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Category:Code Relief or Alternative
MONTHYEARML12249A2362012-10-11011 October 2012
Nuclear Generating Plant - Relief Request #11-001-MX Related to Suspension of Concrete Containment Examination for the Fourth-10-Year Interval of the Inservice Inspection Program
3F0912-08, Relief Request 11-001-MX, Revision 0, Commitment to Submit Alternate Surveillance Requirements Per 10 CFR 50.55a(a)(3)(i)2012-09-19019 September 2012
Relief Request #11-001-MX, Revision 0, Commitment to Submit Alternate Surveillance Requirements Per 10 CFR 50.55a(a)(3)(i)
3F0412-08, Relief Request (RR) 12-001-MX Revision 0, Approval to Use ASME Code Case N-791 for Containment Repair2012-04-30030 April 2012
Relief Request (RR) #12-001-MX Revision 0, Approval to Use ASME Code Case N-791 for Containment Repair
ML1006400842010-03-19019 March 2010
Relief Requests 09 001 II, 09 002 II, and 09 003 II, Third 10-year Interval Inservice Inspection Program Plan.
3F0309-06, Submittal of Relief Request 09-001-IT, Revision 02009-03-30030 March 2009
Submittal of Relief Request #09-001-IT, Revision 0
ML0908204922009-03-20020 March 2009
Submittal of Third Ten-Year Inservice Inspection Interval Relief Requests #09-001-11, #09-002-11 and #09-003-11
ML0822103922008-09-0909 September 2008
Request for Relief No. 07-001-SS Regarding the Fourth 10-Year Interval Inservice Inspection Visual Examination of the Reactor Vessel Support Skirt
ML0812604712008-05-22022 May 2008
Relief Request #08-001-RR, Revision 1, to Install a Weld Overlay on the Dissimilar Metal Weld in the Decay Heat Drop Line
3F0907-05, Relief Request 07-003-RR, Revision 1, and Response to Request for Additional Information2007-09-13013 September 2007
Relief Request #07-003-RR, Revision 1, and Response to Request for Additional Information
ML0601302032006-02-0101 February 2006
Relief Request Subsequent Edition Letter and Addenda to Section XI of the ASME Code for Repair/Replacement Activities
ML0400604752004-01-0606 January 2004
Ltr Safety Evaluation of Relief Request 03-001-RR and 03-0002-RR Concerning Alternative Repair Method and Flaw Characterization for Pressurizer Instrument Nozzle Penetrations
2012-09-19
[Table view]
Category:Letter type:
MONTHYEAR3F0623-01, Report of Investigation Pursuant to 10 CFR 20, Appendix G2023-06-0101 June 2023
Report of Investigation Pursuant to 10 CFR 20, Appendix G
3F0423-03, 2022 Annual Radiological Environmental Operating Report2023-04-18018 April 2023
2022 Annual Radiological Environmental Operating Report
3F0423-02, 2022 Annual Radioactive Effluent Release Report2023-04-18018 April 2023
2022 Annual Radioactive Effluent Release Report
3F0423-01, 2022 Individual Monitoring NRC Form 5 Report2023-04-0404 April 2023
2022 Individual Monitoring NRC Form 5 Report
3F0323-03, Decommissioning Funding Plan for Independent Spent Fuel Storage Installation2023-03-31031 March 2023
Decommissioning Funding Plan for Independent Spent Fuel Storage Installation
3F0323-02, Annual Decommissioning and Irradiated Fuel Management Financial Status Report for 20222023-03-29029 March 2023
Annual Decommissioning and Irradiated Fuel Management Financial Status Report for 2022
3F0323-01, Onsite Property Insurance Coverage2023-03-0202 March 2023
Onsite Property Insurance Coverage
3F0123-01, Proof of Financial Protection2023-01-26026 January 2023
Proof of Financial Protection
3F1222-01, Nuclear Power Station - License Amendment Request 262 Addition of License Condition 2.C.21, License Termination Plan2022-12-12012 December 2022
Nuclear Power Station - License Amendment Request 262 Addition of License Condition 2.C.21, License Termination Plan
3F0522-03, Notification of Revised Decommissioning Cost Estimate2022-05-26026 May 2022
Notification of Revised Decommissioning Cost Estimate
3F0522-01, Safety Analysis Report, Quality Assurance Program and 10 CFR 50.59 - 10 CFR 72.48 Report - May 20222022-05-17017 May 2022
Safety Analysis Report, Quality Assurance Program and 10 CFR 50.59 - 10 CFR 72.48 Report - May 2022
3F0422-02, 2021 Annual Radiological Environmental Operating Report2022-04-0606 April 2022
2021 Annual Radiological Environmental Operating Report
3F0322-01, Annual Decommissioning and Irradiated Fuel Management Financial Status Report for 20212022-03-30030 March 2022
Annual Decommissioning and Irradiated Fuel Management Financial Status Report for 2021
3F0322-03, Drug and Alcohol Testing Error at HHS-Certified Laboratory, Per 10CFR26.719(c)(1)2022-03-10010 March 2022
Drug and Alcohol Testing Error at HHS-Certified Laboratory, Per 10CFR26.719(c)(1)
3F0322-02, 2021 Individual Monitoring NRC Form 5 Report2022-03-0707 March 2022
2021 Individual Monitoring NRC Form 5 Report
3F0222-01, ADP CR3, LLC - Update to Irradiated Fuel Management Program Pursuant to 10 CFR 50.54(bb)2022-02-0909 February 2022
ADP CR3, LLC - Update to Irradiated Fuel Management Program Pursuant to 10 CFR 50.54(bb)
3F0222-02, Onsite Property Insurance Coverage2022-02-0909 February 2022
Onsite Property Insurance Coverage
3F0122-01, License Amendment Request to Remove from the Facility Operating License, Appendix B, Environmental Protection Plan (Non-Radiological) Technical Specifications2022-01-26026 January 2022
License Amendment Request to Remove from the Facility Operating License, Appendix B, Environmental Protection Plan (Non-Radiological) Technical Specifications
3F0122-02, Proof of Financial Protection2022-01-17017 January 2022
Proof of Financial Protection
3F0122-03, Complex - Environmental Protection Plan Report: 2021 Sea Turtle Rescue and Recovery Summary Report2022-01-17017 January 2022
Complex - Environmental Protection Plan Report: 2021 Sea Turtle Rescue and Recovery Summary Report
3F1021-01, Report of Investigation Pursuant to 10 CFR 20, Appendix G2021-10-21021 October 2021
Report of Investigation Pursuant to 10 CFR 20, Appendix G
3F0921-02, Reporting Related to the National Pollutant Discharge Elimination System (NPDES) Permit Id FL0A00004 (Minor) (Rev. C)2021-09-29029 September 2021
Reporting Related to the National Pollutant Discharge Elimination System (NPDES) Permit Id FL0A00004 (Minor) (Rev. C)
3F0921-01, to License Amendment Request, Revision 0, ISFSI Security Plan, Revision a2021-09-14014 September 2021
to License Amendment Request, Revision 0, ISFSI Security Plan, Revision a
3F0721-01, Report of Investigation Pursuant to 10 CFR 20, Appendix G2021-07-13013 July 2021
Report of Investigation Pursuant to 10 CFR 20, Appendix G
3F0621-02, Reporting Related to the National Pollutant Discharge Elimination System (NPDES) Permit Id FL0A00004-001-IW1S2021-06-16016 June 2021
Reporting Related to the National Pollutant Discharge Elimination System (NPDES) Permit Id FL0A00004-001-IW1S
3F0421-05, 2020 Individual Monitoring NRC Form 5 Report2021-04-27027 April 2021
2020 Individual Monitoring NRC Form 5 Report
3F0421-04, ADP CR3, LLC - Supplement to Application for Order Approving Indirect Transfers of Control of Licenses in Connection with Internal Corporate Reorganization2021-04-13013 April 2021
ADP CR3, LLC - Supplement to Application for Order Approving Indirect Transfers of Control of Licenses in Connection with Internal Corporate Reorganization
3F0421-03, Proof of Financial Protection2021-04-0707 April 2021
Proof of Financial Protection
3F0421-01, 2020 Annual Radioactive Effluent Release Report2021-04-0606 April 2021
2020 Annual Radioactive Effluent Release Report
3F0421-02, 2020 Annual Radiological Environmental Operating Report2021-04-0606 April 2021
2020 Annual Radiological Environmental Operating Report
3F0321-07, (XEG)-DOE/NRC Forms 741 742 and 743C2021-03-30030 March 2021
(XEG)-DOE/NRC Forms 741 742 and 743C
3F0321-06, Annual Decommissioning and Irradiated Fuel Management Financial Status Report for 20202021-03-29029 March 2021
Annual Decommissioning and Irradiated Fuel Management Financial Status Report for 2020
3F0321-01, License Amendment Request, Revision to Independent Spent Fuel Storage Installation (ISFSI)-Only Emergency Plan, Draft a, and ISFSI Only Emergency Action Level Bases Manual2021-03-17017 March 2021
License Amendment Request, Revision to Independent Spent Fuel Storage Installation (ISFSI)-Only Emergency Plan, Draft a, and ISFSI Only Emergency Action Level Bases Manual
3F0321-02, License Amendment Request, Rev. 0, ISFSI Security Plan, Rev. a2021-03-17017 March 2021
License Amendment Request, Rev. 0, ISFSI Security Plan, Rev. a
3F0321-05, Onsite Property Insurance Coverage2021-03-15015 March 2021
Onsite Property Insurance Coverage
3F0321-03, Report of Investigation Pursuant to 10 CFR 20, Appendix G2021-03-0909 March 2021
Report of Investigation Pursuant to 10 CFR 20, Appendix G
3F0221-02, Report of Investigation Pursuant to 10 CFR 20, Appendix G2021-02-17017 February 2021
Report of Investigation Pursuant to 10 CFR 20, Appendix G
3F0221-01, ADP CR3, Llc., Crystal River Energy Complex - Environmental Protection Plan Report: 2020 Sea Turtle Rescue and Recovery Summary Report2021-02-0202 February 2021
ADP CR3, Llc., Crystal River Energy Complex - Environmental Protection Plan Report: 2020 Sea Turtle Rescue and Recovery Summary Report
3F0121-02, Request for Exemption from 10 CFR 20, Appendix G, Section Iii.E2021-01-19019 January 2021
Request for Exemption from 10 CFR 20, Appendix G, Section Iii.E
3F0121-01, Report of Investigation Pursuant to 10 CFR 20, Appendix G2021-01-19019 January 2021
Report of Investigation Pursuant to 10 CFR 20, Appendix G
3F1120-02, and Crystal River Nuclear Plant - Application for Order Approving Indirect Transfers of Control of Licenses in Connection with Internal Corporate Reorganization2020-11-19019 November 2020
and Crystal River Nuclear Plant - Application for Order Approving Indirect Transfers of Control of Licenses in Connection with Internal Corporate Reorganization
3F0920-02, Request to Transfer the Quality Assurance Program Approval Form for Radioactive Material Packages2020-09-15015 September 2020
Request to Transfer the Quality Assurance Program Approval Form for Radioactive Material Packages
3F0920-01, License Transfer - Notification of Transfer Date2020-09-15015 September 2020
License Transfer - Notification of Transfer Date
3F0720-03, ISFSI Only Emergency Plan and Implementing Procedure2020-07-21021 July 2020
ISFSI Only Emergency Plan and Implementing Procedure
3F0720-02, License Transfer - Insurance Required of a Licensee Under 10 CFR 140.11(a)(4) and 10 CFR 50.54(w)2020-07-15015 July 2020
License Transfer - Insurance Required of a Licensee Under 10 CFR 140.11(a)(4) and 10 CFR 50.54(w)
3F0520-01, Safety Analysis Report, Quality Assurance Program and 10 CFR 50.59 - 10 CFR 72.48 Report - May 20202020-05-18018 May 2020
Safety Analysis Report, Quality Assurance Program and 10 CFR 50.59 - 10 CFR 72.48 Report - May 2020
3F0420-03, Supplemental Information in Support of Crystal River Unit 3 License Transfer Application - Amended License Conditions2020-04-22022 April 2020
Supplemental Information in Support of Crystal River Unit 3 License Transfer Application - Amended License Conditions
3F0420-01, 2019 Annual Radioactive Effluent Release Report2020-04-0707 April 2020
2019 Annual Radioactive Effluent Release Report
3F0420-02, 2019 Radiological Environmental Operating Report2020-04-0707 April 2020
2019 Radiological Environmental Operating Report
3F0320-04, Decommissioning Funding Plan for Independent Spent Fuel Storage Installation2020-03-19019 March 2020
Decommissioning Funding Plan for Independent Spent Fuel Storage Installation
2023-06-01
[Table view] |
Text
Progress Energy Crystal River Nuclear Plant Docket No. 50-302 Operating License No. DPR-72 Ref: 10 CFR 50.55a April 30, 2012 3F0412-08 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001
Subject:
Crystal River Unit 3 - Relief Request (RR) #12-001-MX Revision 0, Approval to Use ASME Code Case N-791 for the Crystal River Unit 3 Containment Repair Ladies and Gentlemen:
Pursuant to 10 CFR 50.55a(a)(3)(i), Florida Power Corporation (FPC), doing business as Progress Energy Florida, Inc., hereby requests Nuclear Regulatory Commission (NRC) approval of the enclosed alternative to the original Construction Code and ASME Section III, Division 2, for the fourth 10-year interval of the Inservice Inspection Program. Relief Request (RR) #12-001-MX, Revision 0, requests approval to use ASME Code Case N-791, "Shear Screw and Sleeve Splices," as an option for reinforcement splicing for the Crystal River Unit 3 (CR-3) containment repair.
ASME Section Xl IWL, paragraph IWL-4230, "Reinforcing Steel," states, "Damagedreinforcing steel shall be corrected by any method permitted in the original Construction Code or in Section Ill, Division 2, with or without removal of the damaged reinforcement." During the CR-3 containment repair, FPC will select the most appropriate splice type for application from the original Construction Code, ASME Section III, Division 2, or apply ASME Code Case N-791.
This proposed alternative was discussed with the NRC NRR Project Manager for CR-3 during a telephone conference call on March 22, 2012. At that time, FPC communicated the intent to submit this relief request.
FPC requests approval of Relief Request #12-001-MX, Revision 0, by January 31, 2013.
This correspondence contains no new regulatory commitments.
If you have any questions regarding this submittal, please contact Mr. Dan Westcott, Superintendent, Licensing and Regulatory Programs at (352) 563-4796.
S ince rely Blair P. Wunderly Director-Engineering-Nuclear Crystal River Nuclear Plant BPW/scp
Enclosure:
Relief Request #12-001-MX, Revision 0 xc: NRR Project Manager Senior Resident Inspector Regional Administrator, Region II Progress Energy Florida, Inc.
Crystal River Nuclear Plant 15760 W. Power Line Street Crystal River, FL 34428
CRYSTAL RIVER UNIT 3 DOCKET NUMBER 50-302 / LICENSE NUMBER DPR-72 ENCLOSURE RELIEF REQUEST #12-001-MX, REVISION 0
U. S. Nuclear Regulatory Commission Enclosure 3F0412-08 Page 1 of 2 RELIEF REQUEST (RR) #12-001-MX, REVISION 0, APPROVAL TO USE ASME CODE CASE N-791 FOR THE CRYSTAL RIVER UNIT 3 CONTAINMENT REPAIR Proposed Alternative in Accordance with 10 CFR 50.55a(a)(3)(i)
--Alternative Provides Acceptable Level of Quality and Safety--
- 1. ASME Code Component Affected The affected component is the Crystal River Unit 3 (CR-3) containment. The containment is classified as structural Class I.
- 2. Applicable Code Edition and Addenda The applicable Code is American Society of Mechanical Engineers (ASME) Section Xl, 2001 Edition with Addenda through 2003 and ASME Section III, Division 2, for Concrete Containments, 2001 Edition with Addenda through 2003 by reference in paragraph IWL-4230.
- 3. Applicable Code Requirement IWL-4000 applies to Repair/Replacement Activities and is applicable to the CR-3 containment repair. IWL-4230, "Reinforcing Steel," states, "Damagedreinforcing steel shall be corrected by any method permitted in the original Construction Code or in Section III, Division 2, with or without removal of the damaged reinforcement." Therefore, by reference, ASME Section III, Division 2, is applicable to the CR-3 containment repair, and the request to apply ASME Code Case N-791 is consistent with the regulatory framework for CR-3.
- 4. Reason for Request During the course of the CR-3 containment repair, reinforcement will be repaired or replaced, and additional reinforcement will be installed. Reinforcement splicing will be used in accordance with methods permitted in the original Construction Code, American Concrete Institute (ACI) 318-63, "Building Code Requirements for Reinforced Concrete," ASME Section III, Division 2, or Code Case N-791 (once this alternative is approved). CR-3 will choose the reinforcement splicing method that is the most applicable to each specific installation situation.
Shear screw and sleeve splices have been demonstrated to be an effective alternative to the mechanical splice types in ASME Section III, Division 2, and will improve construction efficiency.
- 5. Proposed Alternative and Basis for Use The proposed alternative to the reinforcement installation methods contained in the original Construction Code and ASME Section III, Division 2, is to also use shear screw and sleeve splices in accordance with the provisions of ASME Code Case N-791, "ShearScrew and Sleeve Splices."
Shear screw and sleeve splices in reinforcing bar sizes #6 and #8 were approved for use in a License Amendment for the Sequoyah Nuclear Plant, Unit 1, for their concrete shield building dome (see Precedents information below). The test report submitted to the NRC in support of this amendment demonstrated that the Bar-Lock L-series shear screw and sleeve splice exceeded the ASME Code test requirements of ASME Section III, Division 2, CC-4333.2.3 for mechanical splices by a significant margin. This testing used the qualification criteria of ASME
U. S. Nuclear Regulatory Commission Enclosure 3F0412-08 Page 2 of 2 Section III, Division 2, CC-4333, "Mechanical Splices." The Safety Evaluation for this amendment, in part, stated:
"The licensee has tested more specimens than requiredby the ASME Code, which increases the confidence level for the acceptance of the Bar-Lock's assembly. The static and cyclic test methods and results have met the requirements of the Code.
The results of the additional tests of the 1000 cycles of loading and of the tensile test to failure after the 100 cycles of loading demonstrate that the assemblies exceed the ASME, Section Il/, Division 2, requirements for static and cyclic tests for mechanicalsplices."
Code Case N-791 was approved by ASME on September 20, 2010, and by the American Concrete Institute on October 23, 2010. The Code Case essentially duplicates the requirements of ASME Section III, Division 2, CC-4333 except in the specification of 'essential variables' and 'splicing procedures' where functional differences in mechanical splice types dictate changes in these parameters.
Two important distinctions exist between ASME Code Case N-791 and the License Amendment that was approved by the NRC for Sequoyah: 1) the Code Case applies to all bar sizes, and 2) the Code Case is not limited to approval of a specific splice by manufacturer and series.
Approval of the Code Case by the ASME Section III Committee and ACI indicates broad industry endorsement of the use of shear screw and sleeve splices for nuclear safety-related applications.
Florida Power Corporation (FPC) requests approval to use shear screw and sleeve splices in accordance with the provisions of Code Case N-791, "Shear Screw and Sleeve Splices," ASME Section III, Division 2, in addition to to the reinforcement installation methods contained in the original Construction Code and ASME Section III, Division 2. FPC has determined that use of the proposed alternative, in accordance with10 CFR 50.55a(a)(3)(i), provides an acceptable level of quality and safety.
- 6. Duration of Proposed Alternative The duration of the proposed alternative is through the end of the current interval. This will encompass the duration of the CR-3 containment repair.
- 7. Precedents No requests for approval to use ASME Code Case N-791 have been identified. However, two sizes of this type of splice were approved by the NRC for use at the Sequoyah Nuclear Plant, Unit 1, Docket 05000327, by letter dated April 24, 2003, TAC No. MB8056, Accession No. ML031140078.
- 8. References None.
