Similar Documents at Byron |
|---|
Category:Letter type:RS
MONTHYEARRS-23-117, Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information2023-11-10010 November 2023
Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information
RS-23-114, Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds2023-11-0101 November 2023
Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds
RS-23-100, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-10-13013 October 2023
Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation
RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023
Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans
RS-23-108, Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles2023-10-11011 October 2023
Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles
RS-23-105, Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections2023-10-10010 October 2023
Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections
RS-23-093, License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel.2023-09-29029 September 2023
License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel.
RS-23-094, Relief Request I4R-24, Alternative for Post-Peening Reexamination Frequency for Reactor Pressure Vessel Head Penetration Nozzle Number 752023-09-29029 September 2023
Relief Request I4R-24, Alternative for Post-Peening Reexamination Frequency for Reactor Pressure Vessel Head Penetration Nozzle Number 75
RS-23-091, Relief Request I4R-25, Alternative Requirements for Reactor Pressure Vessel Inservice Inspection Intervals2023-09-26026 September 2023
Relief Request I4R-25, Alternative Requirements for Reactor Pressure Vessel Inservice Inspection Intervals
RS-23-083, Withdrawal - Proposed Alternatives Related to the Steam Generators2023-06-27027 June 2023
Withdrawal - Proposed Alternatives Related to the Steam Generators
RS-23-077, Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-06-16016 June 2023
Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations
RS-23-075, Application for Technical Specification Improvement to Extend the Completion Time for Condition B of Technical Specification 3.5.1, Accumulators, Using the Consolidated Line Item Improvement Process2023-06-0707 June 2023
Application for Technical Specification Improvement to Extend the Completion Time for Condition B of Technical Specification 3.5.1, Accumulators, Using the Consolidated Line Item Improvement Process
RS-23-056, Response to Request for Additional Information to Braidwood Station, Unit 1, and Byron Station, Unit 1, for Steam Generator License Renewal Response to Commitment 102023-04-20020 April 2023
Response to Request for Additional Information to Braidwood Station, Unit 1, and Byron Station, Unit 1, for Steam Generator License Renewal Response to Commitment 10
RS-23-055, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2023-04-10010 April 2023
Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors
RS-23-049, Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-23023 March 2023
Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations
RS-23-045, Constellation Energy Generation, LLC Submittal of Fitness for Duty Performance Data Reports for 2022 Per 10 CFR 26.717(c) & 10 CFR 26.2032023-02-28028 February 2023
Constellation Energy Generation, LLC Submittal of Fitness for Duty Performance Data Reports for 2022 Per 10 CFR 26.717(c) & 10 CFR 26.203
RS-23-038, Response to Request for Additional Information for the Byron Proposal to Reinsert an Accident Tolerant Fuel Lead Test Assembly2023-02-27027 February 2023
Response to Request for Additional Information for the Byron Proposal to Reinsert an Accident Tolerant Fuel Lead Test Assembly
RS-23-040, Constellation Energy Generation, LLC, Supplemental Information - Proposed Alternatives Related to the Steam Generators2023-02-21021 February 2023
Constellation Energy Generation, LLC, Supplemental Information - Proposed Alternatives Related to the Steam Generators
RS-23-003, Constellation Energy Generation, LLC, Summary of Changes to Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-102023-01-31031 January 2023
Constellation Energy Generation, LLC, Summary of Changes to Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-10
RS-22-123, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator2022-12-0707 December 2022
Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator
RS-22-126, Constellation Energy Generation, LLC - Request to Use Provisions of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI2022-11-30030 November 2022
Constellation Energy Generation, LLC - Request to Use Provisions of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI
RS-22-110, Supplemental Information - Proposed Alternatives Related to the Steam Generators and Request.2022-09-20020 September 2022
Supplemental Information - Proposed Alternatives Related to the Steam Generators and Request.
RS-22-097, License Amendment Request to Reinsert an Accident Tolerant Fuel Lead Test Assembly2022-08-31031 August 2022
License Amendment Request to Reinsert an Accident Tolerant Fuel Lead Test Assembly
RS-22-093, Advisement of Leadership Changes for Constellation Energy Generation, LLC and Submittal of Updated Standard Practice Procedures Plans2022-08-18018 August 2022
Advisement of Leadership Changes for Constellation Energy Generation, LLC and Submittal of Updated Standard Practice Procedures Plans
RS-22-086, R. E. Ginna Nuclear Power Plant - Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam.2022-08-10010 August 2022
R. E. Ginna Nuclear Power Plant - Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam.
RS-22-084, Response to Request for Additional Information Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator .2022-06-17017 June 2022
Response to Request for Additional Information Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator .
RS-22-074, Response to Request for Additional Information - Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds .2022-05-20020 May 2022
Response to Request for Additional Information - Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds .
RS-22-073, Supplemental Information Regarding License Amendment Request -Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube.2022-05-19019 May 2022
Supplemental Information Regarding License Amendment Request -Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube.
RS-22-057, Constellation Radiological Emergency Plan Addendum Revision2022-04-21021 April 2022
Constellation Radiological Emergency Plan Addendum Revision
RS-22-037, License Amendment Request - Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control2022-04-21021 April 2022
License Amendment Request - Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control
RS-22-051, Constellation Energy Generation, LLC - Update to Correspondence Addressees and Service Lists2022-04-12012 April 2022
Constellation Energy Generation, LLC - Update to Correspondence Addressees and Service Lists
RS-22-050, Supplemental Information - Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds2022-04-0808 April 2022
Supplemental Information - Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds
RS-22-047, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2022-04-0808 April 2022
Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors
RS-22-049, Constellation Energy Generation, LLC, Supplemental Information to Correct Typographical Errors in Constellation'S Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for2022-04-0404 April 2022
Constellation Energy Generation, LLC, Supplemental Information to Correct Typographical Errors in Constellation'S Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for V
RS-22-045, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2022-01, Preparation and Scheduling of Operator Licensing Examinations2022-03-25025 March 2022
Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2022-01, Preparation and Scheduling of Operator Licensing Examinations
RS-22-014, Application to Adopt TSTF-246, RTS Instrumentation, 3.3.1 Condition F Completion Time2022-03-24024 March 2022
Application to Adopt TSTF-246, RTS Instrumentation, 3.3.1 Condition F Completion Time
RS-22-041, Withdrawal of License Amendment Request to Revise Technical Specifications 5.6.5, Core Operating Limits Report (COLR) to Add References to NRC Approved Topical Report with Administrative Changes2022-03-22022 March 2022
Withdrawal of License Amendment Request to Revise Technical Specifications 5.6.5, Core Operating Limits Report (COLR) to Add References to NRC Approved Topical Report with Administrative Changes
RS-22-036, Supplemental Information - Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds2022-03-10010 March 2022
Supplemental Information - Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds
RS-22-027, Constellation, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated2022-02-23023 February 2022
Constellation, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated P
RS-22-023, Constellation Energy Generation, LLC, Executed Trust Fund Agreement Amendment and Subordinate Trust Agreement2022-02-23023 February 2022
Constellation Energy Generation, LLC, Executed Trust Fund Agreement Amendment and Subordinate Trust Agreement
RS-22-019, Constellation Energy Generation, LLC - Update to Correspondence Addressees and Service Lists2022-02-16016 February 2022
Constellation Energy Generation, LLC - Update to Correspondence Addressees and Service Lists
RS-22-015, Notification of Completion of License Transfer and Request to Continue Processing Pending NRC Actions Previously Requested by Exelon Generation Company, LLC2022-02-0101 February 2022
Notification of Completion of License Transfer and Request to Continue Processing Pending NRC Actions Previously Requested by Exelon Generation Company, LLC
RS-22-008, Application to Revise Technical Specifications 5.6.5, Core Operating Limits Report to Add References to NRC-Approved Topical Report with Admin2022-01-24024 January 2022
Application to Revise Technical Specifications 5.6.5, Core Operating Limits Report to Add References to NRC-Approved Topical Report with Admin
RS-22-004, Supplement to Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements2022-01-0404 January 2022
Supplement to Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements
RS-21-121, Proposed Changes to Decommissioning Trust Agreements and Master Terms2021-12-15015 December 2021
Proposed Changes to Decommissioning Trust Agreements and Master Terms
RS-21-112, Updated 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2021-10-22022 October 2021
Updated 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors
RS-21-103, Updated Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations for Byron Station and Dresden Nuclear Power Station2021-09-28028 September 2021
Updated Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations for Byron Station and Dresden Nuclear Power Station
RS-21-096, Withdrawal of Certification of Permanent Cessation of Power Operations for Byron Station, Units 1 and 2, and Previously Submitted Licensing Actions in Support of Decommissioning2021-09-15015 September 2021
Withdrawal of Certification of Permanent Cessation of Power Operations for Byron Station, Units 1 and 2, and Previously Submitted Licensing Actions in Support of Decommissioning
RS-21-091, Implementation of Insider Threat Program Requirements Associated with the Voluntary Security Clearance Program and Advisement of Leadership Changes2021-09-13013 September 2021
Implementation of Insider Threat Program Requirements Associated with the Voluntary Security Clearance Program and Advisement of Leadership Changes
RS-21-093, R. E. Ginna, Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections2021-09-0101 September 2021
R. E. Ginna, Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections
2023-09-29
[Table view] |
Text
RS-1 1-048 10 CFR 50.55a March 25, 2011 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Byron Station Unit 1 Facility Operating License No. NPF-37 NRC Docket No. STN 50-454
Subject:
Additional Information Related to Byron Station Unit 1, Inservice Inspection Relief Request 13R- 1 9: Alternative Requirements for the Repair of Reactor Vessel Head Penetrations
References:
(1) Letter from J. Hansen (Exelon) to U. S. NRC, "Byron Station Unit 1 Inservice Inspection Relief Request 13R - 19: Alternative Requirements for the Repair of Reactor Vessel Head Penetrations," dated March 24, 2011 (2) Email from N. DiFrancesco (U. S. NRC) to R. McIntosh (Exelon), "Byron Station, Unit No. 1 - Request for Additional Information re: Relief Request 13R-19 (TAC No. ME5877)," dated March 25, 2011 In Reference 1, in accordance with 10 CFR 50.55a, "Codes and standards," paragraph (a)(3)(i),
Exelon Generation Company, LLC (EGC), submitted the Relief Request 13R-1 9 from the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI, "Rules for Inservice Inspection of Nuclear Power Plant Components," on the basis that the proposed alternatives would provide an acceptable level of quality and safety.
Specifically, Reference 1 proposed to perform an alternative repair technique using an embedding weld overlay methodology on the reactor Vessel Head Penetration (VHP) housings and J-groove welds of Byron Station, Unit 1.
During the current Byron Station, Unit 1 Spring 2011 Refueling Outage B1 R17, EGC performed volumetric examinations of the VHPs in accordance with 10 CFR 50.55a(g)(6)(ii)(D), which specifies the use of Code Case N-729 - 1, with conditions. Examination of the VHPs is on going, however, results for the examination of VHP nozzles 64 and 76 did not meet the applicable acceptance criteria; and therefore, EGC is making preparations for a repair. A teleconference was held between EGC and the NRC on March 25, 2011, to discuss a Request for Additional Information (RAI) from the NRC to complete its review of the proposal.
The EGC request for an expedited verbal authorization from the NRC by March 28, 2011, is revised by this letter to support repair activities specific to the VHP nozzles 64 and 76. contains the information requested by the NRC.
March 25, 2011 U. S. Nuclear Regulatory Commission Page 2 contains one new regulatory commitment in this submittal. If you have any questions about this letter, please contact Mr. Richard W. McIntosh at (630) 657-2816.
Respectfully, Darin M. Benyak Director, Licensing and Regulatory Affairs Attachments: 1. Response to Request for Additional Information on Alternative Requirements for the Repair of Reactor Vessel Head Penetrations
- 2. Summary of Regulatory Commitments
ATTACHMENT 1 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION ON ALTERNATIVE REQUIREMENTS FOR THE REPAIR OF REACTOR VESSEL HEAD PENETRATIONS (Page 1 of 4)
NRC QUESTION RAI-1:
NRC staff notes that the licensee requests expedited verbal relief by 1 PM Central Standard Time on March 28, 2011. Staff notes that expedited review and verbal authorization would be difficult for the generic application of the licenses' submittal within that time frame. Therefore, staff requests licensee reconsider the scope of this relief request under Section 1.0 "ASME Code Component(s) Affected" to the items needed for repair this outage, in order to meet the licensee's requested date of verbal authorization.
RESPONSE TO RAI-1:
The Exelon Generation Company, LLC (EGC) request for an expedited verbal authorization from the NRC by March 28, 2011, is revised by this letter to support repair activities specific to reactor Vessel Head Penetration (VHP) nozzles 64 and 76 only. EGC understands that NRC review of the generic application of the relief request will continue, but not on the expedited schedule.
NRC QUESTION RAI-2:
In Reference 2 of the submittal, the NRC requested the following, "The NRC must be notified of changes in flaw(s) or finding new flaw(s) in the j-groove weld beneath a seal weld repair or in the seal weld repair. " In order to add clarity to this request the NRC staff requests that the licensee commit to the following statement; The licensee will notify NRC staff of the Division of Component Integrity or its successor of changes in indication(s) or findings of new indication(s) in the penetration nozzle or J-groove weld beneath a seal weld repair, or new linear indications in the seal weld repair, prior to commencing repair activities.
NRC staff requests this commitment as a finding of these types of indications may invalidate the embedded flaw repair technique as an effective repair for the penetration nozzle in question. Timely notification of NRC staff of ISI indications will allow clear communications to assist NRC staff in determination of the effectiveness of the repair due to the indication in question.
RESPONSE TO RAI-2:
Exelon Generation Company, LLC (EGC) will notify NRC staff of the Division of Component Integrity or its successor of changes in indication(s) or findings of new indication(s) in the penetration nozzle or J-groove weld beneath a seal weld repair, or new linear indications in the seal weld repair, prior to commencing repair activities.
This Regulatory Commitment is on Attachment 2, committed for Byron Unit 1 refueling outages, beginning with B1 R18.
ATTACHMENT 1 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION ON ALTERNATIVE REQUIREMENTS FOR THE REPAIR OF REACTOR VESSEL HEAD PENETRATIONS (Page 2 of 4)
NRC QUESTION RAI-3:
In Section 5.0 of the submittal, Step 1 states that an unacceptable axial or circumferential flaw in a tube below a J-groove attachment weld will be sealed off with an Alloy 52 or 52M weldment, with no additional detail as to the scope of the weldment. WCAP - 15987-P Rev.
2, Reference 1 of the submittal, states in Section 2.2.3, for axial cracks on the penetration tube OD below the j-weld, that the overlay begins %" beyond the Alloy 600/stainless steel interface at the outer periphery of the J -weld and extends down the outer surface of the penetration tube to a point %" beyond the flaw indication. Section 2.2.4, for circumferential cracks in the penetration tube, the scope of the weldment is not specific other than isolation of the flaw. In order to clarify the licensee's implementation of requirements, provide the following; a) State the generic scope of the weldment that will be used to repair an OD flaw in the nozzle below the J-groove weld.
b) State the scope of the weldment being used to repair reactor pressure vessel upper head penetration numbers 64 and 76.
c) In regards to the Table of Item 3 of Section 5.0, "Conditions and Limitations" of Reference 2 of the submittal, answer the following;
- 1. How will each of the four(4) indications be characterized for, I. "Repair Location, "
ii. "Flaw Orientation, " and iii. "Repair NDE"
- 2. Will Note 3 be implemented for "ISI NDE of the repair" for penetration numbers 64 and 76?
RESPONSE TO RAI-3:
a) EGC will provide a supplemental response to this letter to discuss generic scope of the proposed weldment.
b) The stainless steel head cladding will have three beads of 309L stainless steel buffer installed 3600 (degrees) around the interface of the clad and the J-Groove weld metal at Penetrations 64 and 76. The J-groove weld will have three layers of Alloy 52/52M deposited 3600 around the nozzle over and out to the stainless steel buffer.
The nozzle tube will have two layers of Alloy 52/52M deposited 360° around the nozzle and tied into the J-groove overlay. On Penetration 76, the nozzle tube will have the overlay extend down to the lowest possible location that will allow reinstallation of the funnel. On Penetration 64, the nozzle tube will be overlayed to the bottom of the nozzle (i.e., no funnel is installed).
ATTACHMENT 1 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION ON ALTERNATIVE REQUIREMENTS FOR THE REPAIR OF REACTOR VESSEL HEAD PENETRATIONS (Page 3 of 4) c.1(i) Repair Location The following recordable indications were discovered in the reactor head penetration nozzles 64 and 76; 64-1 approximately 1.3 inches counterclockwise from the 180 degree mark 64-2 approximately 0.9 inches counterclockwise from the 180 degree mark 76-1 approximately 1.0 inches clockwise from the 180 degree mark 76-2 between 0 inches and 1.2 inches counterclockwise from the 180 degree mark NOTE: 0 degrees is located at the downhill side of the penetration where the nozzle extension is shortest.
c.1(ii) Flaw Orientation:
The two indications in Penetration 64 are axial flaws on the uphill side. Indication 1 in Penetration 76 is an axial flaw and indication 2 is a circumferential flaw. Both flaws in Penetration 76 are on the uphill side.
The recorded distances of the flaws to the toe of the weld are:
Ultrasonic Testing Liquid Penetrant (PT)
(UT) measured measured distance from Flaw: distance from Toe of Weld:
Toe of Weld:
(inches) .
(inches) 64-1 0.40 0.40 64-2 NA 0.30 76-1 0.08 0.10 76-2 0.16 0.10 c.1(iii) All repair Non-Destructive Examination (NDE) will be a UT of the nozzle from the Inside Diameter (ID) and a PT Examination of the overlayed surface. In addition, response to Item c.2 below is applicable.
c.2 In accordance with Note 3 of the NRC acceptance for WCAP-1 5987-P-Revision 2, (See Reference 4, TAC No. MB8997) the final NDE performed on Penetrations 64 and 76 will include Performance Demonstration Initiative (PDI) UT of the nozzle and PT of the overlayed area. This will constitute 100% of the required examinations for the final NDE on the repair during B1 R17.
ATTACHMENT 1 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION ON ALTERNATIVE REQUIREMENTS FOR THE REPAIR OF REACTOR VESSEL HEAD PENETRATIONS (Page 4 of 4)
For the ISI NDE of the repair for Penetrations 64 and 76 starting with refueling outage B1 R18, Note 3 does not apply since the repair location is in the "VHP Nozzle OD below J-groove weld." Therefore, ISI NDE of the repair for Penetrations 64 and 76 will be performed in accordance with Code Case N-729-1, as amended by 10 CFR 50.55a(g)(6)(ii)(D).
REFERENCES:
(1) Letter from J. Hansen (Exelon) to U. S. NRC, "Byron Station Unit 1 Inservice Inspection Relief Request 13R-1 9: Alternative Requirements for the Repair of Reactor Vessel Head Penetrations," dated March 24, 2011 (2) Email from N. DiFrancesco (U. S. NRC) to R. McIntosh (Exelon), "Byron Station, Unit No. 1 - Request for Additional Information re: Relief Request 13R-19 (TAC No.
ME5877)," dated March 25, 2011 (3) Westinghouse WCAP-15987, Revision 2-A, "Technical Basis for the Embedded Flaw Process for Repair of Reactor Vessel Head Penetrations," December 2003 (4) Letter from H. N. Berkow (U. S. NRC) to H. A. Sepp (Westinghouse Electric Company), "Acceptance for Referencing - Topical Report WCAP-15987-P, Revision 2, 'Technical Basis for the Embedded Flaw Process for Repair of Reactor Vessel Head Penetration,' (TAC NO. MB8997)," dated July 3, 2003 (5) Westinghouse WCAP-1 6401 -P, Revision 0, "Technical Basis for Repair Options for Reactor Vessel Head Penetration Nozzles and Attachment Welds: Byron and Braidwood Units 1 and 2" (6) American Society of Mechanical Engineers Boiler and Pressure Vessel Code Case N-729-1, "Alternative Examination Requirements for PWR Reactor Vessel Upper Heads With Nozzles Having Pressure-Retaining Partial-Penetration WeldsSection XI, Division 1"
ATTACHMENT 2
SUMMARY
OF REGULATORY COMMITMENTS (Page 1 of 1)
The following table identifies commitments made in this document. Any other actions discussed in the submittal represent intended or planned actions. They are described to the NRC for the NRC's information and are not regulatory commitments.
COMMITTED COMMITMENT TYPE COMMITMENT DATE OR "OUTAGE" ONE-TIME ACTION Programmatic (Yes/No) (Yes/No)
Exelon Generation Company, LLC (EGC) will notify NRC staff of the Division of Component Integrity or its successor of changes in indication(s) or findings of new Byron Unit 1 indication(s) in the penetration refueling outages, nozzle or J-groove weld beneath a No Yes beginning with seal weld repair, or new linear B1 R18.
indications in the seal weld repair, prior to commencing repair activities.
