ML062900399

Request for Use of Later Edition and Addenda of the ASME Code

ML062900399
Person / Time
Site:	Oconee
Issue date:	10/24/2006
From:	Marinos E NRC/NRR/ADRO/DORL/LPLII-1
To:	Brandi Hamilton Duke Power Co
Olshan L N, NRR/DORL, 415-1419
References
TAC MC8259
Download: ML062900399 (7)

Text

October 24, 2006 Mr. Bruce H. Hamilton Vice President, Oconee Site Duke Power Company LLC 7800 Rochester Highway Seneca, SC 29672

SUBJECT:

OCONEE NUCLEAR STATION, UNIT 2, REQUEST FOR USE OF LATER EDITION AND ADDENDA OF THE ASME CODE (TAC NO. MC8259)

Dear Mr. Hamilton:

By letter dated September 1, 2005, Duke Power Company LLC submitted a request to use certain paragraphs and related portions of the 1998 edition of the American Society of Mechanical Engineers (ASME), Boiler and Pressure Vessel Code (Code), with the 1999 and 2000 addenda of the Code at Oconee Nuclear Station, Unit 2 (Oconee 2). The request is for the remainder of the first 10-year containment inservice inspection (ISI) interval at Oconee 2, which ended on September 9, 2006.

In its letter dated September 27, 2006, the NRC staff had determined that the identified portions of the 1998 edition with the 1999 and 2000 addenda will provide an acceptable level of quality and safety in lieu of the requirements in the 1992 edition with the 1992 addenda, with the exceptions. The safety evaluation (SE) enclosed with the September 27, 2006, letter contained several errors. Therefore, enclosed is a revised SE.

Sincerely,

/RA/

Evangelos C. Marinos, Chief Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-270

Enclosure:

Safety Evaluation cc w/encl: See next page

SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION INSERVICE INSPECTION PROGRAM REQUEST FOR USE OF LATER EDITION AND ADDENDA OF THE ASME CODE OCONEE NUCLEAR STATION, UNIT 2 DUKE POWER COMPANY LLC DOCKET NO. 50-270

1.0 INTRODUCTION

By letter dated September 1, 2005, Duke Power Company LLC (Duke), the licensee, submitted a request to use certain paragraphs and related portions of the 1998 edition with the 1999 and the 2000 addenda of Section XI of the American Society of Mechanical Engineers (ASME),

Boiler and Pressure Vessel Code (Code), at Oconee Nuclear Station, Unit 2 (Oconee 2). The inservice inspection (ISI) Code of record for Oconee 2 for the second containment 10-year ISI interval is the ASME Code,Section XI, 1992 edition with the 1992 addenda. The request is for the remainder of the first 10-year ISI interval at Oconee 2, which ended on September 9, 2006.

2.0 REGULATORY EVALUATION

The ISI of the ASME Code Class 1, 2, and 3, and MC and CC components is to be performed in accordance with Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components, and applicable edition and addenda as required by Title 10 of the Code of Federal Regulations (10 CFR), Part 50, Section 50.55a(g), except when specific relief has been granted by the Nuclear Regulatory Commission (NRC) pursuant to, 10 CFR 50.55a(g)(6)(i).

Section 50.55a(a)(3) states in part that alternatives to the requirements of paragraph (g) may be used, when authorized by the NRC, if the applicant demonstrates that: (i) the proposed alternatives would provide an acceptable level of quality and safety, or (ii) compliance with the specified requirements would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.

Pursuant to 10 CFR 50.55a(g)(4), ASME Code Class 1, 2, and 3, and MC and CC components (including supports) will meet the requirements, except the design and access provisions and the preservice examination requirements, set forth in ASME Code,Section XI, 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) twelve months prior to the start of the

120-month interval, subject to the limitations and modifications listed therein. The ISI Code of Record for Oconee 2 for the first containment 10-year ISI interval is the ASME Code,Section XI, 1992 edition with the 1992 addenda.

3.0 TECHNICAL EVALUATION

3.1 System/Component(s) for which Later Edition and Addenda is Requested Class 1, 2, and 3 components and component supports required to be examined during the remainder of the first containment 10-year ISI interval, which ended on September 9, 2006.

3.2 Applicable Code Requirements ASME Code of record for the first containment 10-year ISI interval is the 1992 edition with the 1992 addenda of Section XI.

3.3 Licensee Request Pursuant to 10 CFR 50.55a(g)(4)(iv), the licensee requests approval to use selected portions of the ASME Code,Section XI, 1998 edition with the 1999 and 2000 addenda, for Category L-A, Item L.11 and L1.12 examinations, in lieu of the 1992 edition with the 1992 addenda, for the remainder of the Oconee 2 first containment 10-year ISI interval, which ended on September 9, 2006.

3.4 Proposed Subsequent Portions of the ASME Code and Related Requirements To use selected portions of the ASME Code, Section Xl, 1998 edition with the 1999 and 2000 addenda, in lieu of the 1992 edition with the 1992 addenda, for Category L-A, Item L1.11 and L1.12 examinations. This request is limited to Oconee 2 for the duration of the first 10-year containment ISI interval, which ended on September 9, 2006.

4.0 EVALUATION The licensees ISI ASME Code of record is the 1992 edition with the 1992 addenda. The licensees proposed use of portions of subsequent edition and addenda to the ASME Code,Section XI that is incorporated by reference in 10 CFR 50.55a(b)(2) subject to any modifications and limitations is in accordance with 10 CFR 50.55a(g)(4)(iv). The NRC staffs review has focused on whether the related requirements of the respective code and addenda are being met and any modifications and limitations apply.

The NRC staff has reviewed the incorporation of the provisions of IWA-2210 of the requirements of the 1998 edition with the 1999 and 2000 addenda. The licensee identified the related requirements of the 1998 edition with the 1999 and 2000 addenda that will be met. The NRC staffs review determined that the 1998 edition with the 1999 and 2000 addenda provide acceptable requirements for performing Category L-A, Item L1.11 and L1.12 examinations.

The NRC staff notes that the incorporation of the provisions of IWA-2210 would not be acceptable, since its requirements will be deleted under Section IWL-2100 of the 1998 edition, with the 1999 and 2000 addenda, of the ASME Code. However, because the licensee has not

requested to use IWL-2100 of the 1998 edition with the 1999 and 2000 addenda, the licensee will continue to use IWL-2100 of the 1992 edition with the 1992 addenda for the duration of the Oconee 2 first containment ISI interval. Because IWL-2100 does not exempt the licensee from complying with the requirements of IWA-2000, the licensee is required to comply with both IWA-2210 and IWA-2300 of the 1992 edition with the 1992 addenda. Therefore, the NRC staff finds the incorporation of the provisions of IWA-2210 of the 1998 edition with the 1999 and 2000 addenda of the ASME Code acceptable.

The NRC staff has reviewed the incorporation of the provisions Subarticle IWA-2300 of the 1998 edition with the 1999 addenda and 2000 addenda. The licensee identified the related requirements of the 1998 edition with the 1999 and 2000 addenda that will be met. The NRC staff noted that in the 1998 edition, with the 1999 and 2000 addenda, of the Code, under the provisions of Section IWL-2100, it is stated that the requirements of IWA-2000 apply, except that the requirements of IWA-2210 and IWA-2300 are not applicable to visual examinations or qualification of visual examination personnel for concrete containments. It is stated in 10 CFR 50.55a(b)(2)(viii)(F) that Personnel that examine containment concrete surface and tendon hardware, wires, or strands must meet the qualification provisions in IWA-2300. The owner-defined personnel qualification provisions in IWL-2310(d) are not approved for use.

Based on these statements, the NRC staff concludes that the use of the provisions of 1998 edition with the 1992 addenda of the ASME Code for IWA-2300 is acceptable.

5.0 CONCLUSION

Based on the NRC staffs review and comparison of the ASME Section XI Code, the NRC staff finds that the identified portions of the 1998 edition with the 1999 and 2000 addenda will provide an acceptable level of quality and safety in lieu of the requirements in the 1992 edition with the 1992 addenda, with the exceptions described above. The NRC staff authorizes the alternative with this noted exception for the remainder of the first 10-year containment ISI interval at Oconee 2.

Principal Contributor: Z. Cruz-Perez Date:

Oconee Nuclear Station, Units 1, 2, and 3 cc:

Ms. Lisa F. Vaughn Mr. R. L. Gill, Jr.

Duke Power Company LLC Manager - Nuclear Regulatory 526 South Church Street Issues and Industry Affairs P. O. Box 1006 Duke Power Company LLC Mail Code EC07H 526 S. Church St.

Charlotte, North Carolina 28201-1006 Mail Stop EC05P Charlotte, NC 28202 Manager, LIS NUS Corporation Division of Radiation Protection 2650 McCormick Dr., 3rd Floor NC Dept of Environment, Health, & Natural Clearwater, FL 34619-1035 Resources 3825 Barrett Dr.

Senior Resident Inspector Raleigh, NC 27609-7721 U.S. Nuclear Regulatory Commission 7812B Rochester Highway Mr. Peter R. Harden, IV Seneca, SC 29672 VP-Customer Relations and Sales Westinghouse Electric Company Mr. Henry Porter, Director 6000 Fairview Road Division of Radioactive Waste Management 12th Floor Bureau of Land and Waste Management Charlotte, NC 28210 Dept. of Health and Env. Control 2600 Bull St. Mr. Henry Barron Columbia, SC 29201-1708 Group Vice President, Nuclear Generation and Chief Nuclear Officer Mr. Michael A. Schoppman P.O. Box 1006-EC07H Framatome ANP Charlotte, NC 28201-1006 1911 North Ft. Myer Dr.

Suite 705 Mr. Charles Brinkman Rosslyn, VA 22209 Director, Washington Operations Westinghouse Electric Company Mr. B. G. Davenport 12300 Twinbrook Parkway, Suite 330 Regulatory Compliance Manager Rockville, MD 20852 Oconee Nuclear Site Duke Energy Corporation Mr. Bruce H. Hamilton ON03RC Vice President, Oconee Site 7800 Rochester Highway Duke Power Company LLC Seneca, SC 29672 7800 Rochester Highway Seneca, SC 29672 Ms. Karen E. Long Assistant Attorney General NC Department of Justice P.O. Box 629 Raleigh, NC 27602

October 24, 2006 Mr. Bruce H. Hamilton Vice President, Oconee Site Duke Power Company LLC 7800 Rochester Highway Seneca, SC 29672

SUBJECT:

OCONEE NUCLEAR STATION, UNIT 2, REQUEST FOR USE OF LATER EDITION AND ADDENDA OF THE ASME CODE (TAC NO. MC8259)

Dear Mr. Hamilton:

By letter dated September 1, 2005, Duke Power Company LLC submitted a request to use certain paragraphs and related portions of the 1998 edition of the American Society of Mechanical Engineers (ASME), Boiler and Pressure Vessel Code (Code), with the 1999 and 2000 addenda of the Code at Oconee Nuclear Station, Unit 2 (Oconee 2). The request is for the remainder of the first 10-year containment inservice inspection (ISI) interval at Oconee 2, which ended on September 9, 2006.

In its letter dated September 27, 2006, the NRC staff had determined that the identified portions of the 1998 edition with the 1999 and 2000 addenda will provide an acceptable level of quality and safety in lieu of the requirements in the 1992 edition with the 1992 addenda, with the exceptions. The safety evaluation (SE) enclosed with the September 27, 2006, letter contained several errors. Therefore, enclosed is a revised SE.

Sincerely,

/RA/

Evangelos C. Marinos, Chief Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-270

Enclosure:

Safety Evaluation cc w/encl: See next page Distribution:

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