ML060880207
| ML060880207 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry, Watts Bar, Sequoyah  |
| Issue date: | 05/05/2006 |
| From: | Marshall M Plant Licensing Branch III-2 |
| To: | Singer K Tennessee Valley Authority |
| Michael Marshall 301-415-0539 | |
| References | |
| TAC MC8911, TAC MC8912, TAC MC8913, TAC MC8914, TAC MC8915 | |
| Download: ML060880207 (8) | |
Text
May 5, 2006 Mr. Karl W. Singer Chief Nuclear Officer and Executive Vice President Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, Tennessee 37402-2801
SUBJECT:
BROWNS FERRY NUCLEAR PLANT, UNITS 1 AND 2, SEQUOYAH NUCLEAR PLANT, UNITS 1 AND 2, AND WATTS BAR NUCLEAR PLANT, UNIT 1 SAFETY EVALUATION TO USE A LATER EDITION AND ADDENDA OF THE ASME CODE (TAC NOS. MC8911, MC8912, MC8913, MC8914, AND MC8915)
Dear Mr. Singer:
By letter dated November 10, 2005, the Tennessee Valley Authority (TVA, the licensee) submitted a proposal to update all the inservice inspection (ISI) program nondestructive examination (NDE) criteria to the requirements of the 2001 Edition, with the 2003 Addenda, of Section XI of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) at Browns Ferry Nuclear Plant, Units 1 and 2, Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Unit 1, for the remainder of their current 10-year ISI interval.
The Nuclear Regulatory Commission (NRC) staff has completed its review of TVAs request, and concludes that upgrading the ISI NDE requirements to the 2001 Edition, with the 2003 Addenda, of Section XI of the ASME Code addresses all related requirements, associated modifications, and limitations in Title 10 Code of Federal Regulations (10 CFR) 50.55a(b).
Therefore, pursuant to 10 CFR 50.55a(g)(4)(iv), the NRC approves the use of the 2001 Edition, with the 2003 Addenda, for the ISI NDE at Browns Ferry Nuclear Plant, Units 1 and 2, Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Unit 1 for the remainder of their current ISI interval.
Sincerely,
/RA/
Michael L. Marshall, Jr., Chief Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-259, 50-260, 50-327, 50-328, and 50-390
Enclosure:
Safety Evaluation cc w/enclosure: See next page
ML060880207 NRR-106 OFFICE LPL2-2 LPL2-2/PM LPL2-2/LA CPNB/BC OGC LPL2-2/BC NAME SCrane DPickett RSola TChan (by memo)
HWedewer MMarshall DATE 04/24/06 04/24/ 06 04/24/ 06 03/27/06 05/03/06 05/05/06
Page 1 of 2 Mr. Karl W. Singer BROWNS FERRY NUCLEAR PLANT Tennessee Valley Authority SEQUOYAH NUCLEAR PLANT WATTS BAR NUCLEAR PLANT cc:
Mr. Ashok S. Bhatnagar, Senior Vice President Nuclear Operations Tennessee Valley Authority 6A Lookout Place Chattanooga, TN 37402-2801 Mr. Larry S. Bryant, Vice President Nuclear Engineering & Technical Services Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 Mr. Robert J. Beecken, Vice President Nuclear Support Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 Mr. Paul L. Pace, Manager Licensing and Industry Affairs ATTN: Mr. James D. Smith Sequoyah Nuclear Plant Tennessee Valley Authority P.O. Box 2000 Soddy Daisy, TN 37384-2000 Mr. Lawrence E. Nanney, Director Division of Radiological Health Dept. of Environment & Conservation Third Floor, L and C Annex 401 Church Street Nashville, TN 37243-1532 Senior Resident Inspector Sequoyah Nuclear Plant U.S. Nuclear Regulatory Commission 2600 Igou Ferry Road Soddy Daisy, TN 37379 Mr. John C. Fornicola, Manager Nuclear Assurance and Licensing Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 Mr. Glenn W. Morris, Manager Corporate Nuclear Licensing and Industry Affairs Tennessee Valley Authority 4X Blue Ridge 1101 Market Street Chattanooga, TN 37402-2801 General Counsel Tennessee Valley Authority ET 11A 400 West Summit Hill Drive Knoxville, TN 37902 Chairman Limestone County Commission 310 West Washington Street Athens, AL 35611 State Health Officer Alabama Dept. of Public Health RSA Tower - Administration Suite 1552 P.O. Box 303017 Montgomery, AL 36130-3017 Brian OGrady, Site Vice President Browns Ferry Nuclear Plant Tennessee Valley Authority P.O. Box 2000 Decatur, AL 35609 Mr. Bruce M. Aukland, Plant Manager Browns Ferry Nuclear Plant Tennessee Valley Authority P.O. Box 2000 Decatur, AL 35609 Mr. Masoud Bajestani, Vice President Browns Ferry Unit 1 Restart Browns Ferry Nuclear Plant Tennessee Valley Authority P.O. Box 2000 Decatur, AL 35609
Page 2 of 2 Mr. Karl W. Singer BROWNS FERRY NUCLEAR PLANT Tennessee Valley Authority SEQUOYAH NUCLEAR PLANT WATTS BAR NUCLEAR PLANT cc:
Mr. Robert G. Jones, General Manager Browns Ferry Site Operations Browns Ferry Nuclear Plant Tennessee Valley Authority P.O. Box 2000 Decatur, AL 35609 Mr. Scott M. Shaeffer Browns Ferry Unit 1 Project Engineer Division of Reactor Projects, Branch 6 U.S. Nuclear Regulatory Commission 61 Forsyth Street, SW.
Suite 23T85 Atlanta, GA 30303-8931 Mr. Larry S. Mellen Browns Ferry Unit 1 Project Engineer Division of Reactor Projects, Branch 6 U.S. Nuclear Regulatory Commission 61 Forsyth Street, SW.
Suite 23T85 Atlanta, GA 30303-8931 Mr. William D. Crouch, Manager Licensing and Industry Affairs Browns Ferry Nuclear Plant Tennessee Valley Authority P.O. Box 2000 Decatur, AL 35609 Senior Resident Inspector Browns Ferry Nuclear Plant U.S. Nuclear Regulatory Commission 10833 Shaw Road Athens, AL 35611-6970 County Mayor Hamilton County Courthouse Chattanooga, TN 37402-2801 Mr. Randy Douet Site Vice President Sequoyah Nuclear Plant Tennessee Valley Authority P.O. Box 2000 Soddy Daisy, TN 37384-2000 Mr. Michael D. Skaggs Site Vice President Watts Bar Nuclear Plant Tennessee Valley Authority P.O. Box 2000 Spring City, TN 37381 Mr. Paul L. Pace, Manager Licensing and Industry Affairs Watts Bar Nuclear Plant Tennessee Valley Authority P.O. Box 2000 Spring City, TN 37381
Enclosure SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION INSERVICE INSPECTION PROGRAM BROWNS FERRY NUCLEAR PLANT, UNITS 1 AND 2 SEQUOYAH NUCLEAR PLANT, UNITS 1 AND 2 WATTS BAR NUCLEAR PLANT, UNIT 1 TENNESSEE VALLEY AUTHORITY DOCKET NOS. 50-259, 50-260, 50-327, 50-328, AND 50-390
1.0 INTRODUCTION
By letter dated November 10, 2005, the Tennessee Valley Authority (the licensee) submitted a proposal to update all the inservice inspection (ISI) program nondestructive examination (NDE) criteria to the requirements of the 2001 Edition, with the 2003 Addenda, of Section XI of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) at Browns Ferry Nuclear Plant, Units 1 and 2, Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Unit 1, for the remainder of their current 10-year ISI interval.
2.0 REGULATORY EVALUATION
Pursuant to Title 10 Code of Federal Regulations (10 CFR) 50.55a(g)(4), ASME Code Class 1, 2, and 3 components (including supports) will meet the requirements, except the design and access provisions, and the preservice examination requirements set forth in Section XI of the ASME Code, to the extent practical within the limitations of design, geometry, and materials of construction of the components. The regulations require that inservice examination of components and system pressure tests conducted during the first 10-year interval and subsequent intervals comply with the requirements in the latest edition and addenda of Section XI of the ASME Code incorporated by reference in 10 CFR 50.55a(b), 12 months prior to the start of the 120-month interval, subject to the limitations and modifications listed therein.
As stated in 10 CFR 50.55a(g)(4)(iv), 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 10 CFR 50.55a(b), subject to the limitations and modification 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.
The ASME Code of record for ISI at the Browns Ferry Nuclear Plant, Unit 1 is the 1974 Edition, through the Summer 1975 Addenda, which began September 16, 1975, and ends 1 year after restart.
The ASME Code of record for ISI at the Browns Ferry Nuclear Plant, Unit 2 is the 1995 Edition, with the 1996 Addenda, which began May 25, 2001, and ends May 24, 2011.
The ASME Code of record for ISI at the Sequoyah Nuclear Plant, Units 1 and 2 is the 1989 Edition (no addenda), which began December 16, 1995, and ends May 31 2006.
The ASME Code of record for ISI at the Watts Bar Nuclear Plant, Unit 1 is the 1989 Edition, which began May 27, 1996, and ends December 26, 2006.
3.0 AFFECTED PORTIONS OF THE ISI CODE OF RECORD The ISI NDE portions of the ASME Code of record for the specific plants that are being updated to the 2001 Edition, with the 2003 Addenda, of Section XI of the ASME Code are:
Subarticles IWA-2200, up to and including IWA-2240, and the related portions of mandatory Appendices I, III, IV, VII, and VIII. The requirements and limitations of 10 CFR 50.55a(b)(2), paragraphs (xix), (xxi), and (xxii) apply. In the case of Appendix VIII, the reference links back to Appendix VII, and the related special conditions and limitations delineated in 10 CFR 50.55a(b)(2), paragraphs (xiv) through (xvi), and paragraph (xxiv) will be followed.
Subarticle IWA-2300, with the exception that requirements of 10 CFR 50.55a(b)(2)(xviii) will be followed. Personnel trained to the alternative requirements for the performance of visual testing (VT-2) examinations will only be used to perform system leakage and hydrostatic tests in accordance with IWA-5211(a) and (b). Personnel qualified to the IWA-2316 alternative requirements will not be used to perform pneumatic-type system leakage tests.
Subarticle IWA-2600, up to and including, paragraph IWA-2641.
Articles IWA-3000, IWB-3000, IWC-3000, IWD-3000, and IWF-3000.
In accordance with 10 CFR 50.55a(b)(2)(vi), NDE of the licensees primary containment structures are performed to the requirements of Subsection IWE and IWL of the 1992 Edition, with the 1992 Addenda (1992A92). As part of this request to upgrade the ISI NDE program procedures to the 2001 Edition, with the 2003 Addenda, of the ASME Code, the licensee will continue to perform the specific examinations of the containment structures to the 1992A92 ASME Code requirements, with the exception that the qualifications of the NDE personnel for ultrasonic testing will be in accordance with updating to the 2001 Edition, with the 2003 Addenda, of the ASME Code requirements, as requested above.
All other related requirements of the 2001 Edition, with the 2003 Addenda, of the ASME Code, have been addressed as part of the description of the proposed updating described above.
Aspects of Section XI of the ASME Code of record for the units ISI programs, such as weld selection, extent of examinations (Articles IWA-2500, and IW(X)-2500 for each corresponding Class), scheduling, and reporting (Article IWA-6000) are not impacted by this request to use the 2001 Edition, with the 2003 Addenda, of the ASME Code for the NDE procedures. Special conditions and limitations on the use of the 2001 Edition, with the 2003 Addenda, of the ASME Code NDE requirements that are delineated in 10 CFR 50.55a(b)(2), have been addressed as part of the descriptions above.
4.0 TECHNICAL EVALUATION
Use of later editions and addenda of the ASME Code that are incorporated by reference in the 10 CFR 50.55a(b), subject to the limitations and modifications listed therein, is allowed by 10 CFR 50.55a(g)(4)(iv) with staff approval. The licensees proposed upgrade of its ISI NDE requirements to the 2001 Edition, with the 2003 Addenda, of the ASME Code, which has been incorporated by reference into 10 CFR 50.55a(b), should improve the quality and efficiency of ISI at Browns Ferry Nuclear Plant, Units 1 and 2, Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Unit 1. The licensee has identified and will meet all related requirements of the respective 2001 Edition, with the 2003 Addenda, of the ISI NDE requirements of Section XI for the ASME Code, thereby, meeting the requirements of 10 CFR 50.55a(g)(4)(iv).
5.0 CONCLUSION
The staff concludes that the licensees request to upgrade the ISI NDE requirements to the 2001 Edition, with the 2003 Addenda, of Section XI of the ASME Code addresses all related requirements and addresses the associated modifications and limitations in 10 CFR 50.55a(b).
Therefore, pursuant to 10 CFR 50.55a(g)(4)(iv), the staff approves the use of the 2001 Edition, with the 2003 Addenda, for the ISI NDE at Browns Ferry Nuclear Plant, Units 1 and 2, Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Unit 1 for the remainder of their current ISI interval identified in the above Regulatory Evaluation section.
Principal Contributor: Donald Naujock Date: May 5, 2006