ML17297A524

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)

ML17297A524
Person / Time
Site:	Calvert Cliffs, Nine Mile Point, Ginna
Issue date:	11/06/2017
From:	David Wrona Plant Licensing Branch III
To:	Bryan Hanson Exelon Generation Co, Exelon Nuclear
Purnell B
References
CAC MG0079, CAC MG0080, CAC MG0081, CAC MG0082, CAC MG0083, L-2017-LLR-0061
Download: ML17297A524 (7)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 November 6, 2017 Mr. Bryan C. Hanson Senior Vice President Exelon Generation Company, LLC President and Chief Nuclear Officer (CNO)

Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555

SUBJECT:

CALVERT CLIFFS NUCLEAR POWER PLANT, UNITS 1 AND 2; NINE MILE POINT NUCLEAR STATION, UNITS 1 AND 2; AND R. E. GINNA NUCLEAR POWER PLANT- REQUEST TO USE 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)

Dear Mr. Hanson:

By application dated August 10, 2017 (Agencywide Documents Access and Management System Accession No. ML17222A002), Exelon Generation Company, LLC (the licensee) submitted a request, in accordance with paragraph 50.55a(g)(4)(iv) of Title 10 of the Code of Federal Regulations (10 CFR), to use a portion of a later edition and addenda of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (ASME Code) at Calvert Cliffs Nuclear Power Plant (CCNPP), Units 1 and 2; Nine Mile Point Nuclear Station (NMP), Units 1 and 2; and R. E. Ginna Nuclear Power Plant (Ginna). Specifically, the licensee requested approval to implement subarticle 1-2600, "Appendix VIII Examination," of Mandatory Appendix I, "Ultrasonic Examinations," to the 2007 Edition through the 2008 Addenda of the ASME Code,Section XI. This would allow the Appendix VIII performance demonstration techniques to be used at the requested facilities for components to which Appendix VIII is not applicable.

The U.S. Nuclear Regulatory Commission staff has reviewed the subject request and concludes, as set forth in the enclosed safety evaluation, that the licensee has adequately addressed all of the regulatory requirements in 10 CFR 50.55a(g)(4)(iv). Therefore, the staff approves the use of Mandatory Appendix I, subarticle 1-2600, of the 2007 Edition through the 2008 Addenda of the ASME Code at CCNPP Units 1 and 2, NMP Units 1 and 2, and Ginna for the remainder of their current 120-month inservice inspection intervals, as specified in the licensee's application.

B. Hanson If you have any questions, please contact Blake Purnell at 301-415-1380 or via e-mail at Blake.Purnell@nrc.gov.

Sincerely, o~ 9V____,

David J. Wrona, Chief Plant Licensing Branch Ill Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-317, 50-318, 50-220, 50-410, and 50-244

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 PORTION OF A LATER EDITION AND ADDENDA OF THE AMERICAN SOCIETY OF MECHANICAL ENGINEERS BOILER AND PRESSURE VESSEL CODE CALVERT CLIFFS NUCLEAR POWER PLANT, UNITS 1 AND 2; NINE MILE POINT NUCLEAR STATION, UNITS 1 AND 2; AND R. E. GINNA NUCLEAR POWER PLANT.

EXELON GENERATION COMPANY, LLC DOCKET NOS. 50-317, 50-318, 50-220. 50-410. AND 50-244

1.0 INTRODUCTION

By application dated August 10, 2017 (Agencywide Documents Access and Management System Accession No. ML17222A002), Exelon Generation Company, LLC (the licensee) submitted a request, in accordance with paragraph 50.55a(g)(4 )(iv) of Title 10 of the Code of Federal Regulations (10 CFR), to use a portion of a later edition and addenda of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (ASME Code) at Calvert Cliffs Nuclear Power Plant (CCNPP), Units 1 and 2; Nine Mile Point Nuclear Station (NMP), Units 1 and 2; and R. E. Ginna Nuclear Power Plant (Ginna). Specifically, the licensee requested approval to implement subarticle 1-2600, "Appendix VIII Examination," of Mandatory Appendix I, "Ultrasonic Examinations," to the 2007 Edition through the 2008 Addenda of the ASME Code,Section XI. This would allow the Appendix VIII performance demonstration techniques to be used at CCNPP, NMP, and Ginna for components to which Appendix VIII is not applicable.

2.0 REGULATORY EVALUATION

The regulations in 10 CFR 50.55a(g)(4) state, in part, that ASME Code Class 1, 2, and 3 components (including supports) must meet the requirements, except the design and access provisions and the preservice examination requirements, set forth in Section XI of the applicable editions and addenda of the ASME Code to the extent practical within the limitations of design, geometry, and materials of construction of the components. The inservice examination of components and system pressure tests conducted during successive 120-month intervals, following the first 120-month interval, must comply with the requirements in the latest edition and addenda of the ASME Code incorporated by reference in 10 CFR 50.55a(a) 12 months Enclosure

prior to the start of the 120-month interval, subject to the limitations and modifications listed in 10 CFR 50.55a(b). For the current 120-month inservice inspection intervals at CCNPP, NMP, and Ginna, the licensee must comply with the requirements in the 2004 Edition of the ASME Code,Section XI.

Paragraph 50.55a(g)(4)(iv) of 10 CFR states:

lnservice 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 [1 O CFR 50.55a], 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.

Based on the regulations in 10 CFR 50.55a(g)(4)(iv), the U.S. Nuclear Regulatory Commission (NRC) staff finds that it has the authority to approve the use of subsequent editions or addenda of the ASME Code.

3.0 TECHNICAL EVALUATION

3.1 Licensee's Request The licensee stated that the 2004 Edition of the ASME Code,Section XI, is currently applicable to CCNPP Units 1 and 2, NMP Units 1 and 2, and Ginna. Paragraph IWA-2232 of the ASME Code,Section XI (2004 Edition), requires ultrasonic examinations to be conducted in accordance with Mandatory Appendix I. Article 1-2000 of Mandatory Appendix I (2004 Edition) requires the performance of ultrasonic examinations in accordance with Appendix Ill, Appendix VIII, or Article 4 of Section V, without substitution.

The licensee has requested to use of subarticle 1-2600 of Mandatory Appendix I to the 2007 Edition through the 2008 Addenda of the ASME Code,Section XI, in lieu of Article 1-2000 in the 2004 Edition of the ASME Code,Section XI, at CCNPP, NMP, and Ginna. In the 2007 Edition through 2008 Addenda of Section XI, subarticle 1-2600 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 1-1000or1-2000 requirements apply.

This provision permits the use of Appendix VIII performance demonstration techniques for components to which Appendix VIII is not applicable. At CCNPP, NMP, and Ginna, the proposed change will affect any ASME Code components that require an examination where the alternative conditions of subarticle 1-2600 are applicable.

The licensee has requested the use of subarticle 1-2600 in the 2007 Edition through 2008 Addenda of Section XI for the remainder of the current 120-month inservice inspection intervals

for CCNPP, NMP, and Ginna. The table below shows the current 120-month inservice inspection interval, including the start and end dates, for each facility.

INSERVICE INSPECTION PLANT START END INTERVAL CCNPP, Units 1 and 2 4th 10/10/2009 6/30/2019 NMP, Unit 1 4th 8/23/2009 8/22/2019 NMP, Unit 2 3rd 4/5/2008 6/15/2018 Ginna 5th 1/1/2010 12/31/2019 3.2 NRC Staff's Evaluation Based on the requirements in 10 CFR 50.55a(g)(4)(iv), the NRC staff considered the following criteria in its review of the licensee's application:

1. The proposed edition or addenda of the ASME Code are incorporated by reference in 10 CFR 50.55a(a).

2. The proposed edition or addenda of the ASME Code are subject to the conditions listed in 10 CFR 50.55a(b).

3. The licensee requested NRC approval to use the proposed edition or addenda 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 are met.

The licensee has requested to use of subarticle 1-2600 of the 2007 Edition through the 2008 Addenda of the ASME Code,Section XI. The 2007 Edition through the 2008 Addenda of the ASME Code,Section XI, are incorporated by reference in 10 CFR 50.55a(a). Therefore, the NRC staff finds that the first criterion has been satisfied.

There are no conditions in 10 CFR 50.55a(b) related to the ultrasonic testing examinations conducted in accordance with Article 1-2000 of the 2007 Edition through 2008 Addenda of the ASME Code,Section XI. Therefore, the NRC staff finds that the second criterion has been satisfied.

The licensee's August 10, 2017, request constitutes a request to the NRC for approval to use a subsequent edition or addenda of the ASME Code. Therefore, the NRC staff finds that the third criterion has been satisfied.

The licensee states that it will use Article 1-3000, "Examination Coverage," of the 2007 Edition through 2008 Addenda of the ASME Code,Section XI, in conjunction with the components examined in accordance with subarticle 1-2600. Therefore, the NRC staff finds that the fourth criterion has been satisfied.

Based on the above, the NRC staff finds that the requirements in 10 CFR 50.55a(g)(4)(iv) are satisfied, and the licensee's request to use Mandatory Appendix I, subarticle 1-2600, in the 2007 Edition through the 2008 Addenda of the ASME Code,Section XI, for the remainder of the

current inservice inspection intervals for CCNPP, Units 1 and 2, NMP Units, 1 and 2, and Ginna is acceptable.

4.0 CONCLUSION

As set forth above, the NRC staff determined that the licensee's request to use a portion of a subsequent edition and addenda of the ASME Code,Section XI, is acceptable because the regulatory requirements in 10 CFR 50.55a(g)(4)(iv) have been satisfied. Therefore, the staff approves the use of Mandatory Appendix I, subarticle 1-2600, to the 2007 Edition through the 2008 Addenda of the ASME Code,Section XI, at CCNPP Units 1 and 2, NMP Units 1 and 2, and Ginna for the remainder of their current 120-month inservice inspection intervals.

Principal Contributor: D. Render, NRR Date of issuance: November 6, 2017

B. Hanson

SUBJECT:

CALVERT CLIFFS NUCLEAR POWER PLANT, UNITS 1 AND 2; NINE MILE POINT NUCLEAR STATION, UNITS 1 AND 2; AND R. E. GINNA NUCLEAR POWER PLANT - REQUEST TO USE 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) DATED NOVEMBER 6, 2017 DISTRIBUTION:

PUBLIC RidsAcrs_MailCTR Resource LPL 1 R/F RidsRgn1 MailCenter Resource LPL3 R/F JBowen, EDO RidsNrrDmlrMphb Resource RidsNrrPMExelon Resource RidsNrrDorlLpl1 Resource RidsNrrPMCalvertCliffs Resource RidsNrrDorlLpl3 Resource RidsNrrPMNineMilePoint Resource RidsNrrLALRonewicz Resource RidsNrrPMREGinna Resource RidsNrrLASRohrer Resource DRender, NRR ADAMS A ccess1on No. ML17297A524 *b>yema1 OFFICE DORL/LPL3/PM DORL/LPL3/LA DE/MPHB/BC* DORL/LPL3/BC NAME BPurnell SRohrer DAiiey DWrona DATE 10/25/2017 10/24/2017 10/13/2017 11/6/2017 OFFICIAL RECORD COPY