082009-04-28028 April 2009 Annual Radiological Environmental Operating Report for 2008 HNP-09-015, Submittal of 2008 Annual Report in Accordance with Technical Specification 6.9.1.22009-02-0202 February 2009 Submittal of 2008 Annual Report in Accordance with Technical Specification 6.9.1.2 ML0817101312008-06-12012 June 2008 Submittal of Report of Changes Pursuant to CFR 50.59 HNP-07-044, Annual Environmental (Non-Radiological) Operating Report for 20062007-04-24024 April 2007 Annual Environmental (Non-Radiological) Operating Report for 2006 HNP-06-027, Annual Report in Accordance with Technical Specification 6.9.1.22006-02-0202 February 2006 Annual Report in Accordance with Technical Specification 6.9.1.2 HNP-05-100, Annual Radiological Environmental Operating Amended Report2005-09-23023 September 2005 Annual Radiological Environmental Operating Amended Report ML0513003802005-05-0909 May 2005 Report of Changes Pursuant to 10 CFR 50.59 for May 18, 2003 - December 31, 2004 HNP-05-041, Transmittal of Annual Environmental (Non-Radiological) Operating Report for 20042005-04-15015 April 2005 Transmittal of Annual Environmental (Non-Radiological) Operating Report for 2004 HNP-05-016, Annual Operating Report - 20042005-02-16016 February 2005 Annual Operating Report - 2004 HNP-04-057, Annual Environmental (Non-Radiological) Operating Report2004-04-23023 April 2004 Annual Environmental (Non-Radiological) Operating Report HNP-04-014, Annual Operating Report - 20032004-02-24024 February 2004 Annual Operating Report - 2003 HNP-03-043, Annual Environmental Operating Report2003-04-22022 April 2003 Annual Environmental Operating Report HNP-03-017, Annual Operating Report - 20022003-02-19019 February 2003 Annual Operating Report - 2002 HNP-02-057, Annual Environmental (Non-Radiological) Operating Report for 20012002-04-23023 April 2002 Annual Environmental (Non-Radiological) Operating Report for 2001 HNP-02-016, Annual Operating Report for 20012002-02-19019 February 2002 Annual Operating Report for 2001 2024-04-25
[Table view] |
Text
ENERGY June 6, 2013 Serial: HNP-13-050 ATTN: Document Control Desk U.S. Nuclear Regulatory Commiss i on Washington , DC 20555-0001 Shearon Harris Nuclear Power Plant , Unit 1 Docket No. 50-400
Subject:
Annual Report of Changes Pursuant to 1 0 CFR 50.46 Ladies and Gentlemen: David H. Corlett Manager , Regulatory Affa i rs Harris Nuc l ear Pl ant 5413 Shearon Harris Road New Hill NC 27562-9300 919.362.3137 10 CFR 50.46 Pursuant to 10 CFR 50.46(a)(3)(ii), Duke Energy Progress , Inc., formerly known as Carol i na Power & Light Company , hereby submits the enclosed annual report of changes to and errors discovered in the loss of coolant accident analyses for the Shearon Harris Nuclear Power Plant , Unit 1, for the period May 23 , 2012, through April 23 , 2013. This document contains no regulatory commitments. Please refer any questions regarding this submittal to John Caves at (919) 362-2406.
Sincerely , David H. Corlett DHC/jrc
Enclosure:
Annual Report of Changes Pursuant to 1 0 CFR 50.46 cc: Mr. J. D. Austin , NRC Sr. Resident Inspector , HNP Ms. A T. Billoch Colon , NRC Projec t Manager , HNP Mr. V. M. McCree , NRC Regional Adm i nistrator , Region II U.S. Nuclear Regulatory Commission Page 1 of 2 Enclosure to HNP-13-050 Shearon Harris Nuclear Power Plant, Unit 1 Annual Report of Changes Pursuant to 10 CFR 50.46 Reporting Period May 23, 2012, through April 23, 2013 Small Break Loss of Coolant Accident (SBLOCA) Analysis Evaluation Model:
AREVA EMF-2328(P)(A)
, PWR Small Break LOCA Evaluation Model, S-RELAP5 Based , Revision 0, March 2001
. The previous SBLOCA analysis of record was superseded using AREVA's EMF
-2 328, PWR Small Break LOCA Evaluation Model, S
-RELAP5 Based
. This result ed in a change to the peak clad temperature (PCT) of +33
°F. The base analysis of record PCT is 1627
°F.
The SBLOCA analysis is impacted by one error discovered during this reporting period
. The Sleicher-Rouse correlation for heat transfer is used by the S
-RELAP5 code.
One of the equations was initially not programmed in a form consistent with other heat transfer correlations and expected physical trends, which resulted in an impact of +4
°F. Summary of Changes
(°F) Resultant PCT (°F) SBLOCA PCT effective May 22, 2012 1594 Changes during reporting period Revised analysis of record
+33 1627 Errors during reporting period Sleicher-Rouse correlation
+4 1631 SBLOCA PCT effective April 23, 2013 1631 Sum of absolute values of PCT changes during this reporting period 37 The resultant predicted fuel element PCT, accounting for changes and errors in the evaluation model, is within the 2200
°F acceptance criteria in 10 CFR 50.46(b)(1).
U.S. Nuclear Regulatory Commission Page 2 of 2 Enclosure to HNP-13-050 Large Break Loss of Coolant Accident (LBLOCA) Analysis Evaluation Model:
AREVA ANP-3011(P), Harris Nuclear Plant Unit 1 Realistic Large Break LOCA Analysis , Revision 1, as approved by NRC Safety Evaluation dated May 30, 2012. This evaluation model is a plant specific implementation of AREVA EMF-2103(P)(A), Realistic Large Break LOCA Methodology, Revision 0 , April 2003.
The previous LBLOCA analysis of record was superseded using ANP-3011 , Harris Nuclear Plant Unit 1 Realistic Large Break LOCA Analysis
. The NRC safety evaluation documenting approval of ANP
-3011 require s that an adder of 138
°F be applied to calculated peak cladding temperatures to address concerns related to droplet shattering and fuel relocation.
In addition, the base analysis also includes a +14
°F impact for the Sleicher
-Rouse error, as discussed above related to SBLOCA. The base analysis of record PCT is 2071
°F.
The LBLOCA analysis is impacted by one error discovered during this reporting period. There was an error in the calculation of uncertainty for one parameter of the Cathcart
-Pawel oxide growth correlation used to calculate energy released from oxidation of cladding.
This results in a 0 °F impact on PCT.
Summary of Changes
(°F) Resultant PCT (°F) LBLOCA PCT effective May 22, 2012 2081 Changes during reporting period Revised analysis of record Calculated PCT: 1919
°F Conservative adder to account for uncertainties related to droplet shattering and fuel relocation: +138
°F Sleicher-Rouse correlation: +14 °F -10 2071 Errors during reporting period Cathcart-Pawel correlation 0 2071 LBLOCA PCT effective April 23, 2013 2071 Sum of absolute values of PCT changes during this reporting period 10 The resultant predicted fuel element PCT, accounting for changes and errors in the evaluation model, is within the 2200
°F acceptance criteria in 10 CFR 50.46(b)(1).