ML20198T097

Forwards Owners Rept for ISI (Form NIS-1), for ISI Activities Conducted at VEGP Unit 1 During Fall 1997 Maint/Refueling Outage.Summary Rept,Discussed

ML20198T097
Person / Time
Site:	Vogtle
Issue date:	01/16/1998
From:	Mccoy C SOUTHERN NUCLEAR OPERATING CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20198T101	List: ML20198T097 ML20198T121
References
LCV-1136, NUDOCS 9801260450
Download: ML20198T097 (4)

Text

.-

• +

ce f

' C. K NCoy -

Seenhorn Nuclear g

Vca President Op~ sting Company, lac.

Vogtle Project

• ): Nerness Center Parkway

.?0. Box 1295 Birming5 ant Alabana 35701 Tel205992.7122 fax 205 992.0403 i

SOUTHERN COMPANY Energy ro serve uur%rld*

January 16, 1998 LCV-Il36 Docket No.: 50-424 w

U. S. Nuclear Regulatory Commission ATTN:' Document Control Desk Washington, D. C. 20555 Ladies and Gentlemen:

VOGTLE ELECTRIC GENERATING PLANT INSERVICE INSPECTION

SUMMARY

REPORT 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 1 (VEGP-1) during its Fall i 997 maintenance / refueling

- outage. That outage was the first one in the second ten year inservice inspection interval which began May 31,1997. 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.- Also included therein are the " Owner's Reports nor Repair and Replacements (Form NIS 2)" fcr repairs and/or replacements of piping and components which were documented at VEGP-1 from the end of the previous maintenance / refueling outage through the Fall 1997 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.

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

. NIS-1)" is a discussion on the inspection of steam generator tubes performed during the

-U[OUO lll

(

/

lll lll l' ll:1 1

I ll!lljllll 111 9901260450 990116 l

l 9 llt PDR-ADOCK 05000424 G

.PDR

- * * * = ' ' -

+

Q. -

l]

m j.Wm q

t gg l

i U. S. Nuclear Regulatory Commission j

J

E LCV ll36

Page Twof Fall 1997 maintenance / refueling outage. 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, there Twill not be a separate submittal made to the NRC_on the inspection of the steam generator l tubes performed during the subject outage.

J Please note that several steam generator tubes were required to be plugged during the Fall 1997 maintenance / refueling outage at VEGP-1. Pursuant to the requirements of VEGP a

. x 1 Technical Specification 5.6.10.a, a report was submitted to the NRC within 15 days of tne o

completion of the steam generator tubing inspections and identified the number of steam generator tubes which required plugging during the subject outage. That report was j

i su'umitted to the NRC by SNC letter LCV-1105 dated October 13,1997. Details on

_ hich tubes were plugged are included in the discussion provided in the enclosed report.

w

. Several welds examined during the Fall 1997 maintenance / refueling outage as part of the f

second ten-year inservice inspection interval scope of examinations had limitations such that their entire examination volume could not be inspected. The affected welds are identified in the enclosed report. " Full Code E*. amination Coverage" of greater than ninety percent (90%) (as discussed in ASME Section XI Code Case N-460 and as

[

z accepted by the NRC in Regulatory Guide 1.147) was not able to be achieved because of

- physical limitations. Unless the welds in question have not been previously identitled to -

the NRC through the relief request process as having limitations preventing full Code-coverage of greater than 90%, no submittal will be made to the NRC seeking relief. - Any L additional relief requested will be made through futi.re revision (s) to the VEGF-1 and 2 Inservice Inspection Program for the Second Ten-Year Interval as they are identified.

l Bh letter LCV-0817 dated July 30,1996, GPC (the former licensee and operator of VEGP 1and sister company to SNC) identified components that were to be examined during the Fall 1997 maintenance / refueling outage at VEGP-1 in order to complete the ASME g

Section XI Code-required percentage of examinations for the first ten-year inservice -

inspection interval. The ASME Section XI Code makes ' allowances for extensions of Ls (inspection intervals by as much as one year to enable examinations to coincide with a plant Moutage. " Addi_tional components were identified subsequent to submittal of the July 30,

, d _ a 11996 letter and required ekamination in order to fulfill the Code requirements. These '

! additional components were identified during preparation for updating the inservice g

! inspection program in May 1997. Each ^of the remaining components, including the 2 additional components denoted below by an asterisk (*), was examined either prior to, x

[ during/or subseq'uent to the subject outage thereby completing the ASME Section XI w

+1 I

t*

i l

p U. S. Nuclear Regulatory Commission LCV-1136 Page Three Code-required percentage of examinations and tests for the first ten-year inservice inspection interval. The examination results for these components are addressed in the enclose

• report.

WELDS; SUREQRTS:

ERESSURE TESTS:

11208-024-5A' and 5B*

11202-P4-007-S01 through Remaining portions of Class S15 1 Ten-Year Hydrostatic Test (HT-1) 11208-043-5A' and SB' 11203-E4-002-S01 and S02 11208-045-14A' and 14B' 11203-P4-001-S0l' and S02*

VALVE BOLTING; 11208-047-14A* and 14B' 11203-T4-002-S01 and S02 11208U6038 11204-V6-001-WO2' 11208 P6-006-S01' 11204-V6-001-WO5' 11302-P4-001-S0l' 11208-V4-001-WO9' 11302-P4-002-S0l' 11302-011-H036 11592-P7-001-S0l* and S02*

One of the welds which required examination during the Fall 1997 maintenance / refueling outage in order to fulfill the Code requirements for the first ten-year inservice inspection it.terval had limited examination coverage. The weld in question, Boron Injection Tank vessel support pad weldri attachment 11208-V6 001-W05, was not able to have its entire weld length examined using surface examination methods due to the configuration of the support pad welded attachment. A supplemental visual e.xamination was performed for the remainder of the weld length. Since Code comoliance with the examination coverage requirements of 90% or greater could not be achieved for weld 11208-V6-001-W05, SNC submitted a revision to an existing relief request to the NRC by letter LCV-1124 dated December 1,1997, for review and approval.

In addition to the foregoing, GPC letter LCV-0817 indicated that the motor for Reactor Coolant Pump (RCP) #3 would be changed-out during the Fall 1997 maintenance / refueling outage. Because of our practice of rotating motors for preventative maintenance reasons, the flywheel and keyway bore on the replacement motor had been examined prior to the subject outage and fulfills the examination requirements of VEGP Technical Specification 5.5.7 for RCP #3 for the first ten-year inservice inspection interval. The flywheel on the motor which was replaced is expected to be examined during refurbishment of the motor. That activity is expected to occur before the VEGP Unit 2 sixth maintenance / refueling outage cuirently scheduled to begin March 8,1998.

~. -.

f.. * ~ N..

+

i LU. S; Nuclear Regulatory Commission -

LCV-ll364

- Page Four Please. refer to the "ASME Class 3 and Augmented Examinations Summary" section of the

.m enclosed report for details on the examination of the RCP flywheel and keyway bore.

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

activities conducted during the Fall 1997 maintenance / refueling outage at VEGP-1 are provided for your review. Two copies of the subject report are being provided to the.

, - Regional Administrr'or for NRC Region II.

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

Sincerely,-

C. K. McCoy CKM/JAEfjae

Enclosure:

' " Owner's Report for Inservice Inspection (Form WIS-1)" for VEGP-1

. Seventh MaintenanedRefueling Outage (1R7), Fall 1997

~

xc: Southem Nuclear Ooeratina Comoany Mr.' J. B. Beasley, Jr. (w/o encl.).

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

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

NORMS (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.) _

Senior Resident Inspector, Vogtle (w/ encl.) -

t

'l.)

3 i

Y A

j

(

n..-

=,.. -.

?

Vogtle Electric Generating Plant-Unit 1 I

Seventh Maintenance / Refueling Outage. (i R7)

LOwner's Report for Inservice inspection Southern Nuclear Operating Company the southern electric system p

m u.

,-.y c-7 y