ML062700653
| ML062700653 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 09/27/2006 |
| 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: ML062700653 (6) | |
Text
September 27, 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, Unit 2 (Oconee 2). The request is for the remainder of the second 10-year inservice inspection (ISI) interval at Oconee 2, which ended on September 9, 2006.
The enclosed Safety Evaluation (SE) contains the Nuclear Regulatory Commission (NRC) staff's evaluation and conclusions. Based on the information provided in the request, the NRC staff has 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 1989 edition, with the exceptions, as stated in the 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
Mr. Bruce H. Hamilton September 27, 2006 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. MC8258)
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, Unit 2 (Oconee 2). The request is for the remainder of the second 10-year inservice inspection (ISI) interval at Oconee 2, which ended on September 9, 2006.
The enclosed Safety Evaluation (SE) contains the Nuclear Regulatory Commission (NRC) staff's evaluation and conclusions. Based on the information provided in the request, the NRC staff has 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 1989 edition, with the exceptions, as stated in the 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 PUBLIC LPL2-1 r/f RidsOgcRp RidsNrrDorlLpl2-1(EMarinos) RidsNrrLAMOBrien RidsAcrsAcnwMailCenter RidsNrrPMLOlshan RidsRgn2MailCenter(MErnstes)
RidsNrrDorlDpr SLee, EDO Region II RidsNRRDeEema ZPerez, NRR ACCESSION NO. ML062700653 NRR-106
- SE input dated OFFICE NRR/LPL2-1/PM NRR/LPL2-1/LA NRR/EMCB/BC NRR/LPL2-1 NAME LOlshan:
MOBrien KManoly by memo EMarinos DATE 09/27/06 09/27/06 10/31/2005*
09/27/06 OFFICIAL RECORD COPY
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 (ASME Code), at Oconee Nuclear Station, Unit 2 (Oconee 2).
The inservice inspection (ISI) Code of record for Oconee 2 for the second 10-year ISI interval is the ASME Code,Section XI, 1989 edition, no addenda. The request is for the remainder of the second 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 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 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 second 10-year ISI interval is the ASME Code,Section XI, 1992 edition, with the no addenda.
3.0 TECHNICAL EVALUATION
3.1.
System/Component(s) for which Relief is Requested Class 1, 2, and 3 components and component supports required to be examined during the remainder of the second 10-year ISI interval, which ended on September 9, 2006.
3.2.
Applicable Code Requirements ASME Code of record for the second 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, for the remainder of the Oconee 2 second 10-year ISI interval (Class 1, 2, and 3 components and component supports), 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 second 10-year Containment ISI, 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 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 of the ASME Code.
As stated in the the September 1, 2005, letter the licensee will continue to use IWL-2100 of the 1992 edition with the 1992 addenda for the duration of the Oconee 2 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 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 1999 and 2000 addenda of the ASME Code for IWA-2300 is acceptable.
4.0 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 1989 edition, with the exceptions described above. The NRC staff authorizes the alternative with this noted exception for the remainder of the second 10-year ISI interval at Oconee 2.
Principal Contributor: Z. Cruz-Perez Date: September 27, 2006
Oconee Nuclear Station, Units 1, 2, and 3 cc:
Ms. Lisa F. Vaughn Duke Power Company LLC 526 South Church Street P. O. Box 1006 Mail Code EC07H Charlotte, North Carolina 28201-1006 Manager, LIS NUS Corporation 2650 McCormick Dr., 3rd Floor Clearwater, FL 34619-1035 Senior Resident Inspector U.S. Nuclear Regulatory Commission 7812B Rochester Highway Seneca, SC 29672 Mr. Henry Porter, Director Division of Radioactive Waste Management Bureau of Land and Waste Management Dept. of Health and Env. Control 2600 Bull St.
Columbia, SC 29201-1708 Mr. Michael A. Schoppman Framatome ANP 1911 North Ft. Myer Dr.
Suite 705 Rosslyn, VA 22209 Mr. B. G. Davenport Regulatory Compliance Manager Oconee Nuclear Site Duke Energy Corporation ON03RC 7800 Rochester Highway Seneca, SC 29672 Ms. Karen E. Long Assistant Attorney General NC Department of Justice P.O. Box 629 Raleigh, NC 27602 Mr. R. L. Gill, Jr.
Manager - Nuclear Regulatory Issues and Industry Affairs Duke Power Company LLC 526 S. Church St.
Mail Stop EC05P Charlotte, NC 28202 Division of Radiation Protection NC Dept of Environment, Health, & Natural Resources 3825 Barrett Dr.
Raleigh, NC 27609-7721 Mr. Peter R. Harden, IV VP-Customer Relations and Sales Westinghouse Electric Company 6000 Fairview Road 12th Floor Charlotte, NC 28210 Mr. Henry Barron Group Vice President, Nuclear Generation and Chief Nuclear Officer P.O. Box 1006-EC07H Charlotte, NC 28201-1006 Mr. Charles Brinkman Director, Washington Operations Westinghouse Electric Company 12300 Twinbrook Parkway, Suite 330 Rockville, MD 20852 Mr. Bruce H. Hamilton Vice President, Oconee Site Duke Power Company LLC 7800 Rochester Highway Seneca, SC 29672