ML20115H528

Forwards Owners Rept for ISI for ISI Activities Conducted at Plant During Spring 1996 Maint/Refueling Outage

ML20115H528
Person / Time
Site:	Vogtle
Issue date:	07/17/1996
From:	Woodard J GEORGIA POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20115H531	List: ML20115H528 ML20115H617
References
LCV-0817, LCV-817, NUDOCS 9607230176
Download: ML20115H528 (4)

Text

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Georgia Power Company 333 Piedmont Avenue 4

Atlanta. oeorgia 30308 Telzphone 404 526-3195 Mailing Address i

40 inverness center Parkway Post Office Box 1295 Birmingham. Alabama 35201 i

Telephone 205 668-5086 J. D. Woodard tne southem erectnc system Senior Vice President July 17,1996 LCV-0817 tcket No.: 50-424 i

U. S. Nuclear Regulatory Commission ATTN: Document Control Desk l

Washington, D. C. 20555 Ladies and Gentlemen:

VOGTLE ELECTRIC GENERATING PLANT INSERVICE INSPECTION

SUMMARY

REPORT Enclosed is the " Owner's Report for Inservice Inspection (Form NIS-1)" for inservice inspection (ISI) activities conducted at Vogtle Electric Generating Plant, Unit 1 (VEGP-1) during its Spring 1996 maintenance / refueling outage. That panicular outage constituted the "10-Year Inservice Inspection" outage for the first ten years of commercial operation which ends May 31,1997 at VEGP-1. The enclosed report is required by Paragraph l

IWA-6230 of the American Society ofMechanical Engineers (ASME) Boiler and Pressure

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Vessel Code,Section XI,1983 Edition with Addenda through Summer 1983. Also included therein are the " Owner's Reports for Repair and Replacements (Form NIS-2)"

for repairs and/or replacements documented at VEGP-1 from the end of the previous inaintenance/ refueling outage through the Spring 1996 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.

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Included in the enclosed VEGP-1 " Owner's Report for Inservice Inspection (Form l

NIS-1)" is a discussion on the inspection of steam generator tubes performed during the Spring 1996 maintenance / refueling outage. That discussion constitutes the Special Report 9607230176 960717

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i U. S. Nuclear Regulatory Commission LCV-0817 Page Two required by VEGP Technical Specification 4.4.5.5.b to be submitted to the NRC within 12 months following completion of the steam generator tube inspections. As a result, there will not be a separate submittal made to the NRC on the inspection of the steam generator tubes performed during the subject outage. By copy of this letter, the appropriate NRC Regional Administrator is being provided copies of the enclosed repon; thus, compliance j

with the requirements of VEGP Technical Specification 6.8.2 for submittal of Special l

Reports to the appropriate NRC Regional Administrator is met.

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Please note that several steam generator tubes were required to be plugged during the Spring 1996 maintenance / refueling outage at VEGP-1. Pursuant to the requirements of VEGP Technical Specification 4.4.5.5.a and 6.8.2, a Special Report was submitted to the NRC within 15 days of the completion of the steam generator tubing inspections and identified the number of steam generator tubes which required plugging during the subject outage. That Special Repon was submitted to the NRC by Georgia Power Company (GPC) letter LCV-0784 dated April 1,1996. Details on which tubes were plugged are included in the discussion provided in the enclosed report.

The ASME Section XI Code-required percentage of examinations and tests for the first ten-years of commercial operation at VEGP-1 were completed during its Spring 1996 maintenance / refueling outage except for the following:

Nuclear Service Coolin g Water (NSCW) System Transfer Pump Supports 11202-P4-007-S01 thrc. ugh S15, Portions of the Ten-Year Hydrostatic Test, Chemical and Volume Control System (CVCS) Valve 11208U6038 Bolting,

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Internal Surfaces of Safety Injection (SI) System Valves 11204U6128 and 11204U6129, Component Cooling Water (CCW) System Heat Exchanger Supports 11203-E4-002-S01 and S02 and CCW Surge Tank Supports 11203-T6-002-S01 and S02,and Auxiliary Feedwater (AFW) System Piping Support 11302-011-H036.

Please refer to the "ASME NIS-1 Form and Classes 1 and 2 Abstract" section of the enclosed report for details on the outstanding examinations and their proposed resolution.

The remaining valve bolting visual examinations for Si valves 11204U6128 and 11204U6129 are being reported herein pursuant to a request from the NRC in its letter dated November 26,1991 to GPC.

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Geargia Power d U. S. Nuclear Regulatory Commission LCV-0817 Page Three During the course of ultrasonically examining the reactor pressure vessel (RPV) welds during the Spring 1996 maintenance / refueling outage at VEGP-1, limitations in the amount of examination coverage were experienced on eight RPV welds. The affected welds included three upper shell welds, four lower shell welds, and one bottom head weld.

The examinations for those welds were limited in coverage due to physical interferences from either core support lugs, bottom-mounted instrumentation, or reactor coolant system loop nozzles contingent upon the actual weld involved. In each case, the amount of examination coverage for the affected RPV welds was less than ninety percent (90%).

ASME Section XI, Code Case N-460, as approved by the NRC, defines " full-Code coverage" as being examination coverage which is equal to or greater than 90%. Because alternative examinations are not practical for the affected welds, GPC hereby advises the NRC that request (s) for relief from the ASME Section XI Code requirements will be submitted to the NRC, as allowed by 10CFR50.55a, for review and approval. The relief request (s) will be submitted to the NRC by December 1,1997 through a revision to the VEGP-1 ISI Program for the first ten-year inservice inspection interval.

Technical Specification 4.4.10.2 for VEGP requires that each reactor coolant pump (RCP) flywheel (and keyway bere) be inspected per the recommendations of NRC Regulatory Guide 1.14. Position C.4.b.2 of that Regulatory Guide requires that all flywheels be examined by the end of the ten-year inservice inspection interval. Each of the ten-year examinations have occurred during the first ten-year inservice inspection interval at VEGP-1 except for RCP No. 3. Change-out of the motor for that particular pump is scheduled for Fall 1997 during the seventh maintenance / refueling outage at VEGP-1.

Although examination at that time f alls outside the first ten-year inservice inspection interval which ends May 30,1997 at VEGP-1, the ASME Section XI Code makes allowances for extensions ofinspection intervals by as much as on: year to enable inspections to coincide with a plant outage. The Fall 1997 maintenance / refueling outage at VEGP-1 falls within the one-year extension allowed by ASME Section XI. As a result, examination of the flywheel for RCP No. 3 during that outage is considered by GPC to be in compliance with the regulatory requirements and, therefore, is considered to be acceptable. Please refer to the "ASME Class 3 and Augmented Examinations Summary" section of the enclosed report for additional details on the RCP flywheel (and keyway bore) examinations.

Five copies of the " Owner's Report for Inservice Inspection (Form NIS-1)" for ISI l

activities conducted during the Spring 1996 maintenance / refueling outage at VEGP-1 are provided for your review. Two copies of the subject repo t are being provided to the l

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y Georgia Powerd 1-i U. S. Nuclear Regulatory Commission l

LCV-0817 i

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Should there be any questions in this regard, please contact this office.

Sincerely,

\\ukd l

Jh. )Woodard N

'JDW/JAE/jae l

Enclosure:

" Owner's Repon for Inservice Inspection (Form NIS-1)" for VEGP-1 Sixth Maintenance / Refueling Outage (IR6), Spring 1996 -

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xc: Georgia Power Company Mr. J. B. Beasley, Jr. (w/o encl.)

L Mr. W. L. Burmeister (w/o encl.)

l Mr. M. Sheibani (w/o encl.)

NORMS (w/ encl.)

l U. S. Nuclear Regulatory Commission l

Mr. S. D. Ebneter, Regional Administrator (w/ encl.)'

l Mr. C. R. Ogle, Senior Resident Inspector, Vogtle (w/ encl.)

Mr. L. L. Wheeler, Licensing Project Manager, NRR (w/ encl.)

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