ML20236Q298
| ML20236Q298 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 07/13/1998 |
| From: | Woodard J SOUTHERN NUCLEAR OPERATING CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20236Q300 | List: |
| References | |
| LCV-1222, NUDOCS 9807200156 | |
| Download: ML20236Q298 (4) | |
Text
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n J. D.Woodard Southern Nuclear Executive Vice President Operating Company. loc.
40 invemess Center Parkway Post Office Box 1295 Birmingham. Alabama 35201 Tel 205 992.5086 SOUTHERN L COMPANY Energy to Serve hurWorld*
July 13, 1998 LCV-1222 Docket No.: 50-425
. U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555 Ladies and Gentlemen:
VOGTLE ELECTRIC GENERATING PLANT INSERVICE INSPECTION
SUMMARY
REPORT L
Southern Nuclear Operating Company (SNC), the licensee and operator of the Georgia Power Company (GPC)-owned Vogtle Electric Generating Plant (VEGP) submits herein the " Owner's Report for Inservice Inspection (Form NIS-1)" for inservice inspection (ISI) activities conducted at VEGP Unit 2 (VEGP-2) during its Spring 1998 maintenance / refueling outage. The enclosed report is required by Paragraph IWA-6230 of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI,1989 Edition. That particular outage constituted the first maintenance / refueling outage in the adjusted Second Ten-Year Interval for VEGP-2.
Examinations and tests were conductni using the requirements of the 1989 Edition of ASME Section XI, to the extent practical.
~ By letter LCV-0861 dated August 16,1996, GPC (the former licensee for VEGP and sister company to Southern Nuclear Operating Company, the current licensee and operator of VEGP) requested NRC concurrence to update the VEGP-2 ISI Program for the Second Ten-Year Interval approximately two years ahead of schedule. The early L
update of the VEGP-2 ISI Program coincided with the update for VEGP-1 and allowed the ISI programs for the two VEGP units to be performed to the same edition of the ASME Section XI Code, i.e., the 1989 Edition. In its November 27,1996 response to the GPC letter, the NRC indicated its concurrence with the early update for VEGP-2 so that the ISI programs for the two VEGP units would coincide. Further, it was indicated that the 1989 Edition of ASME Section XI was acceptable for the ISI program during the adjusted interval for VEGP-2. Because of the early update, the Spring 1998 maintenance / refueling outage at VEGP-2 became the first outage of the Second Ten-Year 9807200156 900713 f
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- U. S. Nuclear Regulatory Commission LCV-1222 Page Two Interval for that particular unit. However, since there are seven maintenance / refueling outages scheduled for the Second Ten-Year Interval between May 31,1997 and May 30, 2007, none of the examinations performed during the subject outage will be counted toward the Second Ten-Year examination requirements, except in the case of ASME
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Code Categories B-G-1, B-G-2, B-L-2 and B-M-2. The examinations for those particular Code category components are acquired only once during the inspection interval when a component, e.g., a pump or valve, is disassembled for maintenance or repair. All of the remaining examinations and tests performed during the Spring 1998 maintenance / refueling outage at VEGP-2 are being credited to the First-Ten Year Interval thereby completing the examination and testing requirements for that interval.
Included in the " Owner's Report for Inservice Inspection (Form NIS-1)" are the
" Owner's Reports for Repair and Replacements (Form NIS-2)" for repairs and/or replacements of piping and components which were documented at VEGP-2 from the end of the previous maintenance / refueling outage (Fall 1996) through the Spring 1998 maintenance / refueling outage. The supporting documentation, e.g., examination records, equipment and material certifications, etc., from which the enclosed " Owner's Report for Inservice Inspection (Form NIS-1)" was compiled is available for review upon request at the plant site.
With regard to the NIS-2 reports on repairs and/or replacements, only the completed NIS-2 forms are being submitted. Any attachments, e.g., code data reports, etc., that are referenced in the completed NIS-2 forms will be made available for review upon request at the plant site.
A discussion on the eddy current examination of steam generator tubes performed during the Spring 1998 maintenance / refueling outage is included in the enclosed VEGP-2
" Owner's Report for Inservice Inspection (Form NIS-1)". That discussion constitutes the report required by VEGP Technical Specification 5.6.10.b to be submitted to the NRC
- within 12 months following completion of the steam generator tube examinations. As a result, there will not be a separate submittal made to the NRC on the examination of the steam generator tubes performed during the subject outage. Although no steam generator
' tubes were plugged during the outage, SNC submitted a report to the NRC by letter LCV-i 1206 dated April 15,1998, pursuant to VEGP Technical Specification 5.6.10.a which requires that the number of tubes plugged be identified.
During the course of ultrasonically examining the reactor pressure vessel (RPV) welds and several piping welds, limitations in the amount of examination coverage were 1
l U. S. Nuclear Regulatory Commission LCV-1222 Page Three experienced. The welds experiencing limitations are identified in the enclosed report. In each case, the amount of examination coverage was less than ninety percent (<90%).
ASME Section XI Code Case N-460, as approved by the NRC, allows Code acceptance when the reduction in examination coverage is less than ten percent (<10%). Because alternative examinations are not practical for the affected welds due to physical limitations, e.g., core support lugs, bottom-mounted instrumentation, etc., SNC hereby advises the NRC that request (s) for relief from the ASME Section XI Code (and regulatory requirements in the case of the RPV examinations) will be submitted to the NRC, as allowed by 10 CFR 50.55a, for review and approval. The request (s) for relief will be submitted to the NRC by December 1,1998, through a revision to the VEGP-2 ISI Program for the First Ten-Year Interval.
Five copies of the " Owner's Report for Inservice Inspection (Form NIS-1)" for ISI I
activities conducted during the Spring 1998 maintenance / refueling outage at VEGP-2 are provided for your review. Two copies of the subject report are being provided to the Regional Administrator for NRC Region II.
l l
Should there be any questions in this regard, please contact this office.
Sincerely, l
r J. D. Woodard JDW/JAE/jae
Enclosure:
" Owner's Report for Inservice Inspection (Form NIS-1)" for VEGP-2 Sixth Maintenance / Refueling Outage (2R6), Spring 1998 i
l xc: (see next page for distribution) l E
- ---_...__-_._.__________________ _ _ ___a
U. S. Nuclear Regulatory Commission LCV-1222 Page Four xc: Southern Nuclear Operating Comnany Mr. J. B. Beasley, Jr. (w/o encl.)
Mr. W. L. Burmeister (w/o encl.)
Mr. M. Sheibani (w/o encl.)
SNC Document Management (w/ encl.)
U. S. Nuclear Regulatory Commission Mr. D. H. Jaffe, Senior Project Manager, NRR (w/ encl.)
Mr. L. A. Reyes, Regional Administrator (w/ encl.)
Mr. J. Zeiler, Senior Resident Inspector, Vogtle (w/ encl.)
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