ML14176A748
| ML14176A748 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom, Byron, Braidwood, Limerick, Clinton, LaSalle, Crane  |
| Issue date: | 07/18/2014 |
| From: | Travis Tate Plant Licensing Branch III |
| To: | Pacilio J Exelon Generation Co |
| Joel Wiebe, NRR/DORL 415-6606 | |
| References | |
| TAC MF2640, TAC MF2641, TAC MF2642, TAC MF2643, TAC MF2644, TAC MF2645, TAC MF2647, TAC MF2648, TAC MF2649, TAC MF2650, TAC MF2651 | |
| Download: ML14176A748 (7) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. Michael J. Pacilio Senior Vice President Exelon Generation Company, LLC President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555 July 18, 2014
SUBJECT:
BRAIDWOOD, UNITS 1 AND 2; BYRON STATION, UNIT NOS. 1 AND 2; CLINTON POWER STATION, UNIT NO.1; DRESDEN NUCLEAR POWER STATION, UNITS 2 AND 3; LASALLE COUNTY STATION, UNITS 1 AND 2; LIMERICK GENERATING STATION, UNITS 1 AND 2; PEACH BOTTOM ATOMIC POWER STATION, UNITS 2, AND 3; AND THREE MILE ISLAND NUCLEAR STATION, UNIT 1 - REQUEST TO USE A LATER EDITION AND ADDENDA OF THE AMERICAN SOCIETY OF MECHANICAL ENGINEERS BOILER AND PRESSURE VESSEL CODE, SECTION XI (TAC NOS. MF2640, MF2641, MD2642, MF2643, MF2644, MF2645, MF2646, MF2647, MF2648, MF2649, MF2650 AND MF2651)
Dear Mr. Pacilio:
By letter dated September 25, 2013 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML13270A197), ExeiOn Generation Company, LLC (Exelon, the licensee) requested U.S. Nuclear Regulatory Commission (NRC) approval to use a subsequent edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel (ASME Code),Section XI, for inservice examinations of certain components.
Specifically, pursuant to Title 10 of the Code of Federal Regulations (1 0 CFR) 50.55a(g)(4 )(iv),
the licensee requested approval to use the 2007 Edition through the 2008 Addenda of the ASME Code,Section XI, subject to the conditions listed in 10 CFR 50.55a(b), for examinations of Examination Category B-L-1, B M-1, and C-G components, for the remainder of the current 1 0-year inservice inspection intervals specified in Section 3.1 of this safety evaluation (SE).
The NRC staff reviewed the subject request and concludes, as set forth in the enclosed SE, that the use of a subsequent Edition and Addenda of the ASME Code,Section XI requirements is acceptable. Accordingly, the NRC staff concludes that the licensee has adequately addressed all of the regulatory requirements set forth in 10 CFR 50.55a(g)(4)(iv). Therefore, the NRC staff approves the use of the 2007 Edition, 2008 Addenda of the ASME Code,Section XI, for Examination Categories B-L-1, B-M-1, and C-G components.
All other ASME Code, Sections XI, requirements for which the request was not specified remains applicable, including a third-party review by the Authorized Nuclear lnservice Inspector.
If you have any questions, please contact Joel S. Wiebe, Senior Project Manager, at (301) 415 6606 or via e-mail at Joei.Wiebe@nrc.gov.
Sincerely, Travis L. Tate, Chief Plant Licensing 111-2 and Planning and Analysis Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. STN 50-456, STN 50-457, STN 50-454, STN 50-455, 50-461, 50-373, 50-37 4, 50-352, 50-353 50-277, 50-278, AND 50-289
Enclosure:
Safety Evaluation cc w/encl: Distribution via Listserv
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION REQUEST TO USE A LATER EDITION AND ADDENDA OF THE AMERICAN SOCIETY OF MECHANICAL ENGINEERS BOILER AND PRESSURE VESSEL CODE, SECTION XI EXELON GENERATION COMPANY, LLC BRAIDWOOD STATION, UNITS 1 AND 2; BYRON STATION, UNIT NOS. 1 AND 2; CLINTON POWER STATION, UNIT 1; LASALLE COUNTY STATIONS, UNITS 1 AND 2; LIMERICK GENERATING STATION, UNITS 1 AND 2; PEACH BOTTOM ATOMIC POWER STATION, UNITS 2 AND 3; AND THREE MILE ISLAND NUCLEAR STATION, UNIT 1 DOCKET NOS. 50-456, 50-457, 50-454, 50-455, 50-461, 50-373, 50-374, 50-352, 50-353, 50-277, 50-278, and 50-289
1.0 INTRODUCTION
By letter dated September 25, 2013 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML13270A197}, Exelon Generation Company, LLC (Exelon, the licensee) requested U.S. Nuclear Regulatory Commission (NRC or Commission) approval to use a subsequent edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel (ASME Code),Section XI, for inservice examinations of certain components.
Specifically, pursuant to Title 10 of the Code of Federal Regulations (1 0 CFR) 50.55a(g)(4)(iv),
the licensee requested approval to use the 2007 Edition through the 2008 Addenda of the ASME Code,Section XI, subject to the conditions listed in 10 CFR 50.55a(b), for examinations of Examination Category B-L-1, B-M-1, and C-G components, for the remainder of the current 1 0-year inservice inspection (lSI) intervals specified in Section 3.1 of this safety evaluation.
2.0 REGULATORY EVALUATION
In its request, the licensee proposed an alternative to the requirements of the ASME Code, i.e.,
the use of a later edition of the Code in accordance with 10 CFR 50.55a(g)(4)(iv). 10 CFR
- 50. 55a(g)( 4)(iv) states:
lnservice examination of components and system pressure tests may meet the requirements set forth in subsequent editions and addenda of the ASME Code provided Enclosure that they are incorporated by reference in 10 CFR 50.55a(b), subject to the conditions listed in 10 CFR 50.55a(b), 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.
Given that the licensee proposed the use of a later edition of the ASME Code pursuant to 10 CFR 50.55a(g)(4)(iv) and that 10 CFR 50.55a(g)(4)(iv) specifically permits the use of later editions of the ASME Code subject to technical criteria which will be considered below, the NRC staff finds that regulatory authority exists to authorize the use of a subsequent edition of the ASME Code, as requested by the licensee.
3.0 TECHNICAL EVALUATION
3.1 Proposed Subsequent Code Edition and Addenda In its September 25, 2013, submittal, the licensee identified the affected components as the components that are subject to examination under ASME Section XI Examination Categories 8-L-1 (Pressure Retaining Welds in Pump Casings) and 8-M-1 (Pressure Retaining Welds in Valve Bodies) for Class 1 and C-G (Pressure Retaining Welds in Pumps and Valves) for Class 2.
The Code of Record (COR) for the current lSI interval for Code Class 1, 2 and 3, components are specified in Table 1 for each nuclear plant subject to this request. The examinations would not be required to be performed under the COR for the affected components until the last period of the current inspection interval. In lieu of the current COR for each plant, the licensee proposed to use the ASME Code,Section XI, 2007 Edition through the 2008 Addenda for Category B-L-1, B-M-1, and C-G components. The licensee noted that examination categories B-L-1, B-M-1, and C-G are not included in the 2007 Edition through the 2008 Addenda of the ASME Code. The provision in the proposed request will be used for the remainder of the lSI intervals specified in Table 1.
T bl 1 PI a e an san d c d c o es overe dUd R
n er eques t Plant Interval Edition Start End Braidwood Station, Third 2001 Edition, through July 29, 2008 October 17, July 28, 2018, October 16, Units 1 and 2 2003 Addenda 2008 2018 Byron Station, Third 2001 Edition, through January 16, 2006 July 15, 2016 Units 1 and 2 2003 Addenda Clinton Power Station, Third 2004 Edition July 1, 2010 June 30, 2020 Unit 1 LaSalle County Stations, Units 1 Third 2001 Edition, through October 1, 2007 September 30, 2017 and 2 2003 Addenda Limerick Generating Station, Third 2001 Edition, through February 1, 2007 January 31, 2017 Units 1 and 2 2003 Addenda Peach Bottom Atomic Power 2001 Edition, through
- Station, Fourth November 5, 2008 November 4, 2018 Units 2 and 3 2003 Addenda Three Mile Island Nuclear Fourth 2004 Edition April 20, 2011 April 19, 2022 Station, Unit 1 3.2
NRC Staff Evaluation
Section 50.55a(g)(4)(iv) of 10 CFR contains four criteria which must be met prior to use of a subsequent edition of the ASME Code these criteria are:
- 1.
The proposed edition/addendum of the ASME Code is incorporated by reference in 10 CFR 50.55a(b)
- 2.
The proposed edition/addendum of the ASME Code is subject to the conditions listed in 10 CFR 50.55a(b)
- 3.
The licensee shall request Commission approval to use the proposed edition/addendum of the ASME Code
- 4.
If only portions of editions or addenda are to be used all related requirements of the respective editions or addenda must be met.
In evaluating the first criterion, i.e., that the proposed edition/addendum of the ASME Code has been incorporated by reference in 10 CFR 50.55a(b ), the NRC staff notes that Section 10 CFR 50.55a(b)(2) incorporates by reference the ASME Code,Section XI, from the 1970 Edition through the 1976 Winter Addenda, and the 1977 Edition through the 2007 Edition with the 2008 Addenda, which was proposed by the licensee. Therefore, the NRC finds that the first criterion has been satisfied.
In evaluating the second criterion, i.e., the conditions listed in 10 CFR 50.55a(b) are satisfied for the specific proposed subsequent edition and addenda of the ASME Code,Section XI, the NRC staff notes that 10 CFR 50.55a(b) sets no conditions on Examination Categories B-L-1, B-M-1, and C-G of the 2007 Edition through the 2008 Addenda of the ASME Code,Section XI.
Therefore, the NRC staff finds that the second criterion has been satisfied.
In evaluating the third criterion, i.e., the licensee shall request Commission approval to use the proposed edition/addendum of the ASME Code. The NRC staff notes that the licensee's relief request constitutes a request to the Commission for approval to use a subsequent edition/addendum of the ASME Code. Therefore, the NRC staff finds that the third criterion has been satisfied.
In evaluating the fourth criterion, i.e., if portions of subsequent editions or addenda of the ASME Code,Section XI, are used, all related requirements of the respective editions or addenda must be met and that the NRC staff is satisfied that the licensee has listed all related requirements in Examination Categories B-L-1, B-M-1, and C-G of the 2007 Edition through the 2008 Addenda of the ASME Code,Section XI. Therefore, the NRC staff finds that the fourth criterion has been satisfied.
Based on the above, the NRC staff finds that the criteria contained in 10 CFR 50.55a(g)(4)(iv) are satisfied and that the licensee's request to use the 2007 Edition through the 2008 Addenda of the ASME Code,Section XI, for Examination Categories B-L-1, B-M-1, and C-G is acceptable.
4.0 CONCLUSION
As set forth above, the NRC staff determined that the use of a subsequent Edition and Addenda of the ASME Code,Section XI, requirements is acceptable. Accordingly, the NRC staff concludes that the licensee adequately addressed all of the regulatory requirements set forth in 10 CFR 50.55a(g)(4)(iv). Therefore, the NRC staff approves the use of the 2007 Edition throught the 2008 Addenda of the ASME Code,Section XI, for Examination Categories B-L-1, B-M-1, and C-G at the nuclear power plants specified in Table 1 for the remainder of the 1 0-year lSI intervals described in Table 1.
All other ASME Code, Sections XI, requirements for which the request was not specified remains applicable, including a third-party review by the Authorized Nuclear lnservice Inspector.
Principal Contributor: Steven Vitto Date of issuance: July 18, 2014
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