Text

Inservice Insp Final Rept,Second Refueling Outage (Period 1 /Interval 1), Vols 1 & 2
	ML20055F124
Person / Time
Site:	Vogtle
Issue date:	07/05/1990
From:	; SOUTHERN COMPANY SERVICES, INC.
To:	;
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L 1

Georgia Power Company Vogtle Electric Generating Plant Unit 1 Docket No. 50-424 Inservice Inspection Final Report Second Refueling Outage (Period 1/ Interval 1)

Volume 1 Southern CompanyServices

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OWNER _'S REPORT EQB INSERVICE INSPECTION Document Completion Date: June 1990 Owner: Georgia Power Company 333 Piedmont Avenue, H.E.

P. O. Box 4545 Atlanta, Georgia 30302 Generating Plant: Vogtle Electric Generating Plant, Unit 1 River Road P. O. Box 1600 Waynesboro, Georgia 3083C Commercial Operation Date: May 31, 1987 9~

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l Ly TABLE OF CONTENTS i

Y.glume 1 Etati 7-i . i j). Introductioh 1-1

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! ASME NIS-1 Form with Classes 1 and 2. 2-1 l Abstract ,

1 ASME Class-3 and Augmented Examinations- 31 i L Summary ,

Examination Summary Listings f

[ Introduction to' Summary listings 4-1

+ ASME Class l ,

f Equipment Examinations 5-1 j Piping Examinations 61 l i

ASME-Class 2 1

- I t

Equipment Examinations 7-1 !

Piping Examinations 81 !

Supports

> A Introduction and Equipment 91 Support Examinations .;

' Introduction and Piping 10-1 i Support Examinations

-l Snubber Functional Examinations ,

Introduction to Snubber functional 11 1 ,

Testing Listings ;

Inspection Type I 12 1 Inspection Type 11 13-1 .

Inspection Type Ill 14-1 -t Inspection Type IV 15-1

. Pressure Tests 16-1 m Indication Notification Forms 17-1 Examination Drawings 18-1

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L 4 Volume 2 l kh4 h, .

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b N't.2 Forms 'i

, Volume 3'

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. Class 1 Equipment Examination ~ Data 5 Class 1 Piping Examination Data - .;

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~ Class 2 Equipment Examination Data ;

.i Class 2 Pihing Examination Data i

. Volume 4* j Equipment Support Examination Data ,

Piping Support' Examination Data Nuclear Service Cooling Water (NSCW) System ;

Examination Data Volume 5*

UT Calibration' Sheets i p).

-l t UT Qualification Sheets ;

i MT Qualification Sheets (

Personnel' Certifications i 3

i Equipment Certifications UT Scopes ,

Search Units >

NDE Equipment ;

Consumables-Volume 6*-

NDE Procedures Southern Company Services, Inc. '

Georgia Power Company-t

Volumes 3 through 6 are available for review at the plant site upon request, j ,

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o g LIST OF ABBREVIATIONS 5

A-D Anchor-Darling AFW Auxiliary Feedwater System i

, Al GPC Action llem (followed by unique no.)

ASME American Society of Mechanical Engineers

!.. ASNT American Society for Nondestructive Testing '

ASTM American Society for Testing and Materials BC Branch Connection CCSS Centrifugually Cast Stainless Steel >

CE Combustion Engineering CH Closure Head CS Containment Spray CVCS Chemical and Volume Control System ,

ET Eddy Current Examination FB F1ange Bolting FW Feedwater Syste:d GEO Geometric Indications GPC Georgia Power Company HL Hanger Lug HYD Hydraulic Snubber INF Indication Notification Form ISI Inservice Inspection IST Inservice Testing IR Inside Radius LD Longitudinal Seam Weld Extending Downstream LD 1 Longitudinal Seam Weld Downstream inside of Elbow LU-0 Longitudinal Seam Weld Upstream on Outside of Elbow LMT Lambert, MacGil' and Thomas C'g LU Longitudinal Seam Weld Extending Upstresm ,

(j MECH Mechanical Snubber MS Main Steam System MT Magnetic Particle Examination NCI Nonconformance item NDE Nondestructive Examination NI No Indication NRC-B NRC Bulletin (followed by unique no.) <

NRI No Recordable Indication NSCWS Nuclear Service Cooling Water System OR Outside Radius PL Pipe Lug PM Paul-Munroe ENERTErH PR Pipe Restraint PS Dina hpport-PSA Pacific Scientific PSI Preservice Inspection PT Liquid Penetrant Examination RCS Reactor Coolant System RHRS Residual Heat Removal System RI Recordable Indication ,

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- LIST OF ABBREVIATIONS-- (continued) j

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'i f's RLW . Refracted Longitudinal Wave h

? l RLL Restraint Lug:

Relief Request (followed by unique no.)

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RR-SAT: Satisfactory Exams'Results ;

e , 'SCS Southern Company Services m SIS Safety injection System i

UNSAT' Unsatisfactory Exam Results

- UT- Ultrasonic Examination

'VT LVisual Examination- !

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e Introduction L ,

). This report documents the examinations and tests performed at the Vogtle

> Electric Generating Plant Unit 1 (VEGP-1) between November 25, 1988 (date of last examination performed during the first refueling outage) and April 14, 1990 (date of last examination performed during the second maintenance / refueling i outage) to meet the requirements of Article IWA-6000 of the American Society of i Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI,1983 edition with addenda through Summer 1983. In addition, a summary of the following augmented examinations are included in this report: ,

- Technical Specification 4.4.5.0 - Steam Generator Tube Inspections, ;

e

- Technical Specification 4.7.8 - Snubber Examinations, ;

- Georgia Power Company Action Item No. 173" - Feedwat:r Line Cracking, ,

l

- Georgia Power Company letter N0E-01650 (February 26, 1987) - Inservice Inspection of NSCW Spring Hangers, ;

' - Georgia Power Company letter GN-1345 (February 9, 1987) - Augmented Examination on Class 3 NSCW Systems,

- Georgia Power Company, Vogtle Unit 1 Inservice Inspection Program document ISl-P-006, Paragraph 1.10.3 - Volu.netric Examination of Additional Class 2 Piping Welds, -

O - NRC Bulletin 88 09 - Thimble Tube Thinning in Westinghouse Reactors, t !

'# - Georgia Power Company Action item Nos. 87-0131 and 87-0931 - Stagnated Borated Wat ' Systems Crackino,

- Georgia Power Company Action item No. 18270 - Examination Techniques and Personnel Qualifications for Cold leg Accumulator Piping (10 inch Sch.140, ASTM SA-376, Type 316), and

- NRC Bulletin 88 Pressurizer Surge Line Thermal Stratification.

This report also addresses Code-applicable repairs or replacements which were documented since the last maintenance / refueling outage at VEGP-1. The Owner's .

l Reports on Repairs and Replacements (Form NIS-2) are provided in Volume 2 of this report.

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,38 1

FORM NIS-1 OWNER'S REPORT FOR-INSERVICE-INSPECTIONS-As reouired by the Provisions of the ASME Code Rules 1

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[ 1. Owner:' Georgia ~ Power Company, 333 Piedmont Avenue', N.E.

P.O. Box 4545, Atlanta, Georgia 30302 i b 2. . Plant: Vogtle Electric Generating Plant, l P.O. Box 3600, Waynesboro, Georgia 30830 l

3. Plant Unit: One

4. Owner Certification of Authorization: N/A l I

5 5. Commercial Ser. ^t Date: 05/31/87 1

HL 6. National Board number for Unit: N/A h .7. -Components Inspected:'

l

, g Component or . Manufacturer Manufacturer State or National Apportenance or Installer Or Installer Province Board ,

and Address Serial No. Number Number H i

l Reactor Combustion Eng. Inc. 1

. < Pressure 911-West Main St. 8971 N/A- -21668 '

Vessel Chattanooga, TN

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s_ / - -Steam Westinghouse Elec. t Generators NCD Tampa, FL GAGT 1881 N/A. N/A

~1 through 4 through 1884 Pressurizer - Westinghouse Elec. -

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? Scenic. Hwy.-US 90 62189 N/A N/A Pensacola, FL Reactor Coolant' Westinghouse Elec.

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Pump 1 EMD- F1088 N/A' N/A t" Cheswick, PA i'

Selected Pullman Power Prod.

Piping and Williamsport, PA 1201, 1202, N/A N/A Components '1204, 1205 g 1206, 1208, 1301, 1302 1305

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FORM NIS-1 (BACK)'

8. Examination Dates: 11/25/88 to 04/14/90

9. Inspection Interval: 05/31/87 to 05/30/97

10. Abstract of Examinations, include a list of examinations and a statement concerning status of work required for current interval. (See Abstract)

11. -Abstract of_ Conditions Noted (See Abstract)

12. Abstract of Corrective Measures Recommended and Taken (See Abstract)

We certify that the statement made in this report are correct and the examinations and corrective measures taken conform to the rules of the '

ASME Code,Section XI.

Certificate of Authorization No. (if applicable) N/A Expiration Date N/A Date 6/29 19 @ Signed Georaia Power Company Owner By 20 7. MW CERTiflCATE OF INSERVICE INSPECTION { g 1, the undersigned, holding a valid commission issued by the National Board of >

Boiler and Pressur7 P e ni inspectors and the State or Province of Georgia and employed by The r . cam Boiler Inspection and Insurance Company of One State Street, Hartt. d. CT 06102 have inspected the components described in this Owner's Report d ing he period 11/25/88 to 04/14/90, and state that to the best of-my knot .. ige and beV af, the Owner has performed examinations and taken corrective meas v a desce' 'n this Owner's Report in accordance with the requirements of 1: GMT - a , .ection XI.

By signing thit m iiw rother the Inspector nor his employer makes any '

1 warranty, expree c6 U W ,, concerning the examinations and corrective measures describ. v bh .iwner's Report. Furthermore, neither the Inspector nor his employer shall oe liable in any manner for any personal injury or property damage r a loss of any kind arising from or connected with this '

inspection. -

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inspector'W Signature Commission A S7 ( N 1\

NationalBoard,(tatf,t Province, l

1 / p , and Endorsements daw o*20 19 000881/eu 2-2

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ABSTRACT INTRODUCTION / STATUS The ASME Boiler and Pressure Vessel Code,Section XI,1983 edition with addenda' through Summer 1983 (Code),_ is the applicable code for conducting inservice inspection activities during the first ten year _ inspection interval at VEGP-1.

Examinations and tests required by the Code are scheduled in accordance with

" Inspection Program B" as defined in priagraphs IWB-2412 and IWC-2412 in the Code. This "0wner's Report for Inservice Inspection".is for those first inspection pertad toeJostione and tests which were perf,rmed between November 25; 1988 and Apr414, N90, i.e., the period between the completion of the last examinations for the f5rst and second maintenance / refueling outages,_

respectively. The Code-required p M 9tu;c of examinations and tests scheduled for the first inspection period were compicted during this second maintenance / refueling outage, in addition to the summary of inservice inspection activities, this report addresses Code-applicable repairs and replacements documented since the last maintenance / refueling outage. The Owner's Reports on Repairs or Replacements (Form NIS-2) are located in Volume 2 of this report document.

It should be noted that Authorized Nuclear Inservice Inspector (ANil) inspection services were provided for those examinations and tests required by the Code except for functional testing of snubbers which were tested in accordance with VEGP-l' Technical Specification 4.7.8.

CLASS 1 EXAMINAT10M Selected Class I components were examined by Southern Company Services (SCS),

Georgia Power Company, and Westinghouse personnel utilizing UT, mechanized UT, PT, MT, and VT, as applicable. Specific components and examination areas are itemized in the- applicable portions _ of this document. A summary of those components examined are listed below:

- Reactor Pressure Vessel N1, N4, N5, and N8 Outlet Nozzles Inner Radii

- Reactor Pressure Vessel Flange Ligaments

- Reactor Pressure Vessel Shell - to - Flange Weld

- Reactor Pressure Vessel-to-0utlet Nozzles N1, N4, N5, and NB

- Reactor Pressure Vessel Outlet Nozzles N1, N4, N5, and NB to Safe End Welds

- Pressurizer Upper Head-to-N1 and N4 Safety Nozzles

- Pressurizer N1 and N4 Safety Nozzles-to-Safe End Welds

- Pressurizer Support Lug Attachment Weld

- Steam Generator #2 Inlet and Outlet Nozzles Inner Radii

- Reactor Coolant Pump #1 Main Flange Bolts, Sealwater Housing Cap Screws and Bolts

- Valve Bolting

- Valve Body Internal Surfaces

- Piping Welds.-

- Flange Bolting During the scope of examinations conducted by SCS, ten Class I welds were observed to have reportable surface or ultrasonic indications. For details on the reportable, non-geometric indications observed, refer to the respective 2-3

g E ' Indication Notification Forms-(INF) found in:the INF section of this report document. The ten welds.having reportable indications are discussed below:

1. Reactor Coolant System -- Line 053 - 16" Branch Connection-to-Pipe O . (Weld No.'11201-053-1). The ultrasonic examination revealed recordable indications which were determined to be innerbead lack- of fusion. The indications.were evaluated per ASME Section XI, Table IWB-3514-2 and were determined to be of an acceptable size. No corrective action was taken. The weld will be re-examined during the'next VEGP-1 maintenance / refueling outage' (IR3), (Refer to INF 190-Vl-001).

2. Reactor Coolant System - Line 053 - 14" Pipe-to-Safe End (Weld No.

11201-053-6). Five linear indications were observed during the liquid penetrant examination of the subject weld. The indications were evaluated per ASME Section XI, Table IWB-3514-2 and were determined.to be of an acceptable size. No corrective action was taken. (Refer'to INF 190-VI-002).

3. Reactor Coolant System - Line 004 - 29" Safe End-to-Pipe (Weld No.

11201-004-01). Six linear indications were observed during the liquid penetrant examinatior of the subject weld. The indications were evaluated per ASME Section XI, Table IWB-3514-2 and were determined to be of an acceptable ~ size. No corrective action was taken. (Refer to INF 190-Vl-003).

4. Safety injection System - Line 043 - 6" Elbow-to-Pipe (Weld No, 11204-043-4). Four linear indications were observed during the liquid penetrant examination of the subject weld. The indications were evaluated per ASME Section XI, Table IWB-3514-2 and were determined to be of an acceptable size. No corrective action was taken. (Refer to INF 190-V1-004).

5. Safety injection System - Line 043 - 6 Valve-to Pipe (Weld No.

11204-043-1). Two reportable indications, one linear and one rounded, were observed during the liquid penetrant examination of the subject weld. The linear indication was evaluated per ASME Section XI, Table IWB-3514-2 and was determined to be -of an acceptable size. The rounded indication was evaluated per ASME Section 111', NB-5352 and determined to be of an accept-able size. Since ASME Section XI does not address rounded indications, characterization and evaluation of the rounded indication was performed to the ASME Section Ill acceptance standards. No corrective action was taken.

(Refer to INF 190-Vl-005).

6. Safety %jection System - Line 023 - 6" Valve-to-Pipe (Weld No.

11204-023-16). Three linear indications were observed during the liquid penetrant examination of the subject weld. The indications were evaluated per' ASME Section XI, Table IWB-3514-2 and were determined to be of an acceptable size. No corrective action was taken. (Refer to INF 190-Vl-007).

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. 7. Safety-Injection System - Line 124 - 10" Pipe-to . Valve (Weld No.

-11204 124-15). One linear indication was observed during the liquid penetrant examination of the subject weld. The indication was evaluated per O ASME Section XI, Table IWB-3514-2 and was determined to be of an acceptable size. No corrective action was.taken. (Refer to INF 190-Vl-009).

' 8. Reactor Coolant System - Pressurizer Support Lug Attachment (Weld No.

Il201-V6-002-W31). Four reportable indications, one linear'and three rounded, were observed during the liquid penetrant examination of the subject weld. The linear indication was evaluated per ASME Section XI, IWB 3511 and was determined to be of an acceptable size. The rounded indications were evaluated per ASME Section 111, NB-5352 and determined to be of an acceptable size. As noted above, since ASME Section XI does not address' rounded indications, characterization and evaluation of the rounded indications were performed to the ASME Section 111 acceptance standards.

.No corrective action was taken. (Refer to INF 190 V1-010).

9. Reactor Coolant System - Pressurizer Upper Head-to-6* N4 Safety Nozzle (Weld No.Il201-V6-002-W10). Reportable indications were observed during the ultrasonic examination of the subject weld. The indications were evaluated as a slag inclusion and a' laminar flaw. Both indications were acceptable when evaluated per ASME Section XI Code requirements. No corrective action was taken.= (RefertoINF190-Vl-012).

10. Reactor Coolant System - Pressurizer Upper Head-to-6" N1 Safety Nozzle (Weld No. Il201-V6-002-Wil). Reportable indications were observed during the ultrasonic examination of the subject weld. The indications were evaluated

- as a slag inclusion and a laminar flaw. Both indications were acceptable when evaluated per ASME Section XI Code requirements. No corrective action was taken. (Refer to INF 190-VI-013).

In addition to the above reportable indications, Westinghouse observed several reportable indications during examinations they conducted on selected reactor pressure vessel (RPV) welds and components. .The results of those examinations, including the disposition of the reportable indications, are discussed later in this report.

- Westinghouse personnel performed manual and mechanized ultrasonic examinations of selected RPV welds and components during the outage. Westinghouse nondestructive examination procedures GAE-ISI-54, GAE-ISI-55, and GAE-ISI-154 were utilized. The examination areas included the inner radius area of RPV outlet nozzles N1, N4, N5, and N8; threads in flange (" flange ligaments") L01 through L18; vessel shell-to-flange weld from azimuth 0 to 180 degrees; vessel-to-outlet nozzle welds for RPV outlet nozzles N1, N4, N5, and N8, and the outlet nozzle-to-safe end welds for RPV outlet nozzles N1, N4, N5, and NB.

Five reportable, non-geometric indications were observed during the examination of the RPV shell-to-outlet nozzle N4 (Weld No, ll201-V6-001-W28) and the outlet nozzle-to-safe end welds for outlet nozzles N4, N5, and N8 (Weld Nos, ll201-V6-001-W36, W37, and W40, respectively). The five reportable indications were evaluated per ASME Section XI, IWB-3500 (Tables IWB-3512-1 and IWB-3514-2) and were found to be within Code allowable limits. The five indications were O 2-5 1 f

V judged as single planar flaws and were bounded by 50 percent (50%) Distance

,s Amplitude Correction (DAC) measurements in the through-wall and length

( directions.

No recordable indications (NRis) were observed'in each of the reactor' pressure vessel-to-outlet nozzle welds (Weld Nos._ ll201-V6-001-W25, W28, W29, and W32 for' outlet nozzles N1, N4. N5, and N8, respectively). There were no indications (Nis) observed in either the' vessel shell-to-flange weld examination (Weld No.

Il201-V6-001-WO3, O to 180 degrees) or in the " flange ligaments" examinations (component nos, ll201-V6-001-L01 through L18). No recordable indications (NRis) . ,

were observed during the examination of the outlet nozzles inner radius 1 (component nos.11201-V6-001-IR-01, IR-04, IR-05, and IR-08 for outlet nozzles N1, N4, N5, 'and N8, respectively). Geometrical indications were observed in each of the reactor pressure vessel-to-outlet nozzle welds examined (Weld Nos.

11201-V6-001-W25, W28, W29, and W32 for outlet nozzles N1, N4, N5, and N8, respectively). Metallurgical indications attributed to weld interface were observed in each of the outlet nozzle-to-safe end welds examined (Weld Nos, ll201-V6-001-W33, W36, W37, and W40 for outlet nozzles N1, N4, N5, and N8, i respectively). j Details on the RPV examinations performed by Westinghouse, procedures utilized,. j equipment, material and personnel certifications, etc., may be found-in the l Westinghouse Reactor Vessel Inservice Inspection Field Service Report for VEGP-1 l 1R2. The Westinghouse report is available at the plant site for review upon request.

The remainder of the examinations on Class 1 piping and couponents conducted by em SCS, GPC, and Westinghouse did not reveal any reportable indications.

)

d A system leakage test (Test # LT-1) as required by ASME Section XI, Table

IWB-2500-1, Examination Category B-P, was performed on the Class 1 pressure retaining boundary. These visual examinations (VT-2) revealed acceptable minor leakage and boron residue coming from valve mechanical connections.

The ET examinations of steam generator tubing, as required by VEGP-1 Technical Specification 4.4.5.0, were performed by Westinghouse and are discussed-in'the

" Class 3 and Augmented Examinations" portion of this document.

The inner radius area of the inlet and outlet nozzles of Steam Generator No. 2 (examination areas ll201-B6-002-IR-01 and 11201-86-002-IR-02,.respectively) were-visually examined as discussed in Relief Request RR-42 by GPC personnel. No

'o reportable indications were observed. ,

CLASS 2 EXAMINATIONS Selected Class 2 piping welds were examined utilizing UT, PT, and MT. No Class 2 equipment examinations were performed during this maintenance / refueling outage. Specific examination areas are itemized in the applicable portions of this document.

p 2-6

s The Class 2 piping examinations resulted in two welds having reportable surface s

indications. One weld had indications which were detectable by liquid penetrant ,

y l examination while the second weld = had indications which were detectable by

'/ magnetic particle examination. The remainder of the examinations did not reveal ,

any detectable- non geometrical indications of a recordable size during the ultrasonic examination of the welds.

For details on the reportable non-geometric' indications observed, refer to the

-respective'INF found in the INF section of this report document. The two welds having reportable indications are discussed below:

1. Safety Injection System - Line 201 - 12" Tee-to-Pipe (Weld No. 11204-201-7).

. One linear indication was observed during the liquid penetrant examination '

of the subject weld. The indication was evaluated per ASME Section XI,

-Table IWB-3514-2 and was determined to be of an acceptable size. No corrective action was-taken. (Rafer to INF 190-VI-008).

2. Auxiliary Feedwater System - Line 109 - 6" Pipe-to-Elbow (Weld No.

11302-109-40). Two linear indications were observed during the magnetic particle examination of the subject weld. Both indications exceeded the Code - allowable linear indication length. As a result, controlled buffing in the area of the indications was performed thus removing the. indications.

UT thickness measurements were performed prior to and after buffing of the affected area to assure that minimum wall thickness requirements were not >

violated. After the indications were removed-by buffing, the affected area .

was re-examined using the magnetic particle technique. No indications of a recordable size were observed following controlled buffing of the affected q weld area. (Refer to INF 190-Vl-006).

The following Class 2 pressure tests were performed:

. Reactor Head Vent Functional Test (FT-1).

. Safety Injection Pump 1204-P6-003 Discharge Functional Test (FT-4)

ESafety injection Pump 1204-P6-004 Discharge Functional Test (FT-5)

Penetration 33 Functional Test (FT-6)

. Penetration 30 Functional Test (FT-8)

. Containment Spray Train A Functional Test * (FT-12)

. Containment Spray Train B Functional Test * (FT-13)

. Charging Line Inside Containment Inservice Test (IT-1)

- -Letdown Line inside Containment inservice Test (IT-2)

. RC Pumps 1, 2, 3, and 4 Seal Leakoff inside Containment Inservice Test (IT-3)

. RC Pump 1 Seal Injection from Penetration 54 to Valve 006 Inservice Test (IT-4) <

. RC Pump 2 Seal Injection from Penetration 53 to Valve 359 Inservice Test

-(IT-5)

. RC Pump 3 Seal Injection from Penetration 52 to Valve 360 Inservice Test (IT-6)

. RC Pump 4 Seal Injection from Penetration 51 to Valve 361 Inservice Test ,

(IT-7)

RCS Hot leg Sample Lines to Penetration 24 Inservice Test (IT-8)

. Sample Line from Valve 101 to Valve HV-3513 Inservice Test (IT-9)

CVCS Inservice Test with Positive Displacement Charging Pump Operating (Outside Containment) (IT-10)

U 2-7

i Centrifugal Charging Pump (CCP)-1208 P6 002 Discharge Inservice Test (IT-ll)

. CCP 1208-P6-003 Discharge Inservice Test (IT-12)

. Accumulator Tank-1204 V6-002 Inservice Test (IT-14)

(N . Accumulator Tank 1204-V6 003 Inservice Test (IT-15)

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. Accumulator Tank 1204-V6-004 Inservice Test (IT-16)

. Accumulator Tank 1204-V6-005 Inservice Test (IT-17)

. RHR Train A Inservice Test-(IT-18)

. Refueling Water Storage Tank Inservice Test (IT-23)

. Sample Line from Valve 097 to Valve HV-3508 Inservice Test (IT-24)

. Penetration 24 Outside Containment inservice Test (IT-25)

. Containment Coolers 1501-A7-001 and 1501-A7-002 Inservice Test (IT-34)

Containment Coolers 1501-A7-005 and 1501-A7-006 Inservice Test (IT-36)

. Cooling Coils 1511-E7-001 and 1515-A7-001 Inservice Test (IT-38)

. Steam Generator 1201-B6 001 Inservice Test (IT-45)

. Steam Generator 1201-B6-002 Inservice Test (IT-46)

. Steam Generator 1201-B6-003 Inservice Test (IT-47)-

. Steam Generator 1201-B6 004 Inservice Test (IT-48)

. Penetration 7 Inservice Test (IT-49)

. Penetration.8 Inservice Test (IT-50)

. Penetration 9 Inservice Test (IT-51)

Penetration 10 Inservice Test (IT-52)

.. Penetration llB Inservice Test (IT-53)

. Penetration llc Inservice Test (IT-54)

Penetration 12B Inservice Test (IT-55)

. Penetration 12C Inservice Test (IT-56)

. Main Steam Loop 1 Inservice Test (IT-57)

. Main Steam Loop 2 Inservice Test (IT-58)

. Main Steam Loop 3 Inservice Test (IT-59)

. Main Steam Loop 4 Inservice Test (IT-60) l l ) . Main feedwater Loop 1 Inservice Test (IT-71) v . Main feedwater Loop 2 Inservice Test (IT-72)

. Main Feedwater Loop 3 Inservice Test (IT-73)

. Main Feedwater Loop 4 Inservice Test (IT-74)

Main Feedwater Bypass Loop 1 Inservice Test (IT-75)

. Main Feedwater Bypass Loop 2 Inservice Test (IT-76)

. Main Feedwater Bypass Loop 3 Inservice Test (IT-77)

Main Feedwater Bypass Loop 4 Inservice Test (IT-78)

. Excess Letdown Heat Exchanger Inservice Test (IT-79)

. RHRS Cleanup Inservice Test (IT-80)

Examined portions not examined in MW0s 18803844, 18805645, and 18805644.

The visual examinations performed during these pressure tests found only minor leakage at mechanical joints such as valve stem packing and at flanged connections. These leaks were evaluated and determined acceptable for continued

. system operation. However, appropriate corrective action was 1nitiated to correct this minor leakage.

CLASS 1 AND 2 COMPONENT SUPPORTS s

-Snubber examinations and functional tests required by Technical Specification 4.7.8 are discussed in the " Class 3 and Augmented Examinations" portion of

-this document. Visual exams were performed on supports for the Class 'l vessel listed below:

g i j . RCS Pressurizer 2-8

These visual examinations revealed an unsatisfactory condition which t'esulted in an INF. This Indication Notification (Refer to INF 190 Vl-Oll) was evaluated -

/~. 't and.was determined acceptable for continued system operation. No corrective

( ,) _

action was taken. No visual examinations were performed on Class 2 Component '

Supports.

Visual examinations were performed on Class 1 and 2 piping supports in the following systems:

.- Reactor Coolant

. Nuclear Service Cooling Water

. Safety-Injection ,

. Containment Spray

. Chemical and Volume Control

. Auxiliary Feedwater The visual examinations indicated an unsatisfactory condition on two supports in the Reactor Coolant System. This resulted in an INF (Refer to INF 190-Vl-011) to cover both supports. These supports were reworked to correct the unsatisfactory condition. The remaining visual examinations did not reveal any unsatisfactory conditions with the piping supports.

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5h CLASS 3 AND AUGMENTED EXAMINATIONS

SUMMARY

. CLASS 3' EXAMINATIONS s ,r .

Class 3 Pressure Tests System pressure tests were performed on the following Class-3 systems:

. Nuclear Service Cooling Water System Train "A" (IT-26,-IT-27, IT-29, ;

IT-32,IT-81,IT-83,IT-85,IT-88,IT-89,IT-90)

. Nuclear Service Cooling. Water System Train "B" (IT-28, IT-30, IT-31,

t. IT-33,-IT-82, IT-84, IT 86,'IT-87, IT-91, IT-92)

. Chemical and Volume Control System (IT-13, IT-93, IT-94)

. Containment Spray System (IT-22)

. -Auxiliary Feedwater System Trains "A", "B",-& "C" (IT-61, IT-62, IT-63, IT-64,IT-65,IT-66)-

. Safety-Related (ESF) Chilled Water System Train "A" (IT-67)

. Safety-Related (ESF) Chilled Water System Train "B" (IT-68) .

The' visual examinations performed during these pressure tests found only minor

' leakage at mechanical joints such as valve stem packing and at flanged connections. These leaks were evaluated and' determined acceptable for continued i

') system operation. However; appropriate corrective action was initiated to V correct this minor leakage.

Llass 3 Component Suonorts ard Intearal Attachments L Visual examinations were performed on supports and integral attachments for

" the Class 3 components-listed below:

l

. Spent' Fuel Pit Heat Exchanger I . Nuclear Service Cooling Water Piping

. Component Cooling Water Piping

. Auxiliary Feedwater Piping These visual examinations did not reveal any unsatisfactory conditions with the supports or integral attachments.

1.

v/ 3-1

a AUGMENTED INSPECTIONS

~ Technical: SDecification 4.4.5.0 - Steam Generator Tube InSDeCtions

. During the second maintenance / refueling outage at-VEGP-l', the Steam Generator Services Group of the Westinghouse Nuclear Service Division performed eddy current testing of the four VEGP-1 Model F steam generators in parallel and mechanical plugging in one steam generator (Steam Generator No. 2) from February 27, 1990 to March 12, 1990. Selected tubes from each of the four steam generators were inspected rather than only one steam generator in order to enhance the VEGP-1 steam generator inspection program. The results are summarized in Table I-(refer to page 3-6) including the accumulative number of plugged steam generator tubes.

Tables 11 through V (refer to pages 3-7 through 3-10) identify the steam generator tubes with indications by location and percent of wall thickness penetration for Steam Generator Nos. 1 through 4, respectively.

Applicable procedures, personnel qualifications, material and equipment certifications, sign off sheets, and supporting data, etc. can be found in

~

Westinghouse Steam. Generator Primary Services Field Service Report, MRS 4.4 GAE-7, " Eddy Current Testing and Mechanical Plugging," which is available at i the plant site for review upon request.

Bobbin Coil Insoection Inspection Plan Description fm The intent of the test plan was to bring VEGP-1 in line with the Electric l~ j i Power Research Institute (EPRI) PWR Steam Generator Examination Guidelines i

d for steam generator inspections. The EPRI guidelines state that twenty percent l-(20%) of the tubes shall be inspected in each steam generator such that after five cycles, each of the tubes will have been inspected. In addition, the Guideline recommend additional testing for any areas of concern. Plant Technical . specifications also require that reportable defects be inspected. To meet these requirements, forty percent (40%) of the tubes in Steam Generator Nos. 2 and 3 were tested and enough tubes were tested in. Steam Generator Nos. 1 and 4 such that the total tubes inspected after two outages equaled forty percent (40%). All of these tubes were tested full length. Because of a concern for' anti-vibration bar (AVB) wear, the remaining tubes in Rows 21 and higher were tested from reference point 7C to 6H.

Inspection Plan Implementation To summarize the inspection plan, each of the tubes in Row 5 and greater were tested full length from the hot leg side using a 0.560 inch diameter probe.

Rows 3 and 4 were tested through the U bend from the hot leg side with the same diameter probe. Rows 1 and 2 straight section was tested using a 0.560 inch diameter probe; however, because of U-bend restrictions, a 0.520 inch diameter-probe was used in the U-bend region. The untested portion of the tubing in Rows 1 through 4 was tested from the cold leg using a 0.560 inch diameter probe.

O V 3-2

The eddy current bobbin inspection program was conducted in accordance with Westinghouse procedure MRS 2.4.2 GPC-1 using Westinghouse Job Data Sheet GAE-01.

! Per the Job Data Sheet, the withdrawal rate was 24 inches per second and the test frequencies were 630 Khz, 320 Khz, 160 Khz, and 10 Khz.

The bobbin probes used in the inspection of the steam generator tubes were manufactured by Echoram and Zetec. The primary probe used was the EB-560 BBM-UF-design by Echoram. Zetec-designed A-560 SFRM and A-560-$FRM-HF probes were also used. In addition, the Rows 1 and 2 U bends were tested using a A 520 BJFRM-HF probe.

Motorized Rotatina Pancake Coil Inspection (MRPC)

Inspection Plan Description A Motorized Rotating Pancake Coil (MRPC) inspection was performed on eleven hot leg' intersections and seven cold leg intersections in Steam Generator No. 3, as well as two hot leg intersections and five cold leg intersections in Steam Generator No. 4. Each of the intersections selected contained indications with pluggable characteristics based on bobbin coil eddy current inspection. The-purpose of performing the MRPC testing was to further characterize these indications._ MRPC testing of these intersections determined that the indications'were not flaws as the bobbin coil indicated. Hence, it was decided that MRPC testing of these type indications in Steam Generator Nos. I and 2 was not necessary, inspection Plan Implementation Because of tangent indications in the Steam Generator No. 4 cold leg and the-Steam Generator No. 3 hot and cold legs, a MB-520-MRPC-FH-PH probe was used.

Since only straight section indications were present in the Steam Generator No.

4 hot leg, a 560M MRPC probe head was used.

The MRPC inspections were performed in accordance with Westinghouse procedure MRS 2.4.2 GPC-1. Westinghouse Job Data Sheet GAE-02 was used for the Steam Generator No. 4 hot leg. The remaining MRPC testing was done-using Job Data Sheet GAE-03. The test frequencies used were in accordance with those identified on the Job Data Sheets.

Data Evaluation Westinghouse performed a primary and secondary evaluation of the eddy current data. Both the DDA-4 analysis software and the Westinghouse Intelligent Eddy Current Data Analysis (IEDA) System were used for analysis of the eddy current data. IEDA was used as a. secondary analysis of the data.

Prior to the outage, Westinghouse prepared a data analysis training and testing program for the data analysts. The program included training tapes, testing tapes, and a training manual. Both bobbin data and MRPC data were used. The bobbin data used were indications from the baseline examination and the first maintenance / refueling outage at VEGP-1. The MRPC data used in the program were from Alabama Power Company's Farley Nuclear Plant. The training manuals consisted of site-specific guidelines, steam generator information, data analysis checklists and flow charts, set-up information, and pictures of typical indications and structures. The manuals, training tapes, testing tapes, and O answer keys were turned over to GPC at the completion of the job.

3-3

The analysts were required to complete the training prior to performing any ,

inspection analysis. It took approximately two eight hour shifts for each analyst to compete the training. In addition, each analyst had to take the exam

( y using the type of machine on which he was to analyze inspection data (IEDA or U DDA-4). j Evaluation of the eddy current data revealed one tube in Steam Generator No. 2 with a pluggable indication, in addition, three tubes in Steam Generator No. 2' had AVB indications greater than thirty five percent (35%)-that were not previously detected. It was decided that these tubes would be plugged as a precautionary measure. As mentioned pretiously, MRPC inspection of some indications with pluggable characteristics revealed no flaws requiring plugging.

Indications' classified in Steam Generator Nos. 2 and 3 during the baseline examination were reclassified as manufacturing buff marks or other anomolies.

The criteria for these classi_fications are defined in the Vogtle site-specific data analysis guidelines found in Westinghouse report MRS 4.4 GAE-7 which is available at the plant site for review upon request.

The following table below summarizes the indications found:

Steam Generator No. 1 No. 2 No. 3 No. 4 40% and greater through wall 0 1 0- 0

.20% _ 39% through wall 9- 14 20 6 Less than 20% through wall 12 10 21 6 Manufacturing Buff Marks 51 113 161 73 L

1 1 {q'~'j lt should be noted that the above table is based on the largest indication l-per tube.

L. More' details regarding indication distributions can be found in the maps which follow this discussion.

Mechanical Pluaaina Mechanical plug installation was performed in Steam Generator No. 2. The Inconel-690 taper plug was installed using the WL-II mechanical plugging arm.

Four tubes in Steam Generator No. 2 tubes R54C87, R53C90, R50C95, and R40C106, ;

~

were plugged using the WL-Il mechanical plugging system. The U.S. Nuclear Regulatory Commission was notified by Special Report as required by plant Technical Specifications, of the tubes that were required to be plugged during -

the second maintenance / refueling outage at VEGP-1.

l Maos L 1: Composite Plot of E/C Testing - Steam Generator No. 1 (page 3-11) 2: Tubes with Numerical Indications - Steam Generator No.1 (page 3-12) 3: Composite Plot of E/C Testing - Steam Generator No. 2 (page 3-13) 4: Tubes with Numerical Indications - Steam Generator No. 2 (page 3-14) 5: Composite Plot of E/C Testing - Steam Generator No. 3 (page 3-15) l 6: Tubes with Numerical Indications - Steam Generator No. 3 (page 3-16) 7: Composite Plot of E/C Testing - Steam Generator No. 4 (page 3-17)

,V

(') 8: Tubes with Numerical Indications - Steam Generator No. 4 (page 3-18) 3-4

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RQlE The above discussion-on the steam generator tubing inspections,,in addition to fulfilling the ;

reporting requirements of ASME Section XI for :

inservice inspection activities, constitutes the Special Report required by VEGP-1 Technical Specification 4.4.5.5.b to'be submitted to the U.S.

Nuclear Regulatory Commission (USNRC) within' twelve months following completion of the steam generator ,

tube inspections. Accordingly, a separate <

submittal is not 'veing made to the USNRC on the inspection or the steam generator tubes performed during the second maintenance / refueling outage at VEGP-1. A copy of selected volumes of this report containing the above steam generator examination

! discussion is being provided to the USNRC Regional:

Administrator;-thus, compliance with the '

requirements of VEGP-1 Technical Specification i

6.8.2-for submittal of Special Reports to the Regional Administrator of the appropriate USNRC Region office is met.

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TABLE I Steam Total- No. of - No. . No. No. Plugged ' No. Plugged. Total ~No.

Generator -No. Tubes . -. Degraded Defective : Prior'to during of-No. of Tubes Inspected- 'Outaae IR2 .0utaae IR2 Tubes Pluqued 1 5,626 1,514(*) 9- 0- 1 0 1 2,427(**) --

2 5,626 -2,357(*) 14(***) 1 0 .4 4- ,

1,886(**)

3 5,626 2,403(*) 20 0 2 0 2 1,859(**)

4 5,626 1,471(*) 6 0 4 0 4 2,452(**)

(*) Examined full length of tube..

(**) Examined U-bend area of tube _only.

(***) Three tubes were plugged as a precautionary measure.

3-6

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, y: p kkg ,s TABLE 11 Yk -Steam Generator No. 1 Reference Distance from. Wall Thickness- = Plugged-18.qg [olumn Point (1) Reference (in.) Penetration (%). '(Y/N) 28 13. SC 17.62 27- N 24 14 TSH 8.73 15 N ->

28 18 2H 1,42 13 N L45 22 AV5 0.00 17 N 47 74 AV2 0.00 21 N-47 26- AV6 0.00 10 N .

54 35 AV4 0.00 21 N 41 44 AV3 0.00 18' N 52 44 AV4 0.00 15 N :

57 44 AV5 0.00 17 N 57 45 AV5 0.00 12 N

40 47 AV3 0.00 13 N 34 49 BPC 6.96- 29 N !

13 52' 3H 19.54 17 N 35 52 10. 31.89 23 N-55 55 AV2 0.00 20 N ,

39 92 3H 1.03 34 N 42- -104 AV6 0.00 13 N 25 110- AV5. 0.00 22 N !

- 26 116 AV6 0.00 16 N' 24 117 2C 0.00 26 N 7

! )

v The above information is based on the largest indication observed for the respective tube during the second maintenance / refueling outage at VEGP-1. 1 NOTE 1: Reference Point location

Description:

TSC, TSH - Top of Tubesheet- Hot and Cold BPH, BPC - Baffle Plate Hot and Cold

H, #C - (# = Number) of Support Plate Hot and Cold, e.g., 2H, 2C AV1, AV2, AV3, AV4, AVS, AV6 - Anti-Vibration Bars .

1 i

i U

3-7

i l

1 TABLE Ill 1 Steam Generator No. 2

/L.:{>

Reference Distance from- Wall Thickness- Plugged Row Column- Point (1) Reference-fin.) Penetration (%) (Y/N) 25 20 AV5 0.00- 20- N 14 33 5H 14.05 21- N 41 33 AV5 0.16 17 N~

20 44 3H 34.71 15 N 46 50 AV1 0.27 17 N 45 56 AV2 0.00 26 N 32' 60- SC 6.26 16 N 27 62 6H 21.37 21- N 49 69 2C 17.73 37 N :

53 83 AV2 0.00 19 N -

54 85 AV5 0.00 28 N ,

52 86 AV4 0.00 16 N 54 87 AV5 0.00 45 Y 54 88 AV5 0.00 28 N 43- 90 AV4 0.00 23 N 53 90 AV3 0.00 38 Y(*)

40 93 AV2 0.00 13 N 50 94' AV5 0.00 20 N 50 95 AV5 0.00- 39 Y(*)

47 99 AV2 0.00 11 N

,s 32 102 6H 30.40 34 N 102- AV5 0.00 12 N l-l

() 41 42- 102 AV5 0.00 10 N 43 102 -AV3' O.00 28 N 40 106 AV3 0,00 39 Y(*)

The above information is based on the largest indication observed for the respective tube during the second maintenance / refueling outage at VEGP-1.

(*) Tube plugged as a precautionary measure during the second maintenance / refueling outage.

(1) See Note 1, page 3-7..

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TABLE IV St'eam Generator No. 3

' Reference Distance from~ Wall Thickness Plugged Row ' Col u_m_D - Point (1) Reference (in.) Penetration (%) (Y/N) 17' 10 7H 1.30 37 N 38 16 AV6 0.00 24 N 39 -17 AV3 0.00 16- N

= 40 17 AV3 0.00 33 N 50 28 AV4 0.00 24 N-40 30 AV5 0.00 20 N 39 35 AV3 0.00 13 N 45 40 AV5 0.00 20 N 30 42 AV6 16.94 38 N 42 43 AV5 0.00 19 N 35 44 AV6 17.57 35 N 42 50 AV4 0.00 22 N 34 51 TSH 5.23 11 N 44~ 51 7H 4.97 31 N~

48 54 AV6 0.00 18 N 45 58- AV3 0.00 32 N 45 59 AV4 0.00 21 N 21 62 2C 8.29 31 N 45- 62 AV4 0.00 15 N

.45 67 2C 8.49 28 N 49 .72 AV3 0.00 25 N 9 55 55 53' 82 83 84 AV3 AV4 AV4 0.00 0.00 0.00 17 26 17 N

N N

50 85 6H 25.15 18 N 4

54 86 AV6 0.00 12 N 53 88 AV4 0.00 23 N 54- 88 AV1 0.00 11 N 45 92 AV5 0.00 12 N 49: 94 AV4 0.00 17 N 50 94 AV5 0.00 11 N 47 97 AV4 0.00 27 N 48 97 AV3 0.00 23 N 47 98 AV3 0.00 17 N 47 99 AV4 0.00 16 N 41 102 AV3 0.00 20 N 44 102 AV4 0.00 12 N 39- 104 AV5 0.00 11 N 41- 105 AV2 0.00 19 N 39 107 AV2 0.00 15 N 36 110 AV5 0.00 13 N The above information is based on the largest indication observed for the respective tube during the second maintenance / refueling outage at VEGP-1.

(1) See Note 1, page 3-7.

3-9

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TABLE V

['~ j -Steam Generator No. 4 ,

~J . '

Reference Distance from . Wall Thickness Plugged .

Row Column Eoint (1) Reference (in.) _Eenetration (%) (Y/N) '!

' 27- 9- .AV5 0.00 14 N 50' 40 AV4 0.00 21 N 4

- 45. 60 40- 22.01 14 N [

57: ~75 3H .14.06 26 N r I

40 87 AV5 0.00 11 N 44 96 .AV3 0.00 21 N 42 102 AV3- 0.00 17 N 43 102 AV3- 0.00 22. N 44 102 AV3 0.00 35 N 38 107 AV5 0.00 18 N i 37 108 AV3 0.00 19 N . !,

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27- .113 6C 36.35 24 N -

The above information-is based on the largest indication observed.for the f' respective tube during the second maintenance / refueling outage at VEGP-1, (1) See Note 1, page 3-7.

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Technical Specification 4.7.8._- Snubber Inspections ;

7 Mf As required by Technical Specification 4.7.8, each snubber was visually examined i during the VEGP-1:second maintenance / refueling outage (IR2). These examinations revealed no visible indications of' damage or rimpaired operability of the :

. snubbers.

Technical Specification 4.7.8 also requires functional testing of snubbers.

Snubbers were categorized into four types as follows:

Type-I -

Pacific Scientific mechanical snubbers (All sizes) c Type II - Anchor Darling mechanical snubbers (AD-40-thru AD 500)

Type 111 ! Anchor Darling mechanical snubbers (AD-1600 thru AD 12500)

Type IV - Paul-Munroe 1000 kip steam generator hydr:ulic snubbers Each of the snubber types were functionally tested in accordance with one of three different test plans detailed in Technical Specification 4.7.8e as '

follows:

Type 1 - The test plan selected required an initial representative random sample of thirty-seven snubbers to be functionally teited. These ;

thirty seven snubbers were functionally tested and met the functional test acceptance criteria. In addition,-thirty-one m snubbers ~ were functionally tested beccuse they failbd to meet the functional test acceptance criteria during the first maintenance /

L' (V-) _

refueling outage (IRl). Six of these snubbers failed their ,

' functional test. Appropriate engineering evaluations and subsequent corrective : ans were performed.

Tvoe 11 - The test plan selected required an initial representative L. random sample of thirty-seven snubbers plus two snubbers

" which failed to meet the functional test _ acceptance criteria 1 during the first maintenance / refueling outage (lRI). Subsequent functional testing of the snubbers resulted in three which failed their functional test. Two of these failed snubbers were in the initial sample and the remaining one was in an expanded scope. In accordance with Technical Specification 4.7.8e.2, an additional fifty-five snubbers were functionally tested to comply-with Figure 4.7-1 of the Technical Specificht.ons. To summarize, a total of-ninety-four Type 11 snubbers were functionally tested out of which three failed the functional test acceptance criteria'. Appropriate P engineering evaluations and subsequent corrective actions were performed.

Tvoe III - The test plan selected required an initial representative random sample of ten percent (10%) of the population to be functionally l tested. Consequently, twelve snubbers were functionally tested resulting in one snubber which failed the functional test acceptance criteria. In accordance with Technical Specification

?D V 4.7.8e.E, an additional twelve snubbers were functionally tested l

3-19 l

in accordance with the Technical Specification requirements and all

> passed. A total of twenty four Type !!! snubbers were tested.

! Appropriate engineering evaluations and subsequent corrective actions were performed. ,

Tyne IV The test plan sJ.,cted required an initial representative random sample of ten percent (10%) of the population to be functionally tested. Consequently, two snubbers were functionally tested and both passed. Therefore, no additional testing of Type IV snubbers was performed.

In accordance with VEGP 1 Technical Specification 4.7.89, engineering evaluations were performed by SCS for those snubbers which failed functional testing. The engineering evaluations were performed in order to determine the cause(s) of the failures and to determine if the piping systems to which the failed snubbers were attached were adversely affected. In addition to engineering evaluations performed for failed snubbers, one snubber (1-1201 ll7 H601) was found to be outside of its design tolerance and was also evaluated by SCS. Affected piping systems hav:,,9 failed snubbers or having a snubber outside of its design tolerance were returned to their design configuration. Where appropriate, failed snubbers were removed if included in the on going VEGP 1 Snubber Reduction Program. The following is a listing of correspandence associated with the engineering evaluations which are available at the plant site for review upon request:

c.s GPC Transmittal Applicable SCS l } Affected Letter /Date Evaluation Applicable Request for V Snubber +0 Plant site

. letter /Date Enaineerina Review (RER).

1 1201-117-H601 MSV-00195, SG 8983*, 03/20/90 90 0110 04/06/90 SG-9006, 03/30/90 1-1205-006-H016 MSV-00183, SG 8922, 03/09/90 90 0096 03/21/90 1 1208 002-H035 MSV-00183, SG-8916, 03/10/90 90 0075 03/21/90 1-1208 002-H043 MSV-00183, SG 8916, 03/10/90 90 0075 03/21/90 1 1208 002-H044 MSV-00183, SG 8916, 03/10/90 90-0075 03/21/90 1 1208 150 H010 MSV 00183, S6-8932, 03/13/90 90-0094 03/21/90 SG-9019, 04/04/90 MSV 00197, 04/10/90 73 L ' ,

3 20 L

'z: .

4 GPC Transmittal Applicable SCS iN') Affected Letter /Date Evaluation Applicable Request for Snubber to Plant site letter /Date Enaineerino Review (RERI 1 1208 215 H002- MSV 00183, SG 8916, 03/10/90 90 0075 03/21/90

<1 1301 012 H030 MSV-00183, SG 8886, 03/01/90 90 0074. .

03/21/90 1301-012 H032A_ MSV 00183,. SG 8886, 03/01/90 .90 0074 03/21/90 1 1301 012-H032B- < MSV-00183. SG 8886, 03/01/90 90 0074 03/21/90 1-1301-105 H005 MSV-00195, SG 8947, 03/20/90. 90-0095 04/06/90 1-1305 ll7 H001A MSV-00183, SG 8929, 03/12/90 90 0099 03/21/90

1 1322-052 H024 MSV 00163, SG 8923, 03/10/90 90 0088 03/21/90 Interim response-y u 3-21 1

i i

T NRC Information Notice 87-44 / NRC Bulletin 88 09 - Thimble Tube Thinnino in )

,j Wstinchouse Reactors As part of a continuing program in response to NRC concerns with thinning in Bottom Mounted Instrumentation (BMI) flux thimbles in Westinghouse reactors, eddy current examination of each of the fifty eight flux thimbles was performed '.

during the second maintenance / refueling outage at VEGP-1. The purpose of the examinations was to detect and size indications of possible wear on the outer diameter of the flux thimbles. The examination of the flux thimbles was performed by the Westinghouse Nuclear Services Division in accordance with their procedure MP 2.3.1. GAE-1, Revision 1, " Thimble Tube Eddy Current inspection at ;

Vogtle Unit 1."

Examination results for the second examination of the flux thimbles revealed wear indications on twenty-nine thimbles due to external wear in the proximity of the support locations. The indicated wall loss ranged from a minimum of eleven percent (11%) for one thimble to a maximum of forty eight percent (48%) ,

for one thimble. In compartMon, twenty flux thimbles had wear indications i af ter the first cycle of operation, with an indicated wall loss ranging from a minimum of sixteen percent (16%) for one tube to a maximum of forty percent- '

(40%) for one tube. Out of the twenty flux thimbles observed to have wear following the first cycle of operation, twelve were repositioned to obtain new wear surfaces. Nine of the twelve flux thimbles which were repositioned following the first cycle of operation developed new wear indications during the second cycle. Eleven flux thimbles that had "no indications" after the first

,, cycle of operation showed indications after the second cycle. The phrase "no

( ) indication" means that the wall loss was ten percent (10%) or less. Westing-V' house has indicated that the accuracy of their eddy current testing is i10%. ,

Two thimbles that had indications after the first cycle of operation were .

reported to have no detectable defects after two cycles of operation. This is not an uncommon result when eddy current inspection is used to measure wear. Of the two thimbles where the wear disappeared, one had wear of sixteen percent (16%) and the other had wear of eighteen percent (18%) following the first cycle of operation. Considering the normal eddy current accuracy of 110%, these wear scars could have been as small as six percent (6%) and eight percent (8%) which is below the system detectability. This is one possible reason that the scars were not indicated during the second inspection.

The following is a comparison, by percentage wall loss, of flux thimble ,

locations following the first and second cycles of operation (1988 and 1990,

i. respectively):

Thimble Core Number location 1988 (%) 1990 (%)

1* 08 40 37 (18)

2 J7 NDD NDD 3 G9 NDD NDD 4 H6 NDD NDD l

f :[ s 1

3 22 l

f >

I Thimble Core i

i Number LQcation 1988 (%) 1990 (%)

\

s_- 5 F8 NDD NDD 6 J10 NDD NDD l 7 F7 21 29 '

, 8 K6 NDD NDD 9 H11 22 34 !

10 L8 NDD 14 ,

11 G5 20 24 !

12* E9 27 25 (24) ,

13 L10 NDD NDD 14 H4 22 36 15 D8 NDD 22 16 M7 NDD 18 L 17* G12 25 26 (19) 18 Lll NDD NDD 19 L5 NDD NDD 20* E5 26 21 21 Ell NDD 25 22 K12 NDD 21 23 DIO NDD NDD 24 H13 NDD NDD i

25* N8 31 33 (12) 26 H3 NDD NDD 27 08 NDD NDD t 28* C7 26 17 (16)(15) g-ss 29 N6 NDD NDD

() _'

30 31*

F3 D12 NDD 29 NDD 29 32 1.13 NDD 28 33 C5 16 28 34 H2 18 NDD 35* BB 31 28(21) 36* J14 27 34 (20) 37 P9 NDD NDD 38* K2 32 32 (21) 39 B6 NDD NDD 40 F14 NDD 41-(37) 41 N4 NDD NDD 42 D3 16 NDD 43 HIS NDD 25 (19) 44 R8 NDD NDD 45 N13 NDD NDD '

46 J1 NDD 24 (17) 47 A9 21 21 48 P4 NDD NDD 49 D14 NDD NDD 50 R6 NDD NDD l- 51 F1 NDD NDD l 52 L15 NDD NDD 53 Rll NDD 11 54 All NDD NDD 48 l

('} 55 N14 NDD s

l 3-23

b Thimble Core Number- !ocation 1988'(%) 1990 (%)

j i

56* N2 28 26 (23) 57 B3 NDD NDD 58* B13 28 22 in the table above, an asterisk (*) denotes those flux thimbles that were repositioned during the first maintenance / refueling outage. The term *NDD" is ;

used in the table to denote those tubes where no detectable defect was noted. >

Numbers in parentheses () represent the value of a new wear scar on the flux !

thimble that occurred during the second cycle of operation. The values for the ,

second cycle of operation (in the case of the repositioned thimbles) can be confirmed to be the original wear scar since its location is approximately two inches below the new wear scar. Two inches is the approximate distance that the thimbles were repositioned. For those thimbles that were repositioned with no second indication noted in parentheses, it can be taken that no new wear scar occurred. This is the case for three thimbles.

Three flux thimbles were predicted to exceed the sixty five percent (65%)

wall loss criteria during the next cycle of operation. (NOTE: Originally, a maximum wall loss criteria of sixty percent (60%) had been established for the first cycle of operation based on a finite element analysis of a worn flux thimble model by Westinghouse. Re analysis by Westinghouse has shown that a sixty five percent (65%) wall loss is acceptable at VEGP and was used for the purpose of analysis.) As a result, flux thimble nos. 40, 55, and 56 at core

, locations F14, N14, and N2, respectively, were repositioned before returning VEGP 1 to power operation. Repositioning of those flux thimbles effectively i

v) results in a zero wall loss thimble. No corrective action was required for the remaining flux thimbles.

Details on the BMI flux thimble eddy current examinations performed by Westinghouse, procedures utilized, and equipment, material, and personnel certifications may be found in the Westinghouse Flux Thimble Eddy Current Examination Field Service Report for VEGP 1-lR2. The Westinghouse report is available at the plant site for review upon request.

NRC Bulletin 8811 - Pressurizer Surce Line Thermal StratificatiP.D Four welds, 11201-053-1, 4, 5, and 6, in the pressurizer surge line were examined as a result of generic concerns cited in NRC Bulletin 8811.

The ultrasonic examination of weld 11201 053-1 revealed recordable indications which were determined to be innerbead lack of fusion. The indications were reported to GPC by SCS on INF 190-VI-001. The indications were evaluated per ASME Section XI, Table IWB-3514 2 and were determined to be an acceptable size.

No corrective action was taken. Weld 11201 053 1 will be re-examined during the next maintenance / refueling outage (IR3). The ultrasonic examination of the remaining three welds did not reveal any non-geometric indications.

,o a

3-24

i 1

l ) Five linear indications were observed during the liquid penetrant examination of '

weld 11201 053 6. The indications were reported to GPC by SCS on INF 190 VI-002. They were evaluated per ASME Section XI Table IWB 3514 2 and were determined to be of an acceptable size. No corrective action was taken. The liquid penetrant examination of the remaining three welds did not reveal any indications of a recordable size.

The specific welds examined as a result of NRC Bulletin 88-11 are itemized with the Class 1 piping welds.

9PC Action Item No. 1739 - Feedwater Line Crackina Since some Westinghouse plants have a history of steam generator nozzle cracking, GPC has elected to examine selected feedwater piping welds. Selected welds were examined with ultrasonic techniques and no non geometrical indication of a recordable size were detected. However, during the magnetic particle ,

examination of Auxiliary feedwater System weld 11302-109-40, two linear indications were observed. The indications were removed by controlled buffing.

No indications of a recordable size were observed following controlled buffing of the affected weld area. (Refer to INF 190 Vl 006).

GPC Letter N0E - 01650-(February 26. 1987) - Inservice Inspection of Nuclear Service Coolino Water System Sprina Hancers Several Nuclear Service Cooling Water (NSCW) System variable spring - type .

~ (3 supports were examined to determine if settling occurred in the NSCW cooling

(" J- towers which would require adjustments be made to the springs. The position of the tprings were measured and determined to be acceptable.

GPC Letter GN- 1345 (February 9. 1987) - Auamented Examinations on Class 1 Nuclear Service Coolina Water System in the subject letter, GPC committed to perform an augmented ultrasonic examination on one Nuclear Service Cooling Water System piping weld on VEPG-1 during the first inspection period (first 40 months). The ultrasonic examination was performed during the first maintenance / refueling outage (1RI)-at VEGP 1. Visual examinations were performed during the second maintenance /

refueling outage (IR2) on accessible Class 3 portions of the NSCW piping as committed to by the subject GPC letter. The visual examinations were performed during normal system operation and no leaks were found except for mechanical connections such as bolted flanges. Appropriate corrective action was initiated to correct these leaks.

VEGP-1 Inservice Inspection Procram (ISI-P-006) Paracraoh 1.10.3 - Volumetris Examination of Additional Class 2 Pipina Wt]A Selected Class 2 piping welds were examined using ultrasonic examination techniques. No non-geometrical indications of a recordable size were found. The specific welds examined are itemized with the Class 2 piping welds.

g

(

3-25

L GPC Action item Nos. 87-0131 and 87 0931 - Stannant Borated Water Systems Crackina ,

s ;

j As a result of gtneric concerns of pipe cracking in stagnant borated water systems in pressurized water reactors, twenty-four welds in Class 1 and Class 2 piping systems were examined in response to GPC Action items Nos. 87-0131 and 87-0931. Nondes'.ructive examination methods utilized included ultrasonic and/or liquid penetran'. examination techniques.

In Class I systems (Reactor Coolant System and Safety injection System), sixteen welds were examined. There were not any non geometric indications observed during the examination of the Class I welds subject to ultrasonic examination.

However, during the liquid penetrant examination of the Class I welds, four welds in the Safety injection System were observed to have reportable indications. The affected welds included welds 11204-023-16, 11204 043-1, ,

11204 043 4 and 11204 124 15. The liquid penetrant indications were reported to GPC by SC5 on INFs 190 VI-007, 190 VI-005, 190 V1 004, and 190 Vl 009, respectively, for the aforementioned listing of affected welds. The indications were evaluated in accordance with the appropriate ASME Code requirements and were determined to be of an acceptable size. No corrective action was taken.

Liquid penetrant examination of the remaining twelve Class I welds did not reveal any reportable indications.

In Class 2 systems (Safety injection System and Residual Heat Removal System),

eight welds were examined. There were not any non geometric indications observed during the ultrasonic examination of the subject Class 2 welds. During the liquid penetrant examination of the Class 2 welds, one weld in the Safety Injection System, weld 11204 201-7, was observed to have a reportable lq e indication. The indication was reported to GPC by SCS on INF 190-VI-008. The V indication was evaluated in accordance with ASME Section XI, Table IWB 3514-2 and was determined to be of an acceptable size. No corrective action was taken.

Liquid penetrant examination of the remaining seven Class 2 welds did not reveal any reportable indications.

The specific welds examined as a result of GPC Action item Nos. 87-0131 and 87-0931 are itemized with the Class 1 and Class 2 piping welds, GPC Action item No.18270 - Examination Technicues and Personal Oualifications

,fpr Cold tea Accumulator Pipinc (10-inch. Schedule 140. ASTM SA-376. Type 316)

As a result of GPC Action item No. 18270, selected ultrasonic examinations were performed using nondestructive examination procedures and ey.mination personnel l qualified in the detection and sizing of intergranular str'ss corrosion cracking l (lGSCC).

l Specifically, three welds in the Safety injection System, weld numbers 11204 124 15, 16, and 18, were examined using ultrasonic and liquid penetrant examination methods. The ultrasonic examination of the subject welds did not l reveal any non geometric indications. A linear indication was observed during the liquid penetrant examination of weld 11204-124-15. GPC was notified by SCS I of the recordable indication on INF 190 VI-009. The indication was evaluated per ASME Section XI, Table IWB 3514-2 and was determined to be of an acceptable l size. No corrective action was taken. The liquid penetrant examination of the A remaining two welds did not reveal any recordable indications.

3-26

The specific welds examined as a result of GPC Action Item No. 18270

j are itemized with the Class 1 piping welds, wJ Balance of Plant Erosion / Corrosion Inspections Ultrasonic thickness examinations were performed on twenty-one points in the Main Steam, Extraction Steam, Feedwater Heater Drain, and Condensate and :

Feedwater systems. These examinations were performed using a combination of automated P-scan and manual ultrasonic examination techniques per GPC procedure 83302 C, Revision 0, " Component Erosion / Corrosion Inspection." Two points in the Main Steam System, Cold Reheat lines to Moisture Separator Reheaters "A" and "D", were visually examined from inside the piping in lieu of ultrasonic examination due to the piping being permanently insulated. No areas of abnormal wall loss were identified as a result of the ultrasonic and visual' examinations.

h

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v 3 27

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J V .-

Augmented Component or Exam Cal ASME Sect. XI Examination Weld No./ Exam Procedure Cal. Sheet Exam Item No./ Cat. Requirement Description Method No./Rev. Blocks No.(s) Sheet No(s). Results Remarks See Note See Note See Note See Note See Note See Note See Note bee Note See Note See Note A B C D E F G H I J NOTFS:

A. The ASME Section XI Item No. and Category of the examination area are listed in this column.

B. The implementing document, e.g., Tech Specs, NRC Bulletin, etc., requiring performance of augmented examinations is referenced here.

C. Each examination area is listed in this column. The component or weld number typically is similar to the drawing number, e.g., weld number II201-005-8 is found on drawing number 151-1I201-005.

D. The NDE method used during the examination is listed in this column.

E. This column lists the applicable NDE procedures and revisions used for the examination.

F. This column lists the calibration block that was used.

G. This column references the calibration sheet (s) which records calibration, examiner, and any pertinent remarks.

II . This column references the examination data sheet (s) which records exam data, examiners, and any pertinent remarks.

I. The results of the examinations are indicated in this column. The absence of indications is indicated in the column as "NI" or" SAT". The presence of nonrelevant indications or indications which are less than the recording level is indicated in the column as "NRI". The presence of indications deemed recordable are indicated in the column as "RI" or "UNSAT" and are explained in the remarks column of the summary table.

J. The remarks column is used to describe any pertinent features of the examination such as limitations, INFs, etc. Refer to INF section in this report for their disposition.

FIGURE I. EXPLANATION OF

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ASME' Sect. Support. .Part Part Exam Data XI Cat. ISI Class Number Description Examined Method Sheet No. Results Remarks See Note See Note See Note See Note See Note' See Note See Note See Note See Note-A B C D E F G H I NOTES:

A. The ASME Section XI category designation for the equipment support is listed in this column. In addition, ASME Section XI Class 3 examinations required by Table IWD-2500-I for integral attachments are also indicated by examination category.

B. The ASME Section XI Class No., e.g., I, 2, or 3, for the ' system on which the equipment support being examined is listed in this column.

C. The equipment support number is listed in this column.

D. This column lists the purpose of the equipment support being examined.

E. This column lists the specific type of the equipment support being examined.

F. This column lists the applicable NDE method used during the examination.

G. This column references the examination data sheet (s) which serve to document the examination and lists the examiner, any pertinent remarks, etc.

H. The results of the examinations are indicated in this column..

I. The remarks column is used to describe any pertinent. features of the examination such as limitations, reportable results, INFs, etc. Refer to ~INF section in this report for their disposition.

FIGURE 2. EXPLANATION OF EQUIPMENT SUPPORT

SUMMARY

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A. The ASME Section XI category designation for the piping-support is listed in this column. In addition, ASME Section XI Class 3 examinations required by Table IWD-2500-1 for integral attachments are also indicated by examination -

catego ry.

B. The ASME Section class no., e.g.,1, 2, 3, for the system on which the piping support being examined is listed in this column.

C. This column indicates the nominal pipe size in inches for the piping on which the piping support -is being examined._

D. The piping support number is listed in this column.

E. This column lists the name of the manufacturer of any snubbers examined and the size of snubber examined, e.g.,

PSA 1/4. Manufacturer designations are abbreviated and can be found in List of Abbreviations.

F. This column lists the type of piping support which was examined, e.g., . rigid strut, variable spring hanger, etc.

G. This column lists the applicabie '.iDE method used during the examination.

H. This column references the data sheet (s) which serve to document the examination and list the examiner, any pertinent remarks, etc.

I. The results of the examinations are indicated in this column.

J. The remarks column is used to describe any. pertinent features of the examinatior such as limitations, reportable results, INFs, etc. Refer to INF section in this report for their disposition.

FIGURE 3. EXPLANATION OF PIPING SUPPORT

SUMMARY

TABLE FORMAT 000913/eu 10-1

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VEGP-1 SECOND REFUELING OUTAGE 2 j PIPING SUPPORT EXAMINATIONS i

ASME SECT. ISI NPS SUPPORT SNUBBER SUPPORT EXAM EXAM l XI CAT. CLASS (IN.) NUMBER MFGR/ SIZE DESCRIPTION METHOD SNEET NO. RESULTS REMARKS l

F-C 1 6 11201-030 :1035 PSA-3 MECH SNUBBER VT-3,4 590V1V041 SAT F-C 1 6 11201-030-H036 klGID STRUT VT-3 590v1v029 SAT

F-C 1 6. 11201-030-H037 PSA-3 MECH SNUBBER VT-3,4 S90v1v042 SAT F-C 1 6 11201-030-H039 PSA-3 MECH SNUB 9ER VT-3,4 S90V1v043 SAT.

F-8 1 6 11201-030-H040 LIN RESTRAINT VT-3 S90V1v030 SAT F-C 1 6 11201-030-H041 CON SPRING VT-3,4 590v1v044 UNSAT INF 190-V1-011 F-C 1 4 11201-030-H042 PSA-1L MECH SNUBBER VT-3,4 590v1v045 SAT F-C 1 4 11201-030-H043 PSA-3 MECH SNUB 8ER VT-3,4 590v1v046 SAT F-C 1 4 11201-030-H044 PSA-3 MECH SNUBBER VT-3,4 S90v1V047 SAT F-8 1 6 11201-059-H001 LIN RESTRAINT VT-3 590v1v015 SAT F-8 1 3 11201-059-H002 LIN RESTRAINT VT-3 S90v1v016 SAT F-B 1 3 11201-059-H003 L!N RESTRAINT VT-3 $90v1v017 UNSAT 'INF 190-v1 011' F-8 1 6 11201-059-H004 Liu RESTRAINT VT-3 S90v1V013 SAT F-B 1 6 11201-059-H005 LIN RESTRAINT VT-3 S90V1v014 SAT F-C 2 8 11202-001-H010 AD-151 MECH SNUB 8ER VT-3,4 S90v1v048 SAT F-C 2 8 11202-001-H016 AD-151 MECH SNUBBER VT-3,4 S90v1v049 SAT F- 2 8 11202-001-H018 AD-501 MECH SNUB 8ER VT-3,4 S90V1v050 SAT F-B/t B 3 14 11202-002-H014 LIN RACK 3-D VT 590V1V131 SAT.

10-2

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- VEGP-1 SECOND REFUELING OUTAGE P! PING SUPPORT EXAMINATIONS ASME SECT. ISI NPS SUPPORT . SNUBBER SUPPORT ENAM EXAM XI CAT. CLASS (IN.) NUMBER MFGR/ SIZE DESCRIPTION METHOD SWEET ND. RESULTS REMARKS F-B/D-B 3 16 11202-003-H017 LIN RESTRAINT VT-3 590v1V130 SAT F-B/D-B 3 24 11202-004-H021 Liu RACK 3-D VT-3 . S90Viv073 SAT F-B/D-B 3 24 11202-004-H025 LIN RACK 2-D VT-3 S90v1V074 SAT F-B/D-B 3 16 11202-004-H030 LIN RACK 2-D VT-3 S90v1V129 SAT F-B/D-B 3 24 11202-004-H038 LIN RACK 2-D VT-3 590v1V075 SAT F-B/D-B 3 24 11202-004-H039 LIN RESTRAINT VT-3 S90V1V076 SAT F-C/D-B 3 24 11202-004-H044 VAR SPRING VT-3,4 S90V1V051 SAT F-C/D-B 3 24 11202-004-H045A PSA-10' MECH SNUBBER VT-3,4 S90V1V219 SAT F-C/D-B 3 24 11202-004-H0458 PSA-10 MECH SNUBBER VT-3,4 S90V1V219 SAT F-C/D-B 3 24 11202-004-H048 YAR SPRING VT-3,4 S90V1V052 SAT F-C/D-B 3 24 11202-004-H050A PSA-3 MECH SNUBBER VT-3,4 $90v1v220 SAT F-C/D-B 3 24 11202-004-H0508 PSA-3 MECH SNUBBER VT-3,4 S90v1V220 SAT F-B/D-B 3 24 11202-004-H052 LIN RESTRAINT VT-3 S90V1V181 SAT F-C/D-B 3 24 11202-004-H053 AD-1603 MECH SNUBBER VT-3,4 590v1V053 SAT

~

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ASME SECT. IS1 NPS SUPPORT SNUBBER SUPPORT EXAM EXAM XI CAT. CLASS (IN.) NUMBER MFGR/ SIZE DESCRIPTION METHOD SHEET No. RESULTS REMRRES-F-C/D-B 3 24 11202-004-H069 VAR SPRING VT-3,4- S90v1vo63 SAT F-C/D-8 3 24 11202-004-H071 AD-5501 MECH SNUBBER VT-3,4 590v1v056 SAT F-C/D-B 3 24 11202-004-H073A AD-1601- MECH SNUBBER VT-3,4 590v1V223 SAT F-C/D-8 3 24 11202-004-H0738 AD-1601 MECH SNUBBER VT-3,4 590v1V223 SAT F-C/D-B 3 24 11202-004-H07S AD-1601 MECH $NUBBER VT-3,4 590v1v031 SAT F-C/D-B 3 12 11202-007-H002A PSA-3 MECH ShUB9ER VT-3,4 S90v1V218 SAT F-C/D-B 3 12 11202-007 H0028 PSA-3 MECH SNUBBER - VT-3,4 S90v1V218 SAT F-B/D-B 3 12 i'202-007-H007 LIN RESTRAINT VT-3 S90v1V180 SAT F-C 3 12 11202-007-H009 VAR SPRING VT-3,4 590v1v094 SAT F-C 3 12 11202-008-H008 VAR SPRING VT-3,4 590V1v032 SAT F-C 3 12 11202-009-HOO8 VAR SPRING VT-3,4 S90v1v033 SAT F-C 3 12 11202-010-H008 VAR SPRING VT-3,4 $90v1v034 SAT F-C 3 12 11202-011-H008 VAR SPRING VT-3,4 $90v1vo72 SAT F-C 3 12 11202-013-M008 VAR SPRING vi-3,4 $9thrivo64 SAT F-C 3 12 11202-014-H008 VAR SPRING VT-3,4 590V1vo65 SAT F-8/D-B 3 6 11202-029-H002 LIN RESTRAINT VT-3 590v1v077 SAT F-B/D-B 3 6 11202-029-H005 LIN RESTRAINT VT-3 590v1V078 SAT F-B/D-B 3 6 11202-029-H014 LIN RACK 3-D ~VT-3 $90v1vo89 SAT 10-4

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VEGP-1 SECOND REFUELING OUTAGE PIPING SUPPORT EXAMINATIONS ASME SECT. ISI NPS SUPPORT SNUBBER. SUPPORT' ' EXAM EXAM XI CAT. StASS (1W.) NUMBER- MFGR/S!ZE DESCR1Pfl0N METHOD SMEET NO. RESULTS REMARKS F-A/D-B 3 6 11202-029-H021 ANCHOR ~ VT-3 S90V1vo90 SAT F-A/D-B 3 6 11202-029-H025 ANCHOR VT-3 $90v1V091 SAT

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F-C 3 24 11202-088-H036 VAR SPRING VT-3,4 590V1VOSS SAT-F-C 3 24 11202-088-H038 VAR SPRING VT-3,4 S90v1V086 SAT F-C 3 24 11202-088-H050 VAR SPRING WT-3,4 590v1vo66 SAT F-C 3 24 11202-088-H054 VAR SPRING VT-3,4 S90v1V067 SAT F-C 3 24 11202-088-H057 VAR SPRING VT-3,4 590v1V071 SAT F-C 3 24 11202-088-H059 VAR SPRING VT-3,4 590v1V068 SAT.

F-C 3 24 11202-088-HM1 VAR SPRING VT-3,4 S90v1V069 SAT F-B/D-B 3 8 11202-104-H022 LIN RACK 3-D VT-3 S90V1v128 SAT F-B/D-B 3 8 11202-104-H026 ilN RACK 3-D VT-3 S90V1V133 SAT F-B/D-B 3 8 11202-104-H029 LIN RACK 2-C VT-3 S90v1V148 SAT F-B/D-B 3 8 11202-104-HF.e3 LIN RACK 3-D VT-3 $90v1V199 SAT F-B/D-B 3 8 11202-134-H023 LIN RACK 3-D VT-3 590v1v198 SAT F-B/D-B 3 8 11202-134-H027 LIN RACK 3-D VT-3 S90v1V146 SAT F-B/D-B 3 8 11202-134-H031 LIN RACK 3-D - VT-3 S90v1V175 SAT F-B/D-B 3 8 11202-134-H035 LIN RACK 3-D Vf-3 S90V1V147 SAT F-B/D-B 3 18 11202-174-H001 LIN RESTRAINT VT S90v1v195 SAT 10-5 N

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VEGP-1 SECOND REFUEllNG OUTAGE PIPING SUPPORT EXAMINATIONS ASME SECT. ISI NPS SUPPORT SNUBBER SUPPORT EXAM EXAM XI CAT. MFGR/ SIZE DESCRIPTION METHOD SNEET NO. RESULTS REMAMS -

CLASS DINJ NUMBER F-B 2 14 11204-038-P601 Llu RESTRAINT %7-3 $90V1V156 SAT F-B 2 3 11204-057-H001 LIN RESTRAINT VT-3 590v1vi60 SAT F-8 2 4 11204-C57-H012 LIN RESTRAINT VT-3 $90V1V161 SAT

-4 F-8 2 4 11204-057-H020 LIN RESTRAINT VT-3 $90V1V210 SAT i

F-8 2 4 11204-057-H024 LIN RACK 2-0 VT-3 590V1V206 SAT F-B 2 4 11204-057-H030 LIN RESTRAINT VT-3 $90v1V139 SAT F-B 2 4 11204-057-H032 LIN RESTRAINT VT-3 S?Uv1v200 SAT F-B 2 4 11204-057-H034 LIN RESTRAINT VT-3 .590v1V208 SAT F-C 2 4 11204-057-H036 RIGID STRUT VT-3 $90v1v207 . SAT F-B 2 4 11204 063-H001 LIN RACK 2-0 VT-3 S90v1V186 SAT F-C 2 4 11204-063-H011 VAR SPRING VT-3,4 590V1v187 SAT F-B 1 3 11204-076-H025 LIN RESTRAINT VT-3 590v1V080 SAT F-B 1 3 11204-076-H026 LIN RESTRAINT VT-3 $90v1v081 SAT F-B 1 3 11204-076-H028 LIN RESTRA!NT VT-3 $90V1v082 SAT F-B 2 8 11204-177-H011 LIN RACK 2-0 VT-3 S90v1V162 SAT F-C 2 4 11204-197-H019 RIGID STRUT VT-3 590v1V188 SAT ,

i F-C 2 12 11206-001-H012 VAR SPRING VT-3,4 S90v1V163 SAT F-8 2 12 11206-001-H018 LIN RESTRAINT VT-3 590V1V154 SAT 10-10 .

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ISI Class

Snubber Mfar./ Size ~

Scope--

Examined :Results.

l s See Note'A: See Note B 'See Note C 'See Note D, .See Note E-- !

-[

Ji V l t TNOTES:'

b ,

- A. The unique tag number for:the snubber being. examined is listed in this column.' ,

e B. - The ASME Section XI. class no., e.g.. 1,.-.2,.3, for the system on which- t l the snubber being' examined.is: listed in this column.- "- 4

C. This column' lists the name of the manufacturer. of any snubbers-functionally jI tested and the size of snubber examined, e.g., PSA 1/4. Manufacturer!

,J o 9

n

.de'signations z are abbreviated andican be found in List of Abbreviations. .i m:

a D .' ' This column lists the scope of examination in which the snubber is . 'd f functionally tested,'i.e., original scope or: expanded scope. Snubbers .

u; included'in the expanded scope of examination:are. generally as a result .' 3 m -

of other snubber-functional: test failures. at

<3

!- ,-E. The results of tthe functional test of the snubber tested is listed in "-

e' 7g . .this column. '

<}lQ ,

f I

~

FIGURE.4. ' EXPLANATION OF~ SNUBBER FUNCTIONAL TEST RESULTS

SUMMARY

TABLE FORMAT..

n

-1 1 E'

't:

i i

i

Ag' M. ,

001022/eu F 11-1 L

L !

a.

q:

F ,,

~

}

n, 3

~/ \' VEGP 1 SECOND REFUELING OUTAGE

-s ,) ' SNUBBER FUNCil0NAL. TESTS TYPE I SNUBBERS 1AG ISI SNUBBER SCOPE ;

NUMBER M MrGR/ SIZE. EXAMINED RESULTS 11201 021 H001 1 PSA 1 ORIGINAL PASSED 11201 030 H018 i PSA 3 ORIGINAL PASSED 1

11201 030 H042 1 PSA il ORIGINAL PASSED 11201 031 H005 1 PSA 1/4 ORIGINAL PASSED ,

11201-049 H005 1 PSA 35 ORIGINAL PAS $!D 11201 051 H007- 1 PSA 1/2 ORIGINAL PASSED 11201 119 H002 1 PSA 1 ORIGINAL PASSED 1*

11203 021 H008 3 PSA 3 ORIGINAL PASSED 11204 006 H002 2 PSA 3 ORIGINAL PASSED 11204 012 H003 2 PSA 1/2 ORIGINAL PASSED

.. 11204 023 H007 1 PSA 10 PREV. FAILURE PASSED- r f'N

\ )g . 11204 024 H038- 1 PSA 10 ORIGINAL PASSED 11204 031 H017 2 PSA 1/4 ORIGINAL PASSED PSA 3 ORIGINAL . PASSED !

11204 041 H035 2 11204 047 H003 2 PSA 1/4 ORIGINAL PASSED 11204 124 H018 1 PSA 35 ORIGINAL PASSED 11204 199 4021 2 PSA 1 ORIGINAL PASSED 11205 003 H003 2 PSA 1 ORIGINAL PASSED PASSED ;

11205 003 H039 2 PSA 3 ORIGINAL 11205 004 H002 2 PSA 3 PREV. FAILURE PASSED

, 11205 004 H003 2 PSA 3 PREV. FAILURE PASSED 11205 004 H017 2 PSA 3 PREV. FAILURE PASSED 11205 004 H023 2 PSA 10 PREV. FAILURE PASSED 11205 005 H002A 2 PSA 1/4 PREV. FAILURE PASSED 11205 005 H002B 2 PSA 1/4 PREV. FAILURE PASSED

. f%

!3 12 1

i s

/ '

VEGP 1 SECOND REFUELING OUTAGE

\_ ./. SNUBBER FUNCilDNAL TESTS

< TYPE I SWUBBERS TAG !$1 SNUBBER. SCOPE E!MILR [Ljbi EGR/ SIZE EXAMINED PERULTS -

11205 005 H020A 2 PSA 1/2- PREV. FAILURE PAS $[D 11205-005 H020B 2 PSA 1/2 PREV. FAILURE PASSED 11205 006*H016 2 PSA 1/2 PRfV. FAILURE FAILED- 'r 11205 006 H021A 2 PSA 1/4 PREV. FAILURE P'ASSED 11205 006 H0218 2 PSA 1/4 PREV; FAILURE PASSED-11205 006 H026A 2 PSA 1/2 PREV. FAILURE PASSED 11205 006 H026B 2- PSA 1/2 PREY. FAILURE PASSED =

11205 006 H027A 2 PSA 1/4 PREV. FAILURE PASSED 11205 006 H027B 2 PSA 1/4 PREY. FAILURE PASSED 1120$*007 H039 2 PSA 1 ORIGINAL PASSED-11205 010 H019 2 PSA-3 PREV. FAILURE PASSED 11205 027 H006 2 PSA-10 PREV. FAILURE' PASSED l 11205 027 H008 '2 PSA 10 PREV. FAILURE PASSED ,

~

11206 001 N020A 2 PSA 3 ORIGINAL PASSED 11206 002 H028 2' PSA 3 ORIGINAL i SSED 11206-047 H003 2 PSA 1/2 ORIGINAL PASSED 11208 002 H027 2 PSA 1/4 PREY. FAILURE PASSED j 11208 002 H030 2 PSA 1/4 PREV. FAILURE PASSED Y

F 11208 002 H033 2 PSA 1/4 PREV. FAILURE PAS $tD !

1 11208 002-H035 2 "SA 1l4 PREV. FAILURE FAILED 11208 002 H043 2 PSA 1/4 PREV. FAILURE FAILED l 11208 002 H044 2 PSA 1/4 PREV. FAILURE FAILED 1

11208 005 H004 2 PSA 1/4 ORIGINAL PASSED 11208 068 H002 2 PSA-1/2 ORIGINAL PASSED 11208 139 H017 2 PSA 1/4 PREV. FAILURE PASSED iA) v 12 2 A

s E.~1 [

7_%

\ VEGP 1 SECOND REFUELING OuiAGE

, b_._ j - SNUBBER FUNCil0NAL TESTS U

TYPE 1 $NUBBERS

~

1AG ISI SNUBBER SCOPE.

NUMBER f.LJS,3 M*GR/Sl?E (xAMINED Ri$VLT$

11208 215 H002' 2 PSA 1/2 PREV. FAILURE FAILED 11208 215 H601 2 PSA 1 ORIGINAL PASSED ~

11208 411 H020 2 PSA 1 ORIGINAL' PASSED 11208 490 H003 2 PSA*1/4 ORIGINAL' PASSED-11301 008 H017A - PSA 35 ORIGINAL PASSED 11301 008 H0178 - PSA 35 ORIGINAL PASSED 11301 015 H004- 2 PSA 10 PREV. FAILURE PASSED 11301 191 H002 2 PSA 1/2 ORIGlWAi PASSED 11302 013 H010 3 PSA 3 ORIGINAL PAS $!D 11302 109 H012. 2 PSA 3 ORIGINAL PASSED s

.11305 056 H006A - PSA 10L ORIGINAL PASSED

\ .}

f

(,' 11305+056 H0068 - PSA 10L ORIGINAL PASSED 11305-056 H010A -

PSA 10 PREV. FAILURE PASSED' 11305 057 H003 -

PSA 10 PREV. FAILURE. PASSEP 11305 062 H006 2 PSA 100 ORIGINAL PASSED 11305 155 H002A- 2 PSA 10 ORIGINAL PASSED 11322 052-H024 -

PSA 1/2 PREV. FAILURE FAILED I

11901 221 H024 -

PSA 1/2 OR10lNAL PASSED l

1.

I: I 1'

12 3

r

! 1 V

i

[- VEGP 1 SECOND REFUELING OUIAGE SNU9BER FUNCTIDNAL TESTS A' " 'j '" ' '

. TYPE Il SNVBBERS TAG ISi SNUSSER SCOPE E2!)LB CLA$S MfGR/SI2E EXAMikED RESULTS 11201 022 H002f 1 AD 151 ORIGINAL PASSED ,

)

b 11201 030 H602 1 AD 503 ORIGINAL PASSED

.11201 068 H606 2 AD 73 ORIGINAL PASSED !

11201 117 M601 1 AD 503 ORIGINAL' PASSED

/11201 191 H001 1 AD 151 ORIGINAL PASSED-

,s 11201 192 H011 2 AD 41 ORIG 1NAL PASSED ;

11201+194 H010 1 AD 153 ORIGINAL PASSED i

11202 006 H055A 3 AD 501 ORIGINAL PASSED 11202 006 H055B 3 AD 501 ORIGINAL PASSED 1 11'202 038-H030A 3 AD 73 EXPANDED PASSED 11202 038 H0300 3 AD 73 PREV. FAILURE PASSED _ l

. rmI 11202 216 H005 2 AD-501 ORIGINAL PASSED-iU/

~11202 223 H018 2 AD 503- ORIGINAL' PASSED' [

11202 231 H601 2 AD-151 ORIGINAL PASSED 11203 047 H011' 3 AD 503 ORIG 1NAL PASSED 11203 051 H005 3_ AD 501 . EXPANDED PASSED E 11204 141 H601 2 AD 41 ORIGINAL PASSED

'11205 006 H019 2 AD-151 PREV. FAILURE PASSED 11205-007 H604 2 AD-503 ORIGINAL ' PASSED 11206 002 H031 2 AD 503 ORIGINAL PASSED 11208 002 NC39 2 AD-151 ORIGINAL PASSED 1

11208 011 H045 2 AD 41 ORIGINAL PASSED 11208 012 H014 1 AD 501 EXPANDED PASSED 11208 022 H030 2 AD 73 EXPANDED PASSED 11208 023*H081 2 AD-71 ORIGINAL PASSED f%

i !

(.,/ ,

13 1

'~'

fig _

)

i .

.!- f i

( VEGP 1 SECOND REFUELING OUTAGE

_. ( ,/, SNUBBER FUNCil0NAL TESTS TYPE !! SNUBBERS TAG ISI SNUB 8ER SCOPE- +

NUMBER G.L Lit F GD/ SIZE EXAMINED RESULTS 11208 042 H077 2 AD-71 EXPANDED PASSED-

.s 11206 044 H018 2 AD*43 EXPANDED PASSEE L

112,6-0!6 H064 2 AD 43 ORIGINAL PASSED I

in 11:J8 149 H007 2 AD 153 EXPANDED PASSED 11208 149 H008 2 AD 71 EXPANDED PASSED 11208 150 H010 2 AD 43 OR1GINAL FAlLED 11208 449 H013 1 AD 41 ORIGINAL PAS 3ED !

11212 003 H608 2 AD 41 ORIGINAL PASSED 11217 011 H040

AD 501 EXPANDED- PASSED 112 0 015 H001 -

AD 501 EXPANDED PASSED

. 11217 043 H602 - AD 43 ORIGINAL PASSED 'I

_r \

11217 072 H611 3 AD 71 ORIGINAL PASSED

. 11217 265 H611 3 AD 73 ORIGINAL PASSED'

- 11301-010 H046 3 AD-153 EXPANDED PASSED' 11301 012-H030 3 AD 153 ORIGINAL FAILED i

11301 118 H008 2 AD 153 ORIGINAL PASSED 11301 128 H099 2 AD 151 ORIGINAL PASSED '

11301 136 H003 2 AD 71 EXPANDED PASSED 11301 138 H004 2 AD 71 EXPANDED PASSED

'11301 138 H006 2 AD 153L ORIGINAL PASSED

'11301 157 H016 -

AD 71 EXPANDED PASSED 11301 157+H017 -

AD 73 EXPANDED PAftd 11301 157 H018 -

AD 153 EXPANDED PASSED 11301 157 H019 -

AD 73 EXPANDED Pt.SSED 11301 157 H022 -

AD 153L EXPANDED PASSED

k. 13 2

p' L-7 1" % 4 j ) VIGP 1 SECOND REFUELING OUTAGE

.N / SNUBBER FUNCTIDNAL TESTS TYPE ll SNUBBERS TAG 151 SNUBBER' j SGOPE g3ggR, gQi.t - MfGR/$12E EXAMINED RE SUL T S 11301 157 H023A - AD 41 EXPANDED PASSED 11301 157 H023B -

AD 41 EXPANDED PASSED l

AD 41 PASSED I 11301 157 H025' - EXPANDiD 11301 157 H026A - AD 71 EXPANDED PASSED 11301 157 H0268 - AD 71 EXPANDED PASSED

-i 11301 157 H028

- AD 41 ' ORIGINAL PASSED i

~I 11301 157 H030A - AD 41 EXPANDED PASSED i

11301 157 H0308

AD 41 EXPANDED PASSED' -!

11301 157 H031 - AD 73 FxPANDED PASSED 11301 166 H019 -

AD 73 EXPANDED PASSED i 1

. j-q 11301 166 H020

AD-71 EXPANDED PAS $ED

! ) <

's / 11301 166 H021 - AD 71 EXPANDED' PASSED-11301-166 H024 -

AD 71 EXPANDED PASSED 1

1 11301 166 H025 -

AD 153L- EXPANDED PASSED 11301 166 H027 -

AD-71 EXPANDED PASSED l

.j 11301 166 H029 -

AD 73 EXPANDED PASSED' j 11301 166 H030 -

AD 151 ORIGINAL PASSED 11301 166 H031 -

AD 43 EXPANDED PASSED 11301 166 H032 -

AD 73 EXPANDED PASSED, 11301 166-H034 -

AD 43 EXPANDED PASSED 11301 166 H035 -

AD 43 EXPANDED PASSED 11301 167 H014 - AD-71 EXPANDED PASSED 11301 167 H015 - AD 73 EXPANDED PASSED 11301 167 H017 -

AD*73 EXPANDED PASSED 11301 167 H018 - AD 41 EXPANDED PASSED

- /^\

13 3

i

VEGP 1 SECOND REFUELING OUTAGE

-;\,,,j SNUBBER FUNC110NAL TESTS f

, TYPE 11 SNUBBERS l 1AG ISI SNUBBER SCOPE JMg!LR. ELA.H MFGR/812E EXAMINED REsultS .

11301 167 H023 -

AD 153 EXPANDED PASSED j 11301 167 H030- -

AD 153 EXPANDED PASSED i

11301 167 H034 -

AD 43 . EXPANDED. PASSED -l 11301 167 H035 - AD 71- EXPANDED ' PASSED I f

11301 168 H033A - -

AD 43 EXPANDED PASSED 11301 365 H001: 2 AD 151 ORIGINAL PASSED -[

i 11301 368 H004 2 AD 151 EXPANDED PASSED 11301 371.H005 -

AD 71 ' EXPANDED- PASSED f

11302 007 H008 3 AD 41 ORIGINAL PASSED ,

i 11302 107 H016 2 AD 501 ORIGINAL PASSED 11305 081 H009 -

AD 503 EXPANDED PASSED i

,/]- ;

g] 11305 081 H037 -

, AD 503 ORIGINAL PASSED

11305 117.H001A

AD 153 EXPANDED FAILED 11305 117 H001B -

AD 153 EXPANDED PASSED H 11305 117 H006- -

AD 151 EXPANDED PASSED 11305 117 H011 -

AD 71 EXPANDED PAFSED 11322 067 H001 -

AD 71 EXPANDED PASSED 1

I' 11407 003 H021 -

AD 153- EXPANDED PASSED i

12402 024 H001 -

AD-153 ORIGINAL PASSED i

l l

I i

I. .

b 13 4 L

1

i .k i e

'g - VEGP 1 SECOND REFUELING OUTAGE 4 ' )- SNUBBER FUNCil0NAL TESTS TYPE Ill SNUBeERS ,

TAG ISI SNUBBER SCOPE NUMBER [Lil . MFGP/$12E EXAMINED RESULTS

.11201 064 H025- -

AD 1601 ORIGINAL PASSED

% 11202 006 H058 3 AD 5501 ORIGINAL PASSED

'/

11202 006 H061A 3 AD 1601 EXPANDED. PASSED ;

11202 006 HD61B 3 AD*1601' EXPANDED' PASSED

'11202 196 H018-- 2 AD 1603- ORIGINAL PASSED s 11203 055 H017 3 'AD 1603 ORIGINAL PASSED 11204 006 H601 2 AD 1603 ORIGINAL PASSED 11205 004 H018 2 AD 1601 ORIGINAL PASSED 11205 007*H602 2 AD 1603 EXPANDED PASSED 11206 002 H023 2 AD 1603 EXPANDED ~ PASSED 11206 005.H009 2 AD 1603 ORIGINAL PASSED r%.

{ 11208 009 H002 1 AD-1603 ORMINAL PASSED V

s 11301 105 H003 2 AD-12501 EXPANDED PASSED 11301 105 H004- 2 AD 5501 EXPANDED PASSED 11301 105 H005 2 AD 5501 ORIGINAL FAILED' 11301 105 H006- 2 AD 5501 EXPANDED PASSED

.11301 106 H005 2 AD 5501 EXPANDED -PASSED 11301 107 H005 2 AD-5501 EXPAkDED PASSED

-11302 110 H013 2 AD 1601 DRIGINAL PASSED 11305 057 H002A -

AD 5503 ORIGINAL PASSED '

11305 057 H0028 - AD 5503 ORIGINAL PASSED ,

11305 057 H008A -

AD 5503 EXPANDED PASSED l' 11305 057 H008B -

AD-5503 EXPANDED PASSED o v,

11305 061 H011 -

AD 1601 EXPANDED PASSED l

.iLD) 14 1 f

i /.

vtGP 1 $tCOND Rtfutt!NG OUTAGE

$NutttR fuWC110 hat it " $

TYPE IV $NUSDits 1AG 151 $NU6BER SC0tt g pg utGt/112t LikulkID PflVLil 11201 $6 002 $06 2 PM 25701 ORIG 1 hat FAL$t0 11201 n6 002 $08 2 PM 25701 ORICthAL PAS $t0 15 1

i PRESSURE TESTL j

-l ) The following pressure tests were performed prior to the end of the second -

G/ maintenance / refueling outage. These pressure tests included system functional ;

tests, maintenance / system inservice tests, and system leakage tests as required '

by Section XI of the Code. Boundaries for these pressure tests are described in ;

the VEGP 1 Inservice Inspection Plan document (ISI-P 005). No adverse ;

conditions were noted. The examination data for these pressure tests is ;

available for review at the plant site upon request.

System Functional Tests (FTs) :

FT Number Test Descriotion !

i 1 Reactor Head Vent functional Test 4 Safety Injection Pump 1204 P6 003 Discharge functional Test t 5 Safety injection Pump 1204 P6 004 Discharge functional Test 6 Penetration 33 functional Test t 8 Penetration 30 functional Test 12

Containment Spray Train A functional Test 13

Containment Spray Train B functional Test

Examined portions not previously examined in MW0s 18803844,18805645, !

and 18805444.

, System inservice Tests (lisi l V IT Nymhgr Test Descrintion 1 Charging Line Inside Containment Inservice Test 2 Letdown Line Inside Containment inservice Test ;

3 RC Pumps 1, 2, 3, and 4 Seal Leakoff inside Containment inservice Test ,

4 RC Pump 1 Seal Injection from Penetration 54 to Valve 006 Inservice Test 5 RC Pump 2 Seal Injection from Penetration 53 to Valve 359 Inservice Test 6 RC Pump 3 Seal Injection from Penetration 52 to Valve 360 Inservice Test 7 RC Pump 4 Seal Injection from Penetration 51 to Valve 361 Inservice Test t 8 RCS Hot Leg Sample Lines to Penetration 24 Inservice Test 9 Sample Line from Valve 101 to Valve HV-3514 Inservice Test 10 CVCS Inservice Test with Positive Displacement Charging Pump Operating (Outside Containment) -

11 Centrifugal Charging Pump (CCP) 1208 Po 002 Discharge Inservice Test 12 CCP 1208 P6 003 Discharge Inservice Test 13 Boric Acid Transfer Pump Suction System Inservice Test 14 Accumulator Tank 1204-V6-002 Inservice Test 15 Accumulator Tank 1204-V6-003 Inservice Test i 16 Accumulator Tank 1204 V6 004 Inservice Test 17 Accumulator Tank 1204-V6-005 Inservice Test ,

18 RHR Train A Inservice Test ,

22 Spray Additive Tank Inservice lest 23 Refueling Water Storage Tank Inservice Test 24 hmple Line from Valve 097 to Valve HV 3508 Inservice Test l 25 Penetration 24 Outside Containment Inservice Test

! (( ,/~'N 26 NSCW Tr,ain A Inservice Test l 16 1

{

L r

System inservice Tests (ITs) (continued)

IT Number Test Description I

27 NSCW Line 419 Inservice Test 28 NSCW Line 029 Inservice Test-29 NSCW Line 184 Inservice Test 30 NSCW Train B Inservice Test 31 NSCW Line 424 Inservice Test 32 NSCW Line 030 l< service Test 33 NSCW Line 185 Inservice Test 34 Containment Coolers 1501 A7 001 and 1501-A7 002 Inservice Test 36 Containment Coolers 1501 A7-005 and 1501-A7-006 Inservice Test 3B Cooling Coils 1511 E7 001 and 1515 A7 001 Inservice Test 45 Steam Generator 1201 B6 001 Inservice Test 46 Steam Generator 1201 B6 002 Inservice Test 47 Steam Generator 1201 B6 003 Inservice Test 48 Steam Generator 1201-86 004 Inservice Test 49 Penetration 7 Inservice Test 50 Penetration 8 Inservice Test 51 Penetration 9 Inservice Test 52 Penetration 10 Inservice Test 53 Penetration llB Inservice Test 54 Penetration lit inservice Test 55 Penetration 12B Inservice Test 56 Penetration 12C Inservice Test 57 Main Steam Loop 1 Inservice Test 58 Main Steam Loop 2 Inservice Test

^x 59 Main Steam Loop 3 Inservice Test x ) 60 Main Steam Loop 4 Inservice Test

'~'

61 Condensate Storage Tank 1302 V4 001 Inservice Test 62 Condensate Storage lank 1302 V4-002 Inservice Test 63 AFW Inservice Test with Pump 1302-P4 001 Operating 64 AFW Inservice Test with Pump 1302-P4-002 Operating 65 AFW Inservice Test with Pump 1302-P4-003 Operating 66 Auxiliary feed Pump Turbine Inservice Test 67 ESF Chilled Water System Train A Inservice Test 68 ESF Chilled Water System Train B Inservice Test ,

l 71 Main Feedwater Loop 1 Inservice Test l 72 Main Feedwater Loop 2 Inservice Test 73 Main Feedwater Loop 3 Inservice Test 74 Main feedwater Loop 4 Inservice Test 75 Main Feedwater dypass Loop 1 Inservit.e Test 76 Main Feedwater Bypass Loop 2 Inservice Test 77 Main feedwater Bypass Loop 3 Inservice Test 78 Main feedwater Bypass Loop 4 Inservice Test 79 Excess Letdown Heat Exchanger Inservice Test l 80 RHRS Cleanup Inservice Test l

81 NSCW Pump 1202-P4-001 Inservice Test 82 NSCW Pump 1202-P4 002 Inservice Test 83 NSCW Pump 1202-P4-003 Inservice Test 84 NSCW Pump 1202-P4 004 Inservice Test 85 NSCW Pump 1202-P4-005 Inservice Tst 86 NSCW Pump 1202-P4-006 Inservice Test

/ ,' 87 NSCW P m 1202 P4-007 Inservice Test C 88 NSCW Pump 1202-P4-008 Inservice Test 16-2 I

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System Intervice Tests (ITs) (continued)'

IT Number- Inst Descriotion 5( ) ' 89 90 NSCW Line 417 Inservice Test

. NSCW Line 421 Inservice Test 91 NSCW Line 423 Inservice Test !

"< 92 NSCW Line 426 Inservice Test. ;

L - 93 Boric Acid Transfer Pump 1208 P6 007 Inservice Test' 94 Boric Acid Transfer Pump 1208 P6-006 Inservice Test u I j

p System Leakaae Test (LT)

p. LT Number Test Descriotion- f 1

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) 't 7 y INDICATION NOTIFICATION FORMS l The followin Indication Notification Forms (INFs) were issued to Georgia Power

+

Cumpany (GPC by Southern Company Services, Inc. (SCS) due to the report 0ble- i indications being observed during the examination of Class 1, 2, or 3 ,

components, during the second maintenance / refueling outage at VEGP 1: },

INF No. Affected Component / Area INF Disoosition j 190 VI 001 Weld 11201 053 1 Use "as is"; reinspect next I refueling outage (IR3) 190 Vl-002 Weld 11201 053 6 Use "as is"

190 Vl-003 Weld 11201-0041 Use "as-is" 190 VI 004 Weld 11204 043 4 Use "as is" 190 Vl 005 Weld 11204-0431 Use "as-is" 190 Vl-006' Weld 11302109 40 Reworked per MWO 18906059 and re-examined.

190 VI-007 Weld 11204 023-16 Use "as is" 190 VI-008 Weld 11204-201-7 Use "as is" (m) 190-Vl 009 Weld.ll204-124-15 Use 'as-is" 190-VI-010 Weld ll201-V6 002 W31 Usr "as is"

~ 190 VI-011 Hangers ll201-059 H003, Htnger ll201-V6 002 H006 used ll201-030-H041, & "ss-is". Hangers ll201-059 H003 ll201-V6-002-H006- 4 ll201 030-H04) reworked.

190 VI-012 Weld ll201-V6 002-W10 Use "as is" 190 Vl-013 Weld ll201 V6 002 Wil Use "as-is" Copies of the INFs and their attachments are enclosed. Refer to the_ respective INFs'for details on the nature of the indications. The INFs in this section constitute only reportable indications in the SCS scope of work. GPC should be notified of any reportable indications observed by outside contractors by their respective documents which are referenced in this report.

000884/eu 17-1 ;

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indication Notification ADM + H/F . FORM 205 tNr No. 1-5KH MCI i . P sedeny com Date NDE Method Procedure No./Revesiort 3-5-90 / 3 m MUT RPT R MT R RT R ET R vT R other t/1-Y@he. 2 C;mmentti urtrg inservloe inspectim of wld 11201-053-1, uttrusmic irtilcattons wrv detectat. These irtilaatims wtv further titwstigatui wrt emtuatal as inter-brai lack of fusim, acceptable to A9,C Sectim XI,1983 E:litim, Sswer A11etta. Refermoc attaohai data re;xrt SYOV1036.

Signature . Lead NDE inspector $NT Level Date D/f.WN - AkJMeAlnuaaA Title l1 'T* L 779*

Date

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Notitaation Acknowledged By Title Date ,

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SHEET NO, M s s r-re l PAGE 5 0F +' ' ULTRASONIC EXAMINATION EVALUATION SHEET FOR REPORTABLE INDICATIONS Weld Number: //26/- 663 * / Indication number : / : Applicable ASME Code Standard used for evaluation: Section XI w/ Summer 63 Addenda / Article IWB-3514 Characterization of Flaw Indication per Para. IWA-3220 Type of Flau: 508s04/466 PLAAJ44 ; SKETCH MK PG2 dfY t CALCULATIONS 77 Y= /28 * /0 S= 2a = /2 %= A'/8

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ALLOWABLE: /6./ Fo ACCEPTABLE: /

REJECTABLE: ( REVIEWED BY: 44. M d 4 - - AJ Nb Ab4h LEVEL: , UT4 # 5 DATE: 3 '1 *l o SC f f.wdu -

                                                   , 3 9 o w ar OTIttu$t c: man

1 1 SHEET NO. 3 90 V/ U d 36 l PAGE 9 0F 4/ __ j ULTRASONIC EXAMINATION EVALUATION SHEET FOR REPORTABLE INDICATIONS Weld Number: N20/- d5E - / Indication number : 1 1 Applicable ASME Code Standard used for evaluation: Section XI w/ Summer 83 Addenda / Article IWB-3514 ., Characterization of Flaw' Indication per Para. IWA-3220 Type oi F1au: Su8 Spar 4cc AAM48 SKETCH B7~A$.2cf'/

- i rs CALCULATIONS IV S: 6 Y: R.6 7 = /. 0 2a : /Y t: /64~

a = 07 n/1 : . 0// l 1 = 4.Vo aft : 0V6 L-EVALUATED PER TABLE fA/8 - J5/Y-2 INDICATION SIZE: ACTUAL: ___ _ W% ALLOWABLE: /d 8 % ACCEPTABLE: / REJECTABLE: O REVIEWED BY: M. Mi b=e A1.r>w Alt-au U I LEVEL: Il T L W DATE: J "/ - 9 d 505 O'- 3-7 40

MiCation Notification ADM . H/F . FO*iM 205 INF No. 190-V1-002

     . . Finsenes
 , am Date                           NDE Method                                                                                  Procedure No./ Revision 3-4-90                      R ui TPT                    MT      RT C ET R VT C Othe'                                            PT-V-605/ REY. 1                                         l Ctmments                                                                                                                                                                                        l
                   .            Surface examination of weld 11201-053-6 revealed five (5) linear indicat.ans. These indications were evaluated to ASME Section XI, 1983 Editione S,ummer 1983 Addenda and were found to be acceptable.

Signature . Lead NDE n pett $NT Level Date '

  . D.S.,W                          _ _

M __, 3-9-90 Signatur$fleagrCoory/at Title Date W. M, BC / 4.. Ese.c Project Coordinator /Vogtle 3-9-90 Po,t y weievicei .a / ' T itle 3 .. _ Date Nsql Cation m, Acknowledged d . la . - By :~ l\l f o i s' I D 9 1t. Port 3. Disseestson by Operstme Company Comments: (t[f j F .1 k' ' ' j' ug L La O arrective Action IN / f Signatws4. Operating Co. Representative Title , Date l ...s,, , If 1 . . - i i l'. 8. k E. N el I 'l 'f D _ Part 4 Reenemination Commentst

                                                                              !A Signature Examiner                                                $NT Level                                                            Date Port 5. INF Closed                      /
                                             $4. W8W                        WW(SWAM                               M                               S*N~
                                                                                                                /
                     'r y '         }

FErm NO. 9 137t A

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                                  &m Date                                                                                                                                                                                                   PrOCedute No./ Revision I

3-4-90 R ut filPT ['~l MT R RT R ET R VT Rother PT-V-605/ REY. 1 C;mmentu l Surface examination of weld 11201-004-1 revealedsix(6) '

                                                             -                                                             linear indications. The indications were evaluated to ASME Section XI 1983 Edition, Sumer 1983 Addenda and were found to be acceptable.                                                                                                                                               l I
                         $sgnature . Lead NDE inspectet                                                                                                                               SNT Level                                                   Date Iw                                             11.                                        7'd Itv e n                              .2%~                                                                  3-9-90
                                                                                                                                        /4. Eke                                       Nject Coordinator /Voctie                                                      3-9-90                          ,

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                                                                                                                                                     %SI"//26/-00Y                    $90 vip O$3 V0GTLE l1                      Il20f-00 &1                                  Type                                                                                Bat (h Number            Ther;- 4..a:et Penetrant Materials Perietrant w,_ ninwnfLisf                 o ,ane,inen o ,er S K c - N F                                                       19LofP                   w PT*C procesure No. PT- V-t OS                                                                                                                                                                          90 -00 t sinorcMcac                Metrant                  S ACL-MF/S                                                 11A095                   5,,,,e n.,

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                                                                                                                                                                                  $NT Level   Date I

SNT Levet Enamener ERammPr MS D* O E 3- pf-90 matcT/PToAlf$ b Componefits

                                                                 ~2C R=ks (indecatson Descrepteon. Examenateors Lemetateres, etc_)

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i indication Notification ADM . H/F . F 03M . 206 INF No. 190-V1-004

        .1. P enseap NDE Method                                                                           Procedute No./Reyesion
   - am Date 3-4-90                        R UT T PT            MT         RT R ET R VT COther                                    PT-V-605/ REY. 1                           l C;mments:                                                                                                                                                               f
                                                                                                                                                                          )'

Surface examination (PT) of weld 11204-043-4 revealed four (4) linear indications. These indications were evaluated to ASME Section XI 1983 Edition, Sunuur 1983 Addenda and were found to be acceptable. i Signature . Lead NDE inspector $NT Level Date Tw I A ft.stw3 2Z' 3-9-90 Segnature . Lesq or ator// f/ ' Title Date 3-9-90

                         . 2 TM ftIE'cf                             Pro.iect Coordinator /Voetle Po,t a . N.iet.      n                        /

Nettfication Acknowledged By T6tle .

                                                                                       .                                         Date l , . , . l I , 1. . -                                       N. l' I * . s' 4 ,1         ?                                  ~'s      IV  1L' Port 3 Despoortion try Operatene Company Comments:

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i indication Notification ADM . H/F . FORM . 205 INF No. 190-V1- M 5 I Pesidesige am Date NDc Method Drocefure No./ Revision 3-4-90 O ut fi"lPT R ut R RT R ET R vt ['~lother PT V-605/ REY. I commentti Surface examination of weld 11204-043-1 revealed two reportable indications. Indication 1 (a .125" linear) was evaluated to ASE Section XI.1983 Edition. Summer 1983 Addenda, and was found to be acceptable. Indication 2 (a 1/16" rounded) was evaluated to ASME Section III 1983 Edition. Summer 1983 Addenda and was also found to be ac.ceptable. Signature . Lead NDi' inspector SNT Level Date C1 &m Title E 3-10-90 Signature - ad i5re or'/ 9 Date

4. 4 E8~CE. Pro.iect Coordinator /Vontle 3-10-90

 , Peria A eui.ed on              '/

Title Date Notifica,t' ion Acknowlepged By

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                                                                       .'   t 14      I    (-                  ) i D . -:t T s Part 3. DeewtMen any Operating Company Comments:                                                                                                                   i k *.

gl iskIr j tl%# A (, t, reective Actioni f4 Signature . Operating Co. Representative Title Date I r e < s s 15 l r, - /.q' t . Ib *s

                                                                                         .  ,(*             h*          l '.

Part 4 Regnameneteen Comments: k Signature tuaminer SNT Level Date Port 5 INF Closed , 8 L.Yt.z~eY 2 7' m A>OAKel W iz 3 4 6 ' '7 0 l

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   .__._.7._...,__..        .  ,

_ indication Evaluation Report Aux HM Form 320A

          ;_W.                                                                 Isomeirs Drawing Wmter                                    theet Nome.r

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mem Date. NDE Mo'. hon Procedure No./ Revision L14-90 R UT PT- % MT RT ET C VT COther NT-V-505/ REY. 1 C S M sts: During surface examination of weld 11302-109-40, two (2) linear

                    ,               indications were discovered. These indications were evaluated to ASE Section XI 1983 Edition, Summer 1983 Addenda and were found to be re,jectable.
                                                                                                                        ^

Signature . Lead NOE inspector 5NT Level 30 ate 7tS~n /den n'216

2C 4 15-90 ~ r T6tle Date

     $sgnal g . d d C v7          .

s gjj.[tc4 PROJECT COORDINATOR /V0GTLE 3-15-90 pen-+ < .__ i T itle Date NoMitation

3. %Acknowledbd% By /n m., ,s Lai o ett sm, 3 n - 9o Port 3 Depoestson by Operating Company Comments: ;

Re.gqu N ' Re-WOR 1 / orrective Action Penrum conicctten rtseviac Pu nwo + rec 106 ts9 ja -nie neA or ras ypuh71cNS vppM -nl& PitECTICA) 0F JSI PE/SCA/A!EL . 7tkrcAM tit Thuddi% MEA %2 men S rptCK w MLD MTEt, FLN'i'IAIG 70 EN5t'l'E 1kECC b A!O y/Ot &7)pN cF NtoINM NAll RFhthfNFNS RE-tgunas. To tEtimi THE WblMTION5 ME BUU tEmuiCQ.

     . Sign -            rating Co. Representative                               Title                                                Date uts., k. *de.t.nw                                            NE             . bh           -                          3*fb^ N Port 4.Weenemmotion Comments:

As N6AMED SE2 HWO/896~6069 /9NJ) Af*BA MINED . ASF & X 9 ' 6 9 0 l/ N C 3 / Awo 64C4 69aP'/6?N6,

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            '3-13-90                  rut [flPT         MT              RT'         ET C VT R Other      PT-V-605/REV. 1 C4mments:

Surface examination of weld 11204-023-16 revealed'three (3) I linear indications. These indications were evaluated to ASME Section XI, 1983 Edition. Summer 1983 Addenda and were found to be acceptable. Signature . Lead NDE Inspecip/ SNT Level Date

77. An /?f2 JJ 722C 3-16-90 Signatu d Co nato / T6tle Date

            .                 /#"       Yd.Mfdk'                     PROJECT COORDINATOR /V0GTLE                  3-16-90 Per}( . NottMostN>n            /

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INF No. 190-V1-008 1 Pausens em Date NDE Method Procedure No./ Revision - 3-12-90 R uT T PT b MT RT- ET R VT Rother PT-V-605/REV. 1 Commentsr Surface examination of weld 11204-201-7 revealed one (1)_ s linear indication. The indication was evaluated to ASME Section XI, 1983 Edition. Summer 1983 Addenda and was found to be acceptable. SNT Level Date Signature . Lead NDE Inspectgr - U.LlrL /O 2d W 3-16-90 Signat r#ator Title Date ad I p/ Y 2. N C-M PRfLIFcT conenINATOR/VOCTIF 3-16-90 Perf 2 Notifiesten / Noti son knowledgec B - Title Date b l J P me hv ;uw .ieb s f d M k. E!b heu R ' b* h b Part 3. Desii6eition by Operatine Company - Comments: I 8(f U k j LLS 6 ~ A% ~ f bu rrective Actioni N/A Sign Operating Co, Representative Title Date h4 Lb-- %. - C 4 R.. W l ls - S O Part 44eenemeneten Comments: fr% Signature Examiner SNT Levet Date Port 6 INF Closed -

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                                                                                                                                                                                                              - , , , . . , ,         n  ,. ___________.n.,__.                    _ _ _ _ _ _ _ _ . , _

indication MifiC8 tion- ADM . H/F FORM . 205 INF No. E*96-V/*669 3-16-90 CUT- [TlPT - MT C RT ET C VT C Other //*- /.4,85 /ggy/

        --- Comments:

Surface examination of weld 11204-124-15 revealed one (1) linear indication. The indication was evaluated to ASME Section XI,1983 Edition, Sununer 1983 Addenda and was found to be acceptable.

          . Signature . Lead NDE Inspector                             SNT Level                       Date

[]. S.n>IA ltb 3

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                ' Signature . Examiner                                  SNT Level                          Date Port 5. INF Cleasd SCS Sig u                                              Title                             Date
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   ' indication Evaluation Report -                                                                       Aux H/FN. Form 320A Wood Number                      loometric Drewmg Number                  Sheet Number nt/ Unit haria          1              sino s./A 9-is                 Isz sinee-a s                             $96 V/9)//

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  ' Ppd 2 WotHiestiov' Title                                        Date ation Ac nowledged
  '9I          uW . c'.1r a            l ooss ' S.o hl           'se TM. E n4 A                               '5     25-90 Port 3 Disposetson by Operating Company Comments:                                                                                                                     ~

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                                                                                          /

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                 /Ak3f6#776A)$ 3/W                        AbdAJASD <iS*0XFAt[ /A40k97'/ CMS PEL Ai8 - :13d/(c.)                                                                            ,

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1'. = Indication Evaluation Report Aux H/FN. Form 320A nt/ Unit Weld Number leometnc Drawing Number Sheet Number M //Zol-Y6 -602 - L)3/ /6/-//20/ - Y6 - 60 & 690 Y/ A //3 C'_' ._V0C a; Desenpison TL Ell Enamenetion Procoeuro Y Y-lc 0b, EY Enam Methoo JAY

          $d 9 A % $ f L 1) & A l [ 4 N N d A) Y M A Code /YeartAeoenas                                        Exam Cat.

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                  ' Form No.         1379 A

* ~

Syff.ngr-. D40V l\lbO l-i 85054-C-FIG-'1- f GEORGIA' POWER COMPANY PAGE 1 0F 2 VEGP QUALITY CONTROL VISUAL RESTRAINT INSPECTION REPORT 1 REV # ]

c.MWO/0THER # / 2.INSP PROCEDURE #- REV # 3. DRAWING # g/A B5 o 5 4 - (L 0 N/A -

6. BUILDING ROOM / LEVEL S.SYS. DESIGNATOR i

4. TAG f.

                                                                        /ZD /                       durm7                         N6k c-V
                          /QLY- V&> l.)O2-Holo                                                                                                                    ,.

7. TYPE:

Strut Rigid Anchor -O Pipe Strap D Frame V i O Sat Unsat N/A -}

8. GENERAL-EXAMINATION: ------ ------- ----

tag on hanger / support attached a.~I.D. v

b. No' signs of corrosion

c. No, signs of physical damage ~

v

d. No are strikes

e. No-signs of wear,-stripped threads, etc. f h v-Q

                  .f. Load scale attached and readable                                                               v

g. Minimum. thread engagement 7

                  'j. Component alignment correct                                                                  NA                WA           /
                *'k. Component location correct                                                                                                   7 1'. Rod clearance OK (Spring 1Can only)
                                                                                                                ////// /////./f ////                                   ,

Nhen required by Engineering >

l. Sat: Unsat N/A

9. HANGER / SUPPORT TO BUILDING: ------ -------

( I v L a. No~ excessive crack / chipped concrete / grout v" L

b. No loose or missing parts / %Q,,

c. Weld quality acceptable Sat Unsat .N/A

10. HANGER / SUPPORT TO COMPONENT: ------ ------- ----

s. Attachment items not bent / deformed #

l.

b. No missing or loose parts

c. Weld quality acceptable

                                                                                                                        /         _

g Sat Unsat N/A

11. COMPONENT ATTACHMENT:

Integral 0 Nonintegral V ------ ------- ----

a. Attachment items not damaged /

b. No visible evidence of galling /

c. No missing or loose parts / -

d. Wald quality acceptable Sat Unsat N/A

12. SHEAR LUGS: N/A 7

a. Lug (s) not bent / deformed -

b. Wald quality acceptable (Con't)

      .O t

__ .- . a r + - y

9 h:. S 9 b t/I No l (Cont'd) 86054-C FIG 1 GEORGIA-POWER COMPANY

                                - VISUAL RESTRAINT INSPECTION REPORT                       PAGE:2 0F 2 p     VEGP. QUALITY CONTROL

14. TAG #

13.MWO/0THER # lI2Dl ' Vlo ' 00 2

HDi.e 1 5. EXAMINATION RESULTS: @R/DC#

16.D'ESCRIPTION OF DEFICIENCY IF UNSAT: ghg g,g g, 3e[g de Lugte IlLLMUT~lMG Wl14TP TL UOTS AWN WG WkD MI%2 T agomm A> m, TAcx wa d cagesse AT tett thoeum u.cu bl3ML gg g wp ar Z Y/ - 0/ /

A$fMA7"A81 C l}dd A6 /$ kMt

r O 9

17. METHOD OF EXAMINATION:.

Direct Examination / Remote Examination 0

18. EQUIPMENT USED: pusgtgg y y ind sc.,4LE j IRYo M607f 84L MGI WIR OM E TE L ^ 90-o 0 5 be 4 2. G - 9 0 A 'Eishinu '. b )b Y / % ia /k o ti 5 n.10

19. INSPECTOR 7, , hM t4g [ $4gg pnilIhorn LES WI S-2-90

20. EVALUATOR ,

N/A 0 LGELar WE 3.zy 4 4 N/A 0 DAtt d-/0.N 21.ANII REVIEW'/ } ~

.Y

r. LPROCEDURE N05.85400 C, REV 2 VISUAL EXAMINATION OF CORP 0NENT SUPPORTS /HANOER$

              'TAGNUuBERi11241V6002H06-                   ' SERIAL NUSERi N/A                    RECORD ND4 $7.

SUPPORT EXAM N0i 24-TYPE: H CORPONENT DESCRIPT!0N: SUPPORT SIEEL R005:1404 AREA; 140A. LEVEL C BU!LDING:CNTNT

      ;/~y     ~COLD SET: .               .    .NOT SET:                ,
                                                                                    "RESULTS" U          "$VPPORT EXARINATION" .

1 TAG NUMdER ATTACHED = Y LOOAi!0NCORRECT ; -- N 5 N N0 SIGNS OF CORROSION g NO $!GNS OF PHYSICAL DAi4 AGE N0 SIGN OF NEAR, STRIPPED THREADS, EXT $ k NO.ARO SIR!K!$l N AL!GNMENT CORRECT , LOAD SOALE Ai!A0MED ANO REA0ASLE

              ^ CORRECT LCAO SETTING              COLD N'       . HOT N' N
              'NO LOOSE OR MISS!NG PARTS N
               -$PRING RETA!h!RS REMOVED N
               .R00CLEARAN0E!NSIDECAN.

SURFACE TEMPERATURE : . (F) N' ' MINIMUM THREAD ENOAGEMENT, ALL THREA0E0 FASTENERS N

                   " SUPPORTING STRUCTURE TO BUILDING" S
                 .NO EXCES$!VE CRAOKS OR CHIPPE0 00NCRETE/ GROUT
                  'NO LOOSE, M!$$1NG, DAMAGE 0 PARTS (80!.TS, NUTS, ETC,)                  U N'                                 j N!LDQUALITYA00EPTA8LE                                 .

f p " SUPPORT TO SUPPORi!NG STRUCTURE" ATTA0Hp(NT'!TEMS NOT 8ENT OR DEFORnED N e l ; WO LOOSE OR MIS $1NG PARTS N 1 N L .. NELDQUALITYA00EPTABLE l' /7 FREEDOM 0F NOT!0N AT SLIDING SURFACES.

i

                    " SUPPORT TO Comp 0NEhT" i

N

                  -INTEGRAL (1) NON!NTEGRAL (N) 1*
       ,         ' AiiAGNMENT !!!MS NOT BENT OR OEFORMED                                   S S

N0 LOOSE OR MISSING PARTS . '* N0 VISIBLE EVIDENCE OF GALLING $ N NELD QUALITY AC0EPTABLE~ L

SHIM AOCEPTA8LE PER DESIGN ORANINGS

                     "$ HEAR LUGS - PRESSURE 80hN0ARY"                                                                       s N
                > LUG ($) NOT BENT OR OEFORNED

N L WELDCUALITYA00EPTA8LE I "!XAMINATION SUlstARTW RESUti (SATISFACTORY R W SATIFACTORY): U REMARKS ' 80LTS RI N I N AT NOR. TO 8 LOG ATTACH.

,' ' SAT.PER OR T 1 N 3A00 CORRECTED NRP 10/13/06 '^ W/t' lC)1/O L

                   ' EQUIPMENT USED: ' FLASHLIGHT GRAYCARD LEVEL.11           OATE:06/27/06              4 L

p

                   ~!xan! Natl e PERFORMED BY: BAUSEMER F. R.

EVAULATED BY: BAUSENER F. R. LEVEL.11 CATE.08/27/06'y MM JV ' - FIELOS CONIA!N! C ONLY ' NOT USE9 8Y THIS EXAMINATION l AN!!. [ OAi!: f,f,',/ f,', p ,

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OPEAATIONSDEFICIENCYREr0RT L - * =- s===nminaum ,3 m c

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       ~                                                                                                                                                                       '

tietes AND WELDED ANGLE WEEE fok E2EcrioN FMPosES AND iUot

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                         - PR0h1AlRE No 85400-C,VEY' 2 ? Vl$UAL EXAMINATION OF COMPCNENT $UPPORT$/ HANG (R$ .

TA8 MUS ER: 11201V6OffHol~ L SERIAL NUMBER: N/A' RE00R0NO: $7 f3 V' k

                                                                                                             $2PPORTEXANN0:         24                                l h

h LTYPls H' CCMP0 Nut BVlLDING:CNTMt RCC#: -- DESC'<!PT!0Ni 'AR!A: $UPPORf tEVEL: $ft!L ~ ' d-)' C'fLD SET: = 401 SET:

                          . segyPP08! [E;;;;;ATION" :                                                    " RESULT $"
                                                         ~

TAG r,mIER ATTACHED Y N

                          . LOCAI!ON CORRECT                   .

N0 5.GNS OF CORRO$l0N $ NO $.GNS OF PHY$1 CAL DAMAGE $

          ,..            - #Ni!GN OF NEAR, STRlFPE0 T>REA05, EXT                                                   $                                                   1
          't

No ARC STRIKf5 $

                         'ALIGNMENTCORRECT _                                                                       N LOAD SCALE ATTACHED AND READAILE r                                              COLD N*                 M0T h*                          *
                         . CORRECT LOAD $ETTING
                         ~N0 LOO $t OR N!$$1NG PARI $ '                                                           ,N
                      ' * $PRING RETAINER $ $1 MOVED                                                               N N
                    ... A00 CLEARANCE IN$10E CAN
                            $URFACE TEMPERATURE              .                      (F)-                           N8 NIN!WR THREAD ENGAGE"ENT, ALL THREADED FASTENER $                                      N

[ 1 (. **$U9 PORT!NG $TRUCTURE TO BUILDING" t NO EXCES$1VE CtACK$ 04 CHIPPE0 CONCRETE / GROUT ,

           !'                 N0'L00$t,M!$$1NG,DAMAGEDPARTS(80LTS, NUT $,ETC.)                                     U p           l'                 NELDQUALITYACCEPTA8LE                                                                N                                         .o
                              ** SUPPORT TO SUPPORTING STRUCTURE **

ATTACHMENT <lTEMS NOT BENT OR DEFORMED N r NO LOOSE OR MIS $1NG PARTS

                         - NELD QUALITY AC0!PTA8;E 3

N

1: . FREEDOM 0F MOTION AI $LIDING $URFACES l. i ** $UPPORT ?f '0MPCNENi" N _ !NTEGRAL [1] NONINTEGRAL (N)' ATTACNNENT ITER $ DOT BENT OR OEFORMED $ NO LOOSE OR MI$$1NG PARTS $ No V!5!ILE EVIDENCE OF GALLING- S

                         , NELO QUALITY ACCEPTABLE                                                                  N
                               $HIN ACCEPTA8LE PER DESIGN CRAW!hG$                                                                                                  ,
                               **$ HEAR LU6$ - PRE $$URE 800NCARYes LU6($)NOT8ENTORDEFORNED                                                              N NELDQUALITYACCEPTA8LE                                                                N
                               " EXAMINATION $UMARYao ,,

p RESULT ($AT!$FACTORYORUN$ATIFACTORY):U

          .1-                  RERARNS:

80Li$ MIS $1NG AT HGR.' TO OLO6. ATTACH.

[ .

l' EQUIPMENT USED:

FLASHLIGHT GRAYCARD e

EXARINATION PERFORMED SY: 8AUSENER F. R. EVAULATEDBY: 8AU$ENER F. R. LEVEL: !! LEVEL: !! DATE: OATE: 08/27/06Ot/27/06-Id-~_m[F' X A -- M J

                                * - FIELOS CONTAINING ONLy : NOT U$ED BY TN!$ EXAMINATION
                              -ANII 8-.                                                DATE:

f[

                           +i W                        !

SHEET # s,9 bv o i s 19

                     '                                                                                                   85054-C FIG 1-
                   'GaoRGIA POWER COMPANY                                                                                    PAGE 1 0F 2 VEGP QUALITY CONTROL                                 VISUAL RESTRAINT' INSPECTION REPORT REV # 3. DRAWING #,                      REV #

1 .MWO/0THER # 2.INSP PROCEDURE # q(/A 85 0 5 4 - (L O._ u lt+ 7c? of M esos# Lot 5.SYS. DESIGNATOR 6. BUILDING ROOM / LEVEL h/J77)}7~ /Wo 2,

                                          //20/ - 0$9" WCD3                             /2D/

7 .T PE: Strut O Rigid Anchor O Pipe Strap D Frame, [ Sat Unsat N/A

8. GENERAL EXAMINATION: . __ . _______ ....

v'

a. I.D. tag on hanger / support attached <

b. No signs of corrosion v-

c. No signs of physical damage v

d. No arc strikes /

e. No signs of wear, stripped threads, etc. v-

f. Load scale attached and readable -

g. Miniana thread engagement V

j. Component alignment correct NA WA /e

k. Component location correct- v

1. Rod clearance OK (Spring Can only)

Nhen required by Engineering ////// /////// ////

Sat Unsat N/A 9 .KANGER/ SUPPORT TO BUILDING: ...__. __..... ..__

                                                                                                                                                /
     -9                     a. No excessive crack / chipped concrete / gamut

b. No loose or missing parts v

v

c. Wald quality acceptable _

Sat Unsat N/A

10. HANGER / SUPPORT TO COMPONENT: ..__ . _______ ___.

                                                                                                                         /                            -

a. Attachment items not bent / deformed /

b. No missing or loose parts V'

c. Weld quality acceptable Sat Unsat N/A

11. COMPONENT ATTACHMENT: ------ ------- ----

Integral 8' Nonintegral 0

a. Attachment items not damaged

[

b. No visible evidence of galling K

7

c. No missing or loose parts 7

d. Wald q'=11ty acceptable Sat Unsat N/A

12. SHEAR LUGS: N/A [

a., Lug (s) not bent / deformed

b. Weld quality acceptable (Con't)

O -

 ;[         *                                                 '                                             Skat 0 S9CVIVOt 7 ,

GEORGIA PowsR COMPANY (Cont'd) 46064-C FIG 1 ! v!SUAL RESTRAINT INSPECTION REPORT PAGE 2 0F 2 i C< :vtGP QUALITY CONTROL14. TAG # 13.MWO/0THER # ! N[.y ll cl. D59- HCC3 __ IS. EXAMINATION RESULTS: Sat O Unsat [ CDR/DC#

16. DESCRIPTION OF DEFICIENCY IF UNSAT: 'T4@ @ M gMlK m m lO3f bE UUT PPPCO%. TUO s[2h THE@u5 St4D:2T O F U_ s tt 6 l

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f 17 METHOD OF EXAMINATION: . Direct Examination Remote Examination O . 1s.courentwT osgo FLAS H u G,uv ; G ine.k u.nr j I A To A/Eu rm. G t s/_ WitoM E rE L 90-005 ~D u o 4 EG -90 l-3c-5 AlpswbfLben. Wu &ovu 3 0 9o it.insesefoR /nm M.AQ /sw rnmsorn umz art s-z 9o O . var.uAToR #f,o o.sm .,, a ums ti,.m .,

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27 of 33 vtop 00600.C 11 SMEET 1 of k , REQUEST FOR ENe,1NitRING REVIEW G _ N . go o. 00MP!PE 3,1 , PMt? 1: Probles Identtitcation (t) system No. t7O\ Component No. I tics t GQ ecc.*%

                                                                        '(2) Detailed Description of Problest okt KwT ce s u N t n o c.c. s % c i-O lW ~ f dbb f% ACAD it4LiMEtAtt.T ; ICR Q C www_m N R.*.f( AT PM40 3 2. 54 0 , ___SwN\ Ai

4 S uu w c N O A Awwu iAte60 s47 64 Wi(N L*L .

s a wo e ., - M . t 4 4 ao s s.w A S i- s M . pw. 4..vu e c N 07.% ~ i. s m . <,, i % C'4513 (3) Proposed Solution and Justificatient ( ) Personnel Safety [ ] Plant Safety ( ) Regulatory Requirement ( ) ALARA* (x] Other i bc.uest w 4 as ss O . (4) Requested Completion Detet 64 1. A O Estimated Costt Point of Contaet C.ans. k C usiw ' Phase: 413 % Ce*4 A Cs m w + \ cto WV 4flf9C Data Init&ater / Date DtpartsestManager/5yt. / Engr. Supv. Assigned Target Ccaplation Date M #

Copy to Manager Realth Physics and Chemistry FIGURE 1 l

l

VECF 00400 C- 11 28 of 33 ! l SHEET 2 of i

O a ' oo-c '<2

PART 2: Esatseeries Support Department Reytew (5) Dispositions f GA as*)5 Cd wJ ,m a d .- s c.9e2e , L i, !

l l l 1 t i l L O Safety Related No ( } Tee ( k

Document Generated We N Tee (- ) No. _, Eng. Naabours Required for Review b Approvals: Design Ingr. d / Ra'sponsible Easr 9I/

                                                                                                                                       /
                                                                                                                                      /Dat (if applicable) Date Engr. Supe.                                     Mgr./Engt. Support       z N [b./. -

ut. .

                                                                                                                              ..        ou .
                                             ~~

A,,4 v/'v/Y,. 1 . ORIGINM. o FIGURE 1 (CONT'D.) Pt3ee6

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i ,..,.; a ;.':t,y= Ka L 70 -av 2-w C. nemeer. Jr. 50uthern CompanyServices s.. .: g ; er : wa:e .tre ..g , . , . . , , , , , , , , , I April 5, 1990 l Vaatia flat -j laneratina Plant - Unita 1 and i REA VG 0012 iR 90-0L42~ Files X7B01: 4 Leg: 8G 9020 Mr. C. C. Miller Manager of Engineering l Vogtle Project Nuclear Operations l Georgia Power Company 1 Post Office los 1895 lirmingham, AL 35201 -

Dear Mr. Miller ,

At the request of the site, we have reviewed RER 30-0148. This AtR was initiated due to an inspection during 1Rt which found a nut on a pipe O support (Tag #11201-Olg H003) for the 3-inch diameter pipine to the PORV (PV0455A) on the Pressuriser safety relief valve piping to be two (2) threads short of full engagement with the stud. i We have concluded that the "as found" condition is acceptable based on Westinghouse letter (GP-14821), that states the existing thread engagement

results in stress levels that are within the acceptable limits.

If you have any questions, please advise. Var truly yours,

                                                 /                                                                                                                                                ,
                                    $,M. C.                          say, Jr.

WCR/ 1/t,P att G. Sockhold. Jr. M' P. Tehrancht A. f. Cardent J. C. Williams M. W. Morten NORMS C. R. Myer Project File

8. Pietrtyk Mcument File P. D. Rushton

____l_--______.___.___________________________ , , , . . . , , _ . _ . . . . . . , . . ,

S M Etr.H. %Qb VI V 6 44-88062-C FIG 1 GEORGIA FOWER COMPANY PAGE 1 0F 2 i VEGP QUALITY CONTROL VISUAL NANGER INSPECTION REPORT I i 2.INSP PROCEDURE 8 REV # 3. DRAWING # REV # l (~' 1.MWO/0THER # g)/A

3 (

 \                                                 85c52     l C            l      m .itonuo30.aoq, i

4. TAG # 5. TYPE OF COMPONENT:

H8n9'r E' Support '; Brace

_ l b 1101 -o50 404 i ~ '

6. TYPE: Constant Support ;

Strut Spring Can s' { Rigid Anchor : Pipe strap Rack [i j Sat Unsat N/A

7. GENERAL EXAMINATION: ...... ....... ....

a. I.D. tag on hanger / support attached -

b. No signs of corrosion

c. No. signs of physical damage -

l l

d. No arc strikes s _'

e. No signs of wear, stripped threads, etc.

l f. Load scale attached and readab3e v' i

g. Minimum thread engagement"

h. Load setting dia. R 'l t ////// /////// [
1. Surface tesperature 6e c) *F //////'

                                                                                                                           ///////                          ,

j . Component alignment correct u d! _3g_l k.' Component location correct wA l** 1. Rod clearance OK (Spring Can Only) s , r~ I

Spring cans & constant supports only

               **        When required by engineering                                                                                                     !

l Sat Unsat N/A , 8.NANGER/ SUPPORT TO BUILDING: ...... ....... ....

a. No excessive crack / chipped concrete / grout __

we

b. No loose or missing parts

c. Weld quality-acceptable w' _

Set Unsat N/A 9.NANGER/ SUPPORT TO COMPONENT: ...... ....... .... s#

a. Attachment items not bent / deformed

b. No missing or loose parts _ _v ' '

c. Weld quality acceptable Sat Unsat N/A

10. COMPONENT-ATTACNMENT: ------ ------- ----

Integral Nonintegral 9/"

a. Attachment items not damaged v'

b. No visible evidence of galling v' s/

c. No missing or loose parts __'~

s

d. Weld quality acceptable I

                                                        !                                                        Sat           Unsat               N/A
  '~'      11.SNEAR LUGS:                     N/A    ?                     .                                ......            ..____.            --..

a. Lug (s) not bent / deformed

b. Weld quality acceptable 1

l (Con't) ,

sw n movovow \ (Cent'd) SSOS2-C FIG 1 GEORGIA POWER COMPANY PAGE 2 OF 2 VISUAL MANGER INSPECTION REPORT VEGP QUALITY CONTROL ( i c 13. TAG # l 12.MWO/OTHER # ' (]-

   \s                            d !N                              11.01 o bo eto41                             ,

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14. EXAMINATION RESULTSt Unsat C/ DC #

Sat _~

15. DESCRIPTION OF DEFICIENCY IT UNSAT: g gg g

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f 16. METHOD OF EXAMINATION: Direct Examination rf Remote Examination 0

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18. INSPECTOR &tE . !C . 6ru N LI T MI 5590

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     . 3 <      e,...et.n N tacation Ack owiedged By                                                    T atte                                                 Date                                         ?

( tut s r i#se - D..,*s f k Mt* A DEkk t_ hit e D * ~J 7 ' '/ I Port 3. Despeerteen by Operstene company Comments: 1 (C( Q f ' Mid d S * / 5 j I i > ( irrective Action: b /l i

      %fe OperatjngCo. Representative                                              Title                                                  Date
   /      I ksi lkA                   -                                                   %     t'l4 f M r                                        8 1 F - 9C' Port 4 : me nemeneten Comments:

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    .y s DRAWINGS l-        The drawings in this section represent Class 1, 2 and 3 equipment and piping included in the VEGP-1 second maintenance / refueling outage.       These drawings give the identification number and location of welds, supports, and other items that require examination. The drawings are 1         intended for ISI use only and should not be confused with design drawings.

The drawings which follow are listed by sys*em designation, > drawing number, and drawing revision number.

EQUIPMENT DRAWINGS ,

DRAWING DRAWING REVISION SYSTEM NUMBER NUMBER Reactor Coolant ISI-11201-V6-001 (Sh. 1) 4 ISI-11201-V6-001 (Sh. 2) 1 ISI-11201-V6-001 (Sh. 3) 1 ISI-11201-V6-001 (Sh.-4) 1 ISI-11201-V6-001 (Sh. 5) 0 ISI-11201-V6-002 (Sh. 1) 2 , ISI-11201-86-001 Sh. 2 1 ISI-11201-B6-002 Sh. 1 3 , ISI-11201-B6-002 Sh. 2 2 , l ISI-11201-B6-002 Sh. 3 0 + ISI-11201-B6-003 Sh. 2 2 ISI-11201-B6-004 (Sh. 2) 2 : ISI-11201-P6-001 3 Spent Puel Pit Heat ISI-11213-E6-001 0 Exchanger L PIPING DRAWINGS l DRAWING DRAWING REVISION SYSTEM NUMBER NUMBER Reactor Coolant ISI-11201-001 2 , ISI-11201-002 2 ISI-11201-003 3 ISI-11201-004 2 ISI-11201-005 2 ISI-11201-009 2 I ISI-11201-021 4 ISI-11201-025 4 l 18-1 v(3 l

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DRAWING h DRAWING REVISION ' SYSTEM NUMBER NUMBER ISI-11201-029 5 [ ISI-11201-030 5 ISI-11201-031 3 ' ISI-11201-036 4 ISI-11201-053 5 ISI-11201-058 3 : ISI-11201-059 2 : ISI-11201-060 2 , ISI-11201-116 4-ISI-11201-179 4 ISI-11201-183 3 ISI-11201-191 3 I Safety Injection ISI-11204-021 3 ' ISI-11204-023 3 ISI-11204-035 3 ' ISI-11204-036 4 ISI-11204-039 (Sh. 1) 4 , ISI-11204-042 3 ISI-11204-043 3 ISI-11204-076 (Sh. 1) 3 ISI-11204-120 2 '

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  ~() ,                     ISI-11204-199 (Sh. 1)        2     i ISI-11204-201                1 ISI-11204-243                4     ,

Residual Heat ISI-11205-001 3 Removal Chemical and Volume ISI-11208-009 4 control ISI-11208-024 5 , Main Steam ISI-11301-013 4 Auxiliary Feedwater ISI-11302-107 4 , ISI-11302-108 4 ISI-11302-109 5 ISI-11302-110 3 Condensate and ISI-11305-058 2 Feedwater ISI-1130.-060 2 ISI-11305-062 3 : ISI-11305-064 2 18-2

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ML20055F124

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SUMMARY

Dear Mr. Miller ,

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