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Category:Inservice/Preservice Inspection and Test Report
MONTHYEARRA-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-20-0329, Proposed Alternative for Inservice Inspection of the Containment Metallic Liner and Moisture Barriers2021-09-0707 September 2021 Proposed Alternative for Inservice Inspection of the Containment Metallic Liner and Moisture Barriers RA-21-0056, Refueling Outage 32 Steam Generator Tube Inspection Report2021-05-26026 May 2021 Refueling Outage 32 Steam Generator Tube Inspection Report RA-19-0393, Refuel 32 (R2R32) Inservice Inspection Program Ninety Day Owner'S Activity Report2021-03-0808 March 2021 Refuel 32 (R2R32) Inservice Inspection Program Ninety Day Owner'S Activity Report RA-19-0138, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) for Reactor Vessel Cold Leg Dissimilar Metal Weld Inspections2019-07-23023 July 2019 Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) for Reactor Vessel Cold Leg Dissimilar Metal Weld Inspections RA-19-0106, Relief Requested in Accordance with 10 CFR 50.55a(z)(1) for Volumetric or Surface Examination of Code Case N-729-4 Examinations of the Reactor Pressure Vessel Upper Head2019-07-10010 July 2019 Relief Requested in Accordance with 10 CFR 50.55a(z)(1) for Volumetric or Surface Examination of Code Case N-729-4 Examinations of the Reactor Pressure Vessel Upper Head RA-19-0094, Refuel 31 (R231) Owner'S Activity Report, Fifth 10-Year Inservice Inspection Interval2019-02-20020 February 2019 Refuel 31 (R231) Owner'S Activity Report, Fifth 10-Year Inservice Inspection Interval RNP-RA/17-0065, Refueling Outage 30 Steam Generator Tube Inspection Report2017-09-18018 September 2017 Refueling Outage 30 Steam Generator Tube Inspection Report RNP-RA/17-0051, Submittal of Nine Day Inservice Inspection Summary Report2017-06-29029 June 2017 Submittal of Nine Day Inservice Inspection Summary Report RNP-RA/15-0081, Submittal of Ninety-Day Inservice Inspection Summary Report2015-09-17017 September 2015 Submittal of Ninety-Day Inservice Inspection Summary Report RNP-RA/15-0063, Submittal of Ninety Day Inservice Inspection Summary Report - Supplement2015-07-0808 July 2015 Submittal of Ninety Day Inservice Inspection Summary Report - Supplement RNP-RA/14-0061, Submittal of Snubber Examination and Testing Program2014-05-29029 May 2014 Submittal of Snubber Examination and Testing Program RNP-RA/14-0040, Relief Request (RR)-10 for Expanded Applicability for Use of ASME Code Case N-532-4, Repair/Replacement Activity Documentation Requirements and Inservice Summary Report Preparation and Submission, Per 10 CFR 50.55(a)(3)(i)2014-05-0909 May 2014 Relief Request (RR)-10 for Expanded Applicability for Use of ASME Code Case N-532-4, Repair/Replacement Activity Documentation Requirements and Inservice Summary Report Preparation and Submission, Per 10 CFR 50.55(a)(3)(i) RNP-RA/14-0014, Submittal of Ninety Day Inservice Inspection Summary Report2014-01-30030 January 2014 Submittal of Ninety Day Inservice Inspection Summary Report RNP-RA/12-0119, Supplemental Response to Request for Additional Information Related to Relief Request (RR)-07 from Immediate ASME Code Repair of Refueling Water Storage Tank Drain Valve (SI-837) for Fifth Ten-Year Inservice Inspection Program...2012-11-11011 November 2012 Supplemental Response to Request for Additional Information Related to Relief Request (RR)-07 from Immediate ASME Code Repair of Refueling Water Storage Tank Drain Valve (SI-837) for Fifth Ten-Year Inservice Inspection Program... RNP-RA/12-0067, Response to the NRC Request for Additional Information Regarding Inservice Inspection Program Plan for the Fifth Ten-Year Interval2012-06-19019 June 2012 Response to the NRC Request for Additional Information Regarding Inservice Inspection Program Plan for the Fifth Ten-Year Interval RNP-RA/12-0063, Submittal of 90 Day Inservice Inspection Summary Report2012-06-15015 June 2012 Submittal of 90 Day Inservice Inspection Summary Report RNP-RA/12-0064, Response to NRC Request for Additional Information Related to Relief Requests (RR)-2 for the Fifth Ten-Year Interval Inservice Testing Program Plan2012-06-0404 June 2012 Response to NRC Request for Additional Information Related to Relief Requests (RR)-2 for the Fifth Ten-Year Interval Inservice Testing Program Plan RNP-RA/12-0056, Response to NRC Request for Additional Information for the Fifth Ten-Year Interval Inservice Testing Program Plan2012-05-10010 May 2012 Response to NRC Request for Additional Information for the Fifth Ten-Year Interval Inservice Testing Program Plan RNP-RA/12-0017, Inservice Testing Program Plan for the Fifth-Ten Year Interval2012-03-16016 March 2012 Inservice Testing Program Plan for the Fifth-Ten Year Interval RNP-RA/12-0023, Inservice Inspection Program for the Fifth Ten-Year Interval2012-03-14014 March 2012 Inservice Inspection Program for the Fifth Ten-Year Interval ML1103300852011-01-27027 January 2011 H. B. Robinson, Unit 2 - Request for Relief from ASME Boiler and Pressure Vessel Code, Section Xi, for the Fourth Ten-Year Inservice Inspection Program Program Interval (Relief Request No. RR-23) RNP-RA/10-0091, Submittal of 90 Day Inservice Inspection Summary Report2010-09-22022 September 2010 Submittal of 90 Day Inservice Inspection Summary Report RNP-RA/09-0010, Submittal of 90 Day Inservice Inspection Summary Report for Refueling Outage 252009-02-11011 February 2009 Submittal of 90 Day Inservice Inspection Summary Report for Refueling Outage 25 RNP-RA/08-0047, Response to NRC Request for Additional Information on the Steam Generator Inservice Inspection Results2008-04-30030 April 2008 Response to NRC Request for Additional Information on the Steam Generator Inservice Inspection Results RNP-RA/07-0077, Submittal of 90 Day Inservice Inspection Summary Report2007-08-0202 August 2007 Submittal of 90 Day Inservice Inspection Summary Report RNP-RA/06-0001, Submittal of 90 Day Inservice Inspection Summary Report2006-01-16016 January 2006 Submittal of 90 Day Inservice Inspection Summary Report RNP-RA/04-0110, Submittal of 90 Day Inservice Inspection Summary Report2004-08-26026 August 2004 Submittal of 90 Day Inservice Inspection Summary Report RNP-RA/03-0034, Revision to Inservice Testing Program Relief Request IST-RR-3 for Containment Spray Pump Comprehensive Pump Test Requirements2003-04-15015 April 2003 Revision to Inservice Testing Program Relief Request IST-RR-3 for Containment Spray Pump Comprehensive Pump Test Requirements RNP-RA/03-0018, Submittal of 90 Day Inservice Inspection Summary Report2003-02-11011 February 2003 Submittal of 90 Day Inservice Inspection Summary Report RNP-RA/02-0065, Relief Request Number RR-12 for the Fourth Ten-Year Interval Inservice Inspection Program2002-05-14014 May 2002 Relief Request Number RR-12 for the Fourth Ten-Year Interval Inservice Inspection Program ML0205703112002-02-20020 February 2002 Revision 1 to Inservice Testing Program Plan - Fourth Interval. 2023-04-24
[Table view] Category:Letter type:RNP
MONTHYEARRNP-RA/21-0035, Duke Energy Progress, Inc - Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report2021-02-18018 February 2021 Duke Energy Progress, Inc - Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report RNP-RA/20-0234, Independent Spent Fuel Storage Installation, Registration of Use of Spent Fuel Casks2020-07-23023 July 2020 Independent Spent Fuel Storage Installation, Registration of Use of Spent Fuel Casks RNP-RA/20-0199, Registration of Use of Spent Fuel Casks2020-06-25025 June 2020 Registration of Use of Spent Fuel Casks RNP-RA/18-0063, Request for Extension of Due Date for Seismic Probabilistic Risk Assessment Submittal2018-11-29029 November 2018 Request for Extension of Due Date for Seismic Probabilistic Risk Assessment Submittal RNP-RA/18-0060, Transmittal of Core Operating Limits Report2018-10-17017 October 2018 Transmittal of Core Operating Limits Report RNP-RA/18-0050, Response to Supplemental Request for Additional Information Regarding License Amendment Request Proposing to Add a Qualified Offsite Circuit to Technical Specification 3.8.1, AC Sources - Operating and the Use of Load Tap Change2018-08-0101 August 2018 Response to Supplemental Request for Additional Information Regarding License Amendment Request Proposing to Add a Qualified Offsite Circuit to Technical Specification 3.8.1, AC Sources - Operating and the Use of Load Tap Change RNP-RA/18-0044, Supplement to License Amendment Request Proposing to Add a Qualified Offsite Circuit to Technical Specification 3.8.1, AC Sources - Operating and the Use of Load Tap Changers in the Automatic Mode of Operation on the Startup Transform2018-07-11011 July 2018 Supplement to License Amendment Request Proposing to Add a Qualified Offsite Circuit to Technical Specification 3.8.1, AC Sources - Operating and the Use of Load Tap Changers in the Automatic Mode of Operation on the Startup Transformers RNP-RA/18-0039, Transmittal of Emergency Procedure Revisions and 10 CFR 50.54(q) Summary of Analysis2018-06-27027 June 2018 Transmittal of Emergency Procedure Revisions and 10 CFR 50.54(q) Summary of Analysis RNP-RA/18-0041, Independent Spent Fuel Storage Installation - Register as User for Cask2018-06-13013 June 2018 Independent Spent Fuel Storage Installation - Register as User for Cask RNP-RA/18-0036, Response to Request for Additional Information (RAI) Regarding Amendment Request Proposing to Add a Qualified Offsite Circuit to Technical Specification 3.8.1, AC Sources - Operating and the Use ...2018-05-16016 May 2018 Response to Request for Additional Information (RAI) Regarding Amendment Request Proposing to Add a Qualified Offsite Circuit to Technical Specification 3.8.1, AC Sources - Operating and the Use ... RNP-RA/18-0029, Submittal of 2017 Annual Radiological Environmental Operating Report2018-05-0808 May 2018 Submittal of 2017 Annual Radiological Environmental Operating Report RNP-RA/18-0031, (Hbrsep), Unit 2 - 2017 Annual Radioactive Effluent Release Report and Offsite Dose Calculation Manual, Revision 352018-04-23023 April 2018 (Hbrsep), Unit 2 - 2017 Annual Radioactive Effluent Release Report and Offsite Dose Calculation Manual, Revision 35 RNP-RA/18-0015, Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequently Requirements to a Licensee Controlled Program2018-04-16016 April 2018 Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequently Requirements to a Licensee Controlled Program RNP-RA/18-0024, Report of Changes Pursuant to 10 CFR 50.59(d)(2)2018-04-0202 April 2018 Report of Changes Pursuant to 10 CFR 50.59(d)(2) RNP-RA/18-0020, Notification of Change in Licensed Operator Status2018-02-20020 February 2018 Notification of Change in Licensed Operator Status RNP-RA/18-0003, Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report2018-01-23023 January 2018 Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report RNP-RA/17-0085, Request for Additional Information Regarding Application to Revise Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles2018-01-0808 January 2018 Request for Additional Information Regarding Application to Revise Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles RNP-RA/17-0086, Transmittal of Emergency Procedure Revision and 10 CFR 50.54(q) Summary of Analyses2017-12-14014 December 2017 Transmittal of Emergency Procedure Revision and 10 CFR 50.54(q) Summary of Analyses RNP-RA/17-0081, Submittal of Change in Licensed Operators Medical Status2017-12-11011 December 2017 Submittal of Change in Licensed Operators Medical Status RNP-RA/17-0079, Operator License Renewal Application2017-12-0707 December 2017 Operator License Renewal Application RNP-RA/17-0071, Independent Spent Fuel Storage Installation (ISFSI) Registration for Use of General License Spent Fuel Casks2017-10-19019 October 2017 Independent Spent Fuel Storage Installation (ISFSI) Registration for Use of General License Spent Fuel Casks RNP-RA/17-0068, Response to NRC Request for Additional Information Related to License Amendment Request Regarding Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles2017-09-28028 September 2017 Response to NRC Request for Additional Information Related to License Amendment Request Regarding Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles RNP-RA/17-0037, License Amendment Request Proposing to Add a Qualified Offsite Circuit to Technical Specifications 3.8.1, AC Sources-Operating and the Use of Load Tap Changers in the Automatic Mode of Operation on the Startup Transformers2017-09-27027 September 2017 License Amendment Request Proposing to Add a Qualified Offsite Circuit to Technical Specifications 3.8.1, AC Sources-Operating and the Use of Load Tap Changers in the Automatic Mode of Operation on the Startup Transformers RNP-RA/17-0043, Relief Request (RR)-12 for Relief from Volumetric/Surface Examination Frequency Requirements of ASME Code Case N-729-42017-09-22022 September 2017 Relief Request (RR)-12 for Relief from Volumetric/Surface Examination Frequency Requirements of ASME Code Case N-729-4 RNP-RA/17-0065, Refueling Outage 30 Steam Generator Tube Inspection Report2017-09-18018 September 2017 Refueling Outage 30 Steam Generator Tube Inspection Report RNP-RA/17-0060, Notification of Change in Licensed Operator Status2017-08-10010 August 2017 Notification of Change in Licensed Operator Status RNP-RA/17-0058, Notification of Change in Licensed Operator Status2017-08-0303 August 2017 Notification of Change in Licensed Operator Status RNP-RA/17-0055, Transmittal of Core Operating Limits Report for Cycle 312017-07-26026 July 2017 Transmittal of Core Operating Limits Report for Cycle 31 RNP-RA/17-0042, Submittal of the PWROG-14048-P, Revision 1, to Satisfy the Regulatory Commitment Related to the Pressurized Water Reactor Internals Program Plan for Aging Management of Reactor Internals2017-06-29029 June 2017 Submittal of the PWROG-14048-P, Revision 1, to Satisfy the Regulatory Commitment Related to the Pressurized Water Reactor Internals Program Plan for Aging Management of Reactor Internals RNP-RA/17-0051, Submittal of Nine Day Inservice Inspection Summary Report2017-06-29029 June 2017 Submittal of Nine Day Inservice Inspection Summary Report RNP-RA/17-0041, Transmittal of Technical Specifications Bases Revisions2017-05-23023 May 2017 Transmittal of Technical Specifications Bases Revisions RNP-RA/17-0038, (Hbrsep), Unit No. 2 - 2016 Annual Radiological Environmental Operating Report2017-05-0909 May 2017 (Hbrsep), Unit No. 2 - 2016 Annual Radiological Environmental Operating Report RNP-RA/17-0034, Modification of Request for Technical Specification Change to Change Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles (MF9544)2017-05-0202 May 2017 Modification of Request for Technical Specification Change to Change Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles (MF9544) RNP-RA/17-0036, (Hbrsep), Unit No. 2 - 2016 Annual Radioactive Effluent Release Report and Offsite Dose Calculation Manual, Current Revision 342017-04-25025 April 2017 (Hbrsep), Unit No. 2 - 2016 Annual Radioactive Effluent Release Report and Offsite Dose Calculation Manual, Current Revision 34 RNP-RA/17-0031, Provides Additional Information Regarding License Amendment Request to Adopt Technical Specifications Task Force (TSTF) Traveler 522, Revision 02017-04-20020 April 2017 Provides Additional Information Regarding License Amendment Request to Adopt Technical Specifications Task Force (TSTF) Traveler 522, Revision 0 RNP-RA/17-0033, Flood Hazard Mitigating Strategies Assessment (MSA) Report Submittal2017-04-12012 April 2017 Flood Hazard Mitigating Strategies Assessment (MSA) Report Submittal RNP-RA/17-0014, Resubmittal of Request for Technical Specification Change to Change Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles2017-04-0303 April 2017 Resubmittal of Request for Technical Specification Change to Change Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles RNP-RA/17-0028, Submittal of Engineering Calculation in Support of a Request for Technical Specification Change to Change Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles2017-04-0303 April 2017 Submittal of Engineering Calculation in Support of a Request for Technical Specification Change to Change Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles RNP-RA/17-0021, Transmittal of Core Operating Limits Report2017-03-13013 March 2017 Transmittal of Core Operating Limits Report RNP-RA/17-0019, Supplemental Submittal to Correct Marked Up Technical Specifications (TS) Pages Transmitted with Application for Technical Specification Task Force (TSTF)-339, Relocate TS Parameters to the COLR Consistent with WCAP-14483, Revision 22017-03-0808 March 2017 Supplemental Submittal to Correct Marked Up Technical Specifications (TS) Pages Transmitted with Application for Technical Specification Task Force (TSTF)-339, Relocate TS Parameters to the COLR Consistent with WCAP-14483, Revision 2 RNP-RA/17-0015, Independent Spent Fuel Storage Installations - Letter Regarding Report of Changes Pursuant to 10 CFR 72.482017-02-22022 February 2017 Independent Spent Fuel Storage Installations - Letter Regarding Report of Changes Pursuant to 10 CFR 72.48 RNP-RA/17-0016, Independent Spent Fuel Storage Installation - Annual Radioactive Effluent Release Report2017-02-22022 February 2017 Independent Spent Fuel Storage Installation - Annual Radioactive Effluent Release Report RNP-RA/17-0015, H.B. Robinson Steam Electric Plant & ISFSIs - Report of Changes Pursuant to 10 CFR 72.482017-02-22022 February 2017 H.B. Robinson Steam Electric Plant & ISFSIs - Report of Changes Pursuant to 10 CFR 72.48 RNP-RA/16-0100, Response to Apparent Violation in NRC Inspection Report 05000261/2016404, EA-16-2272017-01-24024 January 2017 Response to Apparent Violation in NRC Inspection Report 05000261/2016404, EA-16-227 RNP-RA/16-0097, Transmittal Letter for Response to Inspection Report Temporary Instruction 2201/004, Inspection of Implementation of Interim Cyber Security Milestones 1-7, Inspection Report 05000261/20154052016-12-15015 December 2016 Transmittal Letter for Response to Inspection Report Temporary Instruction 2201/004, Inspection of Implementation of Interim Cyber Security Milestones 1-7, Inspection Report 05000261/2015405 RNP-RA/16-0089, Request for Withdrawal of License Amendment Request for Change Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles2016-11-10010 November 2016 Request for Withdrawal of License Amendment Request for Change Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles RNP-RA/16-0090, Notification of Rescheduled Date for 2017 Emergency Preparedness Graded Exercise2016-11-10010 November 2016 Notification of Rescheduled Date for 2017 Emergency Preparedness Graded Exercise RNP-RA/16-0087, Technical Specifications Section 5.6.6 Post Accident Monitoring Instrumentation Report for Inoperable High Range Containment Area Radiation Monitors2016-10-31031 October 2016 Technical Specifications Section 5.6.6 Post Accident Monitoring Instrumentation Report for Inoperable High Range Containment Area Radiation Monitors RNP-RA/16-0078, Technical Specifications Section 5.6.6, Post Accident Monitoring Instrumentation Report for Inoperable High Range Containment Area Radiation Monitors2016-10-0505 October 2016 Technical Specifications Section 5.6.6, Post Accident Monitoring Instrumentation Report for Inoperable High Range Containment Area Radiation Monitors RNP-RA/16-0079, Response to Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Light Water Reactor Electric Generating Plants.2016-10-0505 October 2016 Response to Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Light Water Reactor Electric Generating Plants. 2021-02-18
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Text
Sharon Wheeler-Peavyhouse DUKE
- ENERGY, H. B. Robinson Steam ElectricPlant Unit 2 Manager- SupportServices PROGRESS Duke Energy 3581 West EntranceRoad Hartsville,SC 29550 Serial: RNP-RA/14-0040 MAY 0 9 2014 10 CFR 50.55a Attn: Document Control Desk United States Nuclear Regulatory Commission Washington, DC 20555-0001 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET NO. 50-261/RENEWED LICENSE NO. DPR-23 RELIEF REQUEST (RR)-10 FOR EXPANDED APPLICABILITY FOR USE OF ASME CODE CASE N-532-4, REPAIR/REPLACEMENT ACTIVITY DOCUMENTATION REQUIREMENTS AND INSERVICE
SUMMARY
REPORT PREPARATION AND SUBMISSION IN ACCORDANCE WITH 10 CFR 50.55A(a)(3)(i)
Pursuant to 10 CFR 50.55a(a)(3)(i), Duke Energy Progress, Inc. hereby requests NRC approval of the following request for the fifth 10-year inservice inspection (ISI) interval for the H. B.
Robinson Steam Electric Plant, Unit No. 2 for relief from the requirements of paragraph IWA-2441 (b) of ASME Code Section XI, 2007 Edition through the 2008 Addenda. The details of the 10 CFR 50.55a request aie enclos~d. ,
Approval of the proposed r'elief request is requested by May 09, 2015.
This letter contains no new Regulatory Comflhmitments.
If you have any-oquestions concerning this rnatter,- p!ease 6ontact Mr. Richard Hightower, Manager - Nuclear Regulatory Affairs at (843)-857-1 329. -
Sincerely, Sharon Y.i ouse Director - Nuclear Org. Effectiveness SWP/jmw
Enclosure:
H. B. RobinsonSte~m Electric Plant, Unit No. 2, Relief Request (RR)-10 for Expanded Applicability for Use of ASME Code Case N-5:32-4, Repair/Replacement Activity Documentation Requirements and Inservice Summary Report"Preparation ard'SSubmission cc: Mr. V. M. McCree, NRC Region 11 Ms. Martha C. Barillas, NRC Project Manager, NRR NRC Resident~lnspector,'HBRSEP Unit No. 2
" :" " ,: ' . ' * '. . , ' ° *- * ' ' : ; ' " " * - *" " "
Ac-t
Nuclear Regulatory Commission Enclosure to Serial RNP-RA/14-0040 Page 1 of 3 ENCLOSURE H. B. Robinson Steam Electric Plant, Unit No. 2, Relief Request (RR)-10 for Expanded Applicability for Use of ASME Code Case N-532-4, Repair/Replacement Activity Documentation Requirements and Inservice Summary Report Preparation and Submission
Nuclear Regulatory Commission Enclosure to Serial RNP-RA/14-0040 Page 2 of 3 Relief Request No RR-10 Request for Relief for Expanded Applicability for use of ASME Code Case N-532-4, Repair/Replacement Activity Documentation Requirements and Inservice Summary Report Preparation and Submission In Accordance with 10 CFR 50.55a(a)(3)(i)
ASME Code Components Affected:
Code Class: All Classes Examination Category: IWA-2441(b) and ASME Code Case N-532-4 Item Number: N/A
==
Description:==
NA Expanded Applicability for use of ASME Code Case N-532-4, "Repair/Replacement Activity Documentation Requirements and Inservice Summary Report Preparation and Submission" Component Number: N/A
Applicable Code Edition and Addenda
The H. B. Robinson Steam Electric Plant, Unit 2 (HBRSEP2) Fifth Ten Year Inservice Inspection Interval (ISI) program is based on the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code,Section XI, 2007 Edition through the 2008 Addenda.
Applicable Code Requirement
IWA-2441(b) requires Code Cases be applicable to the Edition and Addenda specified in the Inspection Plan.
ASME Code Case N-532-4, "Repair/Replacement Activity Documentation Requirements and Inservice Summary Report Preparation and Submission," provides requirements that may be used to document repair/replacement activities.
Reason for Request
Pursuant to 10 CFR 50.55a(a)(3)(i), relief is requested on the basis that the proposed alternative will provide an acceptable level of quality and safety.
On July 21, 2012 HBRSEP2 started its fifth ten-year interval ISI program under the requirements of the 2007 Edition through the 2008 Addenda of ASME Section Xl. When implementing this Edition of ASME Section XI, Paragraph IWA-2441(b) requires code cases be applicable to the Edition and Addenda specified in the Inspection Plan.
Nuclear Regulatory Commission Enclosure to Serial RNP-RA/14-0040 Page 3 of 3 ASME Code Case N-532-4 has an applicability limited up to the 2004 Edition through the 2005 Addenda, which is identified in the latest applicability index for ASME Section XI Code Cases. Since ASME Code Case N-532-4 only applies up to the 2004 Edition through the 2005 Addenda, Paragraph IWA-2441(b) does not allow the use of ASME Code Case N-532-4 for the HBRSEP2 fifth ten-year interval ISI program.
Proposed Alternative and Basis for Use:
HBRSEP2 requests the applicability of ASME Code Case N-532-4 be extended to the 2007 Edition through the 2008 Addenda for use in the plant's fifth interval ISI program. The NRC has accepted the use of ASME Code Case N-532-4 as an acceptable method for repair/replacement activity documentation requirements and inservice summary report preparation and submission in the latest revision of Regulatory Guide 1.147, Revision 16.
No technical changes to ASME Code Case N-532-4 are being proposed in this relief request. This relief request is being submitted to correct a timing situation, which has resulted from the application of the 2007 Edition through the 2008 Addenda of ASME Section XI for HBRSEP2. Since no technical change is proposed in this relief request, HBRSEP2 considers that this alternative provides an acceptable level of quality and safety, and is consistent with provisions of 10 CFR 50.55a(a)(3)(i).
Duration of Proposed Alternative:
Relief is requested for the fifth ten-year ISI interval for HBRSEP2. The fifth ten-year ISI interval began on July 20, 2012 and ends on July 19, 2021.
Precedents:
Oyster Creek Nuclear Generating Station, (Relief Request 15R-07) (TAC No. ME9494)
Dated August 6, 2013