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MONTHYEARML17222A0022017-08-10010 August 2017 Request to Use a Portion of a Later Edition of the ASME B&PV Code, Section XI Project stage: Request ML17227A0472017-08-14014 August 2017 NRR E-mail Capture - Calvert Cliffs, Nine Mile Point, and R.E. Ginna - Request to Use a Later Edition of the ASME BPV Code, Section XI (CAC Nos. MG0079-MG0083) Project stage: Acceptance Review ML17297A5242017-11-0606 November 2017 R. E. Ginna - Request for Use of a Portion of a Later Edition and Addenda of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (CAC Nos. MG0079-MG0083; EPID L-2017-LLR-0061) Project stage: Other 2017-08-10
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Category:Letter
MONTHYEARIR 05000244/20230042024-02-0505 February 2024 LLC - Integrated Inspection Report 05000244/2023004 IR 05000317/20230042024-02-0101 February 2024 Integrated Inspection Report 05000317/2023004 and 05000318/2023004 NMP1L3570, Supplemental Information Letter - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-02-0101 February 2024 Supplemental Information Letter - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation IR 05000220/20230042024-02-0101 February 2024 Integrated Inspection Report 05000220/2023004 and 05000410/2023004 ML24029A0102024-01-29029 January 2024 Request for Information and Notification of Conduct of IP 71111.21.N.04, Age-Related Degradation, Reference Inspection Report 05000317/2024010 and 05000318/2024010 ML24026A0112024-01-26026 January 2024 R. E. Ginna Nuclear Power Plant, Relief Request Associated with Inservice Testing of B Auxiliary Feedwater Pump NMP1L3569, CFR 50.46 Annual Report2024-01-26026 January 2024 CFR 50.46 Annual Report ML24003A8872024-01-19019 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0033 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) 05000318/LER-2023-004, Submittal of LER 2023-004-00 for Calvert Cliffs Nuclear Power Plant, Unit 2, Submittal of Automatic Reactor Trip from Reactor Protection System Actuation Due to Loss of Unit Service Transformer2024-01-16016 January 2024 Submittal of LER 2023-004-00 for Calvert Cliffs Nuclear Power Plant, Unit 2, Submittal of Automatic Reactor Trip from Reactor Protection System Actuation Due to Loss of Unit Service Transformer ML24011A0732024-01-11011 January 2024 Proposed Alternative to the Requirements for Repair/Replacement of Saltwater (SW) System Buried Piping 05000318/LER-2023-002, Forward LER 2023-002-00 for Calvert Cliffs Nuclear Power Plant, Unit 2, Automatic Reactor Trip from Reactor Protection System Actuation Due to Loss of Unit Service Transformer2024-01-0808 January 2024 Forward LER 2023-002-00 for Calvert Cliffs Nuclear Power Plant, Unit 2, Automatic Reactor Trip from Reactor Protection System Actuation Due to Loss of Unit Service Transformer 05000318/LER-2023-003, Forward LER 2023-003-00 for Calvert Cliffs Nuclear Power Plant, Unit 2, Manual Actuation of Auxiliary Feedwater System Due to 22 Steam Generator Feedwater Pump Trip2024-01-0808 January 2024 Forward LER 2023-003-00 for Calvert Cliffs Nuclear Power Plant, Unit 2, Manual Actuation of Auxiliary Feedwater System Due to 22 Steam Generator Feedwater Pump Trip ML24004A2122024-01-0808 January 2024 Senior Reactor and Reactor Operator Initial License Examinations ML24005A0222024-01-0505 January 2024 Revised Steam Generator Tube Inspection Reports ML23354A0012024-01-0404 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0059 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML23304A0642024-01-0202 January 2024 Issuance of Amendment No. 349 to Modify the Long-Term Coupon Surveillance Program IR 05000244/20230102023-12-19019 December 2023 LLC - Age-Related Degradation Inspection Report 05000244/2023010 ML23348A0992023-12-15015 December 2023 R. E. Ginna Nuclear Power Plant Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0029 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML23278A1292023-12-14014 December 2023 Units 1 & 2; Limerick, Units 1 & 2; Nine Mile Point, Units 1 & 2; and Peach Bottom, Units 2 & 3 -Revision to Approved Alternatives to Use Boiling Water Reactor Vessel and Internals Project Guidelines IR 05000410/20243012023-12-14014 December 2023 Initial Operator Licensing Examination Report 05000410/2024301 NMP1L3566, Radiological Emergency Plan Document Revision. Includes EP-AA-1013, Revision 10, Radiological Emergency Plan Annex for Nine Mile Point Station2023-12-14014 December 2023 Radiological Emergency Plan Document Revision. Includes EP-AA-1013, Revision 10, Radiological Emergency Plan Annex for Nine Mile Point Station ML23305A1402023-12-13013 December 2023 Units 1 & 2; Nine Mile Point, Unit 2; Peach Bottom, Units 2 & 3; and Quad Cities, Units 1 and 2 - Issuance of Amendments to Adopt Traveler TSTF-580 ML23347A0092023-12-13013 December 2023 Annual Commitment Change Notification ML23346A0142023-12-12012 December 2023 LLC - Senior Reactor and Reactor Operator Initial License Examinations ML23341A1252023-12-0707 December 2023 Supplemental Response to Part 73 Exemption Request - Withdrawal of Request for Exemption from 10 CFR 73, Subpart B, Preemption Authority Requirements ML23291A4642023-12-0707 December 2023 Issuance of Amendment No. 251 Regarding the Adoption of Title 10 the Code of Federal Regulations Section 50.69, Risk-Informed Categorization and Treatment of SSC for Nuclear Power Plants NMP1L3564, Supplemental Response to Part 73 Exemption Request - Withdrawal of Request for Exemption from 10 CFR 73, Subpart B, Preemption Authority Requirements2023-12-0707 December 2023 Supplemental Response to Part 73 Exemption Request - Withdrawal of Request for Exemption from 10 CFR 73, Subpart B, Preemption Authority Requirements RS-23-125, Request for Exemption from 10 CFR 2.109(b)2023-12-0707 December 2023 Request for Exemption from 10 CFR 2.109(b) ML23289A0122023-12-0606 December 2023 Issuance of Amendment No. 250 Regarding the Revision to Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b NMP1L3563, Submittal of Relief Request I5R-12, Revision 0, Concerning the Installation of a Full Structural Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208)2023-12-0404 December 2023 Submittal of Relief Request I5R-12, Revision 0, Concerning the Installation of a Full Structural Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208) IR 05000220/20234022023-11-28028 November 2023 Security Baseline Inspection Report 05000220/2023402 and 05000410/2023402 ML23331A2992023-11-27027 November 2023 Submittal of Condition Prohibited by Technical Specifications Due to Failure to Sample Diesel Generator Fuel Oil Storage Tank NMP1L3557, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-22022 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation IR 05000317/20230102023-11-20020 November 2023 Biennial Problem Identification and Resolution Inspection Report 05000317/2023010 and 05000318/2023010 ML23321A1392023-11-17017 November 2023 Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information and Request for Additional Information ML23318A4722023-11-14014 November 2023 Supplement to License Amendment Request to Adopt TSTF-59-A ML23317A1032023-11-10010 November 2023 Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums ML23310A0442023-11-0707 November 2023 Project Manager Assignment IR 05000317/20230402023-11-0202 November 2023 95001 Supplemental Inspection Report 05000317/2023040 and Follow-Up Assessment Letter IR 05000317/20230032023-11-0101 November 2023 Integrated Inspection Report 05000317/2023003 and 05000318/2023003 IR 05000220/20234202023-11-0101 November 2023 Security Baseline Inspection Report 05000220/2023420 and 05000410/2023420 ML23305A0052023-11-0101 November 2023 Operator Licensing Examination Approval IR 05000317/20230902023-10-26026 October 2023 Final Significance Determination of a White Finding with Assessment Follow-Up and Notice of Violation; Inspection Report 05000317/2023090 IR 05000244/20230032023-10-25025 October 2023 LLC - Integrated Inspection Report 05000244/2023003 IR 05000220/20230032023-10-25025 October 2023 Integrated Inspection Report 05000220/2023003 and 05000410/2023003 ML23292A0282023-10-19019 October 2023 LLC - Notification of Conduct of a Fire Protection Team Inspection IR 05000220/20235012023-10-17017 October 2023 Emergency Preparedness Biennial Exercise Inspection Report 05000220/2023501 and 05000410/2023501 IR 05000220/20230112023-10-16016 October 2023 Comprehensive Engineering Team Inspection Report 05000220/2023011 and 05000410/2023011 2024-02-05
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Exelon Generation 200 Exelon Way Kennett Square. PA 19348 www.exeloncorp.com 10 CFR 50.55a(g)(4)(iv)
August 10, 2017 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Calvert Cliffs Nuclear Power Plant, Units 1 and 2 Renewed Facility Operating License Nos. DPR-53 and DPR-69 NRC Docket Nos. 50-317 and 50-318 Nine Mile Point Nuclear Station, Units 1 and 2 Renewed Facility Operating License Nos. DPR-63 and NPF-69 N RC Docket Nos. 50-220 and 50-41 O R. E. Ginna Nuclear Power Plant Renewed Facility Operating License No. DPR-18 NRC Docket No. 50-244
Subject:
Request to Use a Portion of a Later Edition of the ASME B&PV Code,Section XI
Reference:
Letter from J. Zimmerman (U.S. Nuclear Regulatory Commission) to M. Pacilio (Exelon Generation Company, LLC), Request to Use a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, 11 Section XI, Rules for lnservice Inspection of Nuclear Power Plant Components 11 (TAC Nos. ME7286, ME7287, ME7288, ME7289, ME7290, ME7291, ME7292, ME7293, ME7294, ME7295, ME7296, ME7297, ME7298, ME7299, ME7300, ME7301, ME7302), dated March 29, 2012(ML120820266) 11 In accordance with 10 CFR 50.55a, Codes and standards, 11 paragraph (g)(4)(iv), Exelon Generation Company, LLC (Exelon) is requesting NRC approval to use a portion of a later edition of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code,Section XI, "Rules for lnservice Inspection of Nuclear Power Plant Components." Specifically, Exelon proposes to implement Mandatory Appendix I, 1-2600, 11 Appendix VIII Examination, 11 from the 2007 Edition through the 2008 Addenda of the ASME B&PV Code. Implementation of Mandatory Appendix I, 1-2600 from the 2007 Edition through 2008 Addenda will permit the use of Appendix VIII Performance Demonstration Initiative (POI) techniques to be used for components to which Appendix VIII is not applicable. The approval of the 2007 Edition through the 2008 Addenda of the ASME B&PV Code for use was first announced in the Federal Register on June 21, 2011 (i.e., 76 FR 36232).
Request to Use a Portion of a Later Edition of the ASME B&PV Code,Section XI August 10, 2017 Page 2 This request was previously approved for the Exelon fleet in the Referenced letter. Revisions to the original submittal are identified with revision bars.
There are no regulatory commitments contained in this letter. Exelon requests your review and approval of this multiple site request by February 1, 2018.
If you have any questions, please contact Tom Loomis (610) 765-5510.
Respectfully, 4,;1-r L Jr-: ~
James Barstow {)
Director - Licensing and Regulatory Affairs Exelon Generation Company, LLC
Attachment:
Request to Use a Portion of a Later Edition of the ASME B&PV Code,Section XI in Accordance with 10 CFR 50.55a(g)(4)(iv) cc: Regional Administrator - NRC Region I N RC Senior Resident Inspector - Calvert Cliffs NRC Senior Resident Inspector - Nine Mile Point NRC Senior Resident Inspector - R. E. Ginna NRC Project Manager - Calvert Cliffs NRC Project Manager - Nine Mile Point NRC Project Manager - R. E. Ginna
Attachment Request to Use a Portion of a Later Edition of the ASME B&PV Code,Section XI in Accordance with 10 CFR 50.55a(g)(4)(iv)
Request to Use a Portion of a Later Edition of the ASME B&PV Code,Section XI In Accordance with 10 CFR 50.55a(g)(4)(iv)
(Page 1 of 3)
In accordance with 10 CFR 50.55a, "Codes and standards," paragraph (g)(4)(iv) and the guidance provided in Reference 1, Exelon Generation Company, LLC (Exelon) requests NRC approval to use specific provisions of a later edition and addenda of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code,Section XI, for the plants identified in Section 2 of this letter. Currently, ASME Section XI, IWA-2232 of the 2004 Edition of Section XI requires that ultrasonic (UT) examinations be conducted in accordance with Mandatory Appendix I. The 2004 Edition of Mandatory Appendix I, I-2000 requires the performance of ultrasonic examinations in accordance with Appendix III, Appendix VIII, or Section V, Article 4, without substitution. In lieu of the 2004 Edition of Mandatory Appendix I, I-2000 Exelon requests the use of Mandatory Appendix I, I-2600 ("Appendix VIII Examination") from the 2007 Edition through the 2008 Addenda of the ASME B&PV Code,Section XI. This provision states:
a) For components to which Appendix VIII is not applicable, examination procedures, personnel, and equipment qualified in accordance with Appendix VIII may be applied, provided such components, materials, sizes, and shapes are within the scope of the qualified examination procedure.
(b) Examination coverage shall be in accordance with I-3000.
(c) No other I-1000 or I-2000 requirements apply.
Exelon will implement I-2600 from the 2007 Edition through the 2008 Addenda of the ASME B&PV Code. This new provision permits the use of Appendix VIII Performance Demonstration Initiative (PDI) techniques for components to which Appendix VIII is not mandatory.
The 2007 Edition through the 2008 Addenda of the ASME B&PV Code was approved for use in Federal Register 76 FR 36232, dated Tuesday, June 21, 2011, and remains approved in 10 CFR 50.55a(a)(1)(ii)(C)(48) and 10 CFR 50.55a(a)(1)(ii)(C)(49).
Industry experience has demonstrated that use of Appendix VIII techniques for detection and characterization of flaws is equal to or surpasses the requirements of the ASME Code,Section XI, Appendix III or Section V, Article 4.
- 1. ASME Code Component(s) Affected:
This change may be applied to examinations where the alternative conditions of I-2600 are applicable.
Request to Use a Portion of a Later Edition of the ASME B&PV Code,Section XI In Accordance with 10 CFR 50.55a(g)(4)(iv)
(Page 2 of 3)
2. Applicable Code Edition and Addenda
PLANT INTERVAL EDITION START END Nine Mile Point Nuclear Power August 22, 2019 Fourth 2004 Edition August 23, 2009 Station, Unit 1 Nine Mile Point Nuclear Power Third 2004 Edition April 5, 2008 June 15, 2018 Station, Unit 2 Calvert Cliffs Nuclear Power Plant, Fourth 2004 Edition October 10, 2009 June 30, 2019 Units 1 and 2 R. E. Ginna Nuclear Power Plant Fifth 2004 Edition January 1, 2010 December 31, 2019
- 3. Proposed Subsequent Code Edition and Addenda (or Portion):
Exelon requests the use of Mandatory Appendix I, I-2600 from the 2007 Edition through the 2008 Addenda of the ASME B&PV Code,Section XI for the remainder of the intervals specified in Section 2.
- 4. Related Requirements:
10 CFR 50.55a(g)(4)(iv) states:
"Inservice examination of components and system pressure tests may meet the requirements set forth in subsequent editions and addenda that are incorporated by reference in paragraph (a) of this section, subject to the conditions listed in paragraph (b) of this section, and subject to Commission approval. Portions of editions or addenda may be used, provided that all related requirements of the respective editions or addenda are met."
10 CFR 50.55a(b)(2) incorporated by reference Section XI, Division 1, of the ASME B&PV Code, 2007 Edition through the 2008 Addenda as approved in Reference 2. There are no limitations or modifications in 10 CFR 50.55a(b)(2) related to Mandatory Appendix I, I-2600
("Appendix VIII Examination") for the 2007 though 2008 Addenda of Section XI.
In addition, the I-3000 Examination Coverage requirements listed in the ASME 2007 Edition with the 2008 Addenda will be utilized in conjunction with the components examined in accordance with I-2600.
- 5. Duration of Proposed Request:
This provision will be used for the remainder of the intervals specified in Section 2.
Request to Use a Portion of a Later Edition of the ASME B&PV Code,Section XI In Accordance with 10 CFR 50.55a(g)(4)(iv)
(Page 3 of 3)
- 6.
References:
- 1. NRC Regulatory Issue Summary 2004-12, "Clarification on Use of Later Editions and Addenda to the ASME OM Code and Section Xl," dated July 28, 2004
- 2. Federal Register 76 FR 36232, dated Tuesday, June 21, 2011
- 3. Letter from J. Zimmerman (U.S. Nuclear Regulatory Commission) to M. Pacilio (Exelon Generation Company, LLC), Request to Use a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code,Section XI, "Rules for Inservice Inspection of Nuclear Power Plant Components" (TAC Nos. ME7286, ME7287, ME7288, ME7289, ME7290, ME7291, ME7292, ME7293, ME7294, ME7295, ME7296, ME7297, ME7298, ME7299, ME7300, ME7301, ME7302), date March 29, 2012 (ML120820266)