ML20012B733

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Owners Data Rept for Inservice Insp Ei Hatch Nuclear Plant, Unit 2,Sept-Dec 1989
ML20012B733
Person / Time
Site: Hatch Southern Nuclear icon.png
Issue date: 03/07/1990
From:
GEORGIA POWER CO.
To:
Shared Package
ML20012B730 List:
References
NUDOCS 9003160186
Download: ML20012B733 (116)


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ENCLOSURE 1 i

OWNERS' DATA REPORT l

l FOR INSERVICE INSPECTION EDWIN I. HATCH NUCLEAR PLANT i

UNIT 2 i

i SEPTEMBER 1989 - DECEMBER 1989 r

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OWNERS' DATA REPORT 1

FOR 1

INSERVICE INSPECTION i

l EDWIN I. HATCH NUCLEAR PLANT 1

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UNIT 2

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SEPTEMBER 1989 - DECEMBER 1989 il

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Ti PAGES TABLE OF-CONTENTS _

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ASME NIS-1 FORM AND SUPPLEMENTARY INFORMATION.

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3 II. - ABSTRACT III.-

EXAMINATION

SUMMARY

'2 20-51 A.

CLASS 1 EXAMINATIONS 52 B.

. CLASS 2. EXAMINATIONS 62-66

-C.-

PRESSURE TESTING 67-75 D.

COMPONENT SUPPORTS 76-89'

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' REACTOR PRESSURE VESSEL INTERNALS 90-96 F..

REPAIRS'AND REPLACEMENTS97-106 G '.

AUGMENTED EXAMINATIONS t

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Portions of this report are compiled from Southern Company" No NOTE:

Services, issued reporttfor the Fall 1989 Refueling Outage at E.I.- ~ Hatch

2, and 3 Components",

This report is available-for review in-the Unit 2.

Nuclear Plant, Records Management Department at the plant' site.'

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LIST OF ABBREVIATIONS ANI/ANII Authorized Nuclear Inspector / Authorized Nuclear Inservice Inspector ASME American Society of Mechanical Engineers ASNT American Society for Nondestructive Testing BC Branch Connection BWR Boiling Water Reactor CH Closure Head CONT Containment CPI Containment Purge and Inerting System CRD Control Rod Drive System CS Core Spray System CTS CTS Power Services, Inc.

CU Clean-up C&L Cramer and Lindell Engineers DCR Design Change Request ECCS Emergency Core Cooling Systems ET Eddy Current Examination EPRI Electric Power Research Institute 9

FB Flange Bolting FPC Fuel Pool Cooling System FW Feedwater System GE General Electric GPC Georgia Power Company HL Hanger Lug HPCI High Pressure Coolant Injection System INF Indication Notification Form IGSCC Intergranular Stress Corrosion Cracking ISI Inservice Inspection i

ITL International Testing Laboratories LD Longitudinal Seam Weld Extending Downstream LD-I Longitudinal Weld Downstream on Inside of Elbow LD-O Longitudinal Weld Downstream on Outside of Elbow Lo Zero Reference Location LPCI Low Pressure Coolant Injection LU Longitudinal Seam Weld Extending Upstream LU-I Longitudinal Weld Upstream on Inside of Elbow LU-O Longitudinal Weld Upstream on Outside of Elbow MSIV Main Steam Isolation Valve O

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. Portions of-this report are compiled from Southern Company; NOTE:

" Nondestructive Examination of Selected-Class li

- Services issued report;;

Hatch.

for the Fall 1989 Refueling Outage-at-E.I".-

2,;and.3: Components",

Nuclear - Plant, ' Unit 2.

1 This. reportJ is available for review in the.

Records-Management. Department at the plant site.

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LIST OF ABBREVIATIONS-t ANI/ANII-Authorized Nuclear Inspector / Authorized Nuclear Inservice

' Inspector ASME American Society of Mechanical Engineers ASNT-American Society for Nondestructive Testing BC Branch Connection BWR Boiling Water Reactor CH Closure Head CONT Containment

. CPI Containment Purge and Inerting System

-CRD Control Rod Drive System CS Core Spray System CTS CTS Power Services, Inc.

CU Clean-up C&L Cramer and Lindell Engineers DCR Design Change Request ECCS Emergency Core Cooling Systems ET Eddy Current Examination EPRI Electric Power Research Institute 9-Flange Bolting FB FPC Fuel Pool Cooling System FW Feedwater System GE General Electric GPC Georgia Power Company HL Hanger Lug HPCI-High Pressure Coolant Injection System

'INF Indication Notification Form IGSCC Intergranular Stress Corrosion Cracking ISI Inservice Inspection ITL-International Testing Laboratories

.LD Longitudinal' Seam Weld Extending Downstream LD-I Longitudinal Weld Downstream on Inside of Elbow LD-O Longitudinal. Weld Downstream on outside of Elbow Lo Zero Reference Location LPCI Low Pressure Coolant Injection LU Longitudinal Seam Weld Extending Upstream LU-I Longitudinal Weld Upstream on Inside of Elbow LU-O Longitudinal Weld' Upstream on outside of Elbow MSIV Main Steam Isolation Valve 1

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O Abbreviations - cont.

MS Main Steam System MSA Main Steam Auxiliary System MT Magnetic Particle Examination MWO Maintenance Work order Nondestructive Examination ENDE NI No Indication Nuclear Regulatory Commission NRC No Recordable Indication NRI OL overlay PL Pipe Lug PLT Plant PR Pipe Restraint PROD Product PS Pipe Support PSW Plant Service Water System PT Liquid Penetrant Examination Georgia: Power Company Quality Control QC RC Reactor Recirculation' System RCIC

. Reactor Core Isolation Cooling System RHR Residual Heat Removal System Residual Heat Removal Service Water System RHRSW RI.

Recordable Indication Recirculation Inlet Nozzle Thermal Sleeve Attachment-RINTSA RL Refracted Longitudinal:

)RL Restraint Lug-RPV Reactor Pressure Vessel e

RX Reactor RWCU Reactor Water Cleanup System SBLC Standby Liquid Control ~ System SCS Southern' Company Services SER Service SRV-Safety Relief Valve Torus Drainage and Purification System TDP TSB Turbine Steam Bypass-System Ultrasonic Examination UT VLV Valve VT Visual Examination This-list is comprised of standard abbreviations used in Inservice All of these abbreviations may not appear in Inspection Documentation.

this report.

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m L-TOTAL NUMBER OF' SHEETS 106 r's FORM NIS-1

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FORM NIS-1 OWNERS' DATA REPORT FOR INSERVICE INSPECTIONS As Required By the Provisions of The ASME Codes Rules

1. Owner: Georcia Power Comoany. 333 Piedmont Ave., NE.

P.O.

Box 4545.

Atlanta. Georaia 30302

2. Plant: Edwin I.

Hatch Nuclear Plant. Route 1.

Box 278. Baxlev GA 31513 3.

Plant Unit 2

4. Owner Certificate of Authorization (if req.) HLA
5. Commercial Service Date 09/05/79
6. National Board No. for Unit EZA t
7. Components Inspected:

Manufacturer State or Component or Appurtenance Manufacturer or Installer Province National or System or Installer Serial No.

Number Board No.

r Rx. Pressure Vessel Combustion Ena.

-70101 N/A 11570 Rx. Pressure Vessel Combustion Ena.

70101 N/A 211570 2B21 Main Steam Pullman Power Prod.

N/A N/A f-~

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2B21 Feedwater Pullman Power Prod.

N/A N/A_

2B21 M.S. Relief Pullman Power Prod.

N/A N/A 2B31 Rx.-Recirc Pullman Power Prod.

N/A N/A

.2B31 Recirc Pomo Byron Jackson N/A N/A

'2C11 CRD Pullman Power Prod.

N/A N/A 2C41 SBLC Pullman Power Prod.

N/A N/A

.2E11 RHR Pullman Power Prod.

N/A N/A 2E21 Core Sorav Pullman Power Prod.

N/A N/A 2E41 HPCI Pullman Power Prod.

N/A N/A 2E51 RCIC Pullman Power Prod.

N/A N/A Note:-

Supplemental sheets in form of lists, sketches, or drawings may be used provided (1) size is 8 1/2 in.

x 11 in., (2) information'in items l'through 6 on this data report is included on each sheet, and (3) each sheet is numbered and the number of sheets are recorded at the top of this form.

Spool piece of fitting numbers too numerous to list for each specific-system.

Material certifications for all piping, fittings, etc., are available for review in the Records Management

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Department at the plant site.

Exception taken to note 2.

cont. on next page 1

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7. Components Inspected (continued):

Manufacturer State or Component Appurtenance Manufacturer or Installer Province National or System or Installer Serial No.

Number Board No.

L2G31 RWCU Pullman Power Prod.

N/A-N/A

'2G41 FPC & CU Pullman Power Prod..

N/A N/A 2N11 M S Auxiliary Pullman Power Prod.

N/A N/A 2N37 Turbine Bvoass Pullman Power Prod.

N/A N/A 2P41 Plt Serv Water Pullman Power Prod, N/A-N/A 2T48 Cont. Purae Pullman Power Prod.

N/A N/A 1

Spool piece of fitting numbers too numerous to list for each-specific system.

Material certifications for all piping, fittings, etc., are available for review in the Records Management Department at the plant site.

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t FORM NIS-1 (Back)

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8. Examination Dates 09/04/89 to 12/12/89.

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9. Inspection Interval from 01/86 to 01/96.
10. Abstract of Examinations.

Include a list of examinations and a statement concerning status of work required for current interval.

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11. Abstract'of Conditions Noted.

1 Abstract of Corrective Measures Recommended and Taken.

L 12.

We certify that the statements made in this report are correct and the examinations and corrective measures taken conform to the rules of the ASME Code,Section XI.

Date 19 ~

Signed Georaia Power comoany By _,

Owner Certificate'of Authorization No.(if applicable) U/_A Expiration Date 846 e

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CERTIFICATE OF INSERVICE INSPECTION i

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l-l I, the undersigned, holding a valid commission issued by the

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_l l-National Board of Boiler and Pressure Vessel Inspectors.and/or the.

L l' State or Province of GA and employed by ****

of Hartford, CT have.

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l inspected the components described in this Owners' Data Report l:

l during the period.09/89 to 12/89 and state that to the best of my

l. knowledge and belief, the owner has performed examinations and taken

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l l corrective measures described in this Owners' Data Report in l?

D l~accordance with the requirements of the ASME Code,Section XI.

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l ll l By signing this certificate neither the Inspector nor his: employer ll

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l_makes any warranty,' expressed or implied,.concerning the h

l examinations and corrective measures described in this owners' Data L

neither the Inspector nor his employer shall be [

l Report.

Furthermore, l liable in any manner for any personal injury or property damage or a ll[

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.I loss of any kind arising from or connected with this inspection.

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I l Date 2 -20 N

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' W Commissions Georaia - GA00115 r

National Board, State, Province,& No.

l Inspector's Signature i

      • The following NIS-1 Form supplementary information and report includes the responses to NIS questions #10, #11, and #12.

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        • Hartford Steam Boiler Inspection and Insurance company.

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1 0-n NIS-1 Form Supplementary Information 1:., v Owners' Data Report'

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L for Inservice Inspection l

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Date:

February 9, 1990 Owner Name & Address:

Georgia Power Company.

333 Piedmont Avenue, N.E.

'c P.O.

Box 4545

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' Atlanta, Georgia 30302 Name & Address of Nuclear Generatina Plant:

Edwin I. Hatch Nuclear Plant Route 1, Box 278 Baxley, Georgia 31513

.Name Assioned to Nuclear Plant Station:

Edwin I. Hatch Nuclear Plant Unit 2

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Comme-rcial Service Date: September 5, 1979 Gross Generatina Capability:

.2436 MWt, 817.3 MWe i

State, Province, or Municioality Assioned Number:

N/A HAljonal Board Number Assioned by Manufacturer:

N/A 1

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-Name of Component-or Part of Comoonent ISI InvqlyAd

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Representative samples of the following components and areas were examined with nondestructive testing techniques.

. Class 1 Reactor Pressure Vessel Reactor Pressure Vessel Closure Head Main Steam Piping System Feedwater: Piping System Residual Heat Removal System Control Rod'Dr.tve System Reactor Recirculation System Core Spray System Reactor Water Cleanup System Valve Internal surfaces Standby Liquid Control System High Pressure Coolant Injection System Reactor Core Isolation Cooling System Class 2 RHR System Core Spray System HPCI System Control Rod Drive System Containment Purge and Inerting System Reactor Water Cleanup System Main Steam-Piping System 5

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Y System Pressure /Leakaae Tests Class Test Recuired System Reactor Pressure Vessel and-Associated-1 1 Hydrostatic Test.

Class 1 Piping and Components 1

1 Hydrostatic Test-

-SBLC.(2C41) 2 2 Hydrostatic Tests--

RHR (2E11)

(partial) 3 2 Hydrostatic Tests t

RHR (2E11) 2 4 Air Flow Tests RHR -- (2E11) 2 1 Hydrostatic Test Main Steam (2N11) 2 1 Functional Test-Core Spray (2E21) 12 1 Functional Test HPCI (2E41) 3 11 Pneumatic Tests Main Steam Relief (2B21) 2 1 Functional-Test PSW (2P41) 3 1 Inservice Test PSW (2P41) 3 13 Hydrostatic Tests-PSW (2P41) 3 l' Inservice. Test FPC (2G41)

Pioe Suecort & Hanaer Examination-Class l' Main Steam System Residual ~ Heat Removal System Reactor Core Isolation Cooling System

. Reactor: Recirculation System Reactor Water' Cleanup System Class 2 High Pressure Coolant Injection System Residual Heat Removal System Reactor Core Isolation Cooling System Main Steam System O

.-Class 3

' Main Steam Safety / Relief Valve Discharge System Plant Service Water System 6

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k Name & Address of Manufacturer of Comoonents:

1.-

Reactor Pressure Vessel and Closure Head:

. Combustion Engineering, Inc.

-Chattanooga, TN 2.

Piping (Classes 1, 2, and 3)

a. Pullman Power Products Division of. Pullman-Kellogg Williamsport, PA
b. General-Electric Company San Jose, CA-Note:

Piping purchased by General Electric and Pullman and installed by Pullman.

Material certifications and manufacturer information are available for review in the Records Management Department at the Hatch Plant Site, 3.

' Piping Supports and Hangers (Classes 1, 2, and 3)

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a. Bergen-Paterson Pipe Support Corporation Laconia, NH b..ITT Grinnell Corporation Providence, Rhode Island
c. Pacific Scientific Anaheim, CA 4.

' Valves, Pumps, and Heat Exchangers

a. Byron-Jackson, Inc.

Los Angeles, CA

b. Crane New York, NY
c. Wm. Powell Company Cincinnati, OH

-d. General Electric San' Jose, CA Date of Inservice Insoection:

7 September 1989 - December 1989

comolation Date of Inservice Insoection:

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December 12, 1989 Name of Inspector:

Donald R. Laakso (ANI/ANII)

Name:& Mailina Address of Insoector's Employer:

The Hartford Steam Boiler Inspection and Insurance Connany.

1117 Perimeter Center West Suite E 301 Atlanta, Georgia 30338 e

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ABSTRACT An Inservice Inspection of selected Class 1, 2

and 3 components at-Georgia Power Company's Edwin I. Hatch Nuclear Plant Unit 2 was performed during the Fall 1989 Maintenance / Refueling Outage.

The components were examined in accordance with the applicable ISI outage Plan, including.any changes made during the outage as approved by GPC.

This outage marked the end of the first 10-Year ISI Inspection Interval for E.I. Hatch Unit 2.

All examinations required to be performed during the interval were to be completed prior to 5-1-90.

Therefore all remaining first interval examinations were scheduled to be performed All examinations were completed and no first interval during the outage.

examinations were deferred.

The nondestructive examinations were performed using VT, PT, MT'and UT examination techniques.

SCS personnel and their contractors; Ebasco and In addition, GE GE_ performed NDE of the selected welds and components.

assisted SCS and Ebasco personnel with VT examination of selected RPV

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SCS NDE procedures were utilized for all ASME Section XI Examinations.

Ebasco and_GE personnel were qualified to the applicable SCS procedures and EPRI certified inspectors were utilized for) all examinations involving IGSCC susceptible materials.

SCS and C&L personnel performed Eddy Current Examinations of non ASME Section XI components per a request from GPC.

C&L procedures were utilized for the performance of the eddy current examinations.

In addition to NDE of Class 1 and 2 welds and components, pressure testing, visual examination of Class 1 valve internal surfaces and visual:

Third examination of pipe supports and hangers were_also performed.

party review (ANII) was utilized for all examinations of ASME Section XI components.

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. Selected components were examined in accordance with the following N. /

documents:

Section XI of the American Society of Mechanical Engineers (ASME)

Boiler and Pressure Vessel Code, " Rules for Inservice Inspection of Nuclear Power Plant Components," 1980 Edition with Addenda through Winter.1981.

United States Nuclear Regulatory Commission, NUREG 0313, Revision 2,

" Technical Report on Material Selection and Processing Guidelines for BWR Coolant Pressure Boundary Piping".

United States Nuclear Regulatory Commission, NUREG 0619, "BWR Feedwater Nozzle and Control-Rod Drive Return Line Nozzle Cracking".

United States Nuclear Regulatory Commission I&E Bulletin 80-13 Visual Examination of Core Spray Spargers.

General Electric Company Service Information Letter-433, Shroud Head Bolting Inspection.

SCS " Inservice Inspection Outage Plan, Edwin I. Hatch Nuclear Plant, Unit 2 1989 Fall Refueling Outage Revision 1, Deviation 001".

SCS "Second Ten-Year Examination Plan, Edwin I. Hatch Nuclear Plant' Unit 2."

United States Nuclear Regulatory Commission NUREG 0803, " Generic Safety Evaluation Report Regarding Integrity of BWR SCRAM System Piping."-

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United States Nuclear Regulatory Commission I&E Bulletin 80-13 Visual l

Examination of Core Spray Spargers.

Case N-479, Boiling Water Reactor (BWR) Main Steam Hydrostatic Test,Section XI, Division 1 Representative samples of the following systems, comprised of selected Class 1.,

2, and 3 components, were examined using various NDE techniques, in accordance with the above documents:

Class 1 Reactor Pressure Vessel (2B11)

Main Steam System (2B21)

Feedwater System (2B21)

Reactor Recirculation System (2B31)

Control Rod Drive System (2C11)

Standby Liquid Control System (2C41)

Residual Heat Removal System (2E11)

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Core Spray System (2E21)

High Pressure Coolant Injection System (2E41)

Reactor Core Isolation Cooling System (2E51)

Valve Internals fs

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Valve Bolting 10 s

Class 2 Residual Heat Removal System (2E11) lf}

Core Spray System (2E21)

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High Pressure Coolant Injection System (2E41)

Containment Purge and Inerting System (2T48)

Control Rod Drive System (2C11) l Reactor Water Cleanup System (2G31)

Reactor Core Isolation Cooling System (2E51)

Main Steam Auxiliary System Piping (2N11)

Turbine Steam Bypass System (2N37)

Class 3 Service Water System (2E11) (2P41)

Fuel Pool Cooling System (2G41)

Main Steam Relief Valve Discharge Piping (2B21)

Other - Augmented.

Eddy-Current Examinations were performed on the following components:

Unit 1 Feedwater Heaters 4A, 4B, 6A, 6B, 7A,,

7B, BA, BB, 10A, 10B, and the main generator stator water coolers and hydrogen coolers.

A separate report issued by C&L and distributed by SCS will include ;

all addy-current examinations.

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UT thickness. measurements were performed on selected components ~1n.the N

Extraction Steam and Condensate Feedwater Piping Systems.

A portion of these components were selected due to their similarity in design and operating conditions to components involved with the "Surry pipe break incident".. A separate report for-these examinations was prepared by SCS and was. submitted to GPC engineering.

Nine. (9) RHR welds, one _(1) Core Spray weld, one (1) HPCI weld, five (5) RCIC welds, one (1) RWCU weld and two-(2) CRD welds were examined using surface _ examinations-techniques (MT or PT) due to. augmented commitments made by GPC.

These exams are not required by the ASME

.Section XI Code due to.certain exemption criteria but are included.in the augmented section of the ISI Program.

'Seven (7) welds in the Class 3 section of the RWCU System outside of the outboard containment isolation valve were examined (UT) per NUREG-0313 per an augmented requirement by the NRC..

These welds were located-in portions of the_ piping system that are classified as non-safety related.

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CLASS 1 EXAMINATIONS

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7 RPV Examinations Four'(4) nozzle-to-shell welds and six (6) nozzle inner radius welds were examined using manual UT techniques.

No reportable indications were detected.

due to an The.RPV_ closure head-to-flange weld was examined (MT & UT) indication detected during the 1985 outage.

There was no significant change in the indication and it was deemed acceptable.

RPV Internal Examinations l

Per ASME Section XI, selected RPV internals were examined.

These examinations included portions of the vessel interior, interior attachments beyond the belt line region and within the belt line region and various RPV internal components.

All thirty-six (36) shroud head hold down bolts were UT examined per-GE I

SIL-433.

Two bolts (#13 and #34) had been previously noted as containing

- UT indications.

These indications were previously evaluated by GE and No new indications were detected and the previously deemed acceptable.

identified indications could not be reproduced during the inspection.

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)The following sections of this owners' Data Report contain the summary of

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i the NDE Examinations performed, provides additional information and _ gives results of those examinations, t

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Edwin I. Match Unit 2 1989 Fatt Refueling Outage Class 1 Components

'Page 1 of 29 RI REflNIKS/SASIC" NDE -

EXAft/ CAL.

ASME EXAM SETNIN PROCEDLNt(

SIEET NO.

NI NRI GEOM /0TNER -

Call 8AAT105 BLOCK SECTION XI EXAM CAT. NO.

F IG. 100.

EXAftlllAT105/ AREA RPV EMARINATIO_NS 64-H x

' NT-N-500/3 589N2n053 Indication froni-MT 81.40 A-3/03 2NC-2 X

UT-N-410/4 S89N2UO65 1985 was 45 Deg.

UT CLOSURE NEAD-TO-FLG 8-A

$89N2C077 UT Cat.

-DAC and thus NRI CENTERLifT STUD 1 TO x

S89H20084 STUD 20 (CW)

$89N2C076 UT Cat.

S89N2UO57 K

$89N20055 UT Cat.

61-N x

UT UT-N-410/4 589N2UO55 83.90 A-T/04 2N2B S89N2C054 UT CaI.

8 LOOP REClRCULATION X

8-D 589N2UO53 letLET NOZZ TO SHELL

$89N20053 UT Cat.

$99N2U052 X

$89N2CO'2 UT Cat.

62 N UT-N-410/4'

$89N20214 x

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83.90 A-1/04 2N3C S89H2C168

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C LOOP MAIN STEAM S-D S89H2U218 x

OUTLET SNELL T0 NOZZ S89N2C175 UT Cat.

589N2U216 x

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Edwin 8. notch tmit 2 1989 Fatt Refueling Outsee Ctess 1 Compsonents Pope 2 of 29 ASME ERfue uBE EM m/ CAL.

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Edwin I. Match '.Anit 2 1989 Talt Refueling Outage Class 1 Congenents Page 5 of 29 ESME SECTION MI EMM EMAN ISE erase / CAL.

El RE8uMMCSteASIC CAT. NO.

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PROCESIDE

$NEET 50.

WJ WRI GEGIVOTHER CAlt9AAfl0N BLOCK FEEDtmTER SYSTEM (Cont'd) 89.11 A-13/03 2321-1FW-185-7 UT UT-n-400/8

$99W24066 K

46-#

O-J PIPE TO TEE NT MT-#-500/3

$89N20165 K

$8942C136 UT Cat.

$89N2U187 UT Thickness i

89.11 A-38A/O 2u21-2TW-18A-2 UT UT-M-400/8

$89N2NO33 N

TT M O-J TEE TO PIPE mi MT-N-500/3

$89W2u285 x

optionetty S89u2C215 UT Cat.

tegr:xted to 589u2U286 N

Class 1 I

$89W2C216 UT Cat.

t l

f l

s9.11 A-38A/00 2m21-27W-18A-3 UT UT-N-400/8

$89N2M060 x

i PIPE TO VALVE MT MT-N-500/3

$89n20065 x

TT-n e-J

$89M2C065 UT Cat.

OptlonetIy S89u2OO68 x

upgraded to

{

S89N2C068 UT Cat.

Class 1 i

$89M2U131 UT Thickpess Malm STEAft SYSTEM I

8/.50 A-5/01 2821-1mS-8A 85R-278 vi vi-M-710/2'

$89M2V144 SAT

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l Edwin I natch LWiit 2 1989 Fett Refueling Outoge i

Class 1 Components Page 6 of 29 cm SECTION XI EmmM EMAM NDE EWW4/ CAL.

El RfaMAES/9A$lt CAT. NO.

FIG. 20.

E3LNt!IIATIM/W IETuls PROCEgyltE SuEET 50.

ul art Gest /0THER CAL 18Enflou 8 LOCK l

14AIN STEAM SYSTEM (Cont'd) 89.11 A-5/01 2s21-1 sis-8s-est-1 UT UT-n-400/8 580m2M088 m

81 #

l S-J BRANCM ComuECTION MT MT-N-500/3 589m2n090 m

Lineer indication

$89N20274 X

detected. See TO PIPE 58942C206 UT Cat.

58942m090. Acceptable sS9n2U275 m

af ter sectronicat I

l 58942C207 UT Cat.

renowet.

I 87.50 A-5/01 2s21-1MS-as-tsa-2FS vi VT-e-710/2 589u2v145 sat 8-G-2 FLANGE 80LiteG i

99.11 A-5/01 2521-19tS-8C-Asst-1 UT UT-n-400/8 589u2N089 x

81-m i

e-J 3RANCn rrum8CTION NT MT-N-500/3 589n2u277 x

589u2C289 UT Cat.

TO PIPE S89n2UZT6 M

I

$89u2C208 UT Cat.

87.50 A-5/01 2821-1MS-8C-ssa-2F8 VT VT-n-710/2 589u2v146 SAT 8-G-2 FlamGE SOLTimG N

0 O

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Edein t. notch tmit 2 1989 Fatt aefuelins cutage Ctess 1 r w s Page 7 of 29 ASME SECTien XI ENast Ouse age EMAN/ CAL.

El SEMMMCS/9ASIC CAT. NO.

FIG. 30.

DIMilIIATIW/AN.A IETul3 PROCEDURE SnEET an, u[

us,1 E UR/0THER CallenAffas stout

~

I

{

MAIN STEAft SYSTEM (Cont'd) 39.11 A-5/01 2821-18tS-5C-CSR-1 UT UT-n-400/8

$89N3e015 x

81-#

3RANCN ComuECTION TO MT NT-N-500/3

$8942u034 m

8-J

(

$89n20034 UT Cat.

l PIPE r

$89n2UO33 x

I 589420033 UT Cat.

l ST.50 A-5/01 2821-1MS-80-852-2FS VT VT-n-710/2

$89#2v147 Sai O-G-2 FLAsNiE BOLTieG i

CORE SPRAY SYSTEN 99.11 A-24/03 2E21-1CS-104-5 UT UT-n-400/8

$89n2u017 x

137-a 0-J EL50W TO PIPE MT NT-N-500/3 589#2U001 X

$8942C001 UT Cat.

89.11 A-25/03 2E21-1CS-10s-3 UT UT-n-400/8

$89u24816 x

137-n 0-J VALVE TO PIPE MT NT-n-500/3

$89m2UO46 x

$8942C066 UT Cat.

S89N2UO67 X

$89u20047 UT Cat.

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EWut/CA*...

RI REIWIAKs/9As1C CAT. 50.

FIG. 50.

ENmelsenTitm/m sETED PeoCE8tmE SIEET E0.

WI g,I GEGE/0TNER CAllGRATION SLOCK 1

VALVE BOLTING 87.70 A-26/03 2E41-F002 VT vi-N-710/2 589M2V148 SAT.

3-G-2 87.70 A-27/05 2E31-F007 WT VT-n-710/2 589u2v108 SAT.

B-G-2 8T.TO A-2T/05 2E51-F008 VT VT-N-710/2

$8942v100 sat.

B-G-2 REACTOR WATER CLEAIRP SYSTEM 89.32 A-38A/0 2G31-1aWCU-3-5 MT NT-n-500/3 sS9u2M098 x

new weld, 0-J PIPE TO BRAflCN cptionetty ComuECTICII t, graded to Ctess 1.

aEACTOR C00UWT PtsEPs 810.20 A-4/02 2RC-9 PUMP LUG-1 PT PT-N-600/2 589u2P011 x

B-K-1 B10.20 A-4/02 2RC-8 PUMP LUG-1A2 PT PT-N-600/2

$89n2PO!2 x-8 t-1 N

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- 1989 Fet t Refueling Outage -

Class 1 Cagenents Page 12 of 29 I

~

l s

gg EXAM WE ERAM/ CAL.

RI NEamaKSteASIC SECTION XI E30s:

CAT. NO.

FIG. 110.

ENMlim4THM/ MEA MTNW PROCEDWE SMEET NO.

NI IRI GEtm/CTE R CALi p flge SLOCK g

="c-0313 EXAftINATI(NIS (Cent'd3 e5.50 A-10/03 2821-1FW-12AS-11 UT UT-n-409/5 589u2P031 x

53-n, 78-n TRAftSITION PIECE TO PT PT-N-600/2 589N2U114 x

3-F S89u2C097 UT Cat.

(03130)

SAFE-END ENTENSION S89N2U118 X

$89N2C101 UT Cat.

S89u20167 x

$89n2C138 UT Cal.

89.11 A-10/03 2821-1FW-12As-12 UT UT-n-409/5 589n2P030 m

78-n SAFE-ESID ENTENSION PT PT-N-600/2

$89n2U168 X

3-J

$8942C139 UT Cat.

(03130)

TO SAFE-TND i

1 85.50 A-10/03 2s21-1FW-12As-13 UT UT-M-409/5

$89n2P029 x

53-n, 78-N SAFE-END TO PT PT-N-600/2 589n2u115 x

g-F

$89M2C098 UT Cat.

(C3130)

TRAstSITION PIECE 589n2U119 x

i i

589M2C102 UT Cat.

$8pn2U169 x

.S89W2C140 UT Cat.

l t

N

.~...

Edwin 1. Hatch (mit 2 1989 Fet( NefueOrig (hetage Class T Camponents Page 13 of 29 RI REmeAIs/SAstC ASME EMAR NDE EMAN/ CAL.

CAT. WO.

FIG, NI?.

EWpull4TIOR/ AREA METuop Pe0CEptAE saEET 90.

El 31 GEOR/OfnER CAttORATION BLOCK SECTION XI EMAn muREG 0313 EMAntaAf t0NS (Cont'd) -

53-N, 78-N e5.50 A-11/06 2s21-1FW-129C-11 UT UT-N-409/5

$89u2P036 x

PT-M-600/2 MM N

TRAmstTION PIECE TO PT 3-F s89M2C081 Ut Cat.

SAFE-ELD EXTENSION (03130) ss9n2U124 N

$89u2C10T UT CaI.

$P%11103 x

$89u2C006 UT Cat.

78-#

39.11 A-11/06 2521-1FW-129C-12 UT UT-n-409/5 589u2P03T x

SAFE-Emp EXTENSION 3-J PT PT-N-600/2 589n2Ue99 X

s-J SWW2C082 UT Cat.

SAFE-END ENTENsl0N (03130) 53-w, 78.n 33.50 A-11/04 2821-1FW-12eC-13 UT-UT-N-409/5 589n2P038 x

PT PT-N-600/2 s99u2ut00 x

SAFE-E W TO 8F

$89n20083 UT Cat.

TRANstTION PIECE (031303 sS9n2U106 X

589N2C08T UT Cat.

s89#2U125 N

s99W2C108 UT Cat.

(#3 (A

~

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Edwin 1. Metch unit 2 1989 Fall Refueling Outoge Class 1 Components Page 14 of 29 ASME ENAM MDE ENAft/ CAL. -

RI SEmeRES/9ASIC SECTion NI EMAse CAT. NO. _

FIG. NO.

[JIMIlg4 TIM /4REA g

PROG,0W(

S E T NO.

3,I.

M GE(34/0TutR CAL 15EATI(pl $ LOCK _

uuREG 0313 EIUWilNATIONS (Cont'd) e5.50 A-11/04 2821-1FW-129D-8 UT UT-N-409/5 589W2P039 X

53 n, 78 n i

TRastSITION PIECE TO

.PT PT-N-600/2 589u2U122 N

j s-F 589N2C105 UT Cat.

(03130)

SAFE-ENO ENTENSIOm S89u20101 X

S89N20084 UT Cat.

$89n2UO95 M

S89u20078 UT Cat.

39.11 A-11/04 2s21-1FW-12so-9 UT UT-n-409/5 589u2P041 M

78-M SAFE-END ENTENSlon PT PT-M-600/2 589u2UO96 x

g-J S89u20079 UT Cat.

f (03130)

TO SAFE-Emo l

e5.50 A-11/04 2821-1tW-12sD-10 UT UT-n-409/5 S89u2P060 x

53-M, 78-M I

B-F SAFE-END TO PT PT-M-600/2 589u2U102 x

$89n20085 UT Cat.

(03130)

TRAftSITION PIECE

$8942U123 x

$89u2C106 UT CaI.

S89n2UO97 x

$89N20000 UT Cat.

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Edwin I. Match Unit 2 1989 Fett Refueling outege Ctess 1 Ccugenents i

Pope 16 of 29 i

ASME SECTION MI EXAM ExAN upE ERAN/ CAL.

EI

  1. ENA8KS/9ASIC CAT. 800.

FIG. WO.

ERMIINATI(m/m 4iu@

PROCEDLEE SIEET a0.

ul W1 GE(m/01NER CAL!ORAT10N 8 LOCK NUREG-0313 EMAHINATIMS (Cent *d) 85.13 A-14/02 2831-1RC-12AR-F-5 UT UT-n-609/5 58942P005 x

85-W, 106-W 8-F S-E TO Is0ZZLE 2x2F PT PT-M-600/2

$89M2UO19 m

S89#20019 UT Cat.

(3313C)

INSI 1986 S89N2UO25 m

S89M2C025 UT Cat.

i S89M2UO22 X

589u2CO22 UT Cat.

85.10 A-14/02 2831-1RC-12AR-G-5 UT UT-n-609/5

$89N2P004 x

85-#, 106-n 8-F S-E TO IIOZZLE 2ts2G PT PT-M-600/2 589u20005 x

589#20002 UT Cet.

(0313C)

INSI 1986 589N2U006 x

$89N2C006 UT Cat.

S89n2Uo07 x

$89u20003 UT Cat.

55.10 A-14/02 2831-1tC-12AR-M-5 UT UT-n-609/5 589N2P008 x

85-8, 106-N S-F S-E 10 n0ZZLE 2N2M PT PT-M-600/2

$89n2Uo02 x

S8pn20016 UT Cat.

- (0313C)

INSI 1986

$89#2U003 x

$89u20014 UT Cat.

$89u2U006 m

589u2 COTS UT Cat.

(,3

%/

Edwin I. Match Unit 2 T

1999 Fett Refueling Outage Ctess 1 C W s Psee 17' of 29.

u.

LSNE SECTION MI ERAM EMAN WDE ERAM/ CAL.

RI REMARKS /SASIC CAT. NO.

FIG. No.

ERMeleATI(m/anEA 8ETNW PROCEDURE SuEET NO.

E M

GEWE/OfuER CAtlgAATION BLOCK NUREG-0313 EMAMinATI(MS (Cant'd) e5.10 A-14/02 2s31-1RC-12AR-J-5 UT UT-n-409/5 589u2Poe9 x

85-#, 108-w S-E TO N0Z2LE 2n2J PT PT-n-600/2 589n2Uo23 x

8-F

$89u20023 UT Cat.

(0313C)

IMSI 1986 S8942UO26 N

$89n20026 UT Cat.

g29n2UO20 N

$89n2C020 UT Cat.

i 83.10 A-14/02 2 31-1RC-12AR-K-5 UT UT-M-409/5

$89u2P010 x

85-n, 108-M S-E TO N0ZZLE 2w2K PT PT-n-600/2

$89u2U828 x

s-F

$89n20028 UT Cat.

i' (0313C)

Inst 1986 S89#2UO30 X

589u20030 UT Cat.

58942WO32 x

$8942CO32 UT Cet.

l 85.10 A-15/02 2831-1CC-12ea-A-5 UT UT-N-409/5 589#2P001 X

85-#, 108-N S-E TO N0ZZLE 2#24 PT PT-#-600/2

$89u2UO10 m

l s-F 58952C007 UT Cat.

i (0313C)

InSI 1986

$89n2UO98 M

589n20006 UT Cat.

S89n2Us99 x

589n20005 UT Cat.

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v Edein I. notch tmit 2 1989 Fat 1 Refuelirig Outage i-Class 1 Components Page 18 of 29 i

LSME

'EMAN ISE Elups/ CAL.

at aEmmutStenstC sECTION MI EMApe CAT. 40.

FIG. 50.

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mi up, et unt EMTNER W IgeaffW SLOCK

==cc-0313 EMAIIIIIATICII5 (Cant'd) e5.10 A-15/02 2831-1tC-1298-8-5 UT UT-n-409/5 58942P002 x

85-#, 108-n

's-F s-E TO N0ZZLE 2N28 PT PT-n-600/2 ss9u2UO11 M

i

$89u2C010 UT Cat.

j (0313C)

Inst 1986 I

s99u2UO13 X

i 589u2C012 UT Cat.

f 589#2UO12 x

s89u20008 UT Cat.

35.10 A-15/02 2s31-tec-12eR-C-5 UT UT-n-409/5 589u2P903 x

85-n, 108-4 j

s-E TO N0ZZLE 2u2C PT PT-n-600/2

$89n2UO15 x

3-F I

s pu2C889 UT Cat.

(0313C)

Inst 1986 S89u2UO14 X

589u2C011 UT Cat.

589u2US16 M

589u20013 UT Cat.

l 85.10 A-15/02 2s31-tec-12se-0-5 UT UT-n-4 W/5 spu2 Pee 6 x

85-n, 108-n s-E TO IIOZZLE 2n2D PT PT-n-600/2 589u2U024 x

5-F N

UT Cat.

(C313C)

Inst 1986 589u2US21 x

$89u2C021 UT Cat.

389u2UOT8 m

sS9u20018 UT Cat.

00

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Edwin 1. notch Unit 2 1989 Fett Refuelins Outsee Class 1 r w s Pese 19 of 29 iM

?

SECTION MI EXAM ExAft NDE EIUWI/ CAL.

RI aEmants/emSIC CAT. No.

FIG. up.

Dustl e TI0lt/AAEA MTuts PROCEntaE SIEET up.

u_1 El EEGt/0TMER CAllgAATI(W BLOCK uunEG-0313 ExAflINATIONS (Cont'e 85.10 A-15/02 2831-1eC-129R-E-5 UT UT-n-409/5 58vn2P907 x

85-n, 108-n e-F S-E TO N0ZILE 2m2E PT PI-n-600/2 589n2UO29 x

589n20029 UT Cat.

l (0313C)

Inst 1986

$89n20031 x

$89n2CO31 UT Cat.

$8942U027 Jt

$89n2CO27 UT Cat.

85.10 A-16/03 2531-1tC-284-1 UT UT-n-409/1

$89n2P017 x

29-n, 84-n e-F N022LE 2W1A TO S-E PT PT-n-600/2

$89n2UOTS X

4

$89u20066 UT Cet.

f (0313C)

Inst 1986

$89n2UOT6 x

$89n2C068 UT Cet.

S89n2UO74 x

589n2C070 UT Cet.

85.10 A-18/03 2e31-1ec-28s-1 UT UT-n-409/5

$89n2P020 x

29 n, 86-n 5-F IIOZZLE 2N18 TO S-E PT PT-N-600/2 S89u2U0F5 m

$89n2C871 UT Cat.

(0313C)

Inst 1986

$89n2WOTT x

$89n2C969 UT t,at.

$89n2Uer9 x

$89u20067 UT Cat.

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SECTION MI EMafe CAT. NO.

FIG. 50.

Em!NATIM/M IETNp NSL2E WT W.

31 31 E M ER CAlt W its SL W samEG-0313 EMAfileAT1W5 (Cont'd)

' 35.10 A-1/06 2C11-1 Cap-3-R-1 UT UT-n-409/5

$8942P060 x

97-#, 78-#,

2n9 N0Z2LE TO Cap PT PT-N-600/2 S8942U269 x

120-N, 53-N S-F S89n2C205 UT Cat.

(03130)

$89N2U264 x

i

$8942C200 UT Cat.

S89N2U263 X

$89u2C199 UT Cat.

$89n2U261 UT Thickness 39.11 A-21/03 2E11-1RNRee-20RS-1 UT UT-n-401/7 S89u2P025 x

130-w TEE TO PIPE PT PT-h-600/2 S8942UO36 K

s-J

$8942C036 UT Cat.

(0313A)

S89u2UO35 x

$89W20035 UT Cat.

589u2U181 UT Thickness 55.50 A-21/03 2E11-1RNRM-20RS-3 '

UT UT-n-409/5 589n2u289 N

130-w, 51 n

$8942C217 UT Cat.

EL90W TO PIPE 0-F 589R2U292 N

i (0313C)

S89n2C219 UT Cat.

589n2U290 N

$89n2C218 UT Cat.

b

$8m!u291 UT Thickness

+

9' w

e w

w m.

s--

a*

a m

m.

2

.m

____,__m__m-______.__

u._._m-.___.m_...m_,m__ _,. _ _ _... _ _.. - _ -.

._m____m._,._.m____m.

.-.m

^

g

, 'p.

(.wY-Edein I. Watch Unit 2 1989 Fett Refueling Outage Ctess 1 r w ts Page 22 of 29 ASME ENAR WE EMAft/ CAL.

El RE8mRES/9ASIC.

SECTION XI

' EMAft CAT. u0.

FfG. 50.

OlNIlm4TItm/W IETEW PROGptM SIEET 30.

E M

Est/0 TIER CALI M Afl W SLM X l

uuREG-0313 EMAfflIIRTICBIS (Cent'd) 85.50 A-22/03 2E11-1tuist-244-10 UT UT-N-409/5 589N2U280 M

131-#, 12-#

58952C211 UT Cat.

D-F PIPE TO EL90W 589N2U267 x

(0313C) 589N2C203 Ut Cat.

589n2U265 x

589N2C201 UT Cat.

(03130) 2u2A UT UT-n-415/3 589u2uo37 x

125-n

$99N20037 UT Cet.

RINTSA E LD (03130) 2n2s UT UT-n-415/3 589e2U038 x

125-M 589n2CO38 UT Cat.

AluTSA E LD i

(03130) 2s2C UT UT-N-415/3 589n2ue39

.x 125-w

$99u2CO39 UT Cat.

AlWTSA WELD (03130) 2N2D UT UT-N-415/3 Spu2uo60 m

125-n

$89N2C060 UT cal.

RINTSA WELD (03130) 2u2E UT UT-n-415/3 58en2UO41 M

125-#

i

$89m2C041 UT Cat.

alNTSA WELD I

Aru

~

~.. -

m

'%d E&in I. Match Unit 2 1999 Fatt Refueling Outoge Ctoss 1 Components Page ?3 of 29 ASME ENAM NDE EXAM / CAL.

RI 804AAKS/SASIC.

SECTION MI EMAN CAT. WO.

FIG. 50.

DWIINTItm/W sETag PEOCEMME SIEET 50.

ul

uRI, EE(m/0THER CAllgAATim SLOCK j

1 uuREG-0313 EMAftinATIGES (Cant'd) j 35.50 A-23/03 2E11-1 Ream-248-10 UT UT-N-409/5

$89u2U279 N

131-n, 12-#

$89N2C212 UT Cat.

PIPE TO Ett0W B-F S89u2U268 x

(0313C) 589u2C204 UT Cat.

S8942U266 x

$99N2C202 UT Cat.

85.50 A-24/03 2E21-1CS-104-20 UT UT-n-400/8

$89u2P028 x

137-W

  • 1PE TO SAFE-END PT PT-N-600/2

$89u2PO42 x

monrelevant 8-F Roirded irreieetion 589n2U200 x

(1313D) 589n2C162 UT Cat.

detected. See 58952U1M UT Thickness

$99u2PO=J.

35.10 A 24/03 2E21-1CS-10A-21 UT UT-n-409/5 589N2P027 x

78-#

SAFE-END TO N0ZZ1E PT PT-N-600/2

$8942U129 x

O-F 589u2C112 UT cal.

(23130)

S89n2U130 x

$89u2C113 UT col.

589N2U201 UT Thickness

$99N2U188 UT Thickness

.b De

g

~] l J.

G J

Edsin I. Match unit 2 1909 fatt Refueling Outoge Ctoss 1 Cemenonents page 26 of 29

~,..

,a AsqE EMAft WE Eman/ CAL.

at mEMASES/SASIC SECTION xl ERM CAT. NO.

FIG. WD.

EMNIIMTIW/M ETNW P90CE9tmE SEET E 31 mi Etm/0TER CALim ATi m aLot*

uumEG-0313 ExistINATIONS (Cant'd).

133-N j

99.11 A-28/03 2G31-teuttse-6-D-1 UT U1-n-401/7 58942POTO M

ORANCM ComuECTION PT

. PT-N-600/2 58942u250 x

3-J 589u2C192 UT Cat.

TO PIPE (0313A) 199u2U248 M

589n2C190 UT Cat.

89.12 A-28/03 2C31-1eutuM-6-D-1LD UT UT-N-401/7

$89u2P069 x

133-n LONGITUDtWAL SEAlt PT PT-N-600/2 seen2u269 x

8-J 58942C191 UT Cat.

(0313A)

WELD ENTEMING DOWNSTREAft I

numEG-0619 ERMINATIONS i

C3.100 A-1/06 2W4A UT UT-N-480/3 589u2U153 x

41-M s89n2C120 UT Cat.

N0ZZLE Im 8-0 i

83.100 A-1/06 2n68 UT UT-N-488/3 s89n2U152 X

61-M

$89u2C130 UT Cat.

eDZ2LE It

' 8-D G3.100 A-1/06 2u4C UT UT-n-480/3 589u2U197 x

61-M

$8952C1d*)

UT Cat.

N0ZZLE IR 9-D b

A

f I

d V

(f Edein 1. Match Unit 2 1989 Fett Refueling Outege Ctess1 r W s Page 25 of 29 i.

(.SfEE ENAft ISE ERM4/ CAL.

RI REmAINLS/9ASIC SECTION MI EXAft CAT. NO.

FIG. NO.

14MuenTIWW ETIES PROCEDutti SmEET N0.

51 g

Est/cinER CAtttRAfl0E SLOCK uuREG-0619 EIUWete4TIGIS (Cant'd) l C3.100 A-1/04 2tmo UT UT-n-480/3

$89u2U151 x

61-w 589#2C131 UT Cat.

e-0 N0ZZLE It A-1/04 2e64 UT UT-N-481/1 58942U189 M

62-#, 53-#

$89#2C150 UT Cat.

STRAIGHT

$89N2U161 N

CTLluDRICAL SORE

$89n2C132 UT Cat.

589u2U193 M

$89u2C154 UT col.

A-1/04 2r%e UT UT-N-481/1 589u2U194 x

62-M, 53-#

S89W2C155 UT Cat.

STRAIGeff

$89M2U190 x

CYLleSRICAL SORE SDW2C151 UT Cet.

i

$89#2U162 x

$8942C133 UT Cat.

A-1/04 2tkC

. UT UT-n-481/1 589n2U163 N

62-n, 53-N

$99N2C134 UT Cet.

STEAIGMT

$89#2UI91 X

CTLle0RICAL BORE S89#2C152 UT Cat.

S89n2U195'

-N 589n2C156 UT Cat.

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Edwin I. notch Unit 2 1989 Fett Refuelins utsee o

Ctess 1 Conquenents P m 28 of 29

. - : = -

w' l

~

I ASME i

ENicI ISE ERAm/ CAL.

R$

SEIGMNtS/SASIC SECTION MI ERAM CAT. 110.

FIG. up.

EMMIMTIm/m IETW PROGEptaf SEET E0.

El IE,,1 EtNt/OTHER CALIMATItNI SLS E e.

f

==rc-0619 E=_ammiles (Cant'd) i 39.11 A-10/03 2521-1FU-12As-15 UT UT-n-400/8 s8 m!no63 x

53-N TRAIISITION PIECE TO mi NT-N-500/3 ss9W2ut09 x

Inefication acceptstrie S-J 589#20092 UT Cat.

ty code.

IIOZ2LE s89u2U196 x

S89n2C089 UT Cat.

39.11 A-11/06 2821-1FW-12eC-10 UT UT-N-400/8

$8942R056 X

56-n, /0-n PIPE TO TRANSITION MT NT-n-500/3 589u2u120 x

e-J S89N2C103 UT Cel.

PIECE l

$99R2U127 X

S89N2C110 UT Cat.

89.11 A-11/04-2s21-1FW-12sc-14 UT UT-n-400/8 58942n955 N

53 #

TRANSITION PIECE TO MT NT-n-500/3 ss9n2U135 m

s-J

$89N2C116 UT Cat.

TRAIISITicII PIECE 89.11 A-11/06 2s21-1FW-12ec-15 UT UT-n-400/8 589N2u854 x

53 n TRAustTION PIECE TO MT

  1. T-n-500/3 sS9u20133 x

s-J 389u2C114 UT Cat.

IIOZZLE

$8952U136 x

A sS9 2e11r UT eat.

[

a

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p I

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I" 49

VISUAL EXAMINATION OF CLASS 1 VALVE INTERNALS 4

This section provides a summation of the ASME required visual examinations of Class 1 valve internal surfaces.

These examinations were performed on eleven (11) valves that were disassembled for maintenance during the 1989 Refueling Outage.

The examinations were performed by Georgia Power Company Quality Control Inspection personnel

==

in accordance with GPC Procedure 45QC-INS-012-0S.

Listed below are the valves examined, the associated MWO number and a brief summary of the results.

VALVE NUMBER MWO NUMBER REMARKS 2B21-F010A 2-89-3104 Steam cuts in hinge pin area, 2-89-4858 LLRT failure 2B21-F022B 2-89-4772 LLRT failure 2B21-F028D 2-89-4771 LLRT failure 9

2B21-F077A 2-89-5490 LLRT failure 2E11-F017A 2-87-5208 Disassembled for IEN 89-01 2E11-F017B 2-89-5060 Disassembled for IEN 89-01 2 Ell-F050A 2-89-1003 Disassembled for TNPO SOER 86-03 2 Ell-F050B 2-89-5205 LLRT failure 2E21-F006A 2-89-1005 Disassembled for INPO SOER 86-03 2E32-F001B 2-89-1944 Disassembled to repair packing leak 2G31-F004 2-89-3834*

Disassembled per engineering commitment concerning back seated valves

  • MWO did not require initial or final ANII review.

O 50

l O

Visual Examination of Class 1 CRD Bolting ASME Section XI requires examination of the CRO Housings (bolts, studs and nuts) whenever the housings are disassembled.

Fifteen (15) CRDs were replaced during the outage which facilitated visual examination (VT-1) of the bolts, studs and nuts.

The subject examination were performed by GPC Q.C. personnel in conjunction with the CRD maintenance / replacement activities.

Listed below are the-CRDs which were examined and the associated MWo numbers.

C.RD E

GED E

26-31 2-89-2499 10-35 2-89-2498 34-23 2-89-2507 10-31 2-89-2506 26-47 2-89-2493 42-43 2-89-2494 18-31 2-89-2505 14-07 2-89-2501 18-43 2-89-2495 34-35 2-89-2497 22-11 2-89-2500 34-39 2-89-2496 14-15 2-89-2503 38-15 2-89-2504-14-11 2-89-2502 No rejectable indications were noted from any of the examinations.

e O

51

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i 1

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CLASS 2 EXAMINATIONS h

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- Edwin T. Hatch thit 2 4

1989 Fatt Refueling Outage Class 2 Components Page 1 of 9 ASME RI REMARES/ BASIC i

EXAM NDE Ex4M/ CAL I

SECTION XI EXAM CAT. No.

FIG. No.

ExAMINATI(NI/ AREA IETu(B PROCEDURE SNEET NO.

M1 NRI GEOM /0THER CAL 1gRATION BLOCK -

i RESIDUAL HEAT REMOVAL SYSTEM C3.20 8-18/C5 2E11-2RNR-168-DS-8PS-1 MT -

MT-N-500/3 589N2M100 x

Linear Indication

. detected. See INF' S89N2M102 x

DEVICE

$89M20300 UT Sizing I89n2022. Acceptabte-CC

(

2E11-RNR-A58

(

S89u20301 UT Evaluation per Para. 21 of ASpE Material Specification -

i for SA-106 C3.20 5-18/05 2E11-2RNR-168-DS-8PS-2 MT MT-H-500/3

$89u2M101-x

-DEVICE C-C 2E11-RNR-A58 C3.20 5-32/03 2E11-2RNR-208-PD-8-1PL-1f

~ MT MT-H-500/3

.S89N2M001-

'x Indication acceptable by coda.

DEVICE 2E11-RNR-M190 C-C C3.20 8-32/03 2E11-2 Rut-208-PO-8-1PL-2

.MT MT-N-500/3

$89n2M002 x

DEVICE 2E11-RNR-M190 C-C C3.20 8-32/03 2E11-2RNR-208-PD-8-1PL-3 MT MT-H-500/3 S89N2M003 x'

DEVICE 2E11-RNR-H190 C-C

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C.

5 5

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x x

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l l

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t t

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C C

C E E T

T T

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x x U U

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N t-u 6 9 7 0 8 7 2 2 3 3 9 0 _

0 5 9 6 9 0 4 4 4 4 6 7 M

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A n

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n E

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C

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(

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1 2 9 2

I

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L t

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I T

t E R E n O e

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S a 2 u

i T

R 4

Y R

R O R

2 O n

S 2 E 2 T 2

T i

C E

1 M

L 1

I 1

E 1

V 1

E A

A 1

V 1

P 1

L X

V E E E

I E A E E 2 T E

O 2 D 2 P 2 V M

ER TA EM 2

O L

3 3

1 0

N A

0 0

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/

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/

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m, f

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- Edein I.~ Metch thit 2

_ 1989 Fall Refueling Outage Ctess 2 C,

-..;s Page 3 of 9

...(

AS8E Rt REMAAKS/SASIC l

ENAR ISE -

ERAM/ CAL SECTION XI EXAM.

CAT. 40.

FIG. No.

ElWWilHAfteII/ AREA gigg Mt0RDUIIE SMEE7 NO.

E 31 GECM/0THER CAllORATION OLOCK RES!"* NEAT m'"_

SYSTERI (Cont'd)

C5.11 a-19/03 2E11-2 Rut-60-RVD 19 MT NT-N-500/3 589u2M034 x-EL90W TO PIPE -

C-F

. f Cone SPRAY SYSTEM

}

C3.20 5-59/03 2E21-2CS-128-5PL-1 mi.

MT-n-500/3 589n2n024 -

x t

DEVICE 2E21-CS-#17 C-C C3.20 e-59/03 2E21-2CS-128-5PL-2 MT -

.' MT-u-500/3 -

S89u2M625 x-DEVICE 2E21-CS-N17 C-C C3.20 B-59/03 2E21-2CS-128-5PL-3 mi

- ni-N-500/3 589#2n026 x'

s 0EVICE 2E21-CS-N17 C-C

+

C3.20 a-59/03 2E21-2CS-128-5PL-4 MT MT-N-500/3'

$89n2n027 x

DEVICE 2E21-CS-N17 C-C C3.20 8-63/03'

.2E21-2CS-208-TS-12PS-1 MT NT-u-500/3 589n2no69

_x.

i DEVICE 2E21-CS-N705 C-C I

Un

.-, a -

-x

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~

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n n

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y,m

);

.Edwin I. natch unit 2 1989 Fall Refueting Outage Ctess 2 Camponents

-.Page 4 of 9 ASME RI REnlWIKS/ BASIC.

ExaN tee EK98/ CAL SECTION xl EXAM CAT. NO. _

FIG. NO.

EXAMINATI(NI/A8EA MTN(5 PROCEDLRE SEET Wo.

E

.E GECNt/0THER CAttgEATION BLOCK CORE SPRAY SYSTEM (Cont'd)

C3.20 8-63/03 2E21-2CS-208-TS-12PS-2 MT MT-N-500/3 589u2M050 x

k

-DEVICE 2E21-CS-N705 C-C C3.20 8-64/03 2E21-2CS-208-TS-17PS NT NT-N-500/3 589n2M028 x

DEVICE 2E21-CS-N703 C-C C6.10 8-2A/00 2E21-2CS-POP-8-1 MT

~ MT-H-500/3 589M2M099 x

FLANGE TO ELBOW C-G i

CORE SPRAY PL5F S HIGN PRESSURE COOLANT INJECTlom SYSTEM C5.21 8-16/03 2E41-2MPCI-8A-SS-4

' MT

'MT-N-500/3 589n2M061 x

52 n

'45-DEGREE EL8OW TO UT-UT-R-400/8 S89N2UO64 x

C-F

$89M2C064 UT Cat.'

PIPE 589M2UO66 UT Thickness S89N2U182 UT Thickness 961 of wetd C3.20 8-67/02 2E41-2HPCI-10-0-13PS MT' MT-H-500/3.

S89W2M051 x

. esamined due DEVICE 2E41-NPCI-A65 CC to configuration.

Ill 6)

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m Edwin I. Netch unit 2 1999 Felt Refueling Outege.

~

Ctess 2 Components Page 5 of 9-

' RI REstARKS/SASIC~

ASME

' NDE -

EXAM / CAL ERAM-CAT. NO.__

FIG, up.

EMAfsIIIATION/ AREA sitiftIOD PROC @uRE

-SWEET m0.

N.J!

E1, GEOM /OTIIER CALISRATION SLOCE SECTION XI EXAM NIGN PRESp_w rau4sif INJECTION SYSTEM (Cont'd)

C3.20 8-M/03 2E41-2tIPCI-14-R-31PL-1 MT Mi-N-500/3 S89N2M032 x

DEVICE

- C-C 2E41-NPCI-R102 C3.20 8-M/03 341-2NPCI-14-R-31PL-2 MT MT-N-500/3 589M2M031 x

DEVICE C-C 2E41-IIPCI-R102 MT-N-500/3 S89N2M030 x

C3.20 8-M/03 2E41-2NPCI-14-R-31PL-3 MT DEVICE.

C-C 2E41-IIPCI-R102 C3.20 s-M/03 2E41-211PCI-14-R-31PL-4 MT Mi-N-500/3 589N2M029 x.

DEVICE

~

C-C 2E41-NPCI-R102

.C3.20 B-M/03 2E41-2tePCI-14-R-44PS=

Mi MT-N-500/3.

589N2MG60 x

DEVICE CC

. 2E41-MPCI-R107 01 N

+.

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j.,

l' Edsin 1. untch tinit 2 I

1 -

'1989 Fall Refueling Outoge Ctess 2 Components Page 6 of 9

. A59E SECTION MI EXAM EXAM

. NDE '

EXAM / CAL-RI REMARKS /SASIC.

CAT. NO.

FIG. NO.

ERMllIIATlou/ AREA IETIItB PROCEDtRE

. SuEET uo.

ul M

GEENt/0THER Call 3RAfl0N SLOCK HIGN PRES $URE rnns natT' IuJECTICII SYSTEM (Cont'd)

'C3.20 8-73/03 2E41-2MPCI-16-TS-6Pt.-1 MT NT-H-500/3 S89M2P085 x

C-C DEVICE 2E41-NPCI-R13 C3.20 B-73/03 2E41-2HPCI-16-TS-6PL-2 MT MT-N-500/3 S89u2P006 x

C-C DEVICE 2E41-NPCI-R13 C3.20 8-73/03 2E41-2NPCI-16-TS-6PL-3 MT '

MT-N-500/3

.S89n2P087 x

C-C DEVICE l

2E41-MPCI-R13 I

'C3.20 B-73/03 2E41-2MPCI-16-TS-6PL-4 MT MT-H-500/3 589u2P088 x

C-C DEVICE l

2E41-MPCI R13 l

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'1989 Felt Refueling Outege Ctess 2 Components l'

,Page 7 of 9 n

i I

ASfE SECTION XI EXAM EMAN IDE EMAM/ CAL' Rt REtulRES/9ASIC 1

CAT. 110.

FIG. NO.

EMMtIIIAf tW/AAEA MTIIOD PROC { DURE SsIEET NO.

.E g- :GEON/OTHEA

' CALISRATION SLOCK RESIOUAL leEAT RESIDWAL IIEAT EMCIIRIIGERS C3.10 8-1/02 2NM-8-2S-1

'MT'-

MT-N-500/3

$89N2M018 '

X C-C UPPER SNELL RIIIG SUPPORT lI

{.

C3.10 '

a-1/02 2NM-6-25-2

MT

- MT-N-500/3

^S89N2M019 X

UPPER SHEL'L RING C-C SUPPORT C3.10 B-1/02 2NK-B-25-3 MY.

MT-N-500/3 S89N2M020 x

C-C UPPER SIIELL RIIIG SUPPORT-C3.10 B-1/02 2NX-a-2S-4 MT MT-N-500/3

$89N2M021 x

C-C UPPER SHELL RIIIG SUPPORT.

C3.10 B-1/02

'2Nx-s-3S-1

~ MT' MT-N-500/3' 589N2M036 x

C-C LOWER SleELL'RltIG SUPPORT-

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Edwin I.' Natch IMit 2 1999 Falt Refueling Outage Ctess 2 Components Page 8 of 9 RI REMARES/ BASIC.:

ASME EMAN ISE.

EMAM/ CAL CAT. NO.

FIG. BO.

EMAnillATICB/ AREA SEfes PROCEDURE SNEET NO.

. NI -

MRI GE(pl/OTHER.

CALISRATION BLOCK SECTION x1--

EXAM RESIDUAL NEAT REMOWAL IIEAT EXCNAalGERS (Cont *d) :

MT-N-500/3

.589M2M037

.x C3.10 8-1/02 2Hxis-3S-2 MT.

LOWER SHELL' RING C-C SUPPORT MAlW STEAM SYSTEM C3.20 8-11/03 2m11-2MSA-24C-14PL-1

-MT NT-H-500/3 589N2M081 x

DEVICE 2W11-MS-A60 C-C C3.20 8-11/03 2N11-2MSA-24C-14PL-2 MT NT-N-500/3

.589N2M080 x

DEVICE 2W11-MS-A60 C-C C3.20 B-11/03 2mt1-2MSA-24C-14PL-3 MT

'MT-N-500/3 589M2M072 x

DEVICE 2m11-MS-A60 C-C C3.20 B-11/03 20111-2MSA-24C-14PL MT MT-N-500/3

$89H2M073 x

DEVICE 2m11-8IS-A60 C-C NT-H-500/3

. $89N2M074 x

C3.20 s-11/03 2m11-2MSA-24C-14PL-5

- MT DEVICE 2N11-MS-A60 CC O

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Edwin 1. Match Unit 2 1989 Fall Refueling Outage

' Class 2 Components

' Page 9 of 9 RI REMARKS /9ASIC ASME EXAM alDE EXAM / CAL.

SECTION XI EXAM

' NJ - NRI GEGE/0THER CALIBRATION SLOCK CAT. NO.

F IG. 100.

EXAMillATION/ AREA BETIKB -

PROCEDUR(

SNEET NO.

MAIN STEAM SYSTEM (Cont'd)

C3.20 B-11/03 2N11-2MSA-24C-14PL-6 MT-MT-N-500/3 S89N2M075 X

DEVICE 2N11-MS-A60 C-C C3.20 B-11/03 2N11-2MSA-24C-14PL-7 MT NT N-500/3 589N2M076' X.

DEVICE 2N11-MS-A60 C-C MT MT-N-500/3 589N24077 X

C3.20 B-11/03 2N11-2MSA-24C-14PL-8 DEVICE 2N11-MS-A60 C-C COIITAllstENT PURGE AND INERTIIIG SYSTEM MT MT-N-500/3 589N2MO38 X

C3.20 8-80/02 2T48-2 CPI-18-P00-1 X-26 PEIIETRATICII C-C TO EL90W

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SUMMARY

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,:A OF L.

l-CLASS 1, 2, AND 3 PRESSURE TESTS

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..o PRESSURE TESTING This section of the report provides a discussion of the pressere tests that were performed during the Plant Hatch Unit 2 Fall 1989 RefuJ1in0 Those pressure tersts were perfortued for the purpose of inservice outage.

inspection on selected Class 1, 2,

and 3 piping systems.

The pressure tests and their boundaries are identified in the inservice examination-plan prepared by Southern Company Services, Revision 1, Deviation 001, Revision 2, Revision 2 Deviation 001 and Revision 2 Deviation 002.

'All pressure tests were performed in accordance with'ASME Section XI, 1980 Edition with Addenda through Winter 1981.

All tests were witnessed-and/or reviewed by the resident ANII.

The completed test reports are available for review'in the Records Management Department at the jobsite.

TESTING Class 1 Two (2) Class 1 Hydrostatic Tests were performed during the outage.

These tests were both performed because this. outage represented the last O-outage in the 10-year ISI inspection interval.

Listed below is a brief description of each test.

2821-HT-1, class 1 System Hydrostatic Test was performed per GPC procedure 42IT-TET-002-2S.

Only minor leakage at mechanical joints was-noted during VT-2 inspection.

Any component which.was disassembled in order to repair leaks was VT-2 examined during startup with the system at normal operating pressure (2005 psig) per GPC procedure 42IT-TET-004-OS.

2C41-HT-4, Class 1 portion of SBLC system performed per GPC procedure 42IT-TET-003-OS.

No leakage was noted.

Class 1 Summary Test I.D.

Procedure MWO Number 2B21-HT-1 42IT-TET-002-2S 2-89-1779 2C41-HT-4 42IT-TET-003-OS 2-89-0298 O

l l

63

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Class 2 i

Three (3). Class 2 Hydrostatic. Tests were performed per ASME Section XI paragraph IWA-5211(d) during the outage.

The tests were performed in-accordance with GPC procedure 42IT-TET-003-OS.

GPC received approval to use ASME Section XI Code Case N-479 for performance of the Main Steam Line Hydro.

This code case allowed the steam lines out to the main turbine stop and bypass valves to be tested in conjunction with the Class 1 System Hydrostatic Test.

Portions of the feedwater (2N21), RWCU (2G31), RCIC '(2E51) and HPCI (2E41) systems

.were optionally upgraded from Class 2 to Class 1 and, included within the hydrostatic test boundary for the main steam / Class 1 system pressure test.

Listed below is a summary of Class 2 Hydrostatic Tests.

Test I.D.

Procedure MWO NUMBER 2E11-HT-2*

42IT-TET-003-OS 2-89-3337 2E11-HT-3*

42IT-TET-003-OS 2-89-3339 l'

2N11-HT-1 42IT-TET-003-OS 2-89-1777

  • partial tests performed due to rework of' required system test boundary.

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only minor leakage at mechanical joints was detected during VT-2 examination and all test results were deemed acceptable..

L

-Class 2 Pressure Tests (other than hydrostatic) i.

Three (3) Class 21 Functional Testa, 2E21-FT-1, 2E41-FT-1 and 2P41-FT-1 were performed during the outage in accordance with ASME Section XI paragraph IWA-5211(b).

These tests were performed using GPC procedure 42IT-TET-004-OS.

Only minor leakage at mechanical joints was detected during the VT-2 examination.

L Four (4) additional Class 2 Flow Tests were performed to satisfy the requirements of ASME Section XI paragraph IWC-5222(d).

The RHR piping:

downstream of the outboard containment isolation valves associated with the torus and drywell spray function was air tested to ensure free flow at all discharge nozzles.

The associated procedure numbers and MWO numbers are listed below.

Test MWQ Procedure

~h 2E11-AT-1 2-89-0297 42SV-E11-006-2S

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2E11-AT-2 2-89-0296 42SV-E11-006-2S 2E11-AT-3 2-89-0295 42SV-E11-007-2S

- 2E11-AT-4 2-89-0292 42SV-E11-007-2S 64

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(j Class 3 Hydrostatic Tests Eleven (11) Class 3 hydrostatic tests were performed per ASME Section XI paragraph IWA-5211(d) during the outage.

These tests were performed on portions of'the RHRSW and PSW system piping.

Listed below is a summary of the tests performed.

Test I.D.

Procedure MWO NUMBER 2E11-HT-17 42IT-TET-003-OS 2-89-0293 2E11-HT-21 42IT-TET-003-OS-2-89-0294 2P41-HT-20 42IT-TET-003-OS 2-89-3364 i

'2P41-HT-21 42IT-TET-003-OS 2-89-3365 e

2P41-HT-24 42IT-TET-003-OS 2-89-3370 2P41-HT 421T-TET-003-OS 2-89-3362 6

2P41-HT-27 42IT-TET-003-OS 2-89-3363 2P41-HT-30.

42IT-TET-003-OS 2-89-3366'

=+

2P41-HT-31 42IT-TET-003-OS 2-89-3368 2P41-HT-32 42IT-TET-003-OS 2-89-3369 2P41-HT-33 42IT-TET-003-OS 2-89-3367 Credit for the performance of four (4) additional hydrostatic tests y

which were performed in conjunction with some plant modifications are

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also being taken.

The subject tests are listed below.

Test I.D.

MWO NUMBER REFERENCE DOCUMENT

'2P41-HT-34 2-86-3685 DCR 83-218 i

2P41-HT-35 2-86-3686 DCR 83-218 2P41-HT-36 2-82-1984 DCR 76-68 2P41-HT-37 2-82-1984 DCR 76-68 e

./

V 65

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Class 3 Pressure Test (other than hydrostatic)

Two (2) Class 3 Inservice Tests, 2G41-IT-1 and 2P41-IT-1, were performed-These tests were in accordance with ASME Section XI during the outage.

paragraph IWA-5211(c) and were performed using GPC procedure 42IT-TET-004-OS.

These tests consisted of the FPC system piping and the PSW piping.

Only minor mechanical joint leakage was detected during the VT-2. examination.

Class 3 pneumatic tests were performed per ASME Section XI_'

-Eleven (11) paragraph IWD-5223(f). _ An ultrasonic test probe was utilized to perform the leakage inspection during the pneumatic test per GPC procedure The ultrasonic test probe was demonstrated to the 42SP-091889-OP-1-OS.

satisfaction of the ANII prior to examination.

Listea below are the actual test numbers.

Test I.D._

PROCEDURE

'MWO NUMBER 2B21-AT-A 42IT-TET-005-OS 2-89-3348 2B21-AT-B 42IT-TET-005-OS 2-89-3349 2B21-AT-C 42IT-TET-005-OS 2-89-3350 l

D 2B21-AT-D 42IT-TET-005-OS 2-89-3352

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2B21-AT-E 42IT-TET-005-OS 2-89-3354 2B21-AT-F 421T-TET-005-OS 2-89-3355 2B21-AT-G 42IT-TET-005-OS 2-89-3356 2B21-AT-H 42IT-TET-005-OS 2-89-3357 2B21-AT-K 42IT-TET-005-OS 2-89-3358 2B21-AT-L 42IT-TET-005-OS 2-89-3360 2B21-AT-M.

42IT-TET-005-OS 2-89-3361 l.

No leakage was detected at any location other than mechanical joints during the examination.

I

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SUMMARY

OF> VISUAL EXAMINATIONS CLASS 1, 2, AND 3 COMPONENT SUPPORTS

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E 2,i Af gpMPONENT SUPPORT EXAMINATIONS This section of the report provides a discussion of the visual examinations performed nr selected component supports on Hatch Unit 2.

._ The subject examinations were performed during the Refueling / Maintenance Outage.

Examinations were performed using SCS Procedure VT-H-730'(VT-3)'.

The procedure and all examination data sheets'are available for review

- at.the plant' site.

j i

Examinations 6

Class 1 Forty-one (41) component supports from the 2B21,.2B31, 2E11, 2E51 and

~ 2G31 systems were visually examined.

Nine (9) unacceptable indications were' detected.-

Class 2 Eighty-one (81) component supports from the 2E11, 2E41 and 2E51 and 2Kll:

systems were visually examined.~

Fourteen (14) of these Class 2 component!

jj,i supports were found unacceptable, w/

~ Class'3 i

Twenty. (20) component supports from-the 2B21 and 2P41 systems were-

. visually examined.

No. unacceptable' conditions were reported.

'After maintenance and/or engineering evaluation,.all of the' unacceptable 4 component supports were determined to be acceptablei Whereimaintenance'

.was involved, the component supports were re-examined to confirm acceptability.

o 9

4 68 t

p 1' Page No. 1L g..q..

1989 E.I. HATCH UNIT 2 PIPE SUPPORTS x )

AS8eE

'~

SUPPORT FIGURE TYPE RESULTS REPORT NO. INF NO.

MWO No.

RESULTS REPORT No. REMARKS-

[

CLASS NUMBER l'

2B21 MS H10 A9 SPRING U

$89H2v107 189H2015 2 89 5301 A

$89H2V178 LOOSE NUTS i

1 2821 MS H11 A9 SPRING A

$89H2V090 NA NA NA NA NA.

.1

~ 2821 MS H12 A9 SPRING A

S89H2V094 NA NA NA NA NA

~1 2821 MS R34 A9. SNUBBER A

589H2v089 NA NA NA NA NA I

1 2B21 MS R35 A9 SNUBBER A

$89H2V091 NA NA NA NA NA 1

2B21 MS R36 A9 SNUBBER A

$89H2v092 NA NA NA NA NA i,

.1 2B21 MS R37 A9 SNUSBER A

$89H2v093 NA NA NA NA NA

.1 '

2B21 RFW R33 A 12 RESTRAINT A

$89h2V153 NA NA NA NA,

WA 1

2B21 ROTATNL& LATERAL A6 ' RESTRAINT A

S89H2v086 NA NA NA NA NA' 1-I2821 ROTATNL& LATERAL A?

RESTRAINT A

$89H2V150 NA NA NA' NA NA 1-2821 ROTAINL& LATERAL A8 RESTRAINT A

S89H2V151 NA NA NA NA NA 1

'2821 ROTATNL& LATERAL A9 RESTRAINT A

$89H2V152.NA

' NA NA NA NA 1-2B21 TOR $10N& LATERAL' A6 RESTRAINT

-A

$89H2v120 NA NA NA NA NA -

- r 1

2821 TORS!0N& LATERAL A*9 RESTRAINT A

$89H2V121. NA NA.

NA NA NA 1'

2B21 TOR $10NSLATERAL' A-12 RESTRAINT U

$89H2v087 189H2015 2 89 5301 A

$89H2V183 MIS $ LNG COTTER PIN

~1

.2B31 HA1 A 16 SPRING A

$89H2V123 NA NA NA NA NA 1

2B31 MA2 A 17 ' SPRING U

589H2V042 189H2021 2 89 5485 A

$89H2V197 IMPROPERSPRI CAN SETTING 1

2831 HA3 A 14 SPRING A

$89H2V190 NA NA NA NA NA b

1 2B31 HA4 A 14 SPRING U

$89H2V186 189H2024 2 89 5485 A

-589H2V198 IMPROPER SPRike CAN SETTING

/" N A

1-2831 HA5 A 16 SPRING A

$89H2V193 NA NA NA NA NA

'1 2831 HA6 A 16 SPRING A

$89H2V192 NA NA NA NA NA gg

i.

l

' Pope No. 2-1989 E.1, HATCH UNif 2 PIPE SUPPORTS 7

[/

l'

- 1ASME SUPPORT FIGURE TYPE

'RESULTS REPORT NO. INF NO.

MWO NO.

RESULT $-REPORT.NO. REMARKS-

-CLASS NUMBER..

~ 1 2831 HA7 A 16 $PRING A

S$9H2V191 NA NA NA NA NA 1

2B31 NB1 A 18 SPRING U

$89H2V187 189H2024 2 89 5485 A

$89H2V199 IMPROPER SpeluG-CAN SETTING t

1-2B31 H82 A 19 $PRING U

$89H2V175 189H2023 2 89 5485 A

$89H2V200 (NPROPER SPRING CAN SETTING-2831 MB3 A 15. SPRING A

$89H2V188 NA NA NA NA NA I-1.

2631 Hs4 A 15 SPRING U

$89H2V185 189H2024 2 89 5485 A

$89H2V201= (MPROPER SPRING-.

CAN SETTING' J

1 2831 Hs5 A 18' SPRING A

$89H2V1% NA NA NA NA -

NA P

1 2s31 Hs6-A 18 SPRING A

$89H2V195 NA NA -

NA

-NA NA g

1' 2831 H87 A 18 ~ SPRING

'A

$89H2V194 NA NA NA NA NA.

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I-1 2831 ESA12 A*17 SNUBBER A

$89H2V044 NA NA NA NA NA i

l l'

1 2831 SSA13 A 17 SNUB 8ER A

$89H2V043 NA NA NA NA NA 3l 1

1 2B31 SSA14 A 17 SNUBBER U

'S89H2V046 189H2014 2 89 5299 A

-589H2V177 LOOSE JAM NUT a.

'1 2831 SSA17 A 17 SNUSSER A-

$89H2V045 NA NA -

NA~~

NA NA'

i f.

L.

-. 2831 SSA19 A 17 SNUSSER A

-S89H2V040 WA NA' NA NA -

NA~

~

1" 1:

2831 SSA20 A 17 SNUstER A

$89H2V041. NA

- NA.

NA NA NA s

l' 2E11*RHR H737 A*20 HANGER A

589H2V095 NA NA NA.

NA' NA 1'-

2E51 RCIC H113 A 27 - SPRING A

$89H2V122 NA

- NA -

NA NA NA 1

2G31 RWCU H23 A 28 ' SPRING A

$89H2V051 NA NA

' NA NA NA 1

2G31 RWCU R166 A 28 SNUB 8ER A

589H2V050 NA NA NA NA NA j

1 2G31 RWCU R167 A 28 SNU88ER U

S89H2V096 189H2013 2 89 5298 A

$89H2V184 LOOSE NUTS k).

.1 2G31 RWCU R168 A 28 SNUBBER A

S89H2V052 NA NA NA NA NA

'i 2.-

2E11 RHR H151 -

B 44 MANGER A

S89H2V172 NA NA NA NA NA 70


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. _ Page NO' 3' I

m. w ;

1989 E.1. HATCH UN11 2 PIPE SUPPORTS

\\M-'

ASME SUPPORT-flGURE TYPE RESutTS REPORT NO. INF NO.

MWO NO.

RESULTS REPORT NO. REMARKS CLASS NUMBER Il 2-2E11 RHR H27 B WO HANGER A

589H2v025 NA NA

-NA NA NA' 2

2E11*RNR H28 B 100 HANGER U

$89H2v019. 18982005 2 89 5001 A

$89H2V166 LOOSE NUT

>i

?

2 2E11 RHR H29 B 100 HANGER A

$89H2V024 NA NA NA NA NA e

2 2E11 RHR H30-S 100 HANCER A

$89H2v021 NA NA NA NA.

NA, 2

2E11 RHR H321 6 14 HANGER U

$89H2v049 189H2005 2 89 5001 A

$89H2V168 LOOSE NUT 2

2E11 RHR H713 8 21 SNUBBER U

$89H2v014 189H2005 2 89 5001 A

$89H2V16$ NIS$1NG WASHER:

2 2E11 RHR HR149 B 44 NGR RESTRAINT A

$89H2V171 NA NA NA NA NA -

2-2E11 RHR R133 8 100 RESTRAINT U

$89H2v020 189H2005 2 89 5001 A

$89H2V167 L00SE NUT AND MIS $ LNG NUT y

- {

'2' 2E11 RHR R134 8 100 RESTRAINT A

$89H2v026 NA NA NA NA :

NA L

2 2E11 RHR R135 B 100 RESTRAINT A

$89H2v023 NA NA NA NA NA 2

'2E11 RHR R136 -

'B 100 RESTRAINT-A

$89H2v022 NA' NA NA NA

' NA' 2

-2E11*RHR R326 8 14 SNUd8ER A

$89H2v048 189H2012 NA NA' NA NO SPACER OR WASHER l

'OECHTEL ACCEPTED AS IS I'

l

2:

2E11 RHR R327 B 14' SNUSSER A

$69H2v047 NA NA NA NA NA

>2 2E41 HPCl*H1 B 73 HANGER U'

$89H2v018 189H2004 2 89 5002 A

$89H2v109 -' THREADED ROD NOT VIslBLE' iHROUGH SIGHT ~

HOLES 2

2E41 HPCI H10 B 69 SPRING A

$89H2v008 NA NA NA NA

/NA 2

2E41 HPCl*H32 8 94 SPRING U

$89H2v061 189H2006 2 89 5119 A

-589H2V160 LOOSE BOLTS

- f\\

2 2E41 HPCI-H33 8 94 HANGER A

$89H2v060 NA NA NA NA NA j

-2 2E41 HPCI H34 8 94 HANGER U.

S89H2v057 189H2006 2 89 5119 A

$89H2V159 LOOSE JAM NUTS

2-2E41 MPCl H6 8 69 SPRING U

S89H2v149 189H2018 2 89 5384 A

$89H2V169 IMPROPER SPRf4 CAN SETilNG 7.1

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"/'N '

1989 E.1. MATCH UNIT 2 PlPE SUPPORTS-

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ASME SUPPORT FIGURE TYPE RESULTS~ REPORT No. INF WO.

MWO NO.

RESULTS REPORT WO. REMARKS 2

CLASS--

NUMSER -

2

. 2E41 HPCI H83 8 16 HANGER A

$89H2v037 NA

. NA N A '.

WA NA 2

2E41 HPCI H84 B 16 HANGER A

$89H2V082 NA NA NA NA NA 4

2' 2E41 HPCI H85 B 16 HANGER A

$89H2v035 NA NA NA NA NA 5

2-2E41 HPCI HR35 B 94 HGR RESTRAINT A

$89H2V055 NA NA NA NA NA

'2' 2E41=HPCI R17 B 69 RESTRAINT A

$89H2V064 NA NA NA NA NA 2

2E41 HPCI R18 B 69 ' RESTRAINT A

$89H2V170 NA NA NA NA NA

'2 2E41 HPC1 R21 8 69 SNUBBER A

$89H2V116 NA NA NA NA NA 2

2E41 MPCI R22 8 69 SNUBBER.

A

$89H2V085 NA NA N A.

NA NA 2

2E41 HPCI R54 5 94 RESTRAINT A

$89H2V063 NA NA NA NA NA t

\\

2

. 2E41 NPCI R56 9 94 RESTRAINT A

$89H2V062 NA NA -

NA NA NA L

2

~2E41 NPCI R57 B 94 RESTRAINT A

$89H2v059 NA NA NA NA NA -

2 2E41 HPCI R58 B 94 RESTRAINT-U S89H2v056 189H2006 2 89 5119 A

$89H2V158 LOOSE JAM NUTS 2'

2E41*HPCl*R59 B 94 RESTRAINT U'

$89H2v058 189H2006 2 89 5119 A

$89H2V162 MISALIGNMENT l-J.

'2-2E41 HPCI R89 8 16-RESTRAINT A

$89H2v036 NA NA NA NA NA 1;.

2 2E41*HPCI R90 0 16 RESTRAINT U

S89H2v084 189H2006 2 89 5119 A

$89H2V164 MIS $ LNG SPACER I,

2-2E41 NPCI R91 8 16 SNUSSER A

$89H2v083 -NA NA NA NA '

'NA i

I t

2' 2E41 MPCI R92 B 16 RESTRAINT A

589H2v110 NA NA NA NA NA 2'

2E41 UX 8 103 HANGER A

$89H2V053 NA NA NA NA NA

'2 2E41 UI' 8 103 HANGER A

$89H2v054 NA NA NA NA NA 2

2E51 2E11 RHR A61 B 88 ANCHOR A

$89H2v115 NA NA NA NA NA 8

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y

-2 2E51 2E11 RNR H209 B 87 HANGER A

$89H2V080 NA NA NA NA NA 2.

2E51 2E11 RHR H212 B 88 HANGER A

$89H2V104 NA NA NA NA NA 72

4

' Page No. 5 s

'1989 E.I. NATCH UNIT 2 PIPE SUPPORTS

/N ti O

K].

'ASME SUPPORT' FIGURE TYPE RESULTS REPORT NO. INF NO.

MWO NO.

RESULTS' REPORT NO. REMARKS

+

- CLASS.

NUMBER i

2

'2E51 2E11*RHR M214' B 88 ' ' HANGER A

$89H2V105 189H2012 NA NA NA MISSING ANCMOR BOLTS

..F BOLT IMPROPERLY INSTALLED-

  • BECHTEL;

. ACCEPTED AS IS 2'

'2E51 2E11 RHR H215 B 88 HANGER A

$89H2V102 189H2012 NA NA NA MISSING ANCHOR'-

BOLTS

.i

  • BECHTEL Li ACCEPTED AS l$

2:

2E51 2E11 RNR H216 B-88 HANGER A

$89H2V101 189H2012

'NA NA NA MIS $1NG ANCHOR BOLTS

  • BECHTEL' ACCEPTED AS IS 4

F 2

2E51 2E11 RNR H218 B 87 HANGER A

$$9H2v079 NA NA NA hA NA l' -U 2 -'

2E51 2E11 RNR*HR210 B 87 HGR RESTRAINT A

$89H2V112 NA NA NA

- NA

'NA j.

=2

2E51 2E11 RNR HR211 B 87 HGR RESTRAINT A

$89H2V081. NA' NA NA NA NA

2 2E51 2E11 RNR HR213-B 88 HGR RESTRAINT A

$89H2V114 NA NA NA NA NA

}2 2E51 2E11 RNR R309.-

.B 88 RESTRAINT

'A

$89H2V113 NA' NA N A '-

NA NA 2.

2E51 2E11 RHR R310 ' B 88 RESTRAINT A

S89H2v103 -NA NA NA' NA -

NA <

'2-2E51 2E11 RNR R311 B 87 RESTRAINT-A

$89H2vo78 NA NA

'NA NA NA 2.

2E51 RCIC A27 B 91 ANCHOR A

$89H2v124~NA NA NA NA NA>

2 ',

2E51 RCIC A67 B 95 ANCHOR A

$89n2v157 NA NA NA NA NA jj 2-2E51 RCIC A7 t 86 ~ ANCHOR A

$89H2v076 NA NA

-NA NA NA 2

2E51 RCIC HR2 B 86 HGR RESTRAINT A-

$89H2v034 NA NA MA NA NA Q2 2E5i.RCic.HR.

B.87 HGR RES m iN1 A

$89H2 077 NA NA NA NA NA l

2

' 2E51 RCIC HR24 B 87 NGR RESTRAINT A

$89H2v111 NA NA NA NA NA 2

2E51 RCIC HR25:

B 91 HGR RESTRAINT A

$89H2v075 NA NA NA NA NA 73

t i

^ Pege,No. 6 1989 E.1. MATCH UNif 2 PlPE SUPPOR15 i

ASME. SUPPORT-FIGURE TYPE RESULTS REDORT NO. INF Ho.

MWO NO.

Result $ REPORT NO. REMARKS CLASS NUMBER 2

2N11 MS H19.

B9 HANGER A

$89H2V012 NA NA NA NA NA 2

2N11 MS H20

-B9 HANGER U

$89H2V011 189H2003 2 89 5053' A

$89H2V118 CAP BETWEEN NUT AND BASEPLATE

'2 2N11 MS*H21 B9 SPRING U

589H2V009 189H2003 2 89 5053 A

$89H2V131 LOOSE Wut 2

2N11 MS H27

' B 12 MANGER A

$89H2V004 NA NA NA NA NA 2

2N11 MS*H28 B*12 SPRING A

589H2v003 NA NA NA NA NA 2

2N11*MS H3 B9 SPRING A

$89H2V027 NA NA NA NA NA 2

2N11 MS H4 09 SPRING A

$89H2V001 NA NA NA NA NA 2

2W11 MS M5 8*9

. HANGER A

$89H2V016 NA

-NA NA NA NA 2~'

2N11 MS H6 5 12 MANGER A

$89H2V032 NA NA NA NA NA 2

2N11 MS H7 B 12 HANGER A

$89H2V006 NA NA NA NA NA 2-2N11*MS R43 99 SNUSSER A

$89H2V029 NA NA NA NA NA 2

2W11 MS R44 B9 SNUSSER A

$89H2V028 NA

. NA -

WA NA NA 2

2N11 MS R45

~B9 SNUSSER U

$89H2V099 189H2011-2+89 5279 A

$89H2V176 LOOSE NUTS-2

'2N11 MS R46

,89 SNUS$ER.

A

$89N2V015 NA NA NA NA NA 2

2N11 MS R47 59 SNUBBER A

$89H2V010 NA NA NA NA NA 2.

.2W11 MS R49 B 12 SNU58ER A

589H2V030 NA NA NA NA NA 2

2N11*MS R50 B 12 $NUstER A

$89H2V033-NA NA NA NA-NA 2

2N11 MS R51

  • B 12 SNUttER A

$89H2V031 NA NA NA NA NA 2

2N11 MS R52 B 12 SNUteER A

$89H2V005 NA NA NA NA NA 2N11 MS R53 B 12 SNU4BER A

$89H2v002 NA NA NA NA 2A 2

-2 2N11 MS R91 8 12 $NUBBER A

$89H2V072 NA hA NA NA NA l

-2 2N11 MS R92 B-9 SNUBSER A

$89H2V013 NA NA NA NA NA 74

4

+

~Pa'ge No.

7,-

1989 E.1. HATCH VNif 2 PIPE SUPPORTS 1

ll

-h~

E SUPPORT E TYPE RESULTS-REPORT NO. INF NO.

MWO NO.

RESULTS REPORT NO. REMARKS 1:

. 3 2821 UI.-

C 113 HANGER A

$89H2V155 NA NA NA

'NA LATER IDENTIFIED AS DCB 1 O'

1 -

3

~2821 U1 C 118 HANGER A

$89H2V154 NA NA NA

'NA LATER IDENTIFIED AS DCA 1 3

2B21 01 C 119 MANGER A

$89H2v142 NA NA

'NA NA LATERIDENTIFIED[

AS DCG 1

~i J

A

$$9H2V143 NA' NA NA -

NA NA "3

2821 t/1 C+119 ANCHOR 3

2821 UI C 121 HANGER A

$89H2V156 NA

. NA NA NA NA 3-

'2821 UI C 120 HANGER A

$89H2V140 NA NA NA NA LATERIDENTIFIEDl D

AS DCC 1'

-3.

2821*UI C 120 ' ANCHOR ~

A

$89H2V341 NA NA NA NA NA-f

-V' 3-2821 UI C 123 HANGER A

$89H2V119 NA' NA NA NA LATER IDENTIFIED AS DCL 1

,i

'3' 2P41 SW R327 C+25 RESTRAINT A

$89H2v074 NA NA NA-NA NA

'i L

IU 3

.2P41 SW R328 C 25 RESTRAINT A

$89H2V038 NA NA NAL NA

.NA 3

2P41 SW R338 C 25

~~1.R RESTRAINT A

$89H2V007' NA NA NA NA '

NA 3'

'2P41 SW R341 C 2$ RESTRAINT A

- $89H2v039 NA NA NA NA NA 1

3

. 2P41 TSW HR733 C 27 HGR RESTRAINT A S89H2V073 NA

.NA NA NA NA l

j _,

3 2P41 Ul_

C 35 HANGER A

$89H2V068 NA NA NA NA NA 6-t 3

~2P41 UX

,C 35-FIELD ANCHOR A

$89H2V069 NA NA NA NA NA i

[i 3

2P41 UI C 35 RESTRAINT A

$89H2v070 NA NA NA NA NA

~)

'3-2P41 UX C 35 HANGER A

$89H2v071 NA NA NA NA NA

_fh' J

'3 2P41 UI C 22 HANGER A

$89H2v067 NA NA NA NA NA

\\

~~3 2P41*UI-C 22 RESTRAINT A

$89H2v066 NA NA NA NA NA

'3

'2P41 UI.

C 22 RESTRA!NT A

$89H2V128 NA NA NA NA NA 75

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SUMMARY

OF

=i REACTOR PRESSURE. VESSEL

- (

\\

t INTERNAL INSPECTIONS-o F

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G nu1CTOR PRE 88URE VESSEL INTERNAL 8 This section of the report provides a summary of the remote visual examinations performed by SCS on selected RPV internals.

Tha visual examinations were performed using SCS procedure VT-H-750.

This procedure l

incorporates requirements for ASME Section XI, GE Service Information Letters and NRC IEB-80-13.

All visual examination tapes were reviewed by SCS or Ebasco certified p

level II and/or III vicual examiners to determine the acceptability.of L

l the various RPV internal components.

CORE SPRAY SPARGER INSPECTION Per the requirements of NRC IEB 80-13, the core spray spargers and' associated piping were visually examined.

Underwater video equipment

[

recorded the examination results to the resolution of a.001' inch L

diameter visual acuity standard.

No reportable indications were found, i]

RPV INSPECTION i

[Y

',,/ ~

The four (4) RPV Clad Specimens at 45, 135, 225 and 315 degree azmuths-were visually inspected.

No reportable indications were found.

u STEAM DRYER /, MOISTURE SEPARATOR INSPECTION Remote visual examinations were performed on various components:of the j

steam dryer which. consisted of:

support ring, stiffeners, stiffener J

welds and' vertical vane bank welds.

Indications were reported during.

previous refueling outages.

GE; determined that the indications were acceptable for continued operation with additional. monitoring requested l

for each outage.

Using higher resolution recorders and monitors a l

comparison of size and location revealed no significant change in any of the' indications.

Two new indications were detected-during the steam dryer inspection.

L These new indications were located next to vertical vane weld #12 and inl drain channel weld #8.

The indications were evaluated by GE and.found to, g

be acceptable.-

[

I h.

L) 77 m - m

JET PUNP INSPECTIONS l

O-Remote visual examinations were perfarmed on all twenty (20) jet pump inlet mixers in the throat area.

During 1988 examination of the Unit 2 inlet mixers reveal.ed evidence of erosion.

Also, visual examination was performed on all twenty (20) jet pump riser brace arm velds.

No change was noted in the throat are erosion and no indications were detected in the riser brace arm welds.

No reportable indications were found.

SMROUD MEAD 20LT EXAMINATIONS Per GE SIL-433, all 36 moisture separator head hold down bolts vere ultrasonically examined using SCS procedure UT-H-418.

No reportable indications were found.

Listed below is an itemized summary of the invessel examination performed.

Drver and Seoarator Stiffeners and welds Four (4) lifting lugs Support ring (360 deg.)

Bank to support ring Skirt to support ring Sized twenty (20) indications and compared to previous outage results O deg. and 180 deg skirt wel!.a O deg. and 180 deg. guides Sixteen (16) drain channel welds (GE SIL-474)

Vessel Area Core Spray piping Core Spray Sparger Feedwater Sparger 180 deg, of. top guide Four (4) clad patch areas Jet punip mixing nozzles Jet pump riser. brace arm to vessel weld The following pages contain a copy of the RPV internal inspection tape log which.is an itemized list of all components and areas visually examined during the 1989 refueling outage.

This log was supplied along

.With the video tapes to the onsite document control department.

78

t l

E.I. MATCH UNIT 2 INVESSEL VISUAL TAPE LOG I

REFUELING OUTAGE NUMBER EIGHT - SEPTEMBER, 1989 i

PAGE 1 OF 11 f

TAPE NUMBER TAPE COUNT COMPONENT DESCRIPTION l-STEAM DRYER INSPECTIONS:

EIH2-89-1 0000-0102

.001",

.003" AND

. 005" CAMERA RESOLUTION ON 9-11-89 0 0900 HOURS EIH2-89-1 0102-1194 LIFTING LUG ASSEMBLY 9 326 DEGREES EIH2-89-1 1194-1620 STIFFENER NUMBERS 22, 23, 24, 25, 26, 27

& 28 ON BANK NUMBER 5 SIDE EIH2-89-1 1620-2163 LIPTING LUG ASSEMBLN 9 214 DEGREES EIH2-89-1 2163-3200 STIFFENER NUMBERS 22, 23, 24, 25, 26, 27 l

}/

&.28 ON BANK NUMBER 4 SIDE

\\

EIH2-89-1 3200-4128 STIFFENER NUMBERS 21, 20, 19, 18, 17, 16, i

15, 14 & 13 ON BANK NUMBER 4 SIDE l

EIH2-89-1 4128-4469 STIFFENER NUMBERS 13, 14, 15, 16, 17, 18, 19, 20 & 21 ON BANK NUMBER 3 SIDE i

EIH2-89-1 4469-4865 STIFFENER NUMBERS 12, 11, 10, 9 & B ON l

BANK NUMBER 3 SIDE EIH2-89-1 4865-5115 STIFFENER NUMBERS 8, 9,

10, 11 & 12 ON BANK NUMBER 2 SIDE l

EIH2-89-1 5115-END STIFFENER NUMBERS 7, 6,

5, 4,

3, 2&1 ON BANK NUMBER 1 AND 2 SIDE EIH2-89-2 0000-0085

.001",

.003 AND

. 005" CAMERA RESOLUTION L

09-11-89 9 1620 HOURS l

EIH2-89-2

'0,085-1275 LIFTING LUG ASSEMBLY 9 34 DEGREES EIH2-89-2 1275-1991 LIFTING LUG ASSEMBIN 0 146 DEGREES EIH2-89-2 1991-2084

.001",

.003" AND.005" CAMERA RESOLUTION ON 9-12-89 0 0900 HOURS j'

.EIH2-89-2 2084-2754 LOWER GUIDE e O DEGREES 4

79 re

f r

l lC

x.

j l

>L~J E.I. NATCH UNIT 2 INVESSEL VISUAL TAPE LOG

]

REFUELING OUTAGE NUMBER EIGHT - SEPTEMBER, 1989 l

l i

PAGE 2 OF 11

' TAPE NUMBER TAPE COUNT COMPONENT DESCRIPTION STEAM DRYER INSPECTIONS:

j EIH2-89-2 2754-2846 UPPER GUIDE @ O DEGREES EIH2-89-2 2846-2917 UPPER GUIDE @ 180 DEGREES EIH2-89-2 2917-3070 LOWER GUIDE @ 180 DEGREES i

EIH2-89-2 3070-3326 SKIRT VERTICAL WELD @ 180 DEGREES EIH2-89-2 3326-3585 SKIRT VERTICAL WELD @ O DEGREES 1

EIH2-89-2 3585-3653 5.5" CRACK LIKE INDICATION ON DRAIN (qj CHANNEL NUMBER EIGHT LEFT SIDE WELD

(

EIH2-89-2 3653-4130 DRAIN CHANNEL NUMBER EIGHT - LEFT SIDE EIH2-89-2 4130-4326 DRAIN CHANNEL NUMBER ONE - RIGHT SIDE EIH2-89-2 4326-4496 DRAIN CHANNEL NUMBER ONE - LEFT SIDE EIH2-89-2 4496-4678 DRAIN CHANNEL NUMBER TWO - RIGHT SIDE EIH2-89-2 4678-4836 DRAIN CHANNEL NUMBER TWO - LEFT SIDE EIH2-89-2 4836-5021 DRAIN CHANNEL NUMBER SEVEN - LEFT SIDE EIH2-89-2 5021-5162 DRAIN CHANNEL NUMBER SEVEN - RIGHT SIDE EIH2-89-2 5162-5187

.001",

.003" AND

.005" CAMERA RESOLUTION ;

ON 9-12-89 0 1740 HOURS

-EIH3-89-3

.0000-0088

.001",

.003" AND

. 005" CAMERA RESOLUTION '

ON 9-13-89 0 0830 HOURS EIH2-89-3 0088-0402 DRAIN CHANNEL NUMBER EIGHT - RIGHT SIDE i

EIH2-89-3 0402-0760 DRAIN CHANNEL NUMBER FIVE - RIGHT SIDE

\\_)

EIH2-89-3 0760-1029 DRAIN CHANNEL NUMBER FIVE-LEFT SIDE BC)

)

?

i 1

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,),

\\

i E.I. MATCH UNIT 2 INVESSEL VISUAL TAPE LOG j

REFUELING OUTAGE NUMBER EIGHT - SEPTEMBER, 1989

)

s PAGE 3 OF 11 TAPE NUMBER TAPE COUNT COMPONENT DESCRIPTION I

STEAM DRYER INSPECTIONS:

E1H2-89-3 1029-1488 DRAIN CHANNEL NUMBER SIX - RIGHT SIDE EIH2-89-3 1488-1757 DRAIN CHANNEL NUMBER SIX - LEFT SIDE EIH2-89-3 1757-1902 DRAIN CHANNEL NUMBER FOUR - LEFT SIDE EIH2-89-3 1902-2080 DRAIN CHANNEL NUMBER FOUR - RIGHT SIDE EIH2-89-3 2080-2567 DRAIN CHANNEL NUMBER THREE - LEFT SIDE EIH2-89-3 2567-2797 DRAIN CHANNEL NUMBER THREE - RIGHT SIDE f-']s EIH2-89-3 2797-2815

.001",

.003" AND

.005" CAMERA RESOLUTION

\\

ON 9-13-89 9 1715 HOURS l

EIH2-89-3 2815-2831

.001",

.003" AND.005" CAMERA RESOLUTION ON 09-15-89 9 0900 HOURS EIH2-89-3 2831-5463 UPPER SUPPORT RING TO BANK WELD EIH2-89-3 5463-END UPPER SUPPORT RING TO BANK WELD @ THE LIFTING LUG 9 146 DEGREES EIH2-89-4 0000-1048 UPPER SUPPORT RING TO BANK WELD FROM VERTICAL BANK WELD' NUMBER 11 TO NUMBER 8 L

EIH2-89-4 1048-1814 FIRST PASS OF THE UPPER SUPPORT RING VERTICAL FACE AREA - 326 DEGREES TO O DEGREES TO 326 DEGREES l

EIH2-89-4

.1814-2569 SECOND PASS OF THE UPPER SUPPORT RING

. VERTICAL FACE AREA - 326 DEGREES TO O DEGREES TO 326 DEGREES SIZING THE INDICATIONS LOCATED ON THE EIH2-89-4 2569-3809 UPPER SUPPORT RING fX/

S1

in O

E.I. MATCH UNIT 2 INVESSEL VISUAL TAPE LOG REFUELING OUTAGE NUMBER EIGHT - SEPTEMBER, 1989 PAGE 4 OF 11 TAPE NUMBER TAPE COUNT COMPONENT DESCRIPTION STEAM DRYER INSPECTIONS EIH2-89-4 3809-4825 BOTTOM EDGE OF THE UPPER SUPPORT RING AND THE SKIRT TO SUPPORT RING WELD EIH2-89-4 4825-4845

.001",

.003" AND.005" CAMERA RESOLUTION ON 09-15-89 e 1950 HOURS EIH2-89-4 4845-4873

.001",

.003" AND.005" CAMERA RESOLUTION ON 09-16-89 9 0930 HOURS EIH2-89-4 4873-5385 VERTICAL BANK TO UPPER SUPPORT RING WELD ON THE 180 DEGREES. SIDE O

EIH2-89-4 5385-5408 RE-LOOKS ON DRAIN CHANNEL NUMBER SIX -

TOP RIGHT SIDE EIH2-89-4 5408-5636 RE-LOOKS ON THE 195 DEGREES UPPER SUPPORT RING AREA i

EIH2-89-4 5636-5750 SIZING THE INDICATIONS ON THE UPPER SUPPORT RING NEAR THE 146 LIFTING. LUG ASSEMBLY EIH2-89-4 5750-END RE-LOOKS ON DRAIN CHANNEL NUMBER THREE -

BOTTOM LEFT SIDE EIH2-89-5 0000-0733 RE-LOOKS ON THE BANK VERTICAL WELD NUMBER TWELVE EIH2-89-5 0733-0830 RE-LOOKS 9 SKIRT PLATE NEAR 0 DEGREES EIH2-89-5 0830-0898 RE-LOOKS 9 UPPER SUPPORT RING 9 358 DEGREES ON THE TOP SIDE EIH2-89-5 0898-1403 VERTICAL BANK NUNBER ONE TO THE UPPER SUPPORT RING O

S2 I

-s

'~

E.I. MATCH UNIT 2 INVESSEL VISUAL TAPE LOG REFUELING OUTAGE NUMBER EIGHT - SEPTEMBER, 1989 PAGE 5 OF 11 TAPE NUMBER TAPE COUNT COMPONENT DESCRIPTION STEAM DRYER AND CORE SPRAY INTERNAL PIPING INSPECTONS:

EIH2-89-5 1403-1710 VERTICAL BANK NUMBER PIVE TO THE UPPER SUPPORT RING EIH2-89-5 1710-1728

.001",

.003" AND.005" CAMERA RESOLUTION ON 09-16-89 @ 1410 HOURS EIH2-89-5 1728-1900 RE-LOOKS AT THE 195 DEGREES ON THE TOP PORTION ON THE UPPER SUPPORT RING AREA EIH2-89-6 0000-0132

.001",

.003" AND.005" CAMERA RESOLUTION ON 09-19-89 9 1215 HOURS

()

EIH2-89-6 0140-1590 10 DEGREE CORE SPRAY DOWNCOMER AND WELDS EIH2-89-6 1590-3451 CORE SPRAY PIPING 10 DEGREE TO THE 90 DEGREE TEE BOX INCLUDING THE PIPING WELDS AND THE 30 DEGREE BRACKET EIH2-89-6 3451-4829 CORE SPRAY PIPING 90 DEGREE TO 170 DEGREE INCLUDING THE PIPING WELDS AND THE 150 DEGREE BRACKET EIH2-89-6 4829-5795 170 DEGREE CORE SPRAY DOWNCOMER AND WELDS EIH2-89-7 0000-1733 190 DEGREE CORE SPRAY DOWNCOMER AND WELDS EIH2-89-7 1733-3116 CORE SPRAY PIPING 190 DEGREE TO 270 DEGREE INCLUDING THE PIPING WELDS AND THE 210 DEGREE BRACKET

' 116-3633 CORE SPRAY PIPING TEE BOX i 270 DEGREES 3

EIH2-89-7 AND WELDS EIH2-89-7 3633-4800 350 DEGREE CORE SPRAY DOWNCOMER AND WELDS Iv B3

p d

E.I.

NATCH UNIT 2 INVESSEL VISUAL TAPE LOG REFUELING OUTAGE NUMBER EIGHT - SEPTEMBER, 1989 PAGE 6 OF 11 TAPE NUMBER TAPE COUNT COMPONENT DESCRIPTION CORE SPRAY INTERNAL PIPING AND CORE SPRAY SPARGER INSPECTONS:

EIH2-89-7 4800-5452 CORE SPARY PIPING 270 DEGREE TO 350 DEGREE INCLUDING THE PIPING WELDS AND THE 330 DEGREE BRACKET EIH2-89-7 5452-5498

.001",

.003" AND.005" CAMERA RESOLUTION ON 09-20-89 0 0010 HOURS EIH2-89-7 5498-END 180 DEGREES OF THE TOP GUIDE EIH2-89-8 0000-2722 REMAINDER OF THE 180 DEGREES OF THE TOP r~)s GUIDE t

EIH2-89-8 2722-4265 UPPER CORE SPRAY SPARGER 270 DEGREE TO 10 TO 90 DEGREES, FIRST PASS ON "A"

SPRAGER EIH2-89-8 4265-5452 UPPER CORE SPRAY SPARGER 90 DEGREE TO 170 TO 270 DEGREES, FIRST PASS ON "C" SPARGER EIH2-89-8 5452-5960 UPPER CORE SPRAY SPARGER 270 DEGREE TO O DEGREES, SECOND PASS ON "A" SPARGER EIH2-89-8 5960-5974

.001",

.003" AND.005" CAMERA RESOLUTION ON 09-20-89 0 0830 HOURS EIH2-89-9 0000-0125

.001",

.003" AND.005" CAMERA RESOLUTION 1--

ON 09-21-89 0 0530 HOURS EIH2-89-9 0125-2290 UPPER CORE SPRAY SPARGER 270 DEGREE TO O TO 270 DEGREES, SECOND PASS ON "A AND C" SPARGERS 100%

EIH2-89-9 2290-3843 LOWER CORE SPRAY SPARGER 270 DEGREE TO 0-TO 270 DEGREES. THIRD PASS ON "B AND D" SPARGERS 100%. POSSIBLE PROBLEM WITH FIRST NOZZLE CW OF THE 190 DEGREE JUNCTION BOX (COUNT 3550)

[~\\]

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84

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)

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E.I. HATCH UNIT 2 INVESSEL VISUAL TAPE LOG REFUELING OUTAGE NUMBER EIGHT - SEPTEMBEA, 1989 PAGE 7 OF 11 TAPE NUMBER TAPE COUNT COMPONENT DESCRIPTION p

CORE SPRAY SPARGER AND TEEDWATER SPARGER INSPECTONS:

EIH2-89-9 3843-4917 LOWER CORE SPRAY SPARGER 270 DEGREE TO O TO 270 DEGREES, FOURTH PASS ON "B AND D SPARGERS 100%

EIH2-89-9 4917-5099 END PLATE WELDS ON THE UPPER CORE SPRAY SPARGERS 9 90 AND 270 DEGREES EIH2-89-9 5099-5273 END PLATE WELDS ON THE LOWFR CORE SPRAY SPARGERS 9 90 AND 270 DEGREES

()

EIH2-89-10 0000-1063 45 DEGREE FEEDWATER SPARGER LEFT END BRACKET AND BRACKET TO VESSEL WALL EIH2-89-10 1063-2391 45 DEGREE FEEDWATER SPARGER TOP PASS (NOZZLE AREA AND NOZZLE WELDS TO SPARGER) 1 EIH2-89-10 2391-2907 45 DEGREE FEEDWATER SPARGER RIGHT END BRACKET AND BRACKET TO VESSEL WALL EIH2-89-10 2907-3572 45 DEGREE FEEDWATER SPARGER PIPING AND l

PIPING WELDS EIH2-89-10 3572-3980 135 DEGREE FEEDWATER SPARGER LEFT END BRACKET AND BRACKET TO VESSEL WALL L

EIH2-89-10 3980-4515 135 DEGREE FEEDWATER SPARGER TOP PASS l

(NOZZLE AREA AND NOZZLE WELDS TO SPARGER)

EIH2-89-10 4515-4735 135 DEGREE FEEDWATER SPARGER RIGHT END BRCKET AND BRACKET TO VESSEL WALL EIH2-89-10 4735-5594 135 DEGREE FEEDWATER SPARGER PIPING AND PIPING WELDS i

O i

B5

-[~i i

~~

E.I.

HATCH UNIT 2 INVESSEL VISUAL TAPE LOG REFUELING OUTAGE NUMBER EIGHT - SEPTEMBER, 1989 I

PAGE 8 OF 11 TAPE NUMBER TAPE COUNT COMPONENT DESCRIPTION FEEDWATER SPARGER INSPECTONS:

EIH2-89-10 5594-5867 225 DEGREE FEEDWATER SPARGER LEFT END BRACKET AND BRACKET TO VESSEL WALL EIH2-89-11 0000-1377 REMAINDER OF THE 225 FEEDWATER SPARGER LEFT END BRACKET AND BRACKET TO VESSEL WALL AND TOP PASS (NOZZLE AREA AND NOZZLE WELDS TO SPARGER)

EIN2-89-11 1377-1704 225 DEGREE FEEDWATER SPARGER RIGHT END i

BRACKET AND BRACKET TO VESSEL WALL r^~

'k EIH2-89-11 1704-1763

.001",

.003 AND.005" CAMERA RESOLUTION w

ON 09-21-89 9 1700 HOURS EIH2-89-11 1763-1823 REMAINDER OF THE 225 DEGREE FEEDWATER SPARGER RIGHT END BRACKET AND BRACKET TO.

VESSEL WALL EIH2-89-11 1823-2577 225 DEGREE FEEDWATER SPARGER PIPING AND PIPING WELDS l

EIH2-89-11 2577-3048 315 DEGREE FEEDWATER SPARGER LEFT END BRACKET AND BRACKET TO VESSEL WALL EIH2-89-11 3048-4002 315 DEGREE FEEDWATER SPARGER TOP PASS (NOZZLE AREA AND NOZZLE WELDS TO SPARGER)

EIH2-89-11 4002-4156 315 DEGREE FEEDWATER SPARGER PIPING AND l-PIPING WELDS 315 DEGREE FEEDWATER SPARGER RIGHT END EIH2-89-11 4156-4788 BRACKET AND BRACKET TO VESSEL WALL (AREA ON RIGHT SIDE OF THE BRACKET TO VESSEL WALL)

B6

E.I. HATCH UNIT 2 INVESSEL VISUAL TAPE LOG REFUELING OUTAGE NUMBER EIGHT - SEPTEMBER, 1989 PAGE 9 OF 11

= TAPE NUMBER TAPE COUNT COMPONENT DESCRIPTION CLADDING PATCHES AND JET PUMP INSPECTIONS:

EIHE-89-11 4788-END CLADDING PATCH NUMBER 1 9 45, 2 9 135, 3 0 225 AND 4 0 315 DEGREES AND.001",

.003" AND.005" CAMERA ESOLUTION ON 09-22-89 9 0535 HOURS EIH2-89-12 0000-2098 JET PUMP NUMBER 1, 2,

3, 4,

5 AND 6 RISER BRACE ARM WELD AND INLET MIXER AREA EIH2-89-12 2098-252?

JET PUMP NUMBER 7 AND 15 RISER BRACE ARM WELD AND INLET MIXER AREA

.O EIH2-89-12 2573-2829 JET PUMP NUMBER 15 AND 16 RISER BRACE ARM WELD EIH2-89-12 2829-2988 JET PUMP NUMBER 16 INLET MIXER AREA EIH2-89-12 2988-3130 JET PUMP RISER BRACE ARM WELD ON JET PUMP NUMBER 17 SIDE EIH2-89 3130-3342-JET PUMP INLET MIXER NUMBER 17, CORRISION - 1/2" X 1/16" SEPARATION SHROUD SIDE EIH2-89-12 3342-3473 JET PUMP RISER BRACE ARM WELD ON THE JET PUMP NUMBER 18' SIDE EIH2-89-12 3473-3664 JET PUMP INLET MIXER NUMBER 18

-EIH2-89-12 3664-3850 JET PUMP RISER BRACE ARM WELD ON THE

-JET PUMP NUMBER 19 SIDE

^

EIH2-89-12 3850-3980 JET PUMP INLET MIXER NUMBER 19-EIH2-89-12 3980-4160 JET PUMP RISER BRACE ARM WELD ON THE JET PUMP NUMBER 20 SIDE EIH2-89-12

'4160-4270 JET PUMP INLET MIXER NUMBER 20 37

s

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1 j

E.I.

MATCH UNIT 2 INVESSEL VISUAL TAPE LOG REFUELING OUTAGE NUMBER EIGHT - SEPTEMBER, 1989

'PAGE 10 0F.11 1

1 TAPE NUMBER TAPE COUNT COMPONENT DESCRIPTION i

JET PUMP INSPECTIONS:

i i

EIH2-89-12 4270-4370 JET PUMP RISER BRACE ARM WELD ON THE JET PUMP NUMBER 8 SIDE EIH2-89-12 4370-4632 JET PUMP INLET MIXER NUMBER 8 EIH2-89-12 4632-4760 JET PUMP RISER BRACE ARM WELD ON THE JET PUMP NUMBER 9 SIDE EIH2-89-12 4760-4933 JET PUMP INLET MIXER NUMBER 9 EIH2-89-12 4933-5098 JET PUMP RISER' BRACE ARM WELD ON THE i'

JET PUMP NUMBER 10 SIDE I-EIH2-89-12 5098-5177 JET PUMP INLET MIXER NUMBER 10 r

EIH2-89-12 5177-5266 JET PUMP RISER BRACE ARM WELD ON THE JET PUMP NUMBER 11 SIDE EIH2-89-12 5266-5270 JET PUMP INLET MIXER NUMBER 11

.l EIH2-89-12 5270-5366 JET PUMP RISER BRACE ARM WELD ON THE JET PUMP NUMBER 12 SIDE EIH2-89-12 5366-5392 JET PUMP INLET MIXER NUMBER 12 EIH2-89-12 5392-5461 JET PUMP RISER BRACE ARM WELD ON THE JET PUMP NUMBER 13 SIDE EIH2-89-12 5461-5523 JET PUMP INLET MIXER NUMBER 13 EIH2-89-12 5523-5570 JET PUMP RISER BRACE ARM WELD ON THE JET PUMP NUMBER 14 SIDE 88

((()

E.I. HATCH UNIT 2 INVESSEL VISUAL TAPE LOG REFUELING OUTAGE NUMBER EIGHT - SEPTEMBER, 1989 p

PAGE 11 OF 11 TAPE NUMBER TAPE COUNT COMPONENT DESCRIPTION JET PUMP INSPECTIONS:

EIH2-89-12 5570-5657 JET PUMP INLET MIXER NUMBER 14 EIH2 89-12 5657-END

.001",

.003" AND.005" CAMERA RESOLUTION ON 09-22-89 9 0440 HOURS EIH2-89-13 0000-0102

.001",

.003" AND.005" CAMERA RESOLUTION ON 09-22-89 9 1800 HOURS O

EIH2-89-13 0102-2540 LOWER CORE SPRAY SPARGER 270 DEGREE TO O TO 270 DEGREES, FOURTH PASS ON "A AND C" I

SPARGERS 100%

EIH2-89-13 2540-2620

.001",

.003" AND.005" CAMERA RESOLUTION ON 09-23-89 0 0900 HOURS EIH2-89-13 2620-3270 RE SCAN ON 45 DEGREE FEEDWATER SPARGER PIPING LOWER SECTION ONLY

./

EIH2-89-13 3270-3593 RELOOK 9 THE 135 DEGREE FEEDWATER SPARGER INDICATION ON THE RIGHT SIDE END BRACKET TO VESSEL WELD EIH2-89-13 3593-4413 CLEANING AND RELOOK 9 THE 135 DEGREE FEEDWATER SPARGER INDICATION ON THE RIGHT SIDE END BRACKET TO VESSEL WELD e

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GPC procedure 42EN-ENG-014-OS provides guidelines for determining the ASME Section XI, Repair / Replacement requirements at E.I. Hatch Nuclear Plant.

The site Repair / Replacement Coordinator maintains an itemized list of Class 1 and 2 Repair / Replacement activities for each cycle.

A brief summary of major activities is included below and the following tables provide an itemized list of those activities which were included in the ISI boundaries.

The two manual RPV head vent valves, 2B21-F001 and 2B21-F002, were l

removed and the bypass vent line was capped off.

This work was performed per DCR 88-132 on MWO 2-89-3210.

Augmented examination of RWCU System welds per NUREG-0313 did not reveal any unacceptable indications.

However a surface indication was chased to the weld root and GPC elected to remove and replace a short section of piping.

Three (3) welds were cut out and replaced with four (4) new welds.

This activity is not included in the following tables because this is non-safety related piping.

However examination results for these welds are included in the Augmented Section of this report.

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All twenty (20) jet pump hold down beams were replaced with a new design per recommendations from GE.

The jet pump hold down beams were replaced on KWO 2-89-4067.

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REPLACE C O 14-15 WITH RE9 JILT GENERAL ELECTRIC NYOU 304 %/A 8d3 2-29-2503 SPARE 2 Cit-CRD-18 2311 1

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REPLACE CRD 25-47 WITH REB]Ili GENERAL ELECTRIC HCR0 DCR h/A M 2-89-2493 SPARE 2011-CRD-34-23 2811 1

REPLACE CRD 34-23 WITH REBUILT GEMERAL ELECTRIC NY3C DCR M/A N 3 2-89-2507 SPARE 2C11-CO-34-35 23t1 1

REPLACE C E 34-35 WITH REW ILT GEMERAL ELECTRIC HYDE DCR N/A N 2-89-2497 SPARE 2 Cit-CRD-34-39 2311 1

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GPC is. committed to perform various augmented NDE examinations.

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Nine (9) RHR welds, one (1) Core Spray weld, one (1) HPCI weld and five (5) RCIC welds were examined due to GPC commitments in exces ASME Section XI requirements for ECCS.

examination results.

No indications were noted in the Two (2) CRD welds and one (1) RWCU weld were examined due to augmente commitments to NUREG-0619.

No indications were detected.

Seven (7) welds in the RWCU System were UT examined per augmented commitments by GPC to NUREG 0313.

downstream of the outboard containment isolation valve which wasT classified as non-safety related by GPC.

The UT exams revealed no unacceptable indications.

However, a PT exam was performed due to some additional surface conditioning on one weld which detected a surface indication.

This indication was chased to the weld root and due to the sensitivity of the exams, GPC elected to remove a section of.

piping and have metallurgical examinations performed to determine the cause of the indication.

Metallurgical examination determined the defect to be a welding flaw and no IGSCC indications existed.

The following tables list the augmented examinations performed and supply reference to supporting documentation.

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145-w PIPE TO PIPE PT PT-n-680/2 S89#2CZ23 UT Cat.

sesetine 1989 S8942U316 X

PT performed try S8942CZ25 UT Cat.

GPC OC.

i S89W2U318 UT Thickness note 2 X

l C-129/0 2s31-3aWCU-4-0-11 UT UT-R-401/T 589n2P051 x

145-w PIPE TO EL90U PT PT-N-600/2 589N2U1T1 X

Lineer indication 589#2C142 UT Cat.

detected. See inF

$89u2U1T4 x

I89N2008. Pipe seetion 1

$89n2C145 UT Cat, was replaced.

U 58942U1TT n

note 1 N

S89#2C148 UT Cat.

589N2U132 UT Thickness

U, uY

.x I

!x

!x-

,1 ]19 :

l]i s :

,1]19~

11

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Edwin 1. notch Unit 2 1989 Fett Refueling Outo9e Augmented Couponents Page 6 of 8 i

ASSE RI aEsennetSteASic EMm seE Emme/ CAL SECTION MI Exase CAT. NO.

FIG. W.

EMMIMTitMt m IETO 6

SEET W.

E E

EEtst/0TER EtMATim SLtKK 6

t c-0313 E-mailous (Cent'd) i C-129/0 2s31-3awas-4-0-17 UT UT-n-401/7 589n2U178 x

145-s i

$8942C149 UT Cet.

Note 1 PIPE TO EL90W

$89u2U175 N

$89u2C146 UT Col.

389u2U172 N

$8942C143 UT Col.

$89u2U159 UT Thickness C-130/0 2sst-3eucu-4-a-5 UT UT-n-481/7

$8meu23s x

145-w

$8952C186 UT Cat.

esote 1 PIPE TO elbow S8952U183 X

$8952C158 UT Cet.

r

$8942u236 x

$89n2C186 UT Cat.

589u2U157 UT Thickness 6

b

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' Edwin 1. Match Unit 2 1987 Fett Refueling Outebe Augmented Components Page 7 of 8 ASME tl REnMMts/9ASIC EMAft ISE EWWI/ CAL SECTION NI EIUWI CAT. 110.

FIG. No.

ENNRIS Ti m/ W IETIIW PROCEDt2E SEET N0.

NI WI GEtBVOTER CALt9EATI(NB SLOCK f

neuREG-0313 ERNIIIIATItWS (Cont'd)

C-130/0 2G31-3mucu-4-R-6 UT UT-N-401/7

$89u2U186 K

145-N 589u2C159 UT Col.

Isote 1 EL90W TO PIPE

$8942U237 X

$89N2C185 UT Cat.

(

S89u2U239 K

$89u2C187 UT Cat.

S8942U158 UT Thickness C-125/0 2G31-3RUCU-6-D-2 UT UT-n-401/7 S89u2P864 X

133-#

$89182M230 x

mote 1 EL90W TO PIPE

$891kt.178 UT Cet.

S89u2u232 x

$89n2C180 UT Cat.

S89u2U236 x

$89n2C182 UT Cat.

$89N2U246 UT Thickness O

Un


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g_

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.c

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Edwin 1. Hetch 1: nit 2 1989,fatt tefueting Outage Aussented Components Page 8 of 8 NSI 0 at-

~

CAttenAT10m OLocK GE M TNga ASME E)U88 suEET No.

El un

' ENAft PROCEpumE SECT 10m X1 EWIW NM.

CAT. NO._

_F IG 380--

tamEG-0313 ElullGinATIGIS NT 133-u I

UT-N-401/7 M

W C*'-

2c31-3aucu-6-o-3 seenzc179 c-125/0 PIPE TO EL50W 589u2U233 UT Cat.

g ggi X

ss9u2u235-UT cat.

ss9u2C183 UT Thickness Md1M W

Weld included in originnt examination scope.

1.

new weld added due to cutout and reptocement of pi e section.

P 2.

tion.. weld emanined in originnt sc e i

Replacement weld due to. cutout and reptocament of p pe sec 3.

and also examined as new besetine.

Examined as Wetine & M MM d N in originnt emmoination scope.

4.

Weld not pipe section.

O 01

ENCLOSURE'2 NRC DOCKET 50-366 l

EDWIN 1. HATCH NUCLEAR PLANT UNIT 2 NONDESTRUCTIVE EXAMINATION OF FEEDWATER N0ZZLE SAFE END, AND CONTROL R0D DRIVE RETURN LINE WELDS DURING THE 1989 MAINTENANCE / REFUELING OUTAGE i

The following information is provided in accordance with NRC NUREG-0619, "BWR Feedwater Nozzle and Control Rod Drive Return Line Nozzle Cracking,"

and pertains to the nondestructive examination (NDE) of feedwater nozzles and safe end welds performed at Georgia Power Company's (GPC) Plant Hatch Unit 2 during the 1989 maintenance / refueling outage.

I.

STARTUP/ SHUTDOWN CYCLES EXPERIENCED When Unit 2 was shut down in September 1989 for maintenance and refueling, 132 startu)/ shutdown cycles had been experienced.

Nineteen (19) startup/slutdown cycles have been experienced since the feedwater nozzles and safe-end welds were last examined during the 1986 maintenance / refueling outage.

II.

NONDESTRUCTIVE EXAMINATION RESULTS provides a summary of the examination results for the feedwater nozzles, safe end, and CRD return line weld examinations o

conducted at Plant Hatch Unit 2 during the 1989 maintenance /

refueling outage.

No significant indications or evidence of cracking were noted during the performance of the examinations.

The scheduled external ultrasonic (li) examinations of the 2N4A; 2N4B, 2N4C, and 2N4D feedwater nozzle safe end-configuration welds (pipe-to-transition l

piece weld and transition piece-to-nozzle weld), nozzle center bore

sections, and nozzle inner blend radii were performed'in accordance with Table 2 of NUREG-0619.

In addition to the UT examinations, a required ASME Code,Section XI surface examination was performed on the safe end configuration welds. The results of previous Plant Hatch Unit 2 feedwater component examinations were provided to the NRC in GPC letter SL-2621, dated June 12, 1987, and consequently, are not included herein.

h 000281 HL-978 E2-1

ENCLOSURE 2 (Continued)

FEEDWATER N0ZZLE SAFE END, AND CONTROL ROD DRIVE RETURN.LINE WELDS DURING THE 1989 MAINTENANCE / REFUELING OUTAGE III.

NONDESTRUCTIVE EXAMINATION METHODS ine NDE methods employed for the examination of the subject feedwater components during the Plant Hatch Unit 2 1989 maintenance / refueling outage were:

(1) manual ultrasonic, and (2) magnetic particle (MT) or penetrant (PT). Ultrasonic scans were performed -on each nozzle center bore section and on the inner blend radius of.each nozzle. Safe end welds were ultrasonically examined and also were examined using surface techniques.

the examination procedures employed.

The subject NDE-references ~ are available at the Hatch Plant site for review by NRC procedures personnel upon request.

IV.

EFFECTS ON PREDICTION OF FUTURE CRACKING TENDENCIES A design change was implemented this outage on the feedwater system in an attempt to reduce low flow feedwater oscillations by slowing the closure time on the feedwater minimum flow bypass control

' valves.

The operating procedures for Unit 2 are now similar to those-for Unit 1.

V.

'0N-LINE LEAKAGE MONITORING An on-line _ leakage monitoring system for _the detection of feedwater leakage,- which could result in nozzle cracks, as described in NUREG-0619, is not installed on Plant Hatch Unit 2 and, therefore, is not applicable.

i 000281 HL-978 E2-2