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| {{#Wiki_filter:DUKE Michael J. Annacone 526 South Church Street ENERGY, Charlotte, NC 28202 Mailing Address: Mail Code EC07H / P.O. Box 1006 Charlotte, NC 28201-1006 980-373-2544 704-382-6056 fax Serial: RA-13-012 June 26, 2013 10 CFR 50.4 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Brunswick Steam Electric Plant, Unit Numbers 1 and 2 Docket Numbers 50-325 AND 50-324/Renewed License Numbers DPR-71 AND DPR-62 Crystal River Unit 3 Nuclear Generating Plant Docket Number 50-302/License Number DPR-72 Shearon Harris Nuclear Power Plant, Unit Number 1 Docket Number 50-400/Renewed License Number NPF-63 H. B. Robinson Steam Electric Plant, Unit Number 2 Docket Number 50-261/Renewed License Number DPR-23 | | {{#Wiki_filter:DUKE ENERGY, Michael 526 SouthJ. Annacone Church Charlotte, NC 28202 Street Mailing Address: |
| | Mail Code EC07H / P.O. Box 1006 Charlotte, NC 28201-1006 980-373-2544 704-382-6056 fax Serial: RA-13-012 June 26, 2013 10 CFR 50.4 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Brunswick Steam Electric Plant, Unit Numbers 1 and 2 Docket Numbers 50-325 AND 50-324/Renewed License Numbers DPR-71 AND DPR-62 Crystal River Unit 3 Nuclear Generating Plant Docket Number 50-302/License Number DPR-72 Shearon Harris Nuclear Power Plant, Unit Number 1 Docket Number 50-400/Renewed License Number NPF-63 H. B. Robinson Steam Electric Plant, Unit Number 2 Docket Number 50-261/Renewed License Number DPR-23 |
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| ==Subject:== | | ==Subject:== |
| Carolina Power & Light Company (CP&L) and Florida Power Corporation (FPC)Capability to Perform Multi-Unit Dose Assessment | | Carolina Power & Light Company (CP&L) and Florida Power Corporation (FPC) |
| | Capability to Perform Multi-Unit Dose Assessment |
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| ==Reference:== | | ==Reference:== |
| : 1. Nuclear Energy Institute (NEI) Letter, Commitment for Implementation of Multi-Unit Dose Assessment Capability;, Pollock to Wiggins; dated March 14, 2013 (ADAMS Accession Number ML13073A522) | | : 1. Nuclear Energy Institute (NEI) Letter, Commitment for Implementation of Multi-Unit Dose Assessment Capability;,Pollock to Wiggins; dated March 14, 2013 (ADAMS Accession Number ML13073A522) |
| : 2. NRC Letter, Industry Implementation of Multi-Unit Dose Assessment Capability;, Wiggins to Pollock; dated February 27, 2013 (ADAMS Accession Number ML13029A632) | | : 2. NRC Letter, Industry Implementation of Multi-Unit Dose Assessment Capability;,Wiggins to Pollock; dated February 27, 2013 (ADAMS Accession Number ML13029A632) |
| : 3. Duke Energy Letter, Crystal River Unit 3 Certification of permanent cessation of power operations and that fuel has been permanently removed from the reactor, J. A. Franke to U.S. NRC, Dated 2/20/13, Serial No. 3F0213-07 (ADAMS Accession Number ML13056A005) | | : 3. Duke Energy Letter, Crystal River Unit 3 Certification of permanent cessation of power operations and that fuel has been permanently removed from the reactor, J. A. Franke to U.S. NRC, Dated 2/20/13, Serial No. 3F0213-07 (ADAMS Accession Number ML13056A005) |
| In accordance with Reference 1, this letter, from Duke Energy Progress, Inc., formally known as Carolina Power & Light Company, and Duke Energy Florida, Inc., formally known as Florida Power Corporation, hereby provides the following information concerning the capability to perform offsite dose assessment during an event involving multiple release pathways (e.g., releases from reactor containments and spent fuel pools) at the Brunswick, Crystal River, Shearon Harris, and H. B. Robinson Nuclear Stations: 1. Summary of current capability to perform multi-unit/multi-source dose assessment. | | In accordance with Reference 1, this letter, from Duke Energy Progress, Inc., formally known as Carolina Power & Light Company, and Duke Energy Florida, Inc., formally known as Florida Power Corporation, hereby provides the following information concerning the capability to perform offsite dose assessment during an event involving multiple release pathways (e.g., |
| | releases from reactor containments and spent fuel pools) at the Brunswick, Crystal River, Shearon Harris, and H. B. Robinson Nuclear Stations: |
| | : 1. Summary of current capability to perform multi-unit/multi-source dose assessment. |
| In the event of a multi-source or multi-unit release accident, dose assessors at the Brunswick, Crystal River, Shearon Harris, and H. B. Robinson Nuclear Stations would take the following actions: | | In the event of a multi-source or multi-unit release accident, dose assessors at the Brunswick, Crystal River, Shearon Harris, and H. B. Robinson Nuclear Stations would take the following actions: |
| United States Nuclear Regulatory Commission RA-1 3-012 Page 2 Qualified dose assessors at each nuclear station perform individual dose assessment calculations using Nuclear Regulatory Commission (NRC) dose assessment model RASCAL (Radiological Assessment and Consequence Analysis), Version 3.0.5. The program does not have the capability to perform simultaneous multiple release point calculations. | | |
| During a multiple release point event, individual dose assessment results are manually summed to determine total offsite dose to the public.2. Anticipated schedule to establish multi-unit/multi-source dose assessment capability on an interim and/or permanent basis if required.Manual summation of dose assessment results provides an interim capability and will continue to be performed until implementation of a multi-unit/multi-source software code.Brunswick, Shearon Harris, and H. B. Robinson will compile design data supporting modeling with a multi-source/multiple release pathway software code such as Raddose V or multi-source/multiple release point modeling capable version of Unified RASCAL Interface (URI), test the new program, develop relevant procedures, perform training, and complete implementation by December 31, 2014.3. A description of the administrative process that will be used to track completion of key actions (e.g., commitment tracking or corrective action program and tracking identifiers). | | United States Nuclear Regulatory Commission RA-1 3-012 Page 2 Qualified dose assessors at each nuclear station perform individual dose assessment calculations using Nuclear Regulatory Commission (NRC) dose assessment model RASCAL (Radiological Assessment and Consequence Analysis), Version 3.0.5. The program does not have the capability to perform simultaneous multiple release point calculations. During a multiple release point event, individual dose assessment results are manually summed to determine total offsite dose to the public. |
| Duke Energy will identify and track key actions through the corrective action program (CAP)as Action Request (AR) 610491.On February 20, 2013, Duke Energy Florida, Inc. certified to the NRC the permanent removal of fuel from the Crystal River Unit 3 reactor vessel. Therefore, Duke Energy has no plans to establish multi-unit/multi-source dose assessment capability at the Crystal River nuclear station.This letter contains one new voluntary regulatory commitment for Brunswick, Shearon Harris, and H.B. Robinson Nuclear Stations. | | : 2. Anticipated schedule to establish multi-unit/multi-source dose assessment capability on an interim and/or permanent basis if required. |
| That voluntary regulatory commitment is identified in Enclosure | | Manual summation of dose assessment results provides an interim capability and will continue to be performed until implementation of a multi-unit/multi-source software code. |
| : 1. Any other actions discussed in this letter should be considered intended or planned enhancement actions.Should you have any questions concerning the content of this letter, please contact Michael Austin, at 980-373-4134 (michaeL austin@duke-energy.
| | Brunswick, Shearon Harris, and H. B. Robinson will compile design data supporting modeling with a multi-source/multiple release pathway software code such as Raddose V or multi-source/multiple release point modeling capable version of Unified RASCAL Interface (URI), test the new program, develop relevant procedures, perform training, and complete implementation by December 31, 2014. |
| corn).Sincerely, ichael J. Annacone, Vice President | | : 3. A description of the administrative process that will be used to track completion of key actions (e.g., commitment tracking or corrective action program and tracking identifiers). |
| -Organizational Effectiveness | | Duke Energy will identify and track key actions through the corrective action program (CAP) as Action Request (AR) 610491. |
| &Regulatory Affairs Enclosure 1. Table of New Voluntary Regulatory Commitments United States Nuclear Regulatory Commission RA-13-012 Page 3 cc: USNRC Region II, Regional Administrator USNRC Region I, Regional Administrator USNRC Resident Inspector
| | On February 20, 2013, Duke Energy Florida, Inc. certified to the NRC the permanent removal of fuel from the Crystal River Unit 3 reactor vessel. Therefore, Duke Energy has no plans to establish multi-unit/multi-source dose assessment capability at the Crystal River nuclear station. |
| -BSEP, Unit Nos. 1 and 2 USNRC Resident Inspector | | This letter contains one new voluntary regulatory commitment for Brunswick, Shearon Harris, and H.B. Robinson Nuclear Stations. That voluntary regulatory commitment is identified in . Any other actions discussed in this letter should be considered intended or planned enhancement actions. |
| -SHNPP, Unit No. 1 USNRC Resident Inspector | | Should you have any questions concerning the content of this letter, please contact Michael Austin, at 980-373-4134 (michaeL austin@duke-energy.corn). |
| -HBRSEP, Unit No. 2 S. T. Hammann (NRC Region I, DNMS/DB)C. Gratton, NRR Project Manager -BSEP, Unit Nos. 1 and 2: CR-3 A. T. Billoch-Col6n, NRR Project Manager -SHNPP, Unit No. 1; HBRSEP, Unit No. 2 D. H. Jaffe, NRR/JLD/PMB, NRC Ms. Sue Perkins-Grew, NEI RA-13-012 Enclosure Enclosure 1 Table of New Voluntary Regulatory Commitments Below is a table of actions that are described within this document and considered voluntary regulatory commitments. | | Sincerely, ichael J. Annacone, Vice President - Organizational Effectiveness & |
| Any other statements in this document are provided for information purposes and are not considered to be regulatory commitments. | | Regulatory Affairs Enclosure |
| Commitment Action Request Number Scheduled Completion Date 1 Brunswick, Shearon Harris, and H. B. Robinson 610491 December 31, 2014 will compile design data supporting modeling with a multi-source/multiple release pathway software code such as Raddose V or multi-source/multiple release point modeling capable version of Unified RASCAL Interface (URI), test the new program, develop relevant procedures, perform training, and complete implementation by December 31, 2014.}} | | : 1. Table of New Voluntary Regulatory Commitments |
| | |
| | United States Nuclear Regulatory Commission RA-13-012 Page 3 cc: USNRC Region II,Regional Administrator USNRC Region I, Regional Administrator USNRC Resident Inspector - BSEP, Unit Nos. 1 and 2 USNRC Resident Inspector - SHNPP, Unit No. 1 USNRC Resident Inspector - HBRSEP, Unit No. 2 S. T. Hammann (NRC Region I, DNMS/DB) |
| | C. Gratton, NRR Project Manager - BSEP, Unit Nos. 1 and 2: CR-3 A. T. Billoch-Col6n, NRR Project Manager - SHNPP, Unit No. 1; HBRSEP, Unit No. 2 D. H. Jaffe, NRR/JLD/PMB, NRC Ms. Sue Perkins-Grew, NEI |
| | |
| | RA-13-012 Enclosure Enclosure 1 Table of New Voluntary Regulatory Commitments Below is a table of actions that are described within this document and considered voluntary regulatory commitments. Any other statements in this document are provided for information purposes and are not considered to be regulatory commitments. |
| | Commitment Action Request Scheduled Number Completion Date 1 Brunswick, Shearon Harris, and H. B. Robinson 610491 December 31, 2014 will compile design data supporting modeling with a multi-source/multiple release pathway software code such as Raddose V or multi-source/multiple release point modeling capable version of Unified RASCAL Interface (URI), test the new program, develop relevant procedures, perform training, and complete implementation by December 31, 2014.}} |
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Category:Graphics incl Charts and Tables
MONTHYEARRA-23-0043, Refuel 33 (R2R33) Inservice Inspection Program Ninety Day Owner'S Activity Report and Analytical Evaluations2023-03-30030 March 2023 Refuel 33 (R2R33) Inservice Inspection Program Ninety Day Owner'S Activity Report and Analytical Evaluations RA-20-0263, Duke Energy Corp. - Request to Use Provision of Later Edition and Addenda of ASME Boiler and Pressure Vessel Code, Section XI for Repair/Replacement Activities in Accordance with 10 CFR 50.55a(g)(4)(iv)2020-09-16016 September 2020 Duke Energy Corp. - Request to Use Provision of Later Edition and Addenda of ASME Boiler and Pressure Vessel Code, Section XI for Repair/Replacement Activities in Accordance with 10 CFR 50.55a(g)(4)(iv) ML16056A1392016-03-11011 March 2016 Correction to the U.S. Nuclear Regulatory Commission Analysis of Licensees' Decommissioning Funding Status Reports HNP-15-043, Response to Request for Additional Information 4 Regarding License Amendment Request to Revise Technical Specification Table 3.3-4 Loss of Offsite Power 6.9 Kv Emergency Undervoltage Primary Setpoints2015-05-13013 May 2015 Response to Request for Additional Information #4 Regarding License Amendment Request to Revise Technical Specification Table 3.3-4 Loss of Offsite Power 6.9 Kv Emergency Undervoltage Primary Setpoints ML14307B7072014-12-10010 December 2014 Supplemental Information Related to Development of Seismic Risk Evaluations for Information Request Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-T BSEP 13-0071, Recommendation 2.3 Seismic Walkdown of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident, Supplement to Walkdown Report2013-07-31031 July 2013 Recommendation 2.3 Seismic Walkdown of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident, Supplement to Walkdown Report RA-13-012, Capability to Perform Multi-Unit Dose Assessment2013-06-26026 June 2013 Capability to Perform Multi-Unit Dose Assessment ML13037A2042013-01-31031 January 2013 Response to Second Request for Additional Information to Support NRC Reactor Systems Branch (Srxb) Technical Review of the CR-3 Extended Power Uprate LAR ML12185A0242012-07-25025 July 2012 Incidental Take Limit Met for Green Turtles at Brunswick Steam Electric Plant, Units 1 and 2 ML1214500142012-05-23023 May 2012 NFPA 805 LAR Status Matrix - May 2012 ML11112A1222011-06-10010 June 2011 Request for Additional Information and Schedule Revision for the Review of the Crystal River Unit 3 Nuclear Generating Plant License Renewal Application (TAC Nos. ME0274 and ME0278) ML1029107172010-10-20020 October 2010 Horizontal Tendons Pages 26-39 ML1020401472010-07-22022 July 2010 NFPA 805 Pilot License Amendment Request Review Schedule Update, July 2010 ML1020302882010-07-13013 July 2010 Photograph - Brunswick Graphics and Sample Results ML1020301692010-07-0707 July 2010 Photos ML1020301682010-07-0707 July 2010 North Carolina Split Sample Results ML1013901262010-05-17017 May 2010 Table of Expiration Dates for Permits Associated with Crystal River Unit 3 for Draft Supplemental Environmental Impact Statement ML1013905052010-05-12012 May 2010 Event Timeline ML1029200882010-03-17017 March 2010 8.4 Inadequate Concrete Structure ML1029200892010-03-17017 March 2010 9.1 Hurricanes or Tornadoes ML1029200902010-03-17017 March 2010 9.2 Seismic Events ML1029200932010-03-17017 March 2010 9.3 Ground Movement ML1028703312010-01-30030 January 2010 5.7 Exhibit 7 Winter 2002-2010 ML1028703432010-01-29029 January 2010 Email - Subject: Detensioning Sequence Spreadsheets ML1027201562010-01-22022 January 2010 Email from Chou, Rich to Morrissey, Thomas, Dated Friday, January 22, 2010, 5:01 PM Cc Lake, Louis, Sykes, Marvin, Franke, Mark and Reyes, Rogerio; Subject: FW: Ctr Level II Schedule, Attachments: 01-25-10 Level 2 Rev E - 11x17.pdf ML1028706302010-01-22022 January 2010 Detensioning Sequence - Case 10 ML1028708112010-01-21021 January 2010 Email - from: Miller, Craig L (Craig.Miller@Pgnmail.Com) to Lake, Louis; Thomas, George; Carrion, Robert; 'Nausdj@Ornl.Gov'; Souther, Martin; 'Trowe@Wje.Com' Cc: Williams, Charles R. Dated Friday, January 22, 2010 8:53 Am Subject: FW: Failu ML1028711752010-01-21021 January 2010 5.3 Maintenance ML1028711742010-01-21021 January 2010 FW: Ctr Level II Schedule ML1028711762010-01-20020 January 2010 from: Williams, Charles R. (Charles.Williams@Pgnmail.Com) to: Lake, Louis; Thomas, George Dated Wednesday, January 20, 2010 5:16 PM Subject: FW: 01-21-10 Containment Repair Project Level 3 Schedule Attachments: 01 -21-10 Level 3 Rev D... At ML1028805012010-01-18018 January 2010 Email - from: Williams, Charles R., to: Lake, Louis; Thomas, George Dated Monday, January 18, 2010 4:18 PM, FW: 01-19-10 Containment Repair Project Level 3 Schedule, Attachments: 01-19-10 Level 3 Rev D - 11x17.pdf ML1028805092010-01-17017 January 2010 Email - from: Williams, Charles R. to: Lake, Louis, Thomas, George, Dated Sunday, January 17, 2010 9:28 Am, FW: 01-18-10 Containment Repair Prokect Level 3 Schedule, Attachments: 01-18-10 Level 3 Rev D - 11x17.pdf ML1028805242010-01-16016 January 2010 Email - from: Miller, Craig L (Craig.Miller@Pgnmail.Com) to: Miller, Craig L; Lake, Louis; Thomas, George; Carrion, Robert; 'Trowe@Wje.Com' Cc: Williams, Charles R. Dated Saturday, January 16, 2010 1:15 PM Subject: Failure Mode 5.1 for Revi ML1028805132010-01-16016 January 2010 Email - from: Miller, Craig L (Craig.Miller@Pgnmail.Com) to: Lake, Louis; Thomas, George; Carrion, Robert; 'Trowe@Wje.Com'; Sealey, Mac Cc: Williams, Charles R. Dated Saturday, January 16, 2010 1:24 PM, Failure Mode 2.6 for Review .. ML1028709162010-01-14014 January 2010 Email - from: Williams, Charles R. (Charles.Williams@Pgnmail.Com) to Lake, Louis; Thomas, George Dated Thursday, January 14, 2010 3:28 PM Subject: FW: 01-15-10 Containment Repair Project Level 3 Schedule ML1028709172010-01-14014 January 2010 Email - from: Williams, Charles R. (Charles.Williams@Pgnmail.Com) to: Lake, Louis; Thomas, George Dated Thursday, January 14, 2010 7:16 Am Subject: FW: 01-14-10 Containment Repair Project Level 3 Schedule ML1028709202010-01-13013 January 2010 5.1 Contamination During Construction ML1028709262010-01-13013 January 2010 Email - from: Williams, Charles R. to Lake, Louis; Thomas, George (Charles.Williams@Pgnmail.Com) Dated Wednesday, January 13, 2010 10:46 Am Subject: FW: 01-13-10 Containment Repair Project Level 3 Schedule ML1019305502010-01-0101 January 2010 10CFR50.75g File: Spreadsheet Groundwater.Xls BSEP Well Samples ML1029105832009-12-28028 December 2009 Engg Repair Work Flow 12-28-09.pdf ML1029106132009-12-22022 December 2009 Email-From: Orf, Tracy to Lake, Louis Dated Tuesday, December 22, 2009 6:31 Am Subject:Fw CR3 Updated Root Cause Information Attachments: 2009 Dec 18 - Root Cause Update for Nrc. Pptx ML1027204462009-12-0808 December 2009 3.4 Exhibit 7, Petrographic Report ML1011708192009-12-0303 December 2009 Root Cause Analysis - PII Metrics as of Dec 3rd 2009 ML1027204522009-12-0303 December 2009 2.2 Exhibit 3, Concrete Pour Data ML1027204452009-12-0303 December 2009 2.11 Concrete Pour Data ML1028711772009-11-23023 November 2009 8.1 and 8.5 ML1028804872009-11-23023 November 2009 3.1 Inadequate Air Content ML0932400582009-11-19019 November 2009 NFPA 805 Pilot License Amendment Request Review and Infrastructure Update, November, 2009 ML1029106712009-10-30030 October 2009 2009 Oct 30 - Root Cause Analysis Metrics.Pptx ML0917603592009-06-25025 June 2009 NFPA 805 Pilot License Amendment Request Review and Infrastructure Update, June 2009 2023-03-30
[Table view] Category:Letter type:RA
MONTHYEARRA-24-0012, Independent Spent Fuel Storage Installation - Annual Radioactive Effluent Release Report2024-02-0505 February 2024 Independent Spent Fuel Storage Installation - Annual Radioactive Effluent Release Report RA-24-0015, Submittal of 2023 Sea Turtle Annual Report2024-01-10010 January 2024 Submittal of 2023 Sea Turtle Annual Report RA-23-0325, Submittal of Procedures CSD-EP-HNP-0101-01, 02, CSD-EP-ONS-0101-01, CSD-EP-RNP-0101-01, and EP-RNP-EPLAN-ANNEX2024-01-0808 January 2024 Submittal of Procedures CSD-EP-HNP-0101-01, 02, CSD-EP-ONS-0101-01, CSD-EP-RNP-0101-01, and EP-RNP-EPLAN-ANNEX RA-24-0006, 10 CFR 50.54(q) Evaluation2024-01-0404 January 2024 10 CFR 50.54(q) Evaluation RA-23-0313, Baffle-Former Bolt (Bfb) Subsequent Inspection Interval Evaluation2023-12-14014 December 2023 Baffle-Former Bolt (Bfb) Subsequent Inspection Interval Evaluation RA-23-0306, Procedures CSD-EP-BNP-0101-01, EAL Technical Basis Document, Revision 006 and CSD-EP-CNS-0101-01, EAL Technical Basis Document, Revision 005, Summary Of.2023-12-12012 December 2023 Procedures CSD-EP-BNP-0101-01, EAL Technical Basis Document, Revision 006 and CSD-EP-CNS-0101-01, EAL Technical Basis Document, Revision 005, Summary Of. RA-23-0318, Supplement to Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-12-0404 December 2023 Supplement to Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation RA-23-0284, RA-23-0284 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-16016 November 2023 RA-23-0284 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation RA-23-0276, Response to Request for Additional Information Regarding License Amendment Request to Align Certain Technical Specification Requirements with Industry Standards Provided in Improved Standard Technical Specific2023-11-0606 November 2023 Response to Request for Additional Information Regarding License Amendment Request to Align Certain Technical Specification Requirements with Industry Standards Provided in Improved Standard Technical Specific RA-23-0281, Procedure EP-ALL-EPLAN, Duke Energy Common Emergency Plan, Revision 5, Summary of Changes2023-11-0101 November 2023 Procedure EP-ALL-EPLAN, Duke Energy Common Emergency Plan, Revision 5, Summary of Changes RA-23-0121, License Amendment Request to Adopt TSTF-258-A, Revision 4, Regarding Changes to Technical Specification Section 5.7, High Radiation Area2023-10-0505 October 2023 License Amendment Request to Adopt TSTF-258-A, Revision 4, Regarding Changes to Technical Specification Section 5.7, High Radiation Area RA-23-0218, Review Request for the Aging Management Program and Inspection Plan for the Shearon Harris Nuclear Power Plant, Unit 1, Reactor Vessel Internals2023-09-21021 September 2023 Review Request for the Aging Management Program and Inspection Plan for the Shearon Harris Nuclear Power Plant, Unit 1, Reactor Vessel Internals RA-23-0225, Procedure AD-EP-ALL-0109, Offsite Protective Action Recommendations, Revision 9, and the Joint Information Center (JIC) Relocation, Summary of Changes2023-09-20020 September 2023 Procedure AD-EP-ALL-0109, Offsite Protective Action Recommendations, Revision 9, and the Joint Information Center (JIC) Relocation, Summary of Changes RA-22-0290, License Amendment Request to Exclude the Dynamic Effects of Specific Postulated Pipe Ruptures from the Design and Licensing Basis Based on Leak-Before-Break Methodology2023-08-30030 August 2023 License Amendment Request to Exclude the Dynamic Effects of Specific Postulated Pipe Ruptures from the Design and Licensing Basis Based on Leak-Before-Break Methodology RA-23-0216, Independent Spent Fuel Storage Installation, Registration of Use of Spent Fuel Casks2023-08-22022 August 2023 Independent Spent Fuel Storage Installation, Registration of Use of Spent Fuel Casks RA-23-0199, Response to Request for Additional Information (RAI) Regarding Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) for Inservice Inspection of the Torus Metallic Liner2023-08-18018 August 2023 Response to Request for Additional Information (RAI) Regarding Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) for Inservice Inspection of the Torus Metallic Liner RA-23-0122, License Amendment Request to Revise the 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors, Categorization Process to .2023-08-17017 August 2023 License Amendment Request to Revise the 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors, Categorization Process to . RA-23-0195, Notice of Intentions Regarding Apparent Violation Response; (EA-23-060)2023-07-20020 July 2023 Notice of Intentions Regarding Apparent Violation Response; (EA-23-060) RA-23-0154, Duke Energy - Response to Request for Additional Information Regarding Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1)2023-07-20020 July 2023 Duke Energy - Response to Request for Additional Information Regarding Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1) RA-23-0136, Duke Energy Response to Request for Additional Information Regarding Proposed Alternative for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1)2023-07-20020 July 2023 Duke Energy Response to Request for Additional Information Regarding Proposed Alternative for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1) RA-23-0141, Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule2023-07-12012 July 2023 Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule RA-23-0142, Mcguire, Units 1 and 2, Oconee, Units 1, 2, and 3, H. B. Robinson, Unit 2, Response to Request for Additional Information Regarding the License Amendment Request to Revise Restrictive Technical Specification Surveillance Require2023-07-0707 July 2023 Mcguire, Units 1 and 2, Oconee, Units 1, 2, and 3, H. B. Robinson, Unit 2, Response to Request for Additional Information Regarding the License Amendment Request to Revise Restrictive Technical Specification Surveillance Require RA-23-0045, Inservice Inspection Program Owner'S Activity Report for Unit 2 Refueling Outage 262023-06-28028 June 2023 Inservice Inspection Program Owner'S Activity Report for Unit 2 Refueling Outage 26 RA-23-0145, Independent Spent Fuel Storage Installation (Isfsi), Registration for Use of General License Spent Fuel Casks2023-06-15015 June 2023 Independent Spent Fuel Storage Installation (Isfsi), Registration for Use of General License Spent Fuel Casks RA-23-0135, Submittal of 30 Day Report Per 10 CFR 26.719(c), Unsatisfactory Performance of Health and Human Services Certified Laboratory2023-06-0707 June 2023 Submittal of 30 Day Report Per 10 CFR 26.719(c), Unsatisfactory Performance of Health and Human Services Certified Laboratory RA-23-0139, Registration for Use of General License Spent Fuel Casks2023-06-0606 June 2023 Registration for Use of General License Spent Fuel Casks RA-23-0120, Supplemental Information Regarding Addition of Feedwater Isolation on Steam Generator Level High-High to Technical Specification 3.3.22023-05-31031 May 2023 Supplemental Information Regarding Addition of Feedwater Isolation on Steam Generator Level High-High to Technical Specification 3.3.2 RA-23-0005, License Amendment Request to Align Certain Technical Specification Requirements with Industry Standards Provided in Improved Standard Technical Specifications2023-05-31031 May 2023 License Amendment Request to Align Certain Technical Specification Requirements with Industry Standards Provided in Improved Standard Technical Specifications RA-23-0041, Response to NRC Regulatory Issue Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations2023-05-30030 May 2023 Response to NRC Regulatory Issue Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations RA-23-0047, Duke Energy Annual Radiological Environmental Operating Report - 20222023-04-26026 April 2023 Duke Energy Annual Radiological Environmental Operating Report - 2022 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-23-0064, Inservice Testing Program Plan and Snubber Program Plan for Sixth 10-Year Inservice Testing (1ST) Program Interval2023-04-24024 April 2023 Inservice Testing Program Plan and Snubber Program Plan for Sixth 10-Year Inservice Testing (1ST) Program Interval RA-23-0046, Annual Radioactive Effluent Release Report - 20222023-04-24024 April 2023 Annual Radioactive Effluent Release Report - 2022 RA-23-0098, Annual Environmental (Nonradiological) Operating Report2023-04-19019 April 2023 Annual Environmental (Nonradiological) Operating Report RA-23-0096, Post Accident Monitoring (PAM) Instrumentation Report2023-04-12012 April 2023 Post Accident Monitoring (PAM) Instrumentation Report RA-23-0063, Notification of Deviation from BWRVIP Guidelines2023-04-11011 April 2023 Notification of Deviation from BWRVIP Guidelines RA-23-0080, Refueling Outage 32 Steam Generator Tube Inspection Report Supplement Pursuant to Technical Specifications Task Force (TSTF) Traveler TSTF-577, Revision 1, Revised Frequencies for Steam Generator Tube2023-04-0505 April 2023 Refueling Outage 32 Steam Generator Tube Inspection Report Supplement Pursuant to Technical Specifications Task Force (TSTF) Traveler TSTF-577, Revision 1, Revised Frequencies for Steam Generator Tube RA-23-0043, Refuel 33 (R2R33) Inservice Inspection Program Ninety Day Owner'S Activity Report and Analytical Evaluations2023-03-30030 March 2023 Refuel 33 (R2R33) Inservice Inspection Program Ninety Day Owner'S Activity Report and Analytical Evaluations RA-23-0036, Biennial Decommissioning Financial Assurance Reports2023-03-30030 March 2023 Biennial Decommissioning Financial Assurance Reports RA-23-0040, Onsite Property Insurance Coverage2023-03-30030 March 2023 Onsite Property Insurance Coverage RA-23-0039, 10 CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums2023-03-30030 March 2023 10 CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums RA-23-0055, Notice of Intent to Pursue Subsequent License Renewal for H. B. Robinson Steam Electric Plant, Unit Number 22023-03-24024 March 2023 Notice of Intent to Pursue Subsequent License Renewal for H. B. Robinson Steam Electric Plant, Unit Number 2 RA-23-0021, Unit 2 Cycle 26 Core Operating Limits Report (COLR)2023-02-22022 February 2023 Unit 2 Cycle 26 Core Operating Limits Report (COLR) RA-22-0257, Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1)2023-02-17017 February 2023 Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1) RA-22-0091, Application to Revise Technical Specifications to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements2023-02-16016 February 2023 Application to Revise Technical Specifications to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements RA-23-0015, Response to Request for Additional Information (RAI) Regarding Addition of Feedwater Isolation on Steam Generator Level High-High to Technical Specification 3.3.22023-02-0909 February 2023 Response to Request for Additional Information (RAI) Regarding Addition of Feedwater Isolation on Steam Generator Level High-High to Technical Specification 3.3.2 RA-22-0081, License Amendment Request to Address Administrative Changes to the Operating License and Technical Specifications2023-02-0707 February 2023 License Amendment Request to Address Administrative Changes to the Operating License and Technical Specifications RA-23-0001, Request to Use a Provision of a Later Edition and Addenda of the ASME Boiler and Pressure Vessel Code, Section XI2023-02-0202 February 2023 Request to Use a Provision of a Later Edition and Addenda of the ASME Boiler and Pressure Vessel Code, Section XI RA-22-0118, License Amendment Request to Revise Restrictive Technical Specification Surveillance Requirement Frequencies2023-02-0101 February 2023 License Amendment Request to Revise Restrictive Technical Specification Surveillance Requirement Frequencies RA-23-0029, Technical Specifications Section 5.6.6 Post Accident Monitoring Instrumentation Report for Inoperable Containment Sump Water Level (Wide Range)2023-01-30030 January 2023 Technical Specifications Section 5.6.6 Post Accident Monitoring Instrumentation Report for Inoperable Containment Sump Water Level (Wide Range) 2024-02-05
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DUKE ENERGY, Michael 526 SouthJ. Annacone Church Charlotte, NC 28202 Street Mailing Address:
Mail Code EC07H / P.O. Box 1006 Charlotte, NC 28201-1006 980-373-2544 704-382-6056 fax Serial: RA-13-012 June 26, 2013 10 CFR 50.4 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Brunswick Steam Electric Plant, Unit Numbers 1 and 2 Docket Numbers 50-325 AND 50-324/Renewed License Numbers DPR-71 AND DPR-62 Crystal River Unit 3 Nuclear Generating Plant Docket Number 50-302/License Number DPR-72 Shearon Harris Nuclear Power Plant, Unit Number 1 Docket Number 50-400/Renewed License Number NPF-63 H. B. Robinson Steam Electric Plant, Unit Number 2 Docket Number 50-261/Renewed License Number DPR-23
Subject:
Carolina Power & Light Company (CP&L) and Florida Power Corporation (FPC)
Capability to Perform Multi-Unit Dose Assessment
Reference:
- 1. Nuclear Energy Institute (NEI) Letter, Commitment for Implementation of Multi-Unit Dose Assessment Capability;,Pollock to Wiggins; dated March 14, 2013 (ADAMS Accession Number ML13073A522)
- 2. NRC Letter, Industry Implementation of Multi-Unit Dose Assessment Capability;,Wiggins to Pollock; dated February 27, 2013 (ADAMS Accession Number ML13029A632)
- 3. Duke Energy Letter, Crystal River Unit 3 Certification of permanent cessation of power operations and that fuel has been permanently removed from the reactor, J. A. Franke to U.S. NRC, Dated 2/20/13, Serial No. 3F0213-07 (ADAMS Accession Number ML13056A005)
In accordance with Reference 1, this letter, from Duke Energy Progress, Inc., formally known as Carolina Power & Light Company, and Duke Energy Florida, Inc., formally known as Florida Power Corporation, hereby provides the following information concerning the capability to perform offsite dose assessment during an event involving multiple release pathways (e.g.,
releases from reactor containments and spent fuel pools) at the Brunswick, Crystal River, Shearon Harris, and H. B. Robinson Nuclear Stations:
- 1. Summary of current capability to perform multi-unit/multi-source dose assessment.
In the event of a multi-source or multi-unit release accident, dose assessors at the Brunswick, Crystal River, Shearon Harris, and H. B. Robinson Nuclear Stations would take the following actions:
United States Nuclear Regulatory Commission RA-1 3-012 Page 2 Qualified dose assessors at each nuclear station perform individual dose assessment calculations using Nuclear Regulatory Commission (NRC) dose assessment model RASCAL (Radiological Assessment and Consequence Analysis), Version 3.0.5. The program does not have the capability to perform simultaneous multiple release point calculations. During a multiple release point event, individual dose assessment results are manually summed to determine total offsite dose to the public.
- 2. Anticipated schedule to establish multi-unit/multi-source dose assessment capability on an interim and/or permanent basis if required.
Manual summation of dose assessment results provides an interim capability and will continue to be performed until implementation of a multi-unit/multi-source software code.
Brunswick, Shearon Harris, and H. B. Robinson will compile design data supporting modeling with a multi-source/multiple release pathway software code such as Raddose V or multi-source/multiple release point modeling capable version of Unified RASCAL Interface (URI), test the new program, develop relevant procedures, perform training, and complete implementation by December 31, 2014.
- 3. A description of the administrative process that will be used to track completion of key actions (e.g., commitment tracking or corrective action program and tracking identifiers).
Duke Energy will identify and track key actions through the corrective action program (CAP) as Action Request (AR) 610491.
On February 20, 2013, Duke Energy Florida, Inc. certified to the NRC the permanent removal of fuel from the Crystal River Unit 3 reactor vessel. Therefore, Duke Energy has no plans to establish multi-unit/multi-source dose assessment capability at the Crystal River nuclear station.
This letter contains one new voluntary regulatory commitment for Brunswick, Shearon Harris, and H.B. Robinson Nuclear Stations. That voluntary regulatory commitment is identified in . Any other actions discussed in this letter should be considered intended or planned enhancement actions.
Should you have any questions concerning the content of this letter, please contact Michael Austin, at 980-373-4134 (michaeL austin@duke-energy.corn).
Sincerely, ichael J. Annacone, Vice President - Organizational Effectiveness &
Regulatory Affairs Enclosure
- 1. Table of New Voluntary Regulatory Commitments
United States Nuclear Regulatory Commission RA-13-012 Page 3 cc: USNRC Region II,Regional Administrator USNRC Region I, Regional Administrator USNRC Resident Inspector - BSEP, Unit Nos. 1 and 2 USNRC Resident Inspector - SHNPP, Unit No. 1 USNRC Resident Inspector - HBRSEP, Unit No. 2 S. T. Hammann (NRC Region I, DNMS/DB)
C. Gratton, NRR Project Manager - BSEP, Unit Nos. 1 and 2: CR-3 A. T. Billoch-Col6n, NRR Project Manager - SHNPP, Unit No. 1; HBRSEP, Unit No. 2 D. H. Jaffe, NRR/JLD/PMB, NRC Ms. Sue Perkins-Grew, NEI
RA-13-012 Enclosure Enclosure 1 Table of New Voluntary Regulatory Commitments Below is a table of actions that are described within this document and considered voluntary regulatory commitments. Any other statements in this document are provided for information purposes and are not considered to be regulatory commitments.
Commitment Action Request Scheduled Number Completion Date 1 Brunswick, Shearon Harris, and H. B. Robinson 610491 December 31, 2014 will compile design data supporting modeling with a multi-source/multiple release pathway software code such as Raddose V or multi-source/multiple release point modeling capable version of Unified RASCAL Interface (URI), test the new program, develop relevant procedures, perform training, and complete implementation by December 31, 2014.