RA-11-079, Request to Use a Portion of a Later Edition of the ASME B&PV Code, Section XI
| ML112800674 | |
| Person / Time | |
|---|---|
| Site: | Dresden, Peach Bottom, Oyster Creek, Byron, Braidwood, Limerick, Clinton, Quad Cities, LaSalle, Crane  |
| Issue date: | 10/07/2011 |
| From: | Jesse M Exelon Generation Co, Exelon Nuclear |
| To: | Office of Nuclear Reactor Regulation, Document Control Desk |
| References | |
| RA-11-079, RS-11-165, TMI-11-146 | |
| Download: ML112800674 (7) | |
Text
RS-11-165 RA-11-079 TMI-11-146 October 7, 2011 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Braidwood Station, Units 1 and 2 Facility Operating License Nos. NPF-72 and NPF-77 NRC Docket Nos. STN 50-456 and STN 50-457 Byron Station, Units 1 and 2 Facility Operating License Nos. NPF-37 and NPF-66 NRC Docket Nos. STN 50-454 and STN 50-455 Clinton Power Station, Unit 1 Facility Operating License No. NPF-62 NRC Docket No. 50-461 Dresden Nuclear Power Station, Units 2 and 3 Renewed Facility Operating License Nos. DPR-19 and DPR-25 NRC Docket Nos. 50-237 and 50-249 LaSalle County Station, Units 1 and 2 Facility Operating License Nos. NPF-11 and NPF-18 NRC Docket Nos. 50-373 and 50-374 Limerick Generating Station, Units 1 and 2 Facility Operating License Nos. NPF-39 and NPF-85 NRC Docket Nos. 50-352 and 50-353 Oyster Creek Nuclear Generating Station Renewed Facility Operating License No. DPR-16 NRC Docket No. 50-219 Peach Bottom Atomic Power Station, Units 2 and 3 Renewed Facility Operating License Nos. DPR-44 and DPR-56 NRC Docket Nos. 50-277 and 50-278
Request to Use a Portion of a Later Edition of the ASME B&PV Code,Section XI October 2011 Page 2 Quad Cities Nuclear Power Station, Units 1 and 2 Renewed Facility Operating License Nos. DPR-29 and DPR-30 Three Mile Island Nuclear Station, Unit 1 Renewed Facility Operating License No. DPR-50 NRC Docket No. 50-289
Subject:
Request to Use a Portion of a Later Edition of the ASME B&PV Code,Section XI In accordance with 10 CFR 50.55a, "Codes and standards," 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 Inservice Inspection of Nuclear Power Plant Components."
Specifically, Exelon proposes to implement Mandatory Appendix 1,1-2600, "Appendix VIII Examination," 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 (PDI) 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 announced in the Federal Register on June 21, 2011 (I.e., 76 FR 36232).
There are no regulatory commitments contained in this letter.
Exelon requests your review and approval of this fleet request by October 7, 2012.
If you have any questions, please contact Tom Loomis (610) 765-5510.
RespectfuIly,
'chael D. Jesse Director - Licensing qhd R ulatory Affairs Exelon Generation Ct:l ny, LLC
Attachment:
Request to Use a Portion of a Later Edition of the ASME B&PV Code,Section XI
Request to Use a Portion of a Later Edition of the ASME B&PV Code,Section XI October 2011 Page 3 cc:
Regional Administrator - NRC Region I Regional Administrator - NRC Region III NRC Senior Resident Inspector - Braidwood Station NRC Senior Resident Inspector - Byron Station NRC Senior Resident Inspector - Clinton Power Station NRC Senior Resident Inspector - Dresden Nuclear Power Station NRC Senior Resident Inspector - LaSalle County Station NRC Senior Resident Inspector - Limerick Generating Station NRC Senior Resident Inspector - Oyster Creek Nuclear Generating Station NRC Senior Resident Inspector - Peach Bottom Atomic Power Station NRC Senior Resident Inspector - Quad Cities Nuclear Power Station NRC Senior Resident Inspector - Three Mile Island Nuclear Generating Station, Unit 1 NRC Project Manager - Braidwood and Byron Stations NRC Project Manager - Clinton Power Station NRC Project Manager - Dresden Nuclear Power Station NRC Project Manager - LaSalle County Station NRC Project Manager - Limerick Generating Station NRC Project Manager - Oyster Creek Nuclear Generating Station NRC Project Manager - Peach Bottom Atomic Power Station NRC Project Manager - Quad Cities Nuclear Power Station NRC Project Manager - Three Mile Island Nuclear Generating Station, Unit 1
Attachment Request to Use a Portion of a Later Edition of the ASME 8&PV Code,Section XI
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) 1 of 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 (for the editions identified in Section 2) requires that ultrasonic (UT) examinations be conducted in accordance with Mandatory Appendix I. Current versions of Mandatory Appendix I, 1-2000 (for the editions identified in Section 2) required the performance of ultrasonic examinations in accordance with Appendix III, Appendix VIII, or Section V, Article 4, without substitution. In lieu of the current versions (for the editions identified in Section 2) of Mandatory Appendix I, 1-2000 (for the editions identified in Section 2), Exelon requests the use of Mandatory Appendix I, 1-2600 ("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 1-3000.
(c) No other 1-1000 or 1-2000 requirements apply.
Exelon will implement 1-2600 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 (POI) 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.
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 1-2600 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) 2 of
2. Applicable Code Edition and Addenda
PLANT INTERVAL EDITION START END Braidwood Station, Third 2001 Edition, through 2003 July 29, 2008 July 28, 2018 Units 1 and 2 Addenda October 17, 2008 October 16, 2018 Byron Station, Units 1 and Third 2001 Edition, through 2003 January 16, 2006 July 15, 2016 2
Addenda Clinton Power Station Third 2004 Edition July 1,2010 June 30, 2020 Dresden Nuclear Power Fourth 1995 Edition, through 1996 January 20, 2003 January 19, 2013 Station, Units 2 and 3 Addenda LaSalle County Stations, Third 2001 Edition, through 2003 October 1, 2007 September 30, 2017 Units 1 and 2 Addenda Limerick Generating Third 2001 Edition, through 2003 February 1, 2007 January 31, 2017 Station, Units 1 and 2 Addenda Oyster Creek Nuclear Fourth 1995 Edition, through 1996 October 15, 2002 October 14, 2012 Generating Station Addenda Peach Bottom Atomic Fourth 2001 Edition, through 2003 November 5, 2008 November 4,2018 Power Station, Units 2 Addenda and 3 Quad Cities Nuclear Fourth 1995 Edition, through 1996 March 10, 2003 April 1, 2013 Power Station, Units 1 Addenda and 2 Three Mile Island Nuclear Fourth 2004 Edition April 20, 2011 April 19,2022 Station, Unit 1
- 3. Proposed Subsequent Code Edition and Addenda (or Portion):
Exelon requests the use of Mandatory Appendix 1,1-2600 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 (b) 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."
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) 3 of 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, 1-2600
("Appendix VIII Examination") for the 2007 though 2008 Addenda of Section XI.
In addition, the 1-3000 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 1-2600.
- 5. Duration of Proposed Request:
This provision will be used for the remainder of the intervals specified in Section 2.
- 6.
References:
- 1. NRC Regulatory Issue Summary 2004-12, "Clarification on Use of Later Editions and Addenda to the ASME OM Code and Section XI," dated July 28,2004 2.
Federal Register 76 FR 36232, dated Tuesday, June 21, 2011