ML20086C995
| ML20086C995 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 06/26/1995 |
| From: | Mccoy C GEORGIA POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20086C998 | List: |
| References | |
| LCV-0594, LCV-594, NUDOCS 9507070399 | |
| Download: ML20086C995 (3) | |
Text
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Georgia Power Company 40 '*ivemess Center Parkway
- Post office Bnx 1295 y
'7 Birmingham. Matuama 35201 Teler., hone 205 877 7122 4
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Georg>b hver C. K. McCoy t
Vice President. Nuclear Vogtle Project the southern e/ Ctrc system t
June 26, 1995
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LCV-0594 Docket No.: 50-425 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555 Gentlemen:
VOGTLE ELECTRIC GENERATING PLANT i
INSERVICE INSPECTION
SUMMARY
REPORT Enclosed is Volume 1 of the Vogtle Electric Generating Plant, Unit 2 (VEGP-2) Inservice Inspection (ISI) Final Report which constitutes the " Owner'. k - irt for Inservice e
Inspection (Form NIS-1)" required by Subsubarticle IWA-L
!the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI,1983 Edition with Addenda through Summer 1983. ISI activities which were conducted at VEGP-2 during the Spring 1995 maintenance / refueling outage are discussed therein. Also included in the enclosed report volume are " Owner's Reports for Repair and Replacements (Form NIS-2)" for repairs and/or replacements documented at VEGP-2 from the end of the previous maintenance / refueling outage through the Spring 1995 maintenance / refueling outage. Volumes 2 through 6 of the ISI Final Repon contain information not typically submitted to the U. S. Nuclear Regulatory Commission (NRC) in the " Owner's Report for Inservice Inspection (Form NIS-1)", e.g., personnel certifications, nondestructive examination procedures, etc., and are not included herein.
Volumes 2 through 6, however, are 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.
Included in the VEGP-2 " Owner's Report for Inservice Inspection (Form NIS-1)" is a discussion on the inspection of steam generator tubes performed during the Spring 1995 9507070399 950626 PDR ADOCK 05000425
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GeorgiaPbwerA U. S. Nuclear Regulatory Commission LCV-0594 Page Two maintenance / refueling outage. That discussion constitutes the Special Repon 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 inspecti'ons. 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
. Reg onal Administrator is being provided copies of the enclosed report volume; thus, compliance with the requirements of VEGP Teclunical Specification 6.8.2 for submittal of Special Repons to the appropriate NRC Regional Administrator is met.
Please note that several steam generator tubes were required to be plugged during the Spring 1995 maintenance / refueling outage. 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.
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That Special Repon was submitted to the NRC by our letter LCV-0585 dated March 24, B
1995. Details on which tubes were plugged are included in the discussion provided in the enclosed report volume, i
In addition to the above, please be advised that limitations were encountered during the performance of the surface examinations of the Centrifugal Charging Pump 002 integrally l
welded suppon brackets. The limitations specifically applied to weld numbers 21208-P6-002-WO3 r:nd 21208-P6-002-WO5 and had not been previously identified.
l Approximately seventy percent (70%) of the required surface area was examined during the 4 uid penetrant examination on each of these 1wo welds. In order for adequate 9
ASMS Section XI Code-required examination coverage to be attained, ninety percent (90%) or more of the requir-d surface area must be examined as addressed in ASME Code Case N-460. The subject code case has been approved for use in NRC Regulatory Guide 1.147. It is impractical to achieve the ASME Section XI Code-required coverage L
' due to the component design and lack of accessibility because ofinterferences from other b
components. Relief from the ASME Section XI Code requirements will be requested from the NRC for the affected welds during a future ISI program revision for VEGP-2 as allowed by 10 CFR 50.55a.
Five copies of Volume 1 of the ISI Final Repon for the Spring 1995 maintenance / refueling
- catage at VEGP-2 are provided for your review. Two copies of the subject report volume are being provided to the Regional Administrator for NRC Region II.
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. GeorgiaPoiver k U. S. Nuclear Regulatory Commission LCV-0594 Page Three Should there be any questions in this regard, please contact this office.
Sincerely, C. K. McCoy CKM/JAE/jae
Enclosure:
Volume 1 of VEGP-2 ISI Final Report, Fourth Maintenance / Refueling Outage (Period 2/ Interval 1) xc: Georgia Power Company l
Mr. J. B. Beasley, Jr. (w/o encl.)
Mr. W. L. Burmeister (w/o encl.)
Mr. M. Sheibani (w/o encl.)
NORMS (w/ encl.)
j U. S. Nuclear Regulatory Commission-Mr. S. D, Ebneter, Regional Administrator (w/ encl.)
l.
Mr. D. S. Hood, Licensing Project Manager, NRR (w/ encl.)
l Mr. B. R. Bonser, Senior Resident Inspector, Vogtle (w/ encl.)
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i I
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ON
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