ML20196F917

Forwards Owner Rept for ISI for Vogtle Electric Generating Plant,Unit 1 Eighth Maint/Refueling Outage. Separate Submittal Will Not Be Made to NRC on SG Tubes Inspected During Subj Outage

ML20196F917
Person / Time
Site:	Vogtle
Issue date:	06/21/1999
From:	Beasley J SOUTHERN NUCLEAR OPERATING CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20196F921	List: ML20196F917 ML20196F971
References
LCV-1356, NUDOCS 9907010009
Download: ML20196F917 (3)

Text

e l , J. B:raie Be:sley, Jr., P.E. Southern Nuclear l Vice President Operating Compa:y. loc.

Vogtle Project 40 Inverness Center Parkway R0. Box 1295 Birmingham, N,abama 35201 Tel 205992.7110 Fax 205 992.0403 SOUTHERN COMPANY Energy to Serve Your \r'orld" l June 21,1999 LCV-1356 1

Docket No.: 50-424 I

U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555 l

Ladies and Gentlemen: l VOGTLE ELECTRIC GENERATING PLANT INSERVICE INSPECTION

SUMMARY

REPORT l Southern Nuclear Operating Company (SNC) submits herein thc " Owner's Report for Inservice Inspection (Form NIS-1)" for inservice inspection activities conducted at Vogtle Electric Generating Plant, Unit 1 (VEGP-1) during its Spring 1999 maintenance / refueling outage. Paragraph IWA-6230 of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI,1989 Edition, requires submittal of the enclosed report. 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.

In addition, " Owner's Reports for Repair and Replacements (Form NIS-2)" are included in the enclosed report for repairs and/or replacements of piping and components that were documented and completed at VEGP-1 from the end of the previous maintenance / refueling outage (Fall 1997) through the Spring 1999 maintenance / refueling outage. 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 inspection of steam generator tubes performed during the Spring 1999 maintenance / refueling outage is included in the enclosed VEGP-1 " 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 inspections. As a result, a separate submittal will not be made to the NRC on steam generator tubes inspected during the subject outage. Although no steam generator tubes were plugged during the outage, SNC l

9907010009 990621 f PDR ADOCK 05000424 G PDR

, U. S. Nuclear Regulatory Commission LCV-1356 j Page Two submitted a report to the NRC by letter LCV-1336 dated March 29,1999, pursuant to VEGP Technical Specification 5.6.10.a which requires that the number of tubes plugged during an outage to be identified.

In addition to components already identified in current requests for relief, one Class 1 piping weld, 11201-058-7 (6" elbow to fiange weld), had limited volumetric examination coverage. Physical limitations due to the geometric configuration of the welded area prevented full ultrasonic examination coverage. As a result, the examination coverage was limited to less than ninety percent (<90%). ASME Section XI Code Case N-460, as approved by the NRC in NRC Regulatory Guide 1.147, allows Code acceptance when the reduction in examination coverage is less than ten percent (<10%). Because it is impractical to achieve the Code-required coverage for the affected weld due to the geometric configuration of the welded area, a request for relief from the ASME Section XI Code requirements will be submitted to the NRC, as allowed by 10 CFR 50.55a, for reviesu and approval. The applicable weld is indicated by " Relief Request Required" in the Ciacs 1 piping weld tables found in the attached report.

No containment examinations were performed during the VEGP-1 Spring 1999 maintenance / refueling outage in response to the NRC rulemaking of 1996 involving Subsections IWE and IWL *.o the 1992 Edition of ASME Section XI with 1992 Addenda.

We currently plan on performing the required examinations for VEGP commencing with the VEGP-2 Fall 1999 maintenance / refueling outage.

Five copies of the " Owner's Report for Inservice Inspection (Form NIS-1)" for ISI activities conducted during the Spring 1999 maintenance / refueling outage at VEGP-1 are provided for your review. Two copies of the subject report are being provided to the Regional Administrator for NRC Region II.

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

Sincerely,

. . Bead! ).

JBB/JAE/

g -.

(

U. S. Nuclear Regulatory Commission LCV-1356 .

Page Three -

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Enclosure:

" Owner's Report for Inservice Inspection (Form NIS-1)" for VEGP-1 Eighth Maintenance / Refueling Outage (1 R8), Spring 1999 ,

xc: Southern Nuclear Operating Company Mr. W. L. Burmeister (w/o enclosure)

Mr. J. T. Gasser (w/o enclosure)

Mr. M. Sheibani (w/ enclosure)

SNC Document Management (w/ enclosure)

U. S. Nuclear Regulatory Commission Mr. R. R. Assa, Project Manager, NRR (w/ enclosure)

Mr. L. A. Reyes, Regional Administrator (w/ enclosure) .

Mr. J. Zeiler, Senior Resident Inspe: tar (w/ enclosure)