ML20097F547

Owner'S Data Rept for ISI Ei Hatch Nuclear Plant Unit 2 Sept-Nov 1995

ML20097F547
Person / Time
Site:	Hatch
Issue date:	01/31/1996
From:	GEORGIA POWER CO.
To:
Shared Package
ML20097F544	List: HL-5105, Forwards Owner'S Data Rept for ISI Ei Hatch Nuclear Plant Unit 2 Sept-Nov 1995, Including Ultrasonic Exams of Austenitic Stainless Steel Piping Welds in Primary Coolant Pressure Boundary,Per GL 88-01 & NUREG-0313,Rev 2 ML20097F547
References
NUDOCS 9602160097
Download: ML20097F547 (107)

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. OWNER'S DATA REPORT FOR INSERVICE INSPECTION i 1

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EDWIN 1. HATCH NUCLEAR PLANT i

UNIT 2 I

j SEPTEMBER 1995 -NOVEMBER 1995 i

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1 9602160097 960212 PDR ADOCK 05000366 l G PDR i

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1 TABLE OF CONTENTS PAGES I. ASME FORM NIS-1 AND SUPPLEMENTARY INFORMATION 1-5 II. ABSTRACT 6-11 III. EXAMINATION

SUMMARY

A. CLASS 1 EXAMINATIONS 12-27 B. CLASS 2 EXAMINATIONS 28-39 C. PRESSURE TESTING 40-41 D. COMPONENT SUPPORTS 42-54  !

E. AUGMENTED EXAMINATIONS 55-57 F. REACTOR PRESSURE VESSEL INTERNALS 58-85 G. REPAIRS AND REPLACEMENTS86-101 IV. CODE CASE

SUMMARY

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NOTE: Portions of this report are compiled from Southern Nuclear Operating Company report; I l

" Nondestructive Examination of Selected Class 1,2, and 3 Components", issued for the Fall 1995 Refueling Outage at E. I. Hatch Nuclear Plant, Unit 2. This report is available for review in the Records Management Department at the plant site.

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LIST OF ABBREVIATIONS ANI/ANII Authorized Nuclear InspectodAuthorized Nuclear Insenvice Inspector >

ASME American Society ofMechanical Engineers ASNT American Society of Nondestructive Testing BC Branch Connection BWR Boiling Water Reactor l CH Closure Head '

l CONT Containment j CPI Containment Purge and Inerting CRD Control Rod Drive CS Core Spray C'U Clean-up C&L Cramer and Lindell DCR Design Change Request ECCS Emergency Core Cooling Systems ET Eddy Current Examination EPRI Electric Power Research Institute FB Flange Bolting FPC Fuel Pool Cooling FW Feedwater i GE General Electric GPC Georgia Power Company HL Hanger Lug HPCI High Pressure Coonant Injection INF Indication Notification Form IGSCC Intergranular Stress Corrosion Cracking ISI Inservice Inspection 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 <

LMT Lambert, MacGill, Thomas, Inc.

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 MS Main Steam MSA Main Steam Auxiliary MT Magnetic Particle Examination MWe Megawatt Electric MWO Maintenance Work Order MWt Megawatt Thermal I NDE Nondestructive Examination i

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Abbreviations - cont.

NI No Indication NRC Nuclear Regulatory Commission  ;

OL Overlay PL Pipe Lug PLT Plant PR Pipe Restraint PROD Product PS Pipe Support PSW Plant Service Water  ;

PT Liquid Penetrant Examination I QC Quality Control ,

RC Reactor Recirculation l

RCIC Reactor Core Isolation Cooling l RHR Residual Heat Removal l RHRSW Residual Heat Removal Service Water RI Recordable Indication RINTSA Recirculation Inlet Nozzle Thermal Sleeve Attachment i RL Refracted Longitudinal RL Restraint Lug RPV Reactor Pressure Vessel RX Reactor RWCU Reactor Water Cleanup  :

SBLC Standby Liquid Control  !

SIAI StructuralIntegrity Associates,Inc. l SER Service SRV Safety Relief Valve SNC Southern Nuclear Operating Company l TBP Turbine Bypass TDP Torus Drainage and Purification UT Ultrasonic Examination VLV Valve VT Visual Examination This list is comprised of standard abbreviations used in Inservice Inspection Documentation. All of these abbreviations may not appear in this report.

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l TOTAL NUMBER OF SHEETS 102 l FORM NIS-1 j FORM NIS-1 OWNERS' DATA REPORT FOR INSERVICE INSPECTIONS As Required By the Provisions of the ASME Codes Rules

1. Ownet - Geornia Power Comoany. 333 Piedmont Ave.. NE. P. O. Box 4545. Atlanta Geornia 30302 1

2. Plant: Edwin I. Hatch Nuclear Plant Route 1. Box 278. Barlav. GA 31513. l

3. Plant Unit 2 4. Owner Certi6cate of Authorization (if req.) Nli

5. Commercial Service Date 09/05/79 6. National Board No. for Unit N/A

7. Components Inspeceo:

Component of Manufacturer State or Appurtenance Manufacturer orInstaller Province National nr_SyRam or Installer Serial No. Number Board No.

Rx. Pressure Vessel Combustion Eng. 70101 N/A 11570 Rx. Pressure Vessel Combustion Eng. 70101 . N]A 11570 2B21 Feedwater Pullman Power Prod.

• N/A N/A 2B31 Reactor Recire.

• Pullman Power Prod. N/A N/A 2C11CRD Pullman Power Prod.

• N/A N/A 2E11 RHR Pullman Power Prod.

• N/A N/A.

2E21CS 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 2OJ3J RWCU Pullman Power Prod.

• N/A N/A 2 Nil MS Auxiliary

• Pullman Power Prod. N/A N/A 2N21 FW Pullman Power Prod.

• N/A N/A 2T47 Primary Cont. Clg. Pullman Power Prod.

• N/A N/A 2T48 Cont. Purge

• Pullman Power Prod. N/A N/A Note: Supplemental sheets in form oflists, sketches, or drawings may be used provided (1) size is 81/2 in. x 11 in., (2) information in items 1 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 or 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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FORM NIS-1 (Back)

8. Examination Dates 04/24/94 to 11/19/95, i

9. Inspection Interval from 01/86 to 01/96.

10. Abstract of Examination. Include a list of examinations and a statement concerning status of work required for current interval. "*

11. Abstract of Conditions Noted. "*

12. Abstract of Corrective Measures Recommended and Taken. "*

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 M '19M Signed Geornia PowerCompany By Mb%f.s V )

y Certificate of Authorization No. (if applicable ) N!/A ExpirationDate N/A CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and/or the State or Province of GA and employed by *"* of Hartford, CT have inspected the components described in this Owner's Data Report during the period 4/94 to 11/95 and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owners' Data Report in accordance with the requirements of the ASME Code, Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owners' Date Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

Date bl W 199b c Commissions CsengGM - GA Oolld Inspector's signature National Board, State, Province, & No.

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

• • " Hartford Steam Boiler Inspection and Insurance Company.

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1. Owner. C ir Comunamv.333 r' ' ' Am. NE P. O. Baz 4545. .' ' - C_.2 M_MS

2. Plass: Ph 1,13" Nuclear Plast h 1. Baz 273. L 8-v. GA 31513.

3. Plast Unit 2 4. Owner Certinomie or Aushumassam (afM)h S. comumenial Savice Date 09W/9 6. National Board Na for Unit N_lA NIS-1 Form Supplementary Information Owner's Data Report for Inservice Inspection OwnerName & Address: Georgia Power Company

) 333 Piedmont Avenue, N.E.

P. O. Box 4545 Atlanta, Georgia 30302 Name & Address ofNuclear Ganaratino Plant:

Edwin I. Hatch Nuclear Plant Route 1, Box 278 Baxley, Gecrgia 31513 Name Assinned to Nuclear Plant Station:

1 Edwin I. Hatch Nuclear Plant Unit 2 l

Commercial Service Date: September 5,1979 l

l Gross Generatina Capacity:

2558 MWt,850 MWe l State. province. or Municipality Assinned Number: N/A

' I National Board Number Assinned by manufacturer: N/A !

l System Pressure /Leakane Tests q

l Syllam Class Test Required

) Reactor Pressure Vessel and 1 1 Leakage Associated Class 1 Piping and Components 1

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1. Owner: Geormia Power Conmanv. 333 Ph Ave.. NE. P. O. Bnx 4543. P'-"- Georain 30302

2. Plant: Edwm 1. liasdi Nuclear Plart Route 1. Box 278. Baxlev. OA 31513.

3. Plant Unit 2 4. Owner Certirmata of Authorustaan (if req.) M l S. Cornmercial Service Date 0995/79 6. National Board No. for Unit N_%

i Name & address of Manufacturer of Components:

1. Reactor Pressure Vessel and Closure Head:

Combustion Engineering, Inc.  !

l Chattanooga, TN l

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2. Piping (Classes 1,2, and 3) '

a. Pullman Power Products l

Division of Pullman-Kellogg Williamsport, PA I I

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 l Hatch Plant Site.

3. Piping Supports and Hangers (classes 1,2, and 3) I

a. Bergen-Paterson Pipe Support Corporation )

Laconia, NH I

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b. E-Systems Enertech Orange, CA

c. Pacific Scientific Anaheim, CA

d. Liesega USA Laconia, NH l 1

4. Valves, Pumps, and Heat Exchangers

a. Byron-Jackson, Inc.

Los Angeles, CA

b. Crane New York, NY

c. Wm. Powell Company I Cincinnati, OH I

d. General Electric San Jose, CA Date ofInservice Inspection: September 1995 to November 1995 i

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1. Ovmsr. oeorma Power Om. 3: 1 W Ave _. NF_ P. O. Box 4543. #t-d- % O 30302

2. Plam; EdLwin I. Ilandi Nuclear Plant Route 1. Box 278. Baxlev. GA 3 IS 13.

3. Plant Unit 2 4. Ownce certirscate or Authoruation (if req.) h

5. CommercialService Dese 0995r/9 6. National Board Na for Unit ff.6 Completion Date ofInservice Inanection:

November 19,1995 Name ofInspector: Donald R. Laakso (ANI/ANII)

Name & Mailing Address ofInspector's Employer:

The Hartford Steam Boiler Inspection and Insurance Company 200 Ashford Center- Nonh Suite 300 Atlanta, Georgia 30338 5

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1. Owner: CM L Cornmenv.333 7 * ^ Aw..NE. P. O. Box 4545. A" CR 30302

3. Plant: Edwin 1. Has& Nuclear PlanL Route I. Box 278. Baxlev. OA 31513.

3. Plant Unit 2 4. Owner Cana6 case of Authoruasson (ifreg) N/A

5. Canunercial Service Date 09@5/79 6. National Board No. for Unit H%

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 1995 Maintenance / Refueling Outage. The l components were examined in accordance with the applicable ISI Outage Plan, including any changes made during the outage as approved by GPC.

Edwin I. Hatch Unit 2 is currently in the third period of the second 10-Year Inspection Interval. The required examinations are presently on schedule as specified in the Second Ten-Year Inspection Plan.

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

SNC and GPC personnel and their contractor GE, performed NDE of the selected welds and components. In addition, GE personnel performed the VT examination of selected RPV internal components. SNC, GE, or GPC NDE procedures were utilized for all ASME Section XI examinations.

GE personnel were qualified to the applicable SNC procedures. EPRI qualified inspectors were utilized l for all examinations involving IGSCC susceptible materials. GE procedures were used for mechanized ultrasonic examination and exams were performed by GE inspectors.

In addition to NDE testing of Class 1 and 2 welds and components, pressure testing, visual examination of Class I component internal surfaces and visual examination of pipe supports and hangers were also performed. Third party review (e.g. an ANII) was utilized for all examinations of ASME Section XI components.

Selected components were examined in accordance with GPC commitments to the following 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, Generic Letter 88-01, "NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping" which invokes much of NUREG 0313, Revision 2, " Technical Report on Material Selection and Processing Guidelines for BWR Coolant Pressure Boundary Piping".

l United States Nuclear Regulatory Commission, Generic Letter 81-11, which modifies and invokes NUREG 0619, "BWR Feedwater Nozzle and Control Rod Drive Return Line Nozzle Cracking" 1

United States Nuclear Regulatory Commission, I&E Bulletin 80-13 Visual Examination of Core Spray Spargers has been closed out via NUREG/CR-4523. The required bulletin actions have been performed satisfactorily and will be continued during every refueling outage.

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SNC " Inservice Inspection Outage Plan, Edwin I. Hatch Nuclear Plant, Unit 21995 Fall Refueling

( Outage."

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1. owner: Georma Power C<mananv. 333 F ' -" Ave.. NE. P. O. Box 4545. .^d" 2.

C M 30302 Plast: Edwin 1. Fa Ne - Plant Ronde 1. Box 278. hk OA 31513.

3. Plant Unit 2 4. Owner Certiricase of Authorustson (ifreq.) N/A

5.  ? -4.1 Service Dese 0995/79 6. National Board No. for Unit N/6 SNC "Second Ten-Year Examination Plan, Edwin I. Hatch Nuclear Plant Unit 2."

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

i Representative samples of the following systems, comprised of selected Class I and 2 Components, were !

examined using various NDE techniques, in accordance with the above documents:

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Reactor Pressure Vessel (2B11) '

Feedwater System (2B21)

Reactor Recirculation System (2B31) ,

Residual Heat Removal System (2El1) l Core Spray System (2E21) 1 High Pressure Coolant Injection System (2E41) l l

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Control Rod Drive System (2Cl1)

Residual Heat Removal System (2El1) l Core Spray System (2E21)

High Pressure Coolant Injection System (2E41)

Reactor Core Isolation Cooling System (2E51)

Reactor Water Cleanup System (2G31) l Main Steam Auxiliary (2N11) i Feedwater System (2N21) l Primary Containment Cooling System (2T47)

Containment Purge and Inerting (2T48) i- Other- Augmented (Non ASME Section XI) l Seven (7) Non-Safety RWCU System welds were examined using ultrasonic examinations techniques L (UT) due to commitments rnade by GPC. These augmented exams are not required by the ASME Section XI Code but were performed due to commitments to GL 88-01.

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1. owner: Omarma Power Camnanv. 333 W Ave.. NE. P. O. Box 4545. .**'" Geormia 30302

3. Plant: . Edwin 1 Hatch Nuclear Plam. Ronde 1. Box 278. Baxley,OA 31111

3. Plam Unit 2 4. Owner Cortiricate of Authorization (if req.) M

5. commercial Service Date 0995/79 6. National Board No. for Unit N3 CLASS I EXAMINATIONS NUREG 0313 GPC is committed to the performance of surface and volumetric examinations on IGSCC susceptible ,

l welds in accordance with NUREG 0313. This commitment is formahd h GPC response to NRC l

Generic Letter 88-01. The below listed summary gives the total number of exams performed by outage end.

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! Catenorv A Two (2) Category A Mts were examined. No indications were found that exceeded Code allowable linuts. '

Category D Four (4) RINTSA welds were examined by UT and no indications were found that exceeded Code l allowable limits.

Other Class 1 Examinations Forty-five (45) ASME Section XI component examinations were performed utilizing UT, MT, PT and VT as applicable. These examinations included: RPV welds, piping welds, valve internals, and valve bolting materials.

Per I&E Bulletin 80-13 (NUREG/CR-4523), the core spray sparger and associated piping were VT examined. Indications are acceptable as is for one more cycle ofoperation per General Electric.

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 RPV internal components. See the Invessel Inspection section of this report for more detailed information.

Nine (9) Class 1 valves were disassembled for maintenance / inspection during the outage. The internals of these valves were VT inspected by GPC QC personnel.

l Per SIL 433, all Shroud Head Bolts were examined. Indications of cracking were recorded Et two (2) of these bolts. All indications were evaluated by General Electric and found to be acceptable for continued service.

l CLASS II EXAMINATIONS Sixty-eight (68) welds were examined using surface and/or volumetric NDE techniques as applicable per l ASME Section XI requirements. Three (3) welds were examined per NUREG-0619 (UT only), fourteen (14) welds were augmented examinations (MT only), and the remaining fifty-one (51) welds were examined per ASME Section XI requirements.

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! 1. Owner: Georma Power Comnany. 3331%aanad Ave..NE. P. O. Box 4540 Atlansa. ocorma 30302 I

2. Plant: Edwm I, Hatch Nh Plant Route 1. Box 278. hlav. GA 319l3.

3. Plant Unit 2 4. Owner Certiricate of Authorussian (if req.) NL%

5. Commercial Service Date 0995/79 6. National Board No for Unit Ela Pressure Testing One (1) Class I system leakage test was performed satisfactorily. The Pressure Test Section of this report provides specific test identification and details.

Component Support Examinations (Class I and 2)

Twenty-nine (29) component supports were VT examined per the requirements of ASME Section XI l during the outage with no recordable indications.

Snubber Examinations (Class 1 and 2) l Forty-eight (48) snubbers were VT examined per GPC QC procedures. All of the snubbers were l determined to be acceptable.

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Auamented Examinations Seven (7) welds in the non-safety portion of the RWCU System were examined by UT per a GPC commitment to the NRC for NUREG 0313, Rev. 2, augmented requirements. No reportable indications were detected.

l Repairs and Replac&ments (Class 1 and 2)

Numerous repair / replacement activities were performed prior to and during the outage. An itemized list of the repair / replacement activities is included in the Repair / Replacement Section of this report.

, Reoortable Indications l

Following is an itemized list of all welds and components which were reported with indications of which l were considered unacceptable. All of these items were either repaired and/or evaluated and then

determined to be acceptable.

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1. owner, C- i T Comoanv. 333 P' ' Avat. NE. P. O. Bar 454$. .A*'-* C A 30302 l 2. Plant: Edwin 1.18" N=" Plant Route 1. Box 271. Rawlav. GA 31513.

l 3. Plant Unit 2 4. Owner Certancese or Austwrushan (if req.) M

$. Caramercial Service Dade 09q$r/9 l

6. National Board No. for Unit N/A Summary ofIndications Identification Indication Corrective Action Support Bolt found missing from base Repaired. MWO 2-95-3197.

2T41-B003A-S01 plate to floor.

Core Spray Internal Piping Crack-like indication found in Acceptable for continued N-2A heat affected zone ofweld 17. operation per GE Lower Core Spray B Linear indications recorded on Acceptable for continued M-1B bracket to shroud attachment operation per GE welds.

Shroud Head Bolts Suspect indications found. Acceptable for continued

1. 10 and #24 operation per GE Valve Bodies Minor gouges found in the body Evaluated as acceptable 2B21-F010B above the spacer ring. per GPC Engineering Valve Bodies Gouge on valve stem. Replaced. MWO 2-95-2847, 2El1-F015A Valve Bolting Thread damage on 3 studs. Evaluated as acceptable 2El1-F015B per GPC engineering.

CRD Bolts Minor pitting localized in area Replaced. MWO 2-95-1442.

near the bolt head.

CRD Bolts Small cracks near the head of Replaced. MWO 2-95-1442.

the bolt.

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1. owner: QegamefowerConssenv.3337 ' Ave.. NE. P. O Box 4545. ?d-^^^ C a 30302

2. Plant: Edwin I.18" Nah PlanL #~** 1. Dos 278. Ha Lv.O A 31513. ,

3. . PlantUnit1 4. Owner Certincase of Authoruation(if%)HQL '

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' 5. ComunercialSe Dem 094509 6. Natsmal Doerd No. fw Unit E%

The following sections contain a summary of the NDE Examinations performed, provide additional information, and provide the results of those examinations.

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1. Owner: C A T C- .333T'- - ' Ave.. NE. P. O. Box 4545. .* d"- C A 30302

2. Plant: Edwm 1. Hatch Nuclear Plant Route 1. Box 278. Ikulev. OA 315E

3. Plant Unit 2 4. Owner Certificate of Authorumbon (ifreq.) E

5. Commercial Service Dese 09W19 6. National Board No. for Unit H%

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SUMMARY

OF CLASS 1 EXAMINATIONS I

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E.L Hatch Unit 2 Class 1 Components Exam / Cal ASME Exam Figure Results Remarks Section XI No. Examination / Area Examination Procedure Cal Block ShootNo. . _ _ _ .

BEkCTORPRESSURENESSEL ASSEMBLY UT-HAT-702V0/00 62-H C-G2K-13 CAL 16 NON-GEOMETRIC B1.30 A-1/05 2C-1 UT-HAT-306V0/01 27-H HA2018 R1 NON-GEOMETRIC INDICATICNS WERE FOUND B-A ^

RPV001 NRI EP B O ASE ASME VESSEL-TO-FLANGE SECTION XI. LIMITED EXAM DUE TO FLANGE - 86.5%

COVERAGE.

UT-HAT-702VD/00 62-H HA2011 RI NON-GEOMETRIC 2 NON-GEOMETRIC 81.12 A-1/05 2C-1-A INDICATIONS WERE FOUND B-A UT-HAT-300VCi00 ASME LO TUDINAL WELD ON UPPER A CE T B O A ME SECTION XI. 93.7%

COVERAGE.

UT-HAT-702V0/00 62-H HA2014 Rt NON-GEOMETRIC 5 NON-GEOMETRIC B1.12 A-1/05 2C-1-B INDICATIONS WERE FOUND UT-HAT-300V0/00 B-A ASME LONGITUDINAL WELD ON UPPER A CE TABLE O ASME SHER SECTION XI. 91.2%

COVERAGE.

UT-HAT-702VD/00 62-H HA2013 Rt NON-GEOMETRIC 23 NON-GEOMETRIC B1.12 A-1/05 2C-1-C INDICATIONS WERE FOUND UT-HAT-300V0/00 B-A ASME LO TUDINALWELD ON UPPER . A CEPTABLE O ASME SECTION XI. 92.1%

COVERAGE.

UT-HAT-702V0/00 62-H HA2016 RI NON-GEOMETRIC 7 NON-GEOMETRIC B1.11 A-1/05 2C-2 RPV INDICATIONS WERE FOUND UT-HAT-300V0/00 B-A A E " CE T B O A ME DDLE SHE SECTION XI. LIMITED EXAM DUE TO STABILIZER BRACKETS. 83.7% COVERAGE Pogo: 13 i. Ow . -m wu O. Box 4543. e c 3o3o2

2. Flest Edws: L Hatch Nuclear Flest Rome L Bos 27L Bexlev.GA 3y13.

3. Em Unit 2 4. Owner Ceru6 case of Aushonzance (sg) E

3. t'W Service Dese 0945/79 6. Nationni Boant No. for Unia E/A

E.1. Hatch Unit 2 Class 1 Compononis Exam / Cal ASME Exam Figure Remarks No. Examination Procedure Cal Block Sheet No. Results Section XI ExaminationfArea UT-HAT-702V0/00 62-H HA2010 RI NON-GEOMETRIC 3 NON-GEOMETRIC B1.12 A-1/05 2C-2-A INDICATIONS WERE FOUND UT-HAT-300V0/00 AND EVALUATED AS B-A ASME LONGITUDINALWELD ON UPPER ACCEPTABLE TO ASME MID SHELL SECTION XI. 95.7%

COVERAGE.

UT-HAT-702V0/00 62-H HA2015 RI NON-GEOMETRIC S NON4EOMETRIC B1.12 A-1/05 2C-2-B INDICATIONS WERE FOUND UT-HAT-300V0/00 B-A LO" A CEPT OASME A E D SECTION XI. 95 6%

COVERAGE.

UT-HAT-702V0/00 62-H HA2012 R1 NON-GEOMETRIC 3 NON-GEOMETRIC B1.12 A-1/05 2C-2-C INDICATIONS WERE FOUND UT-HAT-300V0/00 B-A

'O" " ACCE TAB OASME yD H SECTION XI. 90 4%

COVERAGE.

UT-HAT-702V0/00 62-H HA2009 Ri NONGEOMETRIC 4 NON-GEOMETRIC B1.11 A-1/05 2C-3 RPV INDICATIONS WERE FOUND UT-HAT-300V0/00 AND NUATED AS B-A ASME UPPER MIDDLE SHELL-TO- ACCENN TO ASME LOWER M!DDLE SHELL SECTION XI. 95 8%

COVERAGE.

UT-HAT-702VD/00 62-H HA2006 RI NON-GEOMETRIC 1 NON-GEOMETRIC B1.12 A-1/05 2C-3-A INDICATION WAS FOUND AND g.A UT-HAT-300V0/00 T SME SEC 10 X 91 4

^b COVERAGE.

UT-HAT-702V0/00 62-H HA2007 R1 NON-GEOMETRIC 9 NON-GEOMETRIC B1.12 A-1/05 2C-3-B INDICATIONS WERE FOUND UT-HAT-300VQ/00 B-A LONGITUDINALWELD ON LOWER A CEPTAB E TO A ME ASME MID SHER SECTION XI 94.3%

COVERAGE.

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1. Oumar: Georans Fows Comunemy. 333 Findmann Avat. NE F. O. Bom 4545. ."

2. Flam: Edinn L :" ^" - Fleet - 1. Bam 278. ' .GA 31511

3. FinsaUnit2 4. Owner Ceredianas of 6.Audianamnes 6fm) N/.A NasionalBoent No. for Unit tgA S. CommmercialService Dune OMSU9

E.L Hatch Unit 2 Class 1 Components ASME Exam Figure Exam / Cal Section XI No. Shoot No. Results Remarks Examination / Area Examination Procedure _ Cat Block _ _ _ _ - . _ _ .

2C-3-C UT-HAT-702V0/00 62-H HA2008 RI GEOMETRY 93 6% COVERAGE.

B1.12 A-1/05 B-A UT-HAT-300V0/00 ASME LONGITUDINAL WELD ON LOWER ,

MID SHELL A-1/05 2C-4 RPV UT-HAT-702V0/00 62-H HA2005 RI NON-GE'OMETRIC 9 NON-GEOMETRIC Bl.11 INDICATIONS WERE FOUND B.A UT-HAT-3N AND EVALUATED AS ASME LOWER MIDDLE SHELL- TO- ACCEPTABLE TO ASME LOWER SHER WEW ~ SECTION XI. 96 2%

COVERAGE.

A-1/05 2C-4.A UT-HAT-702V0/00 61-H HA2001 R1 NON-GEOMETRIC 14 NON-GEOMETRIC B1.12 INDICATIONS WERE FOUND e UT-HAT-N AND EVALUATED AS ASME LONGITUDINAL WELD ON LOWER ACCEPTABLE TO ASME SHELL SECTION XI. 90.9%

COVERAGE.

81.12 A-1/05 2F-4-B UT-HAT-702V0/00 61-H HA2002 RI NON-GEOMETRIC 9 NON-GEOMETRIC INDICATIONS WERE FOUND B-A UT-HAT-300V0/00 AND EVALUATED AS ASME LONGITUDINAL WELD ON LOWER ACCEPTABLE TO ASME SHER SECTION XI. 91.9%

COVERAGE.

2C-4-C UT-HAT-702V0/00 61-H HA2003 RI NON-GEOMETRIC 25 NON-GEOMETRIC B1.12 A-1/05 INDICATIONS WERE FOUND B-A UT HAT-300V0/00 AND EVALUATED AS ASME L ITUDINAL WELD ON LOWER ACCEPTABLE TO ASME  :

SECTION XI. 93.7%  !

COVERAGE.

A-1/05 2C-5 RPV UT-HAT-702V0/00 62-H HA2004 RI NON-GEOMETRIC 8 NON-GEOMETRIC B1.11 INDICATIONS WERE FOUND B-A UT-HAT-300V0/00 AND EVALUATED AS ASME LOWER SHELL-TO- BOTTOM ACCEPTABLE TO ASME HEAD TORUS SECTION XI. 95 '"%

COVERAGE.

Page: 15 C- _ r Coa.m.sv.3M T

• Ave NE. P. O. Boat 4545. ." ^ r 30302

i. O.mir-

2. Flama: Edwan L Hasch N-a_, Plans. ** 1. Box 275. Baulev. GA 3 I 513.

3. Plass Unit 2 4. Oumar Certdicate of Amelsonzasson (if reg) HLL

3. Canmmarcast Service Dans 0995/79 6. National Board Nc6 for Unia N/A

E.L Hatch Unit 2 Class 1 Components Exam / Cal ASME Exam Figure Results Remarks Section XI No. Examination / Area Examination Procedure Cal Block Shoot No. _

UT-HAT-702V0/00 63-H HA2017 RI NON-GEOMETRIC 93 NON-GEOMETRIC B1.21 A-1A/05 2C-7 RPV INDICATIONS WERE FOUND UT-HAT-300V0/00 61-H D NMD AS B-A ASME BOTTOM HEAD TORUS- TO- ACCEPTABLE TO ASME BOTTOM HEAD DOME SECTION XI. 95.3%

COVERAGE.

64-H S95H2M060 NRI LIMITED EXAM DUE TO A-3/04 2HC-2 (20-39) MT-H-500/06 B1.40 FLANGE CONFIGURATION.

UT-H-410/06 S95H20149 NRI B-A 89EONGE.

S95H20150 NRI ASME CLOSURE HEAD-TO-FLG CENTERLINE STUD 20 TO STUD S95H2U151 NRI UT-H-419/03 61-H S95H2U210 NRI LIMITED EXAM DUE TO B6 40 A-33/01 2LIG-21 THRU 40 FLANGE SEATING SURFACE -

B-G-1 95% CONGE.

ASME FLANGE LIGAMENTS UT-H-415/06 125-H S95H2U118 RI GEOMETRY 2N2A (RINTSA)

NUREG-03130 RINTSA WELD UT-H415/06 125.H S95H2U119 RI GEOMETRY

. 2N2C (RINTSA)

NUREG-0313D RINTSA WELD UT-l+415/06 125-H S95H2U120 RI GEOMETRY

. 2N2D (RINTSA)

NUREG-0313D RINTSA WELD Page: 16 1. Ouess- Guerma Power Comummer.333 Pasemmut Ave NE P.O. Ben 4543. h Guarama 3030'

2. Mmmt: Eduna L Hatch Nuclear FlamL Route 1. Ben 27L Basisv.GA 31313.

3. PlantLhmit2 4. Owner Cadieses of Assinonsmason (ifreg) N/A S. CommmereimiServiceDese 0945f?9 6. Nh Bosnt No. for Unit H/A

E.L Hatch Unit 2 Class 1 Components ASME Exam Figure ExamtCal Section XI No. Examination / Area Examination Procedure Cal Block Shoot No. Results Remarks 2N2E (RINTSA) UT-FM15/06 12 H4 S95H2U121 RI GEOMETRY NUREG-0313D RINTSA WELD B5.20 A-1/05 2N10 (N-SE) VT-H-720/03 S95H2V059 SAT B-F ASME RPV INST. NOZZLE TO SAFE-END B413 A-1A/05 2N10 (N-SH) VT-H-720/03 S95H2V060 SAT B-E ASME RPV INSTRUMENTATION NOZZLE TO SHELL B5.20 A-1/05 2N11 A (N-SE) UT-H-400(13 158-H S95H2U172 NRI S95H2U173 NRI B-F SIL-571 RPV INST. NOZZLE TO SAFE-END B413 A-1/05 2N11 A (N-SH) VT-H-720/03 S95H2V061 SAT B-E ASME RPV INSTRUMENTATION NOZZLE TO SHELL A-1/05 2N118 (N-SE) UT-H-400/13 156-H S95H2U174 NRI B5.20 S95H2U175 NRI B-F SIL-571 RPV INST. NOZZLE TO SAFE-END Page: 17 A d P.O. Boa 4 M _' e M__W

1. Osmar- ru _ h h .333 r*

h " - 1. Bas 278. N " .GA 313 Q

2. Finsa: Edumm L I' *P

3. F1ssa Unit 2 4. Oumar Candcase of Aanhanzamon (irm) h S. eu service Dese OMsnP 6. NehemelBoardNo forUnit NA

E.I. Hatch Unit 2 Class 1 Components ASME Exam Figure Exam / Cal Section XI No. Examination / Area Sheet No. Results Remarks Examination Procedure Cal Bloc _k 84 13 A-1/05 2N11B (N-SH) VT-H-720/03 S95H2V062 SAT B-E ASME RPV INSTRUMENTATION NOZZLE TO SHELL B5.20 A-1/05 2N12A (N-SE) UT-H-400/13 158-H S95H2U176 NRI B-F S95H2U177 NRI i

SIL-571 RPV INST. NOZZLE TO SAFE-END B413 A-1/05 2N12A (N-SH) VT-H-720/03 S95H2V063 SAT B-E ASME RPV INSTRUMENTATION NOZZLE i

TO SHELL i

B5.20 A-1105 2N128 (N-SE) UT-H-400/13 158-H S95H2U178 NRI B-F S95H2U179 NRI SIL-571 RPV INST. NOZZLE TO SAFE-END ,.

i B4.13 A-1/05 2N128 (N-SH) VT-H-72003 S95H2V064 SAT B-E ASME RPV INSTRUMENTATION NOZZLE TO SHELL B5 20 A-1/05 2N16A (N-SE) VT-H-710/03 S95H2V048 SAT B-F SIL-571 RPV INST. NOZZLE TO SAFE-END

1. Oumer- Ommrmen Power Commmmy.333 Ph Ave NE, P. O. Bos 4545. Aslaman Gamesma 30302

2. FImma- Eduan L Hasch Nacisar Flest Routs 1. Box 17L Bamisv.GA 31513.

3. PlantUnit& 4. Owner Caradkuse of Aasesorismesum (irreg) E ,

S. PM Service Dese 09/05/79 6. Nasional Bened No. for Unit N/A

E.I. Hatch Unit 2 8

Class 1 Components Exam / Cal ASME Exam Figure Remarks No. Examination Procedure Cal Block Sheet No. Results Section XI Examination / Area _

VT-H-720/03 S95H2V065 SAT B413 A-1/05 2N16A (N-SH)

B-E ASME RPV INSTRUMENTATION NOZZLE TO SHELL VT-H-710/03 S95H2V049 SAT BS 20 A-1/05 2N168 (N-SE)

B-F SIL-571 RPV INST. NOZZLE TO SAFE-END VT-H-720/03 S95H2V066 SAT B4.13 A-1/05 2N168 (N-SH)

B-E ASME RPV INSTRUMENTATION NOZZLE TO SHELL S95H2M034 NRI EXAMINED ONE DIRECTION A-33/01 2 NUT-21 THRU 40 MT-H-500/06 B6.10 ONLY DUE TO B-G-1 CONFIGURATION.

ASME CLOSURE HEAD NUTS UT-H-420/06 156-H S95H2U211 NRI B6 20 A-33/01 2 STUD-21 THRU 40 S95H2V058 SAT B-G-1 ASME CLOSURE HEAD STUDS i

VT-H-710/03 S95H2V046 SAT 86.50 A-33/01 2 WASHER-21 THRU 40 B-G-1 ,

ASME CLOSURE HEAD WASHERS

-e 30302 L O===- c - Powere 3M T * - Am_ NE P O. Ihm 4349.J P*o*: 19 Edwim L " ^ ^ T h ** 1_ Bau 27E. D

• GA 31513.

2. Flaut

3. PlanaUnit2 4. Oumar Catdenes of Aambanzamen (ifM) h

s. commmeist servie.Does ope 5n9 6. Nanamat Board Na for thit g&

E.I. Hatch Unit 2 Class 1 Components Exam Figure ExamICal ASME No Examinetton Procedure Cat Block Sheet No. Res h Rem d e Section XI ExaminationtArea GPC N/A - PERFORMED PER 42-IT-TET-B15.10 - CLASS 1 LEAKAGE TEST 006-2S Rev. 7.

B-P ASME PRESSURE RETAINING BOUNDARY LEAKAGE TEST GPC N/A - SEE PAGE 27 EXAMINED BY GPC QC.

B7 80 A-29/03 FLANGE BOLTING B-G-2 ASME CRD HOUSING A-3/04 RPV (HEAD LUGS) MT-H-500/06 S95H2MG32 NRI B8.10 B-H ASME 4 LIFTING LUGS UT-HAT-501V2/00 LFK CM.001 CAL 2 BOLTS VERE FOUND WITH

- - SHROUD HEAD BOLTS SUSPECT INDICATIONS, 009-1 CM&2 CAL DM001 RI GECMETRY EV UATE A NT SIL-433 1 THRU 36 DM002 RI GEOMETRY CRACKED.

DM003 RI GEOMETRY FEEDWATER SYSTEM UT-H-400/13 77-H S95H2M066 NRI ONE-SIDED EXAM DUE TO 89.11 A-1/05 2821-tFW-188-1 VALVE.

S95H20188 NRg MT-H-500/06 B-J VALVE TO PIPE S95H2U189 RI GEOMETRY ASME S95H2U190 N/A T/C RECIRCULATIOfLSYSTEM

-c 30307 Page: 20 n. o ar c =%c -m- - Am NE P. O. h 4545. ?

2. Flama:

P1_ L : -^ W Mast == 1 Item W, '- ' _ GA 31313.

3. Plant Unit 2 4. O.marCWofAustmarntensas( 7)]E&

S. cM service Duas 0995/79 6. Na6ammi Bonni Na for Unit H(A

_ _ _ _ _ _ _ _ . _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . ._____ ___________________________________.____________________________________a

E.I. Hatch Unit 2 Class 1 Components Exam Figure Exam / Cal ASME Nh Remads

. _ . ,ExaminagontAyes __ - _ _ _ _ {xam1y_on P_rocpre_ , Cal BM Resub _ .

DT-H-600/05 154-H S95H2U146 NRI SURFACE EXAM PERFORMED B9 31 A-16 2B31-1RCM-28AS-9BC-4 S95H2U147 NRI BY GPC OC. ONE-SIDED EXAM B.J (DRAFT) UT-H-400/13 T "

BC TO PIPE S95H20148 NRI CONNE NUREG-0313A CONFIGURATION.

2B31-1RCM-28AS-9BC-4 FB VT-H-710/03 S95H2V068 SAT B7.50 A-16 B-G-2 (DRAFT)

ASME FLANGE BOLTING PT-H-600/05 154-H S95H2U185 NRI SURFACE EXAM PERFORMED B9 31 A-18 2831-1RCM-28BS-8BC-4 BY GPC QC. ONE-SIDED EXAM (DRAFT) UT-H-4C0/13 S95H2U186 I B-J BC TO PIPE S95H2018? N E NUREG-0313A CONFIGURATION.

r r

B7.50 A-18 2B31-1RCM-28BS-8BC-4 FB VT-H-710/03 S95H2 h SAT f

B-G-2 (DRAFT)

ASME FLANGE BOLTING CORE SPRAY SYSTEM i UT-H-400/13 137-H S95H2M064 NRI ONE-S!DED EXAM DUE TO B9.11 A-25/07 2E21-1CS-108-4 j NRI PENETRATION MT-H-500/06 S95H2U134 B-J ONRGURATION. [

S95H20135 NRI ASME PIPE TO PENETRATION S95H2U136 N/A T/C HIGlifRESSURE CQOLANUNJECnQK1YSIFJI6

?

1. Ommer: C _ L__ t'm_333 f ' ' Ave NE P.O.. Bos 4545. Asiness.Geeruna 30302

2. Plass: Edurin L :* - ;* h " 1. Boa 271 P-

• OA 31513.

3. PlantUmitl 4. Ovumar Cartdkmes of Asaharuanom Wrg)MbL

$. CommmmmsalServiceDuas OWO509 6. Nana==8 Board h for Uma g

E.I. Hatch Unit 2 Class 1 Components ASME Exam Figure Exam / Cal Section XI No. Exam: melon / Area Examination Procedure Cal Block Sheet No. Results Remarks B9.11 A-28.06 2E41-1HPCI-1CH}-21 UT-H-400/13 54-H S95H2M065 NRI B4 MT-H-500/06 S95H2U191 NRI ASME PENETRATION TO PIPE S95H2U192 NRI l

l YALYEBOLIING B7.70 A- 13 2B21-F010B BOLTING GPC N/A -

EXAMINED BY GPC OC. MWO 2-95-3015. SAT.

B-G-2 450C-INS-010-OS ASME VALVE BOLTING B7.70 A- 5 2821#0130 BOLTING GPC N/A -

EXAMINED BY GPC QC. MWO B&2 450C-INS-010-OS 2-94-3430. SAT.

ASME VALVE BOLTING B7.70 A- 5 2821f013H BOLTING GPC N/A -

EXAMINED BY GPC OC. MWO B-G-2 450C-INS-010-OS 2-95-2204. SAT.

ASME VALVE BOLTING B7.70 A- 5 2821#013L BOLTING GPC N/A -

EXAMINED BY GPC OC. MWO B-G-2 450C-INS-04 GS 2-94-3436. SAT.

ASME VALVE BOLTING B7.70 A- 5 2821f013M BOLTING GPC N/A - EXAMINED BY GPC OC. MWO B-G-2 450C-INS-010-OS 2-94-3437. SAT.

ASME VALVE BOLTING Page: 22

1. Ouesr. Geersma Power Camamer.333 hadumamt Ava. NE F.O. Bom 4343. Adme.Gamuna 3030;

2. Flama: Edmum L Headi Nusisar FM Emuts L Ben 27L Ibadsv. OA 31313.

3. Fissa Unit 2 4. Owner certnesse of Amihanzesson (irreg) H(A

3. ComunsruialserviosDess OPovi9 6. Nasiammi Baant Na for Unit H/A

E.8. Hetch Unit 2 6 Class 1 Components ASME Enem Fleuro Exam / Cal Section XI No. Examination / Area Examination Procedure Cal Block Sheet No. Results Romerks B7.70 A-6/06 2B21-F028A BOLTING VT-H-710/03 S95H2V050 SAT B42 AS'AE VALVE BOLTING =

B7.70 A-7/07 2821-F028B BOLTING VT-H-710/03 S95H2V051 SAT B-G-2 ASME VALVE BOLTING B7.70 A-8/07 2821-F028C BOLTING VT-H-710/03 S95H2V052 SAT B-G-2 ASME VALVE BOLTING B7.70 A-9/06 2821-F0280 BOLTING VT-H-710/03 S95H2V053 SAT B-G-2 ASME VALVE BOLTING 87.70 A-22 2E11-F015A BOLTING GPC N/A -

EXAMINED BY GPC QC. MWO 9-G-2 45QC-INS-010-OS 262847. SAT.

ASMF VALVE BOLTING o===r- " F="=r "

p 23 1- 333 Y ^ ^= NF_ P. O. Baz 4541_^ ^" e 3030:

2. Plass: Estuna L 18" r - Plant *- 1. Bam 27L

• _ GA 31311

3. Pinus Unit 2 4. Onear Candemas eth(irg)n S. CM Serviam Dune 0943/79 6. Nasional Bened Na forIMt Ng

E.I. Hatch Unit 2 Class 1 Components ExamlCal ASME Exam Figure Remarks No. Examination Procedure Cal Block Sheet No. Results Section XI Examination / Area .

N/A EXAMINEt; JY GPC QC. MWO A-23 2E11-F015B BOLTING GPC -

i B7.70 2-95-28491rlREAD DAMAGE 450C-INS-010-OS ON 3 STUDS FOUND DURING B-G-2 ASME VALVE BOLTING INSPECTION THREAD DAMAGE EVALUATED AS PEING CAUSED BY DISASSEMBLY. NO REDUCTION IN BOLT INTEGRITY. BOLTS ACCEPTABLE FOR CONDNUED SERWCE PER GPC ENGINEERING EVALUATION.

VT-H-710/03 S95H2V067 SAT B7.70 A- 23/05 2E11-F017B BOLTING B-G-2 ASME VALVE BOLTING N/A - EXAMINED BY GPC OC. MWO .

A-24 2E21-F005A BOLTING GPC B7.70 2-95-2845 SAT.

450C-INS-010-OS B-G-2 ASME VALVE BOLTING N/A EXAMINED BY GPC QC. MWO i,7.70 A-25 2E21-F005B BOLTING GPC -

2-95-2846. SAT.

450C-INS-010-OS B-G-2 ASME VALVE BOLTING YALYE BQDIES

^e 303 Pogo: M 1. Oumar- C Feuer P 333 7 ^ ^ Ave NE. P. O. Bam 4541_^ ^"

2. Plama: Eduna L : ^

• N h ** 1. Bam 27L - ' . GA 31513.

3. Plant Unit 2_ 4. Oumur Cartm5emme ofh(ifg)g S. Commmansel Servies Dano 0945D9 6. Nasional Board Na for Unit li/A

E.1. Hatch Unit 2 Class 1 Coenponents ASME Exam Figure Exam / Cal Section XI No- Examination / Area Examination Procedure Cal Block Shoot No. Results Remarks B12 50 A- 13 2821-F010B BODIES GPC N/A - EXAMINED BY GPC OC. MWO B-M-2 450C-INS-010-OS 2-95-3015. SAT. MINOR GOUGES FOUND IN THE BODY ASME VALVE BODIES ABOVE THE SPACER RING AREA. EVALUATED BY ENGINEERING AS ACCEPTABLE.

B12.50 A- 5 2B21-F013D BODIES GPC N/A -

EXAMINED BY GPC QC. MWO B-M-2 43OC-INS-010-OS 2-94-3430. SAT.

ASME VALVE BODIES B12.50 A- 5 2B21f013H BODIES GPC N/A -

EXAMINED BY GPC QC. MWO B-M-2 450C-INS-01M)S 2-95-2204. SAT.

ASME VALVE BODIES B12.50 A- 5 2B21-F013L BODIES GPC N/A -

EXAMINED BY GPC QC. MWO B-M-2 450C-INS-010-OS 2-94-3436. SAT.

ASME VALVE BODIES B12.50 A- 5 2B21f013M BODIES GPC N/A - EXAMINED BY GPC QC. MWO B-M-2 450C-INS-010-OS 2-94-3437. SAT.

ASME VALVE BODIES i

l

1. Ommer- Omarma Fouw Commmmmv. 333 Flehmus Avt. NE P. J. Ben 4545. h Omarna 303 Page: 25 2. Fiumt Edom L Headi Nedser Finut. Rauts 1. Bos 275. Badsv. OA 31513.

3. Flamt Unit 2 4. Omust Carnar-sa of Audinnasanas (ifreg) Hgk

5. CommmercialServiceDese 0945/79 6. NW Board No. far Unit H/A

E.l. Hatch Unit 2 Class 1 Components ASME Exam Figure ExamtCal Section XI No. Examination / Area Examination Procedure Cal Block Sheet No. Results _

Remarks , __

A- 22 2E11-F015A BODIES GPC N/A - EXAMINED BY GPC QC. MWO B12 50 2-95-2847. SAT. VALVE STEM B-M-2 450C-INS-010-OS HAS A GOUGE. STEM FOUND ASME VALVE BODIES TO BE ACCEPTABLE AFTER REPLACEMENT. SOME THREAD DAMAGE ON BONNET HOLES WHICH WAS REPAIRED / EVALUATED GPC N/A - EXAMINED BY GPC OC. MWO B12.50 A-23 2E11-F0158 BODIES 2-95-2849. PITTING NOTED IN 3-M-2 450C-INS-010-OS STUFFING BOX EVALUATED ASME VALVE BODIES AS ACCEPTABLE BY GPC ENGINEERING.

GPC N/A - EXAMINED BY GPC QC. MWO B12.50 A-24 2E21-F005A BODIES 2-95-2845. SAT.

B-M-2 450C-INS-010-OS ASME VALVE BODIES GPC N/A - EXAMINED BY GPC OC. MVO B12.50 A-25 2E21-F005B BODIES 2-95-2846. SAT.

B-M-2 450C-INS-010-OS ASME VALVE BODIES

1. Oumer- Qasras huur Comammy.333 Pasement Ave NE P.O. Box 4543. Allaman.Qamens 393tv, Page: g 2. Pimmt: Edumm L Hamh Nustaar PiemL Route 1. Bos 275. Basisv. OA 3 } }l3.

3. P W Unit 2 4. Owner Cartdhme ofAnshanzatsas (ifreq.) &

S. W Servios Dune 0945/79 6. NM Board Net for Unit H(A

! 1. Owner: Georma rower Comnany. 333 Piedmont Ave.. NE. P. O. Box 4345. #1==* Geornia 30302

2. Plass: Edwm 1. Had Nuclear Plant Route 1. Box 278. Eadev. GA 31313.

3. Plant Unit 2 4. Owner Certificate of Authorgataan (ifreq.) h

5. CommercialService Dale 0905r79 6. National Board No. for Urh Nf3 VISUAL EXAMINATION OF CLASS 1 CRD BOLTING l ASME Section XI requires examination of the CRD components (bolts, studs, and nuts) whenever the l housings are disassembled. Twenty (20) CRDs were replaced during the outage which facilitated visual  ;

examination (VT-1) of the bolts, studs, and nuts. The subject examinations were performed using GPC QC personnelin conjunction with the CRD maintenance / replacement activities. Listed below are the .

CRDs which were examined using GPC procedure 45QC-INS-010 0S. The majority of the bolts were  !

found to have minor pitting generally locahzed in the area near the bolt head. Four (4) out of the one  ;

hundred sixty (160) bolts examined were found to have small cracks near the head of the bolt. These l types ofindications on CRD bolting are addressed in General Electric SIL No. 483. All bolts with pitting {

or cracking were replaced. I 34-35 10-39 10-15 18-03 26-27 18-23 38-47 26-23 26-19 22-47 10-43 02-31 22-15 38-23 14-19 46-39 46-15 22-27 02-19 14-31

+

e I

27

.- . _ _ - . ~ . . _ . .~ , . .. . , - -

1 1

1. Oeer: Cnorma Power Comsany. 333 7 '--- ^ Ave.. NE. P. O. Box 4545. F'-"- C--e 30302

3. Plant: Edwm L lian Nuclear Plant. D== 1. Box 278. Baxlev. OA 31513.

3. Plant Unit 2 4. Owner Certificase of Authoruscan (if req.) R S. CaesnarcialServiceDate 09W79 6. National Board No. for Unit E3 l 1

I

. l i

l I l l

\

h i i

i J I

SUMMARY

1 l

OF CLASS 2 EXAMINATIONS i I i

I

)

)

i

. I a

28 i

'u E.1. Hatch Unit 2 Class 2 Components ASME Exam Figure ExamtCal Section XI No. Examination / Area Examination Procedure Cat Block Sheet No. Results Remarks __

CONIBOLRQD DRIVE SYSTEM

- B-83/04 2C11-2CRD-3-2FW-1611 UT-H400/13 4-H S95H2U107 NRI ONE-SIDED EXAM DUE TO S95H2U108 NRg REDUCER.

NUREG-0619 PIPE TO REDUCER

- B-83/04 2C11-2CRD-4-2FW-1611 UT-H-400/13 142-H S95H2U109 NRI LIMITED EXAM DUE TO S95H2U110 NRI CONFIGURATION 35%

CO N GE.

NUREG-0619 REDUCER TO TEE RESIQUALEEAI.RE.AOVEL l SYSTM

- B-97/03 2E11-2RHR-4-HS-11 MT-H-500/06 S95H2M059 NRI AUGMENTED PIPE TO 45 DEGREE ELBOW

- B-97A/03 2E11-2RHR-4-HS-14 MT-H-500/06 S95H2M056 NRI AUGMENTED ELBOW TO PIPE .

- B-33/04 2E11-2RHR-4B-PD-D-1 MT-H-500/06 S95H2M014 NRI AUGMENTED BC TO VALVE MT-H-500/06 50-H S95H20180 NRI SURFACE EXAMINATION C5.21 B-67 2E11-2RHR-68-SS-3A NRI PERFORMED BY GPC OC.

C-F (DRAFT) UT-H-400/13 S95H2U181 -

01 MM.

PIPE TO CAP S95H2U182 NRI ASME S95H20193 N/A T/C

, 1. Onomr- c--- L_ e .333 7 '

• Am NE. P. O. Bom 4545. ." ^ c 303u2 Page: O 2. Flama: Edevin L la" W Flest Ramas 1. Box 27L Basisv. GA 31513.

3. Flest Unit 2 4. Owner Condemas of Ausherunases (if reg)N/A

5. cW Serms omae 0943/79 6. Nh Board No. Far Unit E/A

E t Hatch Unit 2 Class 2 Components ASME Exam Figure Exam / Cal Section XI No- Examinabon/ Area Examination Procedure Cal Block Sheet No. Results Remarks C5 21 B-20/04 2E11-2RHR-6B-SS-9 MT-H-500/06 50-H $95H2M018 NRI C-F UT-H-400/13 S95H2U163 NRI ASME PIPE TO ELBOW S95H2U164 NRI S95H2U165 N/A T/C C5.11 B-23/05 2E11-2RHR-8-FPS-12 MT-H-500/06 S95H2M057 NRI C-F ASME PIPE TO 45-DEGREE ELBOW C5.11 B-23/05 2E11-2RHR-8-FPS-16 MT-H-500/06 S95H2M068 NRI C-F ASME PIPE TO ELBOW C5.11 B-24/03 2E11-2RHR-10A-SWDS-8 450C-INSMS Q95H2M043 NRI EXAMINSD BY GPC OC.

ASME VALVE TO ELBCPW C5.11 B-25/03 2E11-2RHR-108-SWDS-2 MT-H-500/06 S95H2M001 NRI C-F ASME PIPE TO VALVE C511 B-14/08 2E11-2RHR-16A.OS-4 MT-H-500/06 S95H2M007 NRI C-F ASME PIPE TO ELBOW s

B-26/04 2E11-2RHR-16A44XI-5 450C-INS-006 OS Q95H2M044 NRI EXAMINED BY GPC QC.

C5.11 C-F ASME PIPE TO ELBOW Cam many. 333 h Am NE. P. O. Bos 4545. .' e 30302

l. Owear- C 7

2. Fiest: Edenn L Hans Numinar h Emma L Bas 27L Basisy.OA 31513. ,

Page: 30 3. Fi sumit2 4. O= rC.redic.a.or4.an.nammancirro6)La

5. CommmmuniserviceDune OM5n? 6. NM Board Na for Unit EA

4 E l. Hatch Unit 2 Class 2 Components ASME Exam Figure Exam / Cal Section XI No. Examination / Area Examination Procedure Cal Block Sheet No. Results Remarks

- B-27/03 2E11-2RHR-16A-HXO-2BC-1/ 2E11 MT-H-500/06 S95H2M010 NRI 2RHR-4A-HXO AUGMENTED PIPE TO BC C511 B-26 2E11-2RHR-16A-SS-5A 450C-!NS-006-OS Q95H2MOS6 N/A EXAMINED BY GPC QC.

MWO 2-95-2301 FW-001.

C-F (DRAFT)

ASME PIPE TO CAP C3 20 B-18/06 2E11-2RHR-168-DS-SPL-1 THRU 8 MT-H-500/06 S95H2M031 NRI C-C ASME DEVICE 2E11-RHR-R129 C5.11 8-21/07 2E11-2RHR-16B-SH4 MT-H-500/06 S95H2M002 NRI C-F ASME 45-DEGREE ELBOW TO PtPE B-30 2E11-2RHR-16B-SS-4A 450C-INS-006-OS 095H2M057 N/A EXAMINED BY GPC QC.

C5.11 MWO 2-95-2300 FW-001.

C-F (DRAFT) ,

ASME PIPE TO CAP B-35/04 2E11-2RHR-20A-D-1 450C-INS-006-OS Q95H2M045 NRI EXAMINED BY GPC QC.

C5.11 C-F ASME TEE TO PIPE 2E11-2RHR-20A-D-2 450C-INSNS 095H2M046 NRI EXAMINED BY GPC QC.

C5.11 B-35/04 C-F ASME P1PE TO 45-DEGREE ELBOW 7,,_ e .333 7 Ave. NE. P. O. Box 4545. f C 30302

l. Owear- C-31 2. Plasa- Edwin I. Hasch Mh Plad. ** 1. Box 273. Baslev. GA 31513.

88' 3. Plant Unit 2 4. Ownw CataScam of Ausboruasson (ifreg) N/A

5. rW Savice Dese 0945n9 6. Naticaal Board No. for Unit E/A

E.L Hatch Unit 2 Class 2 Components ASME Exam Figure Exam / Cal Section XI No- Examination / Area Examination Procedure Oal Block Shoot No. Results Remarks C5.11 B-35/04 2E11-2RHR-20A-D-11 450C-INS-006-OS Q95H2M047 NRI EXAMINED BY GPC QC.

C-F ASME PIPE TO ELBOW C511 B-29/04 2E11-2RHR-20A-PD-C-8 450C-INS-006-OS 095H2M048 NRI EXAMINED BY GPC QC.

C-F ASME VALVE TO PIPE C3.20 B-36/03 2E11-2RHR-20B-D-11PL-1 THRU 4 MT-H-500#IS S95H2M011 NRI C-C ASME DEVtCE 2E11-RHR-H169 C3.20 B- 36/03 2E11-2RHR-268-D-11PL-5 THRU 12 MT-H-500/06 S95H2M012 NRI C-C ASME DEVICE 2E11-RHR-R241 C511 B-37/04 2E112RHR-20C-D-5 450C-INS-006-OS 095H2M049 NRI EXAMINED BY GPC QC.

C-F 14FnnE VALVE TO PIPE B-40/04 2E11-2RHR-24A-BP-20 450C-INS-006-OS 139-H Q95H2M050 NRI MT BY GPC QC. ONE-SIDED C5 21 S95H2U123 N/A T/C EXAM DUE TO TEE C-F UT-H-400/13 C N GU N ON.

ASME PIPE TO TEE S95H2U128 NRI S95H2U132 RI GEOMETRY B-43/03 2E11-2RHR-24A-TS-A-17 450C-INS-006-OS 139-H 095H2M051 NRI MT BY GPC QC. ONE-SIDED C5 21 UT-H-400/13 S95H2U122 N/A T/C EXAM DUE TO VALVE C-F CONRGURATION.

ASME VALVE TO PIPE S95H20130 NRI S95H2U131 Rt GEOMETRY

1. Owner: Geornia Ptmar Comsany.333 Ph Ave NE.P. O. Box 4545. Aslaman.Osaman 30302 Page: 32 2. Fi n: se-. L M Naher Man. RcWe 1. Box 2M.Bh.GA 31513.

3. Finsa Unit 2 4. Owner Caridicune of Asaharuseen (ifrug) N/A

5. Commmercial Service Dane 0945n9 6. Naniemel Board Na for Unit N/A

E.I. Hatch Unit 2 Class 2 Components ASME Exam Figure ExamtCal Section XI No. Examination / Area Examination Proceduas Cal Block Sheet No. Results Remarks

- B-49/04 2E11-2RHR-248-TS-B-17BC-1 MT-H-500/06 095H2M039 NRI

/2E11-2RHR-48-TS-B S95H2M009 NRI AUGMENTED PIPE TO BC C1.10 B-1/03 2HX4-2 UT-H-400/13 73-H Q95H2M052 NRI LIMITED EXAMINATION DUE 72-H S95H2U124 N/A T/C TO SUPPORT LUG C-A "

ASME UPPER SHELL RING TO LOWER S95H20125 NRI O E SHELL RING S95H2U126 RI GEOMETRY S95H2U127 NRI S95H2U129 NRI C3.10 B-1/03 2HX-A-3S-2 450C-INS-006-OS 095H2M053 NRI EXAMINED BY GPC QC.

C-C ASME LOWER SHELL RING SUPPORT C3.10 B-1/03 2HX4-3S-3 450C-INS-006-OS Q95H2M054 NRI EXAMINED BY GPC QC.

C-C ASME LOWER SHELL RING SUPPORT C3.10 B-1/03 2HX-A-3SA 450C-INS-006-OS Q95H2M055 NRI EXAMINED BY GPC QC.

C-C ASME LOWER SHELL RING SUPPORT CORE SPRAY SYSIEM C5.11 B-54/05 2E21-2CS-108-11 MT-H-500/06 S95H2M063 NRI C-F ASME PIPE TO VALVE

1. Oumer: Georms E Commemy.33M Am.NE. F.O. Bos1545. Atlasen.h 19302

2. Planc Edwan L Had Nudeur Fimus. Rees I. Boa 27L Basler. OA 31513.

Page: 33 3. Fi s uma2 4. o m.,C e s e g % m

3. CammacialServiosDune 094309 6. Nassomal Board Na for Unit NA

E.I. Hatch Unit 2 Class 2 Components ASME Exam Figure Exam / Cal i Section XI No. Examination / Area Examination Procedure Cal Block Sheet No. Results Remarks _-._

C511 B-58/04 2E21-2CS-12A-34 MT-H-500/06 S95H2M028 NRI C-F ASME PIPE TO ELBOW C3 20 B-61/05 2E21-2CS-20A-TS-12PS-1 A # ND 2A 450C-INS-006-OS 095H2M036 NRI EXAMINED BY GPC OC.

C-C ASME DEVICE 2E21-CS-R41 C5.11 B-63/05 2E21-2CS-208-TS-2 450C-INS-006-OS Q95H2M035 NRI EXAMINED BY GPC QC.

i C-F ASME PIPE TO 45-DEGREE ELBOW C6.10 B-2A/02 2E21-2CS-POP-B-1BC/ MT-H-500/06 S95H2M013 NRI RR 3.1.3 C-G ASME SHAFT ELBOW TO BC CORE SPRAY PUMP B titG11 PRESSURELCQQLAMI19JECTION SYSTEM

- B-94/02 2E41-2HPCI-4-MFL-1 450C-INS-006-OS Q95H2M040 NRI EXAMINED BY GPC QC.

AUGMENTE3 BRANCH CONNECTION TO PIPE B-94/02 2E41-2HPCI-4-MFL-4 MT-H-500/06 S95H2M025 NRI AUGMENTED PIPE TO ELBOW 4

1. Ommer- Geormas Power Commany. 333 Ptadmansa Ave NE P. O. Bos 4543. AllemaL Ommemma 30302 Page: 34 2. Plant: Edwum L Handi Nuclear Plant Romas 1. Bos 278. Baslev.GA 31313.

3. Plant Unit 2 4. Ommer Cert:6cuse of Assinarustaan (ifreg) h S. PW Service Dese 0943n9 6. National Board No. Far Unit 2Ff.A

E l Hatch Unit 2 Class 2 Components Exam Figure Exarn/ Cal ASME No. Exarnination Procedure Col Block Sheet No. Results Remarks Section XI Examination / Area _

' MT-H-500/06 52-H S95H2M020 NRI ONE-SIDED EXAM DUE TO C5 21 B-16/04 2E41-2HPCI-8A-SS-1 RI GEOMETRY REDUCER.

UT-H-400/13 S95H2U101 C-F REDUCER TO PIPE ,

S95H2U102 RI GEOMETRY ASME MT-H-500/06 S95H2U169 NRI MT PERFORMED BY GPC OC.

C5 21 B-16 2E41-2HPCI-8A-SS-SA MWO 2-95-2301 FW-003.

UT-H-400/13 154-H S95H2U170 NRI C-F (DRAFT)

S95H2U171 NRI ASME PIPE TO CAP S95H2U194 N/A T/C B-67/03 2E41-2HPCI-10-D-10 MT-H-500/06 54-H S95H2M006 NRI C5 21 UT-H-400/13 S95H2U160 N/A T/C C-F 595H2U161 NRI ASME TEE TO REDUCER S95H2U162 NRI B48/05 2E41-2HPCI-10-D-29 MT-H-500/06 54-H S95H2M023 NRI C5.21 UT-H-400/13 S95H2U157 NRI C-F S95H2U158 RI GEOMETRY ASME PIPE TO TEE S95H2U159 N/A T/C 137-H Q95H2M041 NRI MT PERFORMED BY GPC QC.

C5.21 B-70/05 2E41-2HPCI-10-TL-1 450C-INS-006-OS NRI ONE-SIDED EXAM DUE TO UT-H-400/13 S95H20183 C-F ' CONFIGURATION.

S95H2U184 NRI ASME TEE TO PIPE 8-66/07 2E41-2HPCI-14-R-33 MT-H-500/06 116-H S95H2M029 NRI C5 21 UT-H-400/13 S95H2U207 NRI C-F S95H2U208 NRI ASME PIPE TO 45-DEGREE ELBOW 095H2M038 NRI EXAMINED BY GPC OC.

- B-73/05 2E41-2HPCI-16-TS-12 450C-INS-006-OS AUGMENTED VALVE TO PIPE

1. Ouser* C--- Power P .333 7 * ^ Am NE. P. O. Box 4545. ." ^C W Page: J3 g m mt- ; h ** 1. h M - ._GA 31513.

3. PlassUmia2 4. Owear Candemas of Anaharumanam Grreg) E(A, S. c6 Service Daae 094309 6. Nassanal Bond No, for Umia H/A

E.L Hatch Unit 2 Class 2 Components ASME Exam Figure ExamlCal Section XI No. Examination / Area Examination Procedure Cat Block Sheet No. Results Remarks _ _

450C-INS-006-OS 095H2M042 NRI EXAMINED BY GPC QC.

- B-7325 2E41-2HPCI-16-TS-24 AUGMENTED PIPE TO REDUCER C5.11 B-74/03 2E41-2HPCI-18-TD-1 MT-H-500/06 S95H2M019 NRI C-F ASME FLANGE TO TEE C511 B-69/04 2E41-2HPCI-20-TD-14 MT-H-500/06 S95H2M003 NRI C-F ASME PIPE TO TEE l

l C5.11 B-69/04 2E41-2HPCI-20-TD-23 MT-H-500/06 S95H2M004 NRI C-F ASME ELBOW TO PIPE I

BEACIOREOftfUSOLATION COOLIPiG SYSTEM

- B-88/02 2E51-2RCIC-4-PS-5 MT-H-500/06 S95H2M016 NRI i

AUGMENTED PtPE TO ELBOW

- B-95/03 2E51-2RCIC-4-SS-13 MT-H-500/06 S95H2M069 NRI At9MENTED PIPE TO ELBOW

l. Oumer- Gammen Ptmer Campany. 333 Ph Am. NF. P. O. Bas 4343. Adaman.Gamrma 30302 Page: 36 2h Fhm L M Nasher h Emm 1.BoaM h QA 31313.

3. PlantUnit1 4. Owner CartScene of Aushernmon (ifg) N/A

3. ComunarinalService Daae OM5n9 6. National Board New for Unit H/A

E.L Hatch Unit 2 Class 2 Components ASME Exam Figure ExamICal Section XI No. Examination / Area Examination Procedure Cal Block Sheet No. Results R3 marks

- B-89/02 2E51-2RCIC-6-CST-9 MT-H-500/06 S95H2M015 NRI AUGMENTED PIPE TO 45 DEGREE ELBOW

- B-87/02 2E51-2RCIC-6-PS4BC/ 2E51- MT-H-500/06 S95H2M017 NRI

. 2RCIC-3-PS AUGMENTED PIPE TO BRANCH CONNECTIONS

- B-86/04 2E51-2RCIC-6-TS-10 MT4500/06 S95H2M021 NRI AUGMENTED ELBOW TO VALVE C511 B-82/06 2E51-2RCIC-10-TD-17 MT-H-500/06 S95H2M005 NRI C-F ASME PIPE TO VALVE REACIDfONATER CLEAN-UP SYSTEM

- B-83/04 2G31-2RWCU4-2FW-33 UT-H-400/13 142-H S95H2U111 NRI ONE-SIDED EXAM DUE TO S95H2U112 NRI TEE CONFIGURATION.

NUREG-0619 TEE TO PIPE MAIN STEAM AUXILIARY SYSTEM 2N11-2MSA-10C-SSR-2 MT-H-500/06 54-H S95H2M058 NRI ONE-SIDED EXAM DUE TO C5 21 B-6/04 N/A T/C VALVE CONFIGURATION.

C-F UT-H-400/13 S95H20166 ASME PIPE TO VALVE S95H2U167 R1 GEOMETRY S95H2U168 NRI

1. Oumar Georma PetswCommmmmw.333 Fisheet Ava NE P.O. Ben 4545.hGamrpa 30302 Page: 37 2. Mme: FJwm L M Nudmar Mem. Ram 1 Bm 24 Peutw. GA M513.

3. Fins Unit 2 4. Quem caressene of Amemnamnem (irg)]FA

3. commesseint servios Duae OMSUP 6. Nansmel Based Not for Unit WA

E.I. Hatch Unit 2 Class 2 Components Exam Figure Exam / Cal ASME No. Examination Procedure Cat Block Sheet No. Results Remarks Section XI Examination / Area __

C5 21 B-7/04 2N11-2MSA-16A-18 MT-H-500/06 53-H S95H2M027 NRI UT-H-400/13 S95H2U115 RI GEOMETRY C-F 45-DEGREE ELBOW TO PIPE S95H2U116 RI GEOMETRY ASME S35H2U117 N/A T/C 2N11-2MSA-24A-5PL-1 THRU 8 MT-H-500/06 S95H2M061 NRI C3.20 B-9/06 C-C ASME DEVICE 2N11-MS-R45 C3 20 B-11/06 2N11-2MSA-2&1PS-1 THRU 2 MT-H-500/06 S95H2M026 NRI C-C ,

ASME PIPE SUPPORT C5.21 B-12/06 2N11-2MSA-24D4 L*: H-500/06 152-H S95H2M067 NRI UT-H-400/13 S95H2U204 N/A T/C C-F PIPE TO ELBOW S95H2U205 RI GEOMETRY ASME S95H2U206 R1 GEOMETRY C3 20 B-12/06 2N11-2MSA-24D-11PL-1 THRU 8 MT-H-500/06 S95H2M022 NRI C-C ASME DEVICE 2N11-MS-A60 FEEDWATER SYSTEM MT-H-500/06 77-H S95H2M024 NRI ONE-SIDED EXAM DUE TO B9.11 A-38A/02 2N21-2FW-18A-3 RI GEOMETRY VALVE CONFIGURATION. RR UT-H-400/13 S95H20113 B-J PIPE TO VALVE S95H20114 RI GEOMETRY ASME CONTAINMENIEURGE AND INERTING SYSTEM

1. Owear- Georma Power Cammmer. 333 Pamemmma Am.NF_ P.O. Das 4545. Alleman. Immemma 3030 Page: 3 8 2. Plant: Edma L Hassh Nusamer Flamt. Emmas 1. Bas 271 Bastav. GA 31513.

3. FlautUnit & 4. Owear Candcase a( Amesanamenau (irm)h

3. rW Servios Does 0995/79 6. Nasional Boent Net for Unit N/%

E.I. Hatch Un!t 2 Class 2 Components Exam / Cal ASME Exam Figure Remarks Examination Procedure Cal Block Sheet No- Results Section XI No. Examination / Area

' - - ~ ~

2T48-2 cpl 4-SVD4 MT-H-500/06 S95H2M008 NRI C5.11 B-77/05 C-F ASME PIPE TO ELBOW MT-H-500/06 S95H2M062 NRI C3 20 B-78/04 2T48-2 CPI-18-PID-2PL-1 THRU 8 C-C ASME DEVICE 2T48-CPUR-R49 095H2M037 NRI EXAMINED BY GPC QC.

B-78/04 2T48-2 CPI-18-PID4 MT-H-500/06 C5.11 C-F 45-DEGREE ELBOW TO P!PE i ASME MT-H-500/06 S95H2M030 NRI C511 B-79/06 2T48-2 CPI-20-PIT-5 C-F ASME VALVE TO PIPE

- 333 7 " ^ Ava NE. P. O. Bam 4345 ? ^^ ^r 3030

1. Quesr- C -- L_ t' GA 31513.

Page: 2. Flam: Edwin L !" ^ ^ P h Ranma 1 Bam 278. '

3. PimmtUnit1 4. Oumar candcase of Amakenzamos (if eng)]&L

3. M ServiosDass ONOS/79 6. NasionalBoard No,for Unit N/A

_ _. . .. . _ _ _ .-._._..m, . . . _ _ _ _ . .m.. ........._m._....__. . . . _ . . _ .._ _

b 1, Owner: C_ _ L_ C- .333 P' ' [

Ave.. NE P. O. Box 4543. P'--- Omarna 30302

i. 3. Plam: Edwm L 18 *A N 8- Plant ha 1. Box 278. n-4.GA 31 SI?.

3. Plam Usst 2 4. Owner Certificate of Authorustaan (if req.) E 4 5. ^ .-l Service Dane 0995/77 6. National Board No. for Unit E!%

4 4

4 4

4

'l 4

SUMMARY

OF

, CLASS 1 AND 2 PRESSURE TESTS PRESSURE TESTING 40

. _ - . .. -->- .~ -. _ - - ,- - -_ - -- -~ - . . . - - - . . _ - - .

1. Ownar: Oss r C- 1. 333 P' * ^ Ave.. NF_ P. O. Box 4545. PI--*- Gm a 30302

2. Plant: Edwin 1. H *A Nuclear Plant. h=*= 1. Box 278. B--t-v. GA 31513.

3. Plam Unit 2 4. Owner Certiricate of Authoruauan (if req.) M S. Conumercial service Dese 0995/79 6. National Board No. for Unit N_/2 l i

CLASS 1 AND 2 PRESSURE TESTS GENERAL This section of the report provides a discussion of the pressure tests which were performed during the l 1995 Plant E. I. Hatch Unit 2 Fall Refueling Outage. These pressure tests were performed for the l purpose ofinservice inspection of Class I components. No Class 2 pressure tests were performed this

) outage. The pressure tests and their boundaries are identified in the Inservice Inspection Plan Documents prepared by Southern Nuclear Operating Company.

All pressure tests were performed in accordance with ASME Section XI,1980 Edition with Addenda through Wm~ ter 1981. All tests were witnessed and/or reviewed by the resident ANIL The completed test reports are available for review in the Records Management Department at Plant E. I. Hatch.

CLASS 1 PRESSURE TESTS One (1) Class 1 Leakage Test was performed during the outage per ASME Section XI, paragraph IWA-5211(a). The test was performed per GPC procedure 42IT-TET-006-2S, ISI Pressure Test of the Class 1 System.

TEST RESULTS One (1) fillet weld on a small bore reactor water sample line was found cracked during the VT-2  !

examination. This weld was repaired / replaced prior to startup. The VT-2 examination also found some  !

minor leakage at mechanicaljoints. Any component which was disassembled prior to startup or to repair leakage, was re-examined during startup at normal operating pressure (1035 psig) per GPC procedure 42IT-TET-004-0S, Operating Pressure Testing ofPiping and Components.

CLASS 1 PRESSURE TEST

SUMMARY

i TEST I.D. PROCEDURE MWO NUMBER 2B21-LT-1 42IT-TET-006-2S 2-95-0377 i

I 41

l l

1. Owner: C u T- O . 333 P' * ^ Ave.. NE. P. O. hx 4545. .* '- C u 30302  !

2. Plant: FAwin I. Ilmarti Nah PlanL Rouse 1. Box 278. b-i v.O A 31513.

3. Plant Unit 1 4. Owner certifxans of Ausharutation (ifreq.) E

$. CanmarcialServiceDese 09@$/79 6. Naticaal Board No, for Unit H/6 l

I l l J

l I  !

I 1

l l

}

i

SUMMARY

OF VISUAL EXAMINATIONS CLASS 1 AND 2 COMPONENT SUPPORTS 1

1 i

l 1

i l

i i

f l

t 1

i 42

-- __ = . . - . _ .

1. Owner: oeorma Power comoanv. 333 Picenant Ave,. NE P. O. Box 4545. Mf=da ocornia 30302

3. Plant: Edwm I. Hatch Nuclear Plant. Route I. Ibx 278. Baxlev OA 31513.

3. Plant Unit 2 4. Owner Ceruficate of Authoruation Of req.) M

5. Commercial service Date Q997r79 6. National Board No. far Unit H3 COMPONENT SUPPORT EXAMINATIONS This section of the report provides a discussion of the visual examinations performed on selected component supports on Hatch Unit 2. Pipe Supports inspected are listed on separate tables as part of this

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

) Examinations were performed using SNC Procedure VT-H-730 (VT-3 and VT-4). The procedure and all examination data sheets are available for review at the plant site.

Class 1 One (1) component support from the 2B11 system was visually examined. No unacceptable indication was detected.

Class 2 Twenty-eight (28) component supports from the 2El1,2E21,2E41,2E51, and 2T47 systems were visually examined. No unacceptable indications were detected.

O m

6 43

E.I. Hatch Unit 2 Support Components ASME Exam Figure ExamlCat Class No. Examination / Hanger Type Location Elevation Shoot No. Results Remarks 1

1 2B11-SK1 - 2811-A001-S01 DRYWELL 114 S95H2V054 SAT REACTOR VESSEL 2 2E11-SK4 - 2E11-8001A-S01 NE DIAG 112 S95H2V031 SAT HT EXCH 2 2E11-SKS - 2E11-C002A-S01 NE DIAG 122 S95H2V030 SAT PUMP 2 2E21-SK6 - 2E21-C001 A-S01 NE DIAG 87 S95h"2V055 SAT '

PUMP 2 2E41-SK7 - 2E41-C001-S01 SE DIAG 112 S95H2V021 SAT PUMP 2 2E51-SK8 - 2E51-C001-S01 NW DIAG 87 S95H2V033 SAT PUMP 2 2T47-SK9 - 2T47-8007A-S01 DRYWELL 183 S95H2V045 SAT COOLING UNIT 2 2T47-SK9 - 2T47-8010A-S01 DRYWELL 114 S95H2V044 SAT COOLING UNIT 2 B-101/02 2E11 - RHR-R138 SE DIAG 94 S95H2V013 SAT-RESTRAINT C 30302

l. Ommer- CTP . 333 W Am_ NE P. O. Box 4545. .

I Edheim I. Haach W Plant *- 1. Boz M Baulev OA 31513.

2. Plant:

3. PlantUnit2 4. Owner Carh8Eeda of Amehariraham (if reg) h -

3. rW Servios Date OM509 6. Natiemmi Board No. For Unit E/&

____m._ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ . - _ _ - - __ ._a_a . v-

E.I. 64atch Unit 2 -

Support Components Exam Figure ExamlCal ASIAE '

No. Location Elevation Sheet No. Results Remarks Class ExamirN Type 2E11 - RHR-R139 SE DIAG 94 S95H2V014 SAT 2 B-101/02 RESTRAINT B-19/05 2E11 - RHR-H202 TORUS 122 S95H2V025 SAT 2 (

HANGER B-19/05 2E11 - RHR-H203 TORUS 122 S95H2V026 SAT  ;

2 HANGER I

TORUS 122 S95H2V027 SAT I 2 B-19/05 2E11 - RHR-H204 HANGER B-23/05 2E11 - RHR-R81 RWCU HX ROOM 178 S95H2V043 SAT  ;

2 i RESTRAINT ,

2E11 - RHR-R82 RWCU HX ROOM 178 S95H2V042 SAT 2 B-23/05 RESTRAINT i

2E11 - RHR-H178 NE DIAG 113 S95H2V037 SAT 2 B-27/03 SPRING 2E11 - RHR-A50 TORUS 121 S95H2V034 SAT 2 B-34/06 ANCHOR t I

i 2E21 - CSE SE DIAG 123 S95H2V015 SAT 2 B-59/06 ANC:iOR t

1. Oumer- GurumaFeuerCommamv.333 h Ave NE.P.O.Das4341 AslamatGammma 30302 Page: D 2. Flame: Edma L Hans Nacieur Flemt. Rauts I. Bos 27L Basisy. GA 31313.

3. FismUnia 3 4. Owns condemas of Amihanamnem (irreg) N/A

s. commmeistserviceDee 0943n9 6. Nasienni Based Net for Unit H%

e

E.I. Hatch Unit 2 Support Components Exam Figure Exam / Cal ASME No. Examination / Hanger Type Location Bevation Sheet No. Results Remarks

] ass __

2 B-59/06 2E21 - CS-R70 SE DIAG 108 S95H2V016 SAT RESTRAINT 2 B-5906 2E21 - CS-R71 SE DIAG 108 S95H2V017 SAT RESTRAINT B40/05 2E21 - CS-A32 REACTOR BLDG 162 S95H2V023 SAT 2

ANCHOR 2 B-608/03 2E21 - CS-H83 SE DIAG 95 S95H2V035 SAT SPRING B-61/05 2E21 - CS-R41 TORUS 87 S95H2V029 SAT 2

RESTRAINT B-16/04 2E41 - HPCI-H85 NW DIAG 120 S95H2V040 SAT 2

HANGER 847/03 2E41 - HPCI-A65 TORUS 120 S95H2V041 SAT 2

ANCHOR B-68/05 2E41 - HPCI-H70 HPCI ROOM 120 S95H2V036 SAT 2

SPRING B-68/05 2E41 - HPCI-R75 HPCI ROOM 120 S95H2V018 SAT 2

RESTRAINT

1. Oumar C- T P w 333 7 - Ave NE P. O. Bar 4545. ." " ^- c -- 3034 Page 4b 2. w w 13-44. % w == 1. Boa M ha%.GA 3I513.

Quest Certdeses of Aushanassomm (ifreq.} h

3. PlastUnit2

5. Commmecisiservice Does OP45/79 6. N=ew Banni No. for Unit H(A

t E.I. Hatch Unit 2 Support Componoms l

ASME Exam Figure w Class No. Examination / Hanger Type Location Elevation Sheet No, m g ,

2 B48/05 2E41 - HPCI-R79 HPCI ROOM 120 S95H2V019 SAT RESTRAINT ,

2 B- 2E51 - RCIC-H709 TORUS 120 S95H2V056 SAT 70A(D W RESTRAINT

^P 30302 I. Ommer C-- Fwuser -_'3 E " Tm NE. P. O_ Bam 4545_ _^

EdurinL T *I h *

• I Boa 271 ' _ GA 31313.

2. PImat:

3. Plant Unit 2 4. Ommer Candemas of Authoremma= (irreg)If/A

3. rWSeviosDm 0Pe$n9 6. hianni sond Na srunit tu_A Pae.: 47

. . . . -.m ._ ._ _ _ _ . m. _ _ _ _ . . . _ . _ _ __ .__ _ _ _

l. Owner. C - r C- .333 F ^ ^ Ave.. NE. P. O. Bor 4545. M'" C -s 30302

3. Plass: Edmn 1. Hatch Nuclear Plant. Route 1. Box 273. Baxlev. OA 31513.

3. Plast Unit 2 4. Owner Cert:6cate off " t: :' -- (if req.) E

5. comunercial service Dese 0995/79 6. National Board No, for Unit Nf%

SNUBBER SUPPORT EXAMINATIONS This section of the report provides a discussion of the visual examination (VT) performed on snubber supports. All safety related snubbers were VT examined by GPC QC personnel using GPC procedure l 45QC-INS-012-0S (VT-3). l The subject examinations were performed prior to and during the Refueling / Maintenance Outage. The procedure and all examination data sheets are available for review at the plant site.

l l

Examinations Class 1 Sixteen (16) snubbers from the 2B21,2B31,2El1, and 2E41 systems were visually examined. No l unacceptable indications were detected. l Clats_2 Thiny-two (32) snubbers from the 2El 1, 2E21, 2E51, 2N11, 2T46, and 2T48 systems were visually examined. No unacceptable indications were detected.

i 1

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48

1. Owner: Georma Power Comnanv. 333 Piedmont Ave NE. P. O. Ibx 4545. Atlanta. (har=a= 3^3 2L Plant- Edwin L Haede Nuclear Plant. Route I. Box 278. Baxlev. GA 31513.

3. Plam Unit 2 4. Owner cert:6 case or Amiharuation (irreq.)h i CommercialService Dane 0945n9 6. National Board No. ror Unit E3 E. L Hatch Unit 2 Snubbers ASME Exam Figure

. Class No. Examination / Hanger Tvoe Locat ion Elevation Results Remarks 1 A-7/07 2B21-MS-R49A Drywell 167 Sat Mechanical Snubber 1 A-7/07 2B21-MS-R49B Drywell 167 Sat -

Mechanical Snubber 1 A-8/07 2B21-MS-R44A Drywell 150 Sat Mechanical Snubber 1 A-8/07 2B21-MS-R44B Drywell 150 Sat Mechanical Snubber 1 A-17/04 2B31-SS-A20 Drywell 138 Sat Replaced MWO 2-95-2582

' Hydraulic Snubber - Evaluated by GPC Engineering as degraded, not a failure.

1 A-18/05 2B31-SS-B1 Drywell 117 Sat Hydraulic Snubber j I A-18/05 2B31-SS-B2 Drywell 125 Sat Replaced MWO 2-95-1118 Hydraulic Snubber Evaluated by GPC Engineering as degraded, not a failure.

1 A-18/05 2B31-SS-B3 Drywell 125 Sat Hydraulic Snubber 49

J L 1 Owner- Omarman Power Ceamiemv.333 Ph Ave NF_ P. O. Ihr 4545. Atleman.Geeruna MM

2. Plant: Edwin L Hands Nudear Pimmt. h 1. Hos 278. m=8-v. GA 31513.

3. Plum Unit 2 4. Owner Certdienee erAusheriantsee (ir%) h

5. CanumarcselServiaDese 0993/19 6. Nationni Board Na ror Unit EL4 E. I. Hatch Unit 2 Snubbers ASME Exam Figure Class No. Examination / Hanger Tvoe Is=* ion Elevatina Resuhs Remarks 1 A-18/05 2B31-SS-B6 Drywell 137 Sat Hydraulic Snubber 1 -

2B31-S40-H1 Drywell 120 Sat Mechanical Snubber 1 A-21/05 2ElI-RHR-R342 Drywell 139 Sat Mechanical Snubber 1 A-22/05 2El1-RHR-R355 Drywell I50 Sat Deleted MWO 2-95-2592 Mechanical Snubber Evaluated by GPC Engineering as degraded, not a failure.

1 A-23/05 2E11-RHR-R350 Drywell 15 3 Sat Mechanical Snubber 1 A-23/05 2El1-RHR-R357A Drywell 150 Sat Mechanical Snubber 1 A-26/06 2E41-HPCI-R113B Drywell 145 Sat Mechanical Snubber 1 A-26/06 2E41-HPCI-RI12 Drywell 145 Sat Replaced MWO 2-95-2%9 Mechanical Snubber Evaluated by GPC Engineering as degraded, not a failure.

50

.)

I. Owner: Georma Power Caseenv.333 Pie &nos Ave NF_ P. O. Box 4545. Atlansa.n 30302

2. Plam: Edwin L Hasch Nuclear Pimm. *- 1. Box 275. sa..i.v. OA 31513.

3. Plant Umt 3 4. Owner Certificate of Authanzation (if reg) E

5. commercial Service Deee 099509

6. National Board Na ror Unit H3 E. I. Hatch Unit 2 Snubbers ASME Exam Figure Class No. Examination /Hanner Tvoe Location Elevation Results Re.-rks 2 B-15/05 2El1-RHR-R292A Torus 118 Sat Mechanical Snubber 2 B-17/07 2El1-RHR-R93B Torus 118 Sat Hydraulic Snubber 2 B-17/07 2EI1-RHR-R705A Torus 118 Sat Mechanical Snubber 2 B-18/06 2EIl-RHR-R129A Torus 123 Sat Hydraulic Snubber 2 B-18/06 2E11-RHR-R129B Torus 123 Sat Hydraulic Snubber 2 B-19/05 2El1-RHR-R297A Torus 118 Sat Mechanical Snubber 2 B-21/07 2E11-RHR-R100 Torus 119 Sat Hydraulic Snubber 2 B-21/07 2El1-RHR-RIO5A Torus 1I8 Sat Mechanical Snubber 2 B-21/07 2El1-RHR-R106 Torus 118 Sat Mechanical Snubber 51

l. Owner. Georana Power Commany,333 Pushnunt Ave NF_ P.O. Box 4543, Atlanta.Georma 30302

2. Phut Edunn L liasch Nuclear Plant. Route 1. Box 278. Bexley.GA 31513.

3. Plam Unit 2 4. Owner Certdicade of Authernasson (ifreq.)M

5. commercialServiceDase 09M5n9 6. National Board Na for Unit E3 E. I. Hatch Unit 2 Snubbers ASME Exam Figure Class No. Examination / Hanger Tvoe Location Elevation Results Remarks 2 B-21/07 2El1-RHR-R708 Torus 119 Sat Mechanical Snubber 2 B-26/04 2El1-RHR-R251 A NE Diag i19 Sat Hydraulic Snubber 2 B-32/04 2El1-RHR-R282 SE Diag 103 Sat Hydraulic Snubber 2 B-32/04 2El1-RHR-R285B SE Diag 100 Sat Hydraulic Snubber 2 B-40/04 2El1-RHR-R253 NE Diag 118 Sat Hydraulic Snubber 2 B-42/06 2El1-RHR-R225 Torus 90 Sat Mechanical Snubber 2 B-42/06 2El1-RHR-R230 Torus 90 Sat Mechanical Snubber 2 B-60B/03 2E21-CS-R82B SE Diag 97 Sat Replaced MWO 2-95-2570 Mechanical Snubber Evaluated by GPC Engineering as degraded, not a failure.

2 B-86/04 2E51-RCIC-R705 Torus 89 Sat Replaced MWO 2-95-2571 Mechanical Snubber Evaluated by GPC Engineering as degraded, not a failure.

52

1. Owner- Geonna Pouver Comnany. 333 I%hnant Ave NF_ y P. O. Box 4545. Atlanta. Georma 30302

2. Plant- Edusin L Hasde Nuclear Plasd. Rouse 1. Box 278. Baxlev. GA 31513.

3. Finnt Unit 2 4. Owner Certificase bf h (if req )h S. Cornrnercial Service Date 0995/79 6. National Board No. for Unit F_/A E. I. Hatch Unit 2  ;

Snubbers .

ASME Exam Figure -

Class No. Examination / Hanger Tvoe Location Elevation Results Remarks  :

i 2 B-6/04 2N11-HPS-R67B Con Bay 156'10 Sat Mechanical Snubber j 2 B-7/04 2N11-MS-R70 Con Bay 149 Sat Mechanical Snubber 2 B-7/04 2N11-MS-R72 Con Bay 149 Sat l Hydraul;c Snubber 1 2 B-9/05 2N11-MS-R44A Con Bay 154 Sat Hydraulic Snubber 2 B-10/07 2N11-MS-R38A Con Bay 149 Sat Hydraulic Snubber

. t 2 B-12/06 2N11-MS-R50A Con Bay 154 Sat Hydraulic Snubber 2 B-12/06 2N11-MS-R50B Con Bay 154 Sat Hydraulic Snubber l l

2 -

2N11-MS-A60D Con Bay 153 Sat Mechanical Snubber l 2 -

2 nil-MS-R61B Con Bay 154 Sat ReplacM MWO 2-95-3030 Mechanical Snubber Evaluated by GPC Engineering as degraded, not a failure.  ;

i 53

1. Owner- Oecrea Power Company. 333 Piemhnunt Ave NE. P.O. Box 4545. Atlanta.Geomas 30302

2. Plam: fatyn L 11anch Nuclear Plant Rowe 1. Box 278. Baxlev. GA 31513.

3. Plast U st 2 4. Owner Certificate of Authernation (ifreg)N!&

S. Commacial Service Dese 0905r19 6. National Board No. for Unit E/A E. I. Hatch Unit 2 Snubbers ASME Exam Figure Class No. Examinatica/ Hanger Tvoe Location Elevation Results Rerrerks 2 - 2N11-MS-R62A Con Bay 154 Sat Replaced MWO 2-95-3030 Mechanical Snubber Evaluated by GPC Engineering as degraded, not a failure.

2 -

2T46-SGTS-R65B A/H Room 197 Sat Hydraulic Snubber 2 -

2T48-CPUR-R12 Rx Bldg. 185 Sat Hydraulic Snubber 2 -

2T48-CPUR-R13 Rx Bldg. 185 Sat Hydraulic Snubber ,

2 --

2T48-CPUR-R55 Rx Bldg. 130 Sat Hydraulic Snubber -

t L

i 54

.- - - _ _ _ - _ -_- --_-____ _ _- _--____ _ __-- - -- -_ _ - _ --_ _. . = _ - - _ _ _ _ _ _ _ - _ _ _ _ . . - _ _ - _ _ _ _ - _ _ _ _

-v . -

1 1

1. Owner: Geormia Power Comnany. 333 Puuhnant Ave.. NE. P. O. Box 4543. Mi-- Oeonna 30302 l

3 Plant: Edwin I. liao* Nuciaar Plant Dad

• 1. Box 278. Baxlev. OA 31$13.

3. Plant Unit 2, 4. Owner Certificate of Authonzatson (if req.)h

5. CommercialServiceDate 09W79 6. National Board No. for Unit ti%

i

SUMMARY

OF i l

NON-S AFETY NUREG-03I3, REV. 2 INSPECTIONS I i

l I

l l

55

E.I. Hatch Unit 2 Class 3 C-1 ;- - n'a ASME Exam Figure ExamlCat Section XI No. ExaminationfArea Examination Procedure Cal Block Sheet No. Results Remarks REACIQB.WAIER_ CLEAN-UP_SYSIEM

- C-128/02 2G31-3RWCU-4-BD-3 UT-H-400/13 145-H S95H20201 NRI

- S95H2U202 NRI NUREG-0313S ELBOW TO REDUCER S95H2U203 N/A T/C

- C-129/01 2G31-3RWCU-4-D-1 UT-H-400/13 145-H S95H2U154 NRI

- S95H2U155 NRI NUREG-0313S REDUCER TO TEE S95H20156 N/A T/C

- C-129/01 2G31-3RWCU-4-D-2 UT-H-400/13 145-H S95H20137 NRI

- S95H2U138 NRI NUREG-0313S TEE TO PIPE S95H2U139 N/A T/C

- C-126/01 2G31-3RWCU-5-BS-1 UT-H-400/13 153-H S95H2U195 RI GEOMETRY ONE-SIDED EXAM DUE TO

- S95H2U196 NRI FLANGE CONFIGURATION.

NUREG-0313S REDUCER TO PIPE S95H2U197 N/A T/C

- C-126/01 2G31-3RWCU-5-BS-2 UT-H-400/13 153-H S95H2U198 NRI ONE-SIDED EXAM DUE TO S95H20199 NRI FLANGE CONFIGURATION.

NUREG-0313S PIPE TO FLANGE S95H2U200 N/A T/C

- C-125/01 2G31-3RWCU-6-D 1 UT-H-400/13 133-H S95H2U143 N/A T/C ONE-SIDED EXAM DUE TO S95H2U144 NRI VALVE CONFIGURATION.

NUREG-0313S VALVE TO ELBOW S95H2U145 NRI C- Power P 333 7

• Ave _ NE P. O_ Bas 4341_^ C_ -

1. Ow

2. Muut Eden L Hatch Nuclamr FimuL Emms 1. Bas 27L Basisy.GA 31$13.

Page: 56 3. ri muws2 4. O-== c=amaa. orammer===.e gm > n S. Commmercamt Service Dame OMSU9 6. Namammi Board New for Unit N/.A

E.1. Hatch Unit 2 Class 3 Components ExanVCal ASME Exam Figure Results Remarks Section XI No. Examination / Area Examination Procedure Cal Block Sheet No. - - .

UT-H400/13 133-H S95H20140 NRI

- C-125/01 2G31-3RWCU-6-D-5 S95H2U141 NRI S95H2U142 N/A T/C NUREG-03135 PtPE TO ELBOW .

^ Ave NE. P. O. Box 4545. _" '- -- r----- 30302

1. Oumer- C- T O w .3337" Page: 57 2. Plant: Eden I_ Het Nu&ar h Ram 1 Box 278. Baey. GA 31513.

3. FlestUnit2 4. Owner Cartdicaec ofAusborua m (ifreg) M6L

5. C 2 Service Dese 0945/79 6. National Boant No. forUnit N/A

I i

1. Owner: GeonnaT - Cc __ . 333T' ' - Ave.. NE. P. O. Box 4545. Pi-~- C O 30302

3. Plae Edwin I. Hatch Nuclear Plant Route 1. Box 278. Baxlev. GA 31513.

3. Plant Unit 2. 4. Owner Certifx:ase of Authanzacon (if req.) h

5. Commercial Service Date 0995/79 6. National Doerd No. for Unit N/A l

l i

l 1

l

SUMMARY

OF REACTOR PRESSURE VESSEL INTERNAL INSPECTIONS l

e i

l I

l l

58

E.I. Hatch Unit 2 IVVI Components ASME Exam Figure Exam / Cal Section XI No. Examination / Area Examination Procedure Cal Block Sheet No. Results Remartis _ _ _ .

IN-YESSELYlSUAL INSPECTIONS B13 21 2-BN-8-1 D-13 VT-H-750/06 S95H2V100 NI B-N-2 '

ASME TOP GUIDE HOLD DOWNS @

187.5* j B13 21 2-BN-8-1 D-14 VT-H-750/06 S95H2V100 NI B-N-2 ASME TOP GUIDE HOLD DOWNS @

202.5*

B13.21 2-BN-8-1 D-15 VT-H-750/06 S95H2V100 NI B-N-2 ASME TOP GUIDE HOLD DOWNS @

217.5*

B13.21 2-BN-8-1 D-16 VT-H-750/06 S95H2V100 NI B-N-2 ASME TOP GUIDE HOLD DOWNS @

232.5* . i 2-BN-8-1 D-17 VT-H-750/06 S95H2V100 NI B13.21 B-N-2 ASME TOP GUIDE HOLD DOWNS @

247.5* .

B13 21 2-BN-8-1 D-18 VT-H-750/06 S95H2V100 NI B-N-2 ASME TOP GUIDE HOLD DOWNS @

262.5*

1. Owner: 93erms Egun.Gengenv.333 Pinement Ave NE. P. O. Box 4545. " c--- 303 i Page: 5$ 2. No E6nn L M Ne&w Flam. Rom 1. Bw 27L Bahr. GA 31313.

3. Pied Unit 2 4. Owner Canadicans of Amesensessen (if reg.) h

3. M Service Does 9995/7P 6. Nossommi Boeni Na for Unit H%

E.L Hatch Unit 2 IWI Components ExamfCal ASME Enarn Figure No. Examination Procedure Cal 88ock N M** Results Remark _s Section XI ExaminationfArea VT-H-750/06 S95H2V100 NI B13 21 2-BN-8-1 D-19 B-N-2 ASME TOP GUIDE HOLD DOWNS @

277.5*

t VT-H-750/06 S95H2V100 NI B13.21 2-BN-8-1 D-20 B-N-2 ASME TOP GUIDE HOLD DOWNS @

292.5*  !

VT-H-750dO6 S95H2V100 NI B13.21 2-BN-8-1 D-21 5 B-N-2 ASME TOP GUIDE HOLD DOWNS @  !

307.5*

U VT-H-750/06 S95H2V100 til B13.21 2-BN-8-1 D-22 i d-N-2 ASME TOP GUIDE HOLD DOWNS @

322.5*  ;

VT -750f06 S95H2V100 NI B13.21 2-BN-8-1 D-23 B-N-2 ASME TOP GUIDE HOLD DOWNS @  !

337.5* i l

VT-H-750/06 S95H2V100 N1 B13.21 2-BN-8-1 D-24 B-N-2 l

ASME TOP GUIDE HOLD DOWNS @

352.5*

l r

1. Oumer: c--_ r._ Commany 333 T' " - ^ Am NE.P.O. Han 4545 J" C__ M

2. Plass: Edume 1. ?'" r PM *- 1_ Bas 27L Bouluv. GA 31513.

• 8* 3. Plass Umia 2 4. Owmar Candicune of h(ifreg) HQL S. cW Service Dune opo$ny 6. Noaiemmi Bened No. for Umia ELS i

f

E.I. Hatch Unit 2 .

6 IVVI Components ExamK:af ASME Exam Figure Roma.ks Examination Procedure Cal Block Sheet No. Results Section XI No. ExaminationIArea S95H2V100 RI RE-EXAMINATION OF DRYER VT-H-750/06

-- 2-BN-17-1 PREVIOUSLY RECORDED

• INDICATIONS.

-- TEAR ON TOP PLATE NEAR 180*

AZIMUTH VT-H-750/06 S95H2V100 Ni

- 2-BN-6-3 E-22

-- SHROUD HEAD HOLD DWN BRCKTS ATTACH WELD AZIMUTH 215 DEG VT-H-750/06 S95H2V100 NRI

-- 2-BN-6-3 E-23

-- SHROUD HEAD HOLD DWN BRCKTS ATTACH WELD AZIMUTH 225 DEG VT-H-750/06 S95H2V100 NI

-- 2-BN-6-3 E-24

-- SHROUD HEAD HOLD DWN BRCKTS ATTACHWELD AZIMUTH 235 DEG VT-H-750/06 S95H2V100 NI

-- 2-BN-6-3 E-25

-- SHROUD HEAD HOLD DWN BRCKTS ATTACHWELD AZIMUTH 245 DEG VT-H-750/06 S95H2V100 NRI

-- 2-BN4-3 E-26

-- SHROUD HEAD HOLD DWN BRCKTS ATTACH WELD AZIMUTH 255 DEG

__333 7 " ^ Ave _ NF P. O. Box 4545. ." e 30302

1. Owear- C 7. f'

2. Flass: El-_. L lMI" Plant *= L Bos 273. n -a-y_ GA 31513.

Page: b1 3. Pine this 2 4. Owear Canaru:sse of Auemnance Ofreg)tu_A S. W Service Dese 094509 6. Neasonal Board Na for Unit 1[/A

. E.1. Hatch Unit 2 IVVI Components ASME Exam Figure Exam / Cal Section XI No. Examination / Area Examination Procedure Cal Block S j No. _Res_ults . _ , _, Remarks .

-- 2-BN4-3 E-27 VT4750/06 S95H2V100 N1

-- SHROUD HEAD HOLD DWN BRCKTS ATTACH WELD AZIMUTH 265 DEG

-- 2-BN-6-3 E-28 VT-H-750/06 S95H2V100 N1

-- SHROUD HEAD HOLD DWN BRCKTS ATTACH WELD AZIMUTH 275 DEG

-- 2-BN-6-3 E-29 VT-H-750/06 S95H2V100 N1

-- SHROUD HEAD HOLD DWN BRCKTS ATTACH WELD AZIMUTH 285 DEG

-. 2-BN-6-3 E-30 VT&750/06 S95H2V100 Ni

-- SHROUD HEAD HOLD DWN BRCKTS ATTACH VELD AZIMUTH 295 DEG B13.22 2-BN-8-2 F-25 42-43 VT-H-750/06 S95H2V100 NI B-N-2 ASME CORE TOP GUIDE CELLS r

813.22 2-BN-8-2 F-26 42-47 VT-H-750/06 S95H2V100 N1 B-N-2 j CORE TOP GUIDE CELLS  ;

ASME

1. Owner- Georma Power Commany.333 hedmos Ave NE. P. O. Boa 4545. Aslama paprsma 30302 Page: 62 2. Phe- Edom L Het Neder Flam. Roues I. Box 275. Badry. OA 31313.

3. PlamUnit2 4. Owner Cah ofAmsbonansson (ifreg.) N(A

3. CommmeraalSaviceDese 094509 6. National Board Na for Unit H/.&

E.I. Hatch UnM 2 IVVI Components Exam / Cal ASME Exam Figure Remarks No. Examination Procedure Cal Block Sheet No. Roeults Section XI Examination / Area _

VT-H-750/06 S95H2V100 NI B13 22 2-BN-8-2 F-3146-43 B-N-2 ASME CORE TOP GUIDE CELLS VT-H-750/06 S95H2V100 N:

B13 22 2-BN-8-2 F-58 42-07 B-N-2 ASME CORE 10P GUIDE CELLS VT-H-750/06 S95H2V100 N1 B13.22 2-BN-8-2 F-59 42-11 S95H2V100 NI B-N-2 ASME CORE TOP GUIDE CELLS VT-H-750/06 S95H2V100 NI B13.22 2-BN-8-2 F-63 46-11 B-N-2 ASME CORE TOP GUIDE CELLS VT-H-750/06 S95H2V100 Ni B13 22 2-BN-8-2 F-7810-11  ;

B-N-2 ASME CORE TOP GUIDE CELLS VT-H-750/06 S95H2V100 NI B13.22 2-BN-8-2 F-108 06-43 i B-N-2 ASME CORE TOP GUIDE CELLS i

1

1. Oumar C-7P 333 7 ' Ave NF_ P. O. Bas 4341 J r um

2. Plant: Edwin L Heada W Flame. ** 1. Box 27L Budsv. OA 31313.

Page: 53 3. Fi maumina. 4.wcmarmg%)n i CommmercialServiceDese 09430P 6. Nasional Beant No. for Unit E%

E.I. Hatch Unit 2 IVVI Components Exam Figure Exam / Cal ASME Section XI No. Examination Procedure Cal Block Sheet No. Results Remarks Examination / Area _ _ _ _ _

F-11210-43 VT-H-750/06 S95H2V100 NI B13 22 2-BN-8-2 B-N-2 ASME CORE TOP GUIDE CELLS 2-BN-8-2 F-11310-47 VT-H-750/06 S95H2V100 N1 B13 22 B-N-2 ASME CORE TOP GUIDE CELLS G-8 VT-H-750/06 S95H2V100 NI 813.10 2-BN-3-3 B-N-1 ASME EXAMINATION OF VESSEL INTERIOR VT-H-750/06 S95H2V100 NI B13.22 2-BN-6-4 H-9 @ 135' B-N-2 SIL-572 SHROUD SUPPORT LEDGE TO RPV WELD VT-H-750/06 S95H2V100 NI B13.22 2-BN-6-4 H-9 @ 225' B-N-2 SIL-572 SHROUD SUPPORT LEDGE TO RPV WELD VT-H-750/06 S95H2V100 NI B13.22 2-BN4-4 M-9 @ 315*

S95H2V100 NI B-N-2 SHROUD SUPPORT LEDGE TO S95H2V100 NI StL-572 RPV WELD

1. Oumer- Georma Posser Comummmv.333 Ph Ave NE.P.O. Bos 4345. Aussa,Gearma 303

2. Plant: Edwin L Hamh Naciser FlamL Rauls 1. Box 27L Baulev.GA 31513.

Page: 64 3. N M 2- A NN ef h&MM

3. Commmacial Servies Dane 0943/79 6. Nh8 Board Na for Unit N/A

E.B. Hatch Unit 2

IVVI Components ASME Exam Figure Exam / Cal Section XI No. Examination / Area Examination Procedure Cal Block Sheet No. Res h RMs VT-H-750/06 S95H2V100 NI B 2 2-BN-6 4 H-9 @ 45*

B-N-2 ,

SIL-572 SHROUD SUPPORT LEDGE TO >

RPV WELD B13.22 2-BN-6-4 H-10 ID VT4750/06 S95H2V100 NI B-N-2 SIL-572 VERT WELD 230 DEG WELD V-2 H-14 OD VT&750/06 S95H2V100 NI B13 22 2-BN-64 B-N-2 SIL-572 VERT WELD 230 DEG WELD V-2 i

2-BN4-4 H-13 OD VT4750/06 S95H2V100 NI 813.22 B-N-2 SIL-572 VERT WELD 230 DEG WELD V-2 H-15 OD VT&750/06 S95H2V100 NI B13 22 2-BN-6-4 l B-N-2 SIL-572 VERT WELD 230 DEG WELD V-2 L

B13.22 2-BN-6-4 H-10 OD VT-H-750/06 S95H2V100 NI B-N-2 SIL-572 VERT WELD 230 DEG WELD V-2 e um 1 Omeur: C---- T_ Commmanv. 333 T' " ^ Ava NE P. O. Das 4545. .- -

pag.: 55 2. ri-c u--tr-m w =- t n== 2m - ..GA MSR

3. FlamUnit3 4. Owmar Carm6 cane of Amihasismeina(ifm) N/.&

$. PM Servios Duse 094509 6. NationalBoent Na for Unit H(A

t E.L Hatch Unit 2 IWI Compo:wnts ASME Emam Figure Exam / Cal Section XI No. Examination / Area Examination Procedure Cal Block Shoot No. Results Remarks B13 22 2-BNM H-13 ID VT-H-750/06 S95H2V100 NRI B-N-2 SIL-572 VERTICAL WELD 50 DEG WELD V-5 B13 22 2-BN-6-4 H-14 ID VT-H-750/06 S95H2V100 NI B-N-2 SIL-572 VERT WELD 230 DEG WELD V-6 B13 22 2-BN-6-4 H-15 ID VT-H-750/06 S95H2V100 NI ,

B-N-2 SIL-572 VERT WELD 140 DEG WELD V-7 B13.22 2-BN-6-4 Q-1 VT-H-750/06 S95H2V101 NI B-N-2 SIL-572 SHROUD RESTRAINT NO.1 @ 45*

SHROUD RESTRAINT ASSEMBLY B13 22 2-BN4-4 Q-2 VT-H-750/06 S95H2V101 NI 3 B-N-2 SIL-572 SHROUD RESTRAINT NO.1 @ 45*

CLEVIS PIN CONTACT AREA B13 22 2-BN-6-4 Q-3 VT-H-750/06 S95H2V101 NI B-N-2 ,

SIL-572 SHROUD RESTRAINT NO.1 @ 45' LOW SPRNG CONTACT AREA TO SHROUD

1. O wour Georms PowerCe .333 hadunant Ave NE.P.O.Bom 4545. AdamaL Gmuman 3034

2. Mont: Edenn L Headi Nedser h Route 1. Bos 27L Basisv. OA 31$13.

pag.: 56 3. mumaz 4. % m orAmeion ag% m

3. FW5srviosDese OM$n? 6. Naniemal Board Not sur Unit ]gA

E.I. Hatch Unit 2 IWI Components Examr.at ASME Exam Figure Remarks No- Examination Procedure Cat Block Sheet No.~ Results Section XI ExaminationtArea VT-H-750/06 S95H2V101 NI B13 22 2-BNM Q-4 B-N-2 SIL-572 SHROUD RESTRAINT NO.1 @ 45' LOWER SPRING CONTACT AREA TO RPV VT-H-750/06 S95H2V101 NI B13 22 2-BNM Q- 5 B-N-2 SIL-572 SHROUD RESTRAINT NO.1 @ 45*

MID SUPPORT CONTACT AREA TO RPV VT-H-76. * ,, S95H2V101 NI B13.22 2-BN4-4 Q-6 B-N-2 SIL-572 SHROUD RESTRAINT NO 1 @ 45' UP STAB CONTACT AREA TO SHROUD VT-H-750/06 S95H2V101 NI B13 22 2-BN-6-4 Q-7 B-N-2 SIL-572 SHROUD RESTRAINT NO.1 @ 45*

UPPER STAB. CONTACT AREA TO RPV VT-H-750/06 S95H2V101 N1 B13 22 2-BNM Q-8 B-N-2 SIL-572 SHROUD RESTRAINT NO.1 @ 45' CORE PLATE WEDGE ASSEMBLY VT-H-750/06 S95H2V101 N1 B13.22 2-BNM Q- 9 B-N-2 SIL-572 SHROUD RESTRAINT NO.2 @ 135' SHROUD RESTRAINT ASSEMBLY e M

1. Oumar C __ Foner Commmmv.333 7 * - Avat NIL P. O. Best 4545. _^

Page: 67 Mwin L * *T M ** 1. Boa 278. ' " ;.GA 31313.

2. Flmd:

3. Flama Unit 2 4. Owner Candenes of Amherumsson (ifg) h

5. CesamarcantserviosDues 0P45/79 6 Nh BoardNo. trUnit N(A

E.I. Hatch Unit 2 IVVI Components ExanVCal ASME Exam Figure Remarks No-Results -.

Section XI Examination / Area

- . - . . . - - - - . -_---Examination Procedure Cal Block Sheet No.

VT-H-750/06 S95H2V101 NI B13.22 2-BN-6-4 Q-10 B-N-2 Sil-572 SHROUD RESTRA!NT NO 2 @

135* CLEVIS PIN CONTACT AREA VT-H-750/06 S95H2V101 N1 B13.22 2-BNM Q-11 B-N-2 SIL-572 SHROUD RESTRAINT NO.2 @ 135*

SPRING CONTACT AREA TO SHROUD VT-H-750/06 S95H2V101 NI B13 22 2-BN-6-4 Q-12 B-N-2 Sit-572 SHROUD RESTRAINT NO.2 @ 135' LOW SPRING CONTACT AREA TO RPV VT-H-750/06 S95H2V101 NI B13.22 2-BN-6-4 Q-13 B-N-2 SIL-572 SHROUD RESTRAINT NO 2 @ 135*

MID SUPPORT CONTACT AREA TO RPV VT-H-750/06 .S95H2V101 NI B13 22 2-BNM Q-14 B-N-2 SIL-572 SHROUD RESTRAINT NO.2 @ 135' UP STAB CONTACT AREATO SHROUD VT-H-750/06 S95H2V101 NI B13.22 2-BN-6 4 Q-15 B-N-2 Sit-572 SHROUD RESTRAINT NO.2 @ 135*

UPPER STAB. CONTACT AREA TO RPV

-e 1030;

1. Osmar- e = Pouer P 333 7 ^ - Ave _ NIL P. O Bam 4541_^

we 1. Baz M ' ';_GA 31313.

Page: 68 2. FW FJwin L - " r

3. Flam Unit 2 4. Ouest candcmas of Amnhanssanom (ir%) R

& Natiemal Board No. For Unit 2F]A

5. CommmaminiServiceDune (IM$@

E.I. Hatch Unit 2 8 IVVI Components ASME Exam Figure Exam / Cal Section XI No. Examination / Area Examination Procedure Cal Block Sheet No- Results __

Remarks B13.22 2-BNM Q-16 VT-H-750/06 S95H2V101 NI B-N-2 SIL-572 SHROUD RESTRAINT NO.2 @ 135*

CORE PLATE WEDGE ASSEMBLY B13 22 2-BN-6-4 Q-17 VT-H-750/06 S95H2V101 NI B-N-2 Sil-572 SHROUD RESTRAINT NO.3 @ 225*

SHROUD RESTRAINT ASSEMBLY B13 22 2-BNM Q-18 VT-H-750/06 S95H2V101 N1 B-N-2 SIL-572 SHROUD RESTRAINT NO.3 @ 225*

CLEVIS PIN CONTACT AREA B13.22 2-BN-6-4 Q-19 VT-H-750/06 S95H2V101 Ni, B-N-2 SIL-572 SHROUD RESTRAINT NO.3 @ 225*

LOW SPRG CONTACT AREA TO SHROUD B13.22 2-BNM Q-20 VT-H-750/06 S95H2V101 NI B-N-2 SIL-572 SHROUD RESTRAINT NO 3 @ 225' LOW SPR.ING CONTACT AREA TO RPV B13.22 2-BNM Q-21 VT-H-750/06 S95H2V101 NI B-N-2 SIL-572 SHROUD RESTRAINT NO.3 @ 225' MID SUPPORT CONTACT AREA TO RPV

. 333 7 " c 30302

1. Queer- C-- Power P Ave NE. P. O. Baz 4545 _^

Page: 69 2. m ma t uninw m m.m.1.Bm2R h OA 3M13.

3. FIssa Unit 2 4. Oumar Car *#==a= af Aanhanashes (if %) E(A

3. PWServiceDese OWO309 6. NanomalBoardNo forUnit E&

E l. Hatch Unit 2 IVVI Components ASME Exam Figure ExamtCal Section XI No. Examination / Area Examination Procedure Cal Block Shoot No. Results Remarks 2-BN-6-4 Q-22 VT-H-750/06 S95H2V101 NI B13.22 B-N-2 SIL-572 SHROUD RESTRAINT NO.3 @ 225' UP STAB CONTACT AREA TO SHROUD B13 22 2-BN4 4 Q-23 VT&750/06 S95H2V101 NI B-N-2 SIL-572 SHROUD RESTRAINT NO.3 @ 225' UPPER STAB. CONTACT AREA TO RPV 2-BN4-4 Q-24 VT&750/06 S95H2V101 NI B13 22 B-N-2 SIL-572 SHROUD RESTRAINT NO.3 @ 225' CORE PLATE WEDGE ASSEMBLY 2-BN4-4 O-25 VT-H-750/06 S95H2V101 NI B13.22 B-N-2 SIL-572 SHROUD RESTRAINT NO.4 @ 315*

SHROUD RESTRAINT ASSEMBLY 2-BN-6-4 Q-26 VT56-750/06 S95H2V101 NI B13.22 B-N-2 SIL-572 SHROUD RESTRAINT NO.4 @ 315*

CLEVIS PIN CONTACT AREA l

2-BN-6-4 Q-27 VT-H-750/06 S95H2V101 NI B13.22 B-N-2 SIL-572 SHROUD RESTRAINT NO 4 @ 315' LOW SPRG CONTACT AREA TO SHROUD l

1. Owmar- Gennen PowerCammmy.333 Puduma Ave NE.P.O. Bus 4343. Adaman. Gamma p l 1 Pc Edem N h h Emme 1. Bus 2R h OA 31513.

peo*: 70

3. PlantUnit2 4. Oumar Cam $omes of Andhanames (~af req.) N6L

5. CommuscialServiceDuas OP/0509 6. Natiemal Board NeJar Unia B(A l

l l

l

E.1. Hatch Unit 2 IVVI Components ASME Exam Figure Exam / Cal Section XI No. ExaminationfArea Examination Procedure Cal Block Sheet No. Results Remarks -

B13.22 2-BN-6-4 Q-28 VT-H-750/06 S95H2V101 NI B-N-2 SIL-572 SHROUD RESTRAINT NO 4 @ 315*

LOW SPRING CONTACT AREA TO RPV B13 22 2-BN4-4 Q-29 VT-H-750/06 S95H2V101 NI B-N-2 SIL-572 SHROUD RESTRAINT NO.4 @ 315*

MID SUPPORT CONTACT AREA TO RPV B13.22 2-BN-6-4 Q-30 VT-H-750/06 S95H2V101 Ni B-N-2 SIL-572 SHROUD RESTRAINT NO 4 @ 315*

UP STAB CONTACT AREA TO SHROUD B13.22 2-BN4-4 Q-31 VT-H-750/06 S95H2V101 NI B-N-2 SIL-572 SHROUD RESTRAINT NO.4 @ 315' UPPER STAB. CONTACT AREA TO RPV 2-BN-6-4 Q-32 VT-H-750/06 S95H2V101 NI B13.22 B-N-2 SIL-572 SHROUD RESTRAINT NO.4 @ 315*

CORE PLATE WEDGE ASSEMBLY '

.. 2-BN-4-8 J-1 VT-H-750/06 S95H2V100 NI S95H2V100 NI SIL-574 RESTRAINER FOR JET PUMPS 1 &

2 AZIMUTH 30 DEG

1. owner: ooorma Power Camminnv. 333 Finemana Avt. NE. F. O. Boa 4543. Admuss. Gasqua 3030;

2. Finnt Edurin L Hatch Niecisar FlasL Route 1. Bon 278. Basist. OA 31513.

Page: 71 4. h Ch ofAh &6

3. Plasa Useit1

3. PM Service Dese 0993n9 6. National Boent No. For Unit H%

E.L Hatch Unit 2 IWI Components Exam / Cal ASME Exam Figure Cal Block Sheet No. Results Remarks Section XI No. Examination / Area Examination Proc.edure.- - - - . . . . _.

VT-H-750/06 S95H2V100 Nt

-- 2-BN-4-8 J-17 S95H2V100 NI SIL-574 RESTRA;NER FOR JET PUMPS 3 AND 4 AZIMUTH 60 DEG VT-H-750/06 S95H2V100 NI

-- 2-BN-4-8 J-33 S95H2V100 NI blL-574 RESTRAINER FOR JET PUMPS 5 AND 6 AZIMUTH 90 DEG VT&750/06 S95H2V100 N1

-- 2-BN-4-8 J-49 S95H2V100 NI i

SIL-574 RESTRAINER FOR JET DUMPS 7 ,

AND 8 AZIMUTH 120 DEG VT-H-750/06 S95H2V100 NI

-- 2-DN-4-8 J-57 S$L-420 JET PUMP 7 SENSING LINE AZIMUTH 120 DEG i

VT-H-750/06 S95H2V100 NI

-- 2-BN4-8 J-58 SIL-420 JET PUMP 7 SENSING LINE UP ,

SPRT BRKT AZIMUTH 120 DEG VT-H-750/06 S95H2V100 NI

-- 2-BN-4-8 J-59 SIL-420 JET PUMP 7 SENSING LINE LOW SPRT BRKT AZIMUTH 120 DEG c- e. 333 Findsmast Ave._ NE. P. O. Bar 4341 ^ ^c 3030

1. Owear. C _7 l

2. Flesst: FM L Haach W h ** 1. Bog 27L Baulsv.GA 31513.

Page: h 3 FlandUnit2 4. Owner certinemas of Aussionameson (if req.) R

s. commessi servue one. opesop 6. Nasiemal Board No. For Unit E&

i

E.5 Hatch Unit 2 IVVI Componeetts 6

Exam / Cal ASME Exam Figure Results Remarks Section XI No. Examination / Area Examination Procedure Cal Block Sheet No. .

VT-H-750/06 S95H2V100 NI

-- 2-BN-4-8 J-65 S95H2V100 NI SIL-574 RESTRAINER FOR JET PUMPS 9 .

AND 10 AZIMUTH 150 DEG VT-H-750/06 S95H2V100 NI

-- 2-BN-4-8 J-81 S95H2V100 NI SIL-574 RESTRAINFR FOR JET PUMPS 11

& 12 AZIMUTH 210 DEG VT-H-750/06 S95H2V100 NI B13 20 2-BN-4-2 J-81A S95H2V100 N1 B-N-2 ASME RISER BRACE SUPPORT PADS TO VESSELWLD FOR JET PUMPS 11 & 12 VT-H-750/06 S95H2V100 NI

-- 2-BN-4-8 J-818 S95H2V100 NI SIL-551 RISER BRACE ARM FOR JET PUMPS 11 & 12 VT-lh-750/06 S95H2V100 NI

-- 2-BN-4-8 J-97 S95H2V100 NRI SIL-574 RESTRAINER FOR JET PUMPS 13

& 14 AZIMUTH 240 DEG ,

VT-H-750/06 S95H2V100 NI B13.20 2-BN-4-2 J-97A S95H2V100 NI S-N-2 ASME RISER BRACE SUPPORT PADS TO VESSELWLD FOR JET PUMPS 13 & 14

1. Oumar- Georma PowerCommamv.333 Piedmanus Ave NE.P.O.Bos 4343. Adaman.Gennea 30302 73 2. Plass: N M Nuclw Ns. Ram 1. k 2R Bahv. GA 31313.

3. Plasa Unit 2 4. Omier CartaScene of Aushomassen (irreg)N/A

3. PM Service Dese 0953/79 6. Nasional Boant Not for Unit N/A

E.L Hatch Unit 2 IVVI Components ASME Exam Figure Exam / Cal Section XI No. Examination / Area Examination Procedure Cal Block Sheet No. Results Remarks

-- 2-BN-4-8 J-97B VT-H-750/06 S95H2V100 NI

-- S95H2V100 NI SIL-551 RISER BRACE ARM FOR JET PUMPS 13 & 14

-- 2-BN-4-8 J-113 VT-H-750/06 S95H2V100 NI S95H2V100 NI SIL-574 RESTRAINER FOR JET PUMPS 15

& 16 AZIMUTH 270 DEG ,

2-BN-4-2 J-113A VT-H-750/06 S95H2V100 NI B13.20 S95H2V100 NI B-N-2 ASME RISER BRACE SUPPORT PADS TO VESSEL WLD FOR JET PUMPS 15 & 16

-- 2-BN-4-8 J-1138 VT-H-750/06 S95H2V100 NI S95H2V100 NI SIL-551 RISER BRACE ARM FOR JET PUMPS 15 & 16 J-129 VT-H-750/06 S95H2V100 NI

-- 2-BN-4-8 S95H2V100 NI SIL-574 RESTRAINER FOR JET PUMPS 17 AND 18 AZIMUTH 300 DEG J-129A VT-H-750/06 S95H2V100 NI B13.20 2-BN-4-2 B-N-2 S95H2V100 N1 ASME RISER BRACE SUPPORT PADS TO VESSELWLD FOR JET PUMPS 17 & 18

1. Oumer- Georma Power Camammv. 333 Ph Am.NE. P. O. Bas 4545. Asimmen.Ommama 3030

2. Plast: Edwin L Hatch Nuciser PimmL Roues 1. Bos 278. Basist. GA 31313.

Page: 74 3. PlamUnit2 4. Owmar Cah of Authanzames OfrmO NLL

5. c6 Service Dese OM3n9 6. Nhl BonniNo. For Unit F/A

E.1. Hatch Unit 2 IWI Comp;nents ASME Exam Figure ExamfCal Section XI No. Examination / Area Examination Proceduto Cat Block Shoot No. Results Remarks

-- 2-BN-4-8 J-1298 VT-H-750/06 S95H2V100 NI

-- S95H2V100 NI SIL-551 RISER BRACE ARM FOR JET PUMPS 17 & 18

-- 2-BN-4-8 J-137 VT-H-750/06 S95H2V100 NI

-- S95H2V100 NI StL-420 JET PUMP 17 SENSING LINE AZIMUTH 300 DEG

-- 2-BN-4-8 J-138 VT-H-750/06 S95H2V100 NI

-- S95H2V100 NI SIL-420 JET PUMP 17 SENSING LINE UP SPRT BRKT AZIMUTH 300 DEG

-- 2-BN-4-8 J-139 VT-H-750/06 S95H2V100 NI S95H2V100 NI SIL-420 JET PUMP 17 SENSING LINE LOW SPRT BRKT AZIMUTH 300 DEG

-- 2-BN-4-8 J-145 VT-H-750/06 S95H2V100 NI

-- S95H2V100 NI Sil-574 RESTRAINER FOR JET PUMPS 14

& 20 AZIMUTH 330 DEG B13.20 2-BN-4-2 J-145A VT-H-750/06 S95H2V100 Ni B-N-2 S95H2V100 Ni ASME RISER BRACE SUPPORT PADS TO VESSELWLD FOR JET PUMPS 19 & 20

1. Owar Qeormia Power Commen. 333 Ph Ave NE, P.O. Bos 4543. Aslama.Gennan 3030

2. Flama: Edinn L Hech Nacient PlanL Route 1. Bos 278. Baxter.OA 31513.

Page: 75 3. PladUnit2 4. Owear CW of Ausberusham (ifreg) H&L

5. ComunercistServiceDeb 09M09 6. National Board Na for Unit H%

E.L Hatch Unit 2 y IVVI Components ASME Exam Figure Exam / Cal Section XI No. Examination / Area Examination Procedure Cal Block Sheet No. Results Remarks

-- 2-BN-4-8 J-1458 VT-H-750/06 S95H2V100 NI

-- S95H2V100 NI SIL-551 RISER BRACE ARM FOR JET PUMPS 19 & 20

-- 2-BN-17-1 K-1 VT-H-750/06 S95H2V100 NI S95H2V100 N1

-- STEAM DRYER LIFTING EYE AND ROD AZIMUTH 35 DEG K-2 VT-H-750/06 S95H2V100 RI RE-EXAMINATION OF

-- 2-BN-171 S95H2V100 Ni PREVIOUSLY RECORDED WDI N ONS.

-- STEAM DRYER LIFTING EYE AND ROD AZIMUTH 145 DEG K-3 VT-H-750/06 S95H2V100 RI RE-EXAMINATION OF

-- 2-BN-17-1 S95H2V100 NI PREVIOUSLY RECORDED I"'^'"^

-- STEAM DRYER LIFTING EYE AND ROD AZIMUTH 215 DEG K-4 VT-H-750/06 S95H2V100 R1 RE-EXAMINATION OF

-- 2-BN-17-1 S95H2V100 Ni PREVIOUSLY RECORDED

-- STEAM DRYER LIFTING EYE AND ROD AZIMUTH 325 DEG K-5 VT-H-750/06 S95H2V100 RI RE-EXAM NATION OF

-- 2-BN-17-1 S95H2V100 Ng PREVIOUSLY RECORDED

-- STEAM DRYER SUPPORT S95H2V100 NI BRACKET AZIMUTH 34 DEG

1. Owner. C L - C w .333 F " - Ave. NE. P. O. Box 4545 _^ e 30302

• 76 zw - - % w no.i. i. n n 2nh OA 31313.

3. FlaitUnit2 4. Owner Carhfirma* of Aushansabon(if194)]$(

5. Commmercialservice Does 0945/79 6. NasionalBoard NoJor Unit H/A

E.L Hatch Unit 2 iWI Components ASME Exam Figure Exam / Cal Section XI No Examination / Area Examination Procedure Cal Block Sheet No. Results Remarks _

-- 2-BN-17-1 K-6 VT-H-750/06 S95H2V100 RI RE-EXAMINATION OF

" S95H2V100 RI PREVIOUSLY RECORDED

' INDICATIONS.

-- STEAM DRYER SUPPORT ,

BRACKET AZIMUTH 146 DEG

-- 2-BN-17-1 K-7 VT-H-750/06 S95H2V100 RI RE-EXAMINATION OF

-- S95H2V100 NRI PREVIOUSLY RECORDED

-- STEAM DRYER SUPPORT S95H2V100 NRI BRACKET AZIMUTH 214 DEG

-- 2-BN-17-1 K-8 VT-H-750/06 S95H2V100 Rt RE-EXAMINATION OF S95H2V100 Ni PREVIOUSLY RECORDED INDICATIONS.

-- STEAM DRYER SUPPORT BRACKET AZIMUTH 326 DEG

-- 2-BN-18-3 L-11 VT-H-750/06 S95H2V100 NI

-- MOISTURE SEPARATOR LOYER SUPPORT BLOCK O* THRU 360*

-- 2-BN-18-3 L-12 VT-H-750/06 S95H2V100 NI

-- MOIST SEP LWR SPRT BLOCK GUSSETS & ATTACHMENT WELDS 1 - 36

-- 2-BN-7-5 M-1 A VT-H-750/06 S95H2V100 NRI

-- S95H2V100 NI NUREG CR-4523 UPPER CORE SPRAY A PPG, NOZ

& BRCKTS -270 TO 90 DG C_ _ 7 r w _333 7' ' - Ave._ NE. P. O. Bom 4545. I e 3034

1. Oumer:

pg 77 2. Plus: Edwin L P " P - h ** 1 Baz 273 m a-v.GA 315t3.

3. Plass1.hnit 2 4. Owmar cens6cmas er Ausharumsson Of rug.)R

3. Ceammaniel Service Dese 099509 6. National Board Not for Unit ]fA

E.L Hatch Unit 2 IVVI Components ASME Exam Figure Exam / Cal Section XI No. Examination /Aree Examination Procedure Cat Block Sheet No. Results Remarks 2-BN-7-5 M-18 VT-H-750/06 S95FtV100 Rt SEE INF # IC5H2003. LINEAR S95H2V100 RI INDICATIONS ON THE NUREG CR4523 LOWER CORE SPRAY B PPG, NOZ S95H2V100 RI BRACE TO SHROW

& BRCKTS - 270 TO 90 DG S95H2V100 NI EPT BL A I PhR GE S95H2V100 RI EVALUATION.

2-BN-7-5 M-1C VT-H-750/06 S95H2V100 N1 S95H2V100 NI NUREG CR4523 UPPER CORE SPRAY C PPG, NOZ S95H2V100 NI

& BRCKTS - 90 TO 270 DG

-- 2-BN-7-5 M-1D VT-H-750/06 S95H2V100 NI SEE INF # 195H2003. LINEAR S95H2V100 NI INDICATIONS ON THE NUREG CR4523 LOWER CORE SPRAY D PPG. S95H2V100 NI BRACEO SHROW ATTACHMENT WELDS.

NOZ & BRCKTS - 90 TO 270 DG S95H2V100 RI ACCEPTABLE AS IS PER GE S95H2V100 NI EVALUATION.

S95H2V100 RI S95H2V100 NI S95H2V100 RI S95H2V100 RI S95H2V100 NI S95H2V100 RI S95H2V100 NI S95H2V100 RI S95H2V100 RI

-- 2-BN-7-5 M-2A VT-H-750/06 S95H2V100 N1 NUREG CR4523 UPPER CORE SPRAY INLET T-BOX AT 10 DEGREES TO SHROUD 1

1. Oumer. Omarmia Power Censseer. 333 Paedunant Avt. NE. P. O. Boa 4543. Masan.Gammin 31D02

2. Flam: Edene L Headt Nacise. Fleet. Roues 1. Bos 278. Basisv. GA 31513.

Page: 70 3. N Unit 2 4. Ousmer Ch dh g6

3. r'WalServiosDies 099309 6. Nasional Bonni No. For Unit HlA

E.I. Hatch Unit 2 IWI Comporwits ASME Exam Figure Exam / Cal Section XI No. Examination / Area Examination Procedure Cal Block Sheet No. Results Remarks

.. 2-BN-7-5 M-2B VT-H-750/06 S95H2V100 N1 NUREG CR-4523 UPPER CORE SPRAY INLET T.

BOX AT 170 DEGREES TO SHROUD

.- 2-BN-7-5 M-2C VT-H-750/06 S95H2V100 NI NUREG CR-4523 LOWER CORE SPRAY INLET T-BOX AT 190 DEGREES TO SHROUD

.. 2-BN-7-5 M-2D VT-H-750/06 S95H2V100 NI NUREG CR4523 LOWER CORE SPRAY INLET T.

BOX AT 350 DEGREES TO SHROUD

.. 2-BN-7-1 N-1A VT-H-750/06 S95H2V100 NI NUREG CR4523 CORE SPRY INTERN PPG FROM INLET @ 90 (2NSB) TO JUNC BOX

.. 2-BN-7-1 N-1 B VT-H-75006 S95H2V100 NI NUREG CR-4523 CORE SPRY INTERN PPG FROM INLET @ 270 (2NSA) TO JUNC BOX

t. Ommer: e _ power t' 333 7

• Awa_ NF_ P. O. Bau 4S45. AtlantL Gammen 3G302 Pogo: 79 2. Plant: Eduna L Haarg Nedmar Plant Rouer I. Bos 27L Basisv. GA 31313.

3, mg 4, % % g g

3. Commmenaal Service Duas 094509 6. Nasionni Boent Na for Unit N/A

E.L Hatch Unit 2 IVVI Components Exam Figure Exam / Cal ASME Section XI No. Examination Procedure Cal Block Sheet No. Results Remarks Examination / Area _ _ .

VT-H-750/06 S95H2V100 NI SEE INF # 195H2002 LINEAR

-- 2-8N-7-1 N-2A Ng INDICATION 1/2 INCH LONG.

595H2V100 A # A S CORE SPRY INTERN PPG FROM S95H2V100 Ni p g18 D NUREG CR-4523 JUNC BOX @ 90 TO SHROUD @ 10 S95H2V100 NRI OCTOBER 6,1995 S95H2V100 NI S35H2V100 RI

-- 2-BN-7-1 N-2B VT-H-750/06 S95H2V100 N1 S95H2V100 NI CORE SPRY INTERN PPG FROM S95H2V100 NI NUREG CR-4523 JUNC BOX @ 90 TO SHROUD @

170

-- 2-BN-7-1 N-3A VT-H-750/06 S95H2V100 NI S95H2V100 NI NUREG CR-4523 CORE SPRY INTERN PPG FROM JUNC BOX @ 270 TO SHROUD @

190 N-38 VT-H-750/06 S95H2V100 NI

-- 2-BN-7-1 S95H2V100 NI NUREG CR-4523 CORE SPRY INTERN PPG FROM '

JUNC BOX @ 270 TO SHROUD @

350 N4A VT-H-750/06 S95H2V100 NI B13 20 2-BN-7-2 B-N-2 ASME CC;iE SPRAY SUPPORT BRCKT ATTACH WELDS TO VESSEL @ 30

3. Oumer: Gamma Four Cammmmv. 333 h An NE F. O. Bom 4345. Adamak Gamrma 31D0 Page: 30 2. Mmmt Men L M Nasher Mmm. Rames 1. Bau 275. Bamisv. GA 31313.

3. FlautUnit3 4. Ommer cen6me of Ameanismes (irm)]i&L

5. ConsmuoimiserviceDune 094509 6. Neeiemmi Bened New for Unit li/A

E.I. Hatch Unit 2

, IVVI Components ASME Exam Figure Exam / Cal Section XI No. Examination / Area Examination Procedure Cal Block Sheet No. Results Remarks _

B13 21 2-BN-7-2 N-4B VT-H-750/06 S95H2V100 N1 B-N-2 ASME CORE SPRAY SUPPORT BRCKT ATTACH WELDS TO VESSEL @

150 ,

i B13.20 2-BN-7-3 N-4C VT-H-750/06 S95H2V100 NI B-N-2 ASME CORE SPRAY SUPPORT BRCKT ATTACH WELDS TO VESSEL @

210 B13.21 2-BN-7-3 N-4D VT-H-75G/06 S95H2V100 NI B-N-2 ASME CORE SPRAY SUPPORT BRCKT ~

ATTACH WELDS TO VESSEL @

330

-- A-1/05 N-5A VT-H-750/06 S95H2V100 NI NUREG CR4523 A LOOP CORE SPRAY INLET NOZZLE NSA

-- A-1/05 N-58 VT-H-750/06 S95H2V100 NI NUREG CR-4523 B LOOP CORE SPRAY INLET NOZZLE NSB

.. 2-BA-1 O-3E VT-H-750/06 S95H2V100 NI NUREG-0619 FEEDWATER NOZZLE INNER RADIUS @ 225 DEG (2N4C)

1. Owner: Dearma PowerCensmany.333 Piedunant Ave NE.P.O.Bez4343. Asimmen.Gemena 30302

2. Plant: Edwin L Hakh Nudser Plant. Roues 1. Bos 278. Bealsv. GA 315 J3.

Page: 31 3. PleWUnit2 4. Owner CErhnrate c(Auglugsh (ifq) gfg

3. r'W Service Duse 094509 6. National Board No, for Unit H/A

E.t. Hatch Unit 2 IVVI Components ASME Exam Figure Exam / Cal Section XI No. Examination / Area Examination Procedure Cal Block Sheet No. Results Remarks

-- 2-BA-1 0-4E VT-H-750/06 S95H2V100 NI NUREG-0613 FEEDWATER NOZZLE INNER RADIUS @ 315 DEG (2N4D)

B'122 2-BN-14-4 P-4 46-35 VT-H-750/06 S95H2V100 NI B-N-2 ASME FUEL SUPPORT CASTINGS B13 22 2-BN-14-4 P4 49-16 VT-H-750/06 S95H2V100 N1 B-N-2 ASME FUEL SUPPORT CASTINGS B13.22 2-BN-14-4 P-415-04 VT-H-750,96 S95H2V100 NI B-N-2 ASME FUEL SUPPORT CASTINGS l

B13 22 2-BN-144 P-4 07-46 VT-H-750/06 S95H2V100 NI B-N-2 ASME FUEL SUPPORT CASTINGS B13 22 2-BN-14-4 P-4 07-08 VT-H-750/06 S95H2V100 NI B-N-2 ASME FUEL SUPPORT CASTINGS

1. Owner- Osamia Fount Camaanv. 333 Ph asNE F. O. Bom 4545. Aslaman.Gammen 30302

2. Flama: FAurki Yhtda Niaclear Flasm Rama 1 Dat 278, Badsv GA 31113.

Page:d2 3. Fi-a u.k 2 4. o arc unen.or4.anoruma ore

s. c---e. sw om. 09msen 6. NM Dowd Na Er Unk M

E.L Hatch Unit 2 IVVI Components ASME Exam Figure Exam / Cal Section XI No. Examination / Area Examination Procedure Cat Block Sheet No. Results Remarks B13 22 2-8N-14-4 P-4 03-38 VT&750/06 S95H2V100 NI B-N-2 ASME FUEL SUPPORT CASTINGS B13 22 2-BN-14-4 P-4 03-16 VT-H-750/06 S95H2V100 NI B&2 ASME FUEL SUPPORT CASTINGS B13.22 2-BN-14-4 P-4 37-04 VT&750/06 S95H2V100 NI B-N-2 ASME FUEL SUPPORT CASTINGS B13.22 2-BN-144 P-4 37-50 VT&750/06 S95H2V100 NI B-N-2 ASME FUEL SUPPORT CASTINGS B13.22 2-BN-14-4 P-4 50-19 VT&750/06 S95H2V100 NI B-N-2 ASME FUEL SUPPORT CASTINGS B13.22 2-BN-14-4 P-4 45-46 VT&750/06 S95H2V100 N1 8-N-2 ASME FUEL SUPPORT CASTINGS

1. Owmar- e----- NJe ~ .333 7 " ^ Ave. NE P. O. Bar 4541_^ " e Li ;;

Page: 83 2. num: uni- U- r m me i. Bon m - . or 3nr2.

3. Mus this 2 4. Owmar caredman of Ausherumman (if g) h S. rW Service Dese 094309 6. Nh Board No. Er Unit M

E.L Hatch Unit 2 IVVI Components ASME Exam Figure Exam / Cal Sm XI No. Examination / Area Examination Procedure Cal Block Sheet No. Results Remarks B1312 2-BN-14-4 P-4 50-35 VT&750/06 S95H2V100 NI B-N-2 ASME FUEL SUPPORT CASTINGS B13.22 2-BN-14-4 P-4 49-38 VT-H-750/06 S95H2V100 N1 B-N-2 ASME FUEL SUPPORT CASTINGS B13.22 2-BN-14-4 P-4 38-07 VT-H-750/06 S95H2V100 N1 B-N-2 ASME FUEL SUPPORT CASTINGS B13.22 2-BN-14-4 P-4 38-47 VT-H-750/06 S95H2V100 NI B-N-2 ASME FUEL SUPPORT CASTINGS B13.22 2-BN-14-4 P-4 46-15 VT&750/06 S95H2V100 N1 B-N-2 ASME FUEL SUPPORT CASTINGS 813.22 2-BN-14-4 P-4 46-19 VT-H-750/06 S95H2V100 NI B-N-2 ASME FUEL SUPPORT CASTINGS

1. Owner- C- 7 PM. 333 W Ave NE. P. O. Box 4545. ." e 3030: '

2. Plass: Edwin L Hatch Nuclear Flest Rouse 1. Bos 27L Basisy.OA 31513.

Page: 84 3. FlessUnit2 4. Owner Certificase of Authorushea {if reg) H/A

3. rW Service Dese 094309 6. Nasimal Board Na for Unit b2A

E.l. Hatch Unit 2 4

IWI Components Exam / Cal ASME Exam Figure Remarks No Examination Procedure Cal Block Sheet No. Results Section XI ExaminationIArea __.

VF-H-750/06 S95H2V100 NI B13 22 2-BN-14-4 P-415-50 B-N.2 '

ASME FUEL SUPPORT CASTINGS VT-H-750/06 S95H2V100 NI B13.22 2-BN-14-4 P-4 46-39 B-N-2 ASME FLIEL SUPPORT CASTINGS VT-H-750/06 S95H2V100 NI B13.22 2-BN-14-4 P-4 50-23 B-N-2 ASME FUEL SUPPORT CASTINGS VT-H-750/06 S95H2V100 NI B13.22 2-BN-14-4 P-4 50-27 B-N-2 ASME FUEL SUPPORT CASTINGS VT-H-750/06 S95H2V100 NI B13 22 2-BN-14-4 P-4 45-08

[

B-N-2 ASME FUEL SUPPORT CASTINGS Pw. 333 7 - Awt NE P. O. Box 4545. _^ c-- 30E

1. Oumar fr --. 7 Page: 85 2. Pi m: m r. : m = -- i. n- un. -% GA M 513.

3. Piss Unit 2 4. Owear Castdicene of Authanansson (if%)h S. Commmerusal Servios Dune 0945/79 6. NM Boent No. forUnit B

r ]

f I

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1. Owner: C--a P C- .333 P' " - Ave.. NE. P. O. bx 4545. M'--- C s 30302

3. Plag: Edmn 1. lista Nuclear Plant Route 1. Ilox 278. hxlev. GA 31513.

3. Plant Unit 2. 4. Owner Certifwade of Authomation (ifseq.)M

5. CommercialService Date 09W79 6. National Board No. for Unit El%

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SUMMARY

OF CLASS 1 AND 2 1

l REPAIRS AND REPLACEMENTS

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1. Owner: Geornia Power Cornonnv. 333 Pmhnont Ave.. NE. P. O Box 4343. Aff as= Georain 30302

2. Plant: Edwin 1. llatch Nuclear Plant Route 1. Box 278. Baxlev. O A 31 $ 13.

I 3. Plant Unit 2 4. Owner Cerufsate of Authonzauon Ofreg) E i 5. Commercial Servia Date 92.91.2 2 6. National Board No. for Unit E!%

REPAIRS AND REPLACEMENTS i

GPC procedure 42EN-ENG-014-0S 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 listing of Class 1 and 2 repair / replacement activities for each cycle. The following tables provide an itemized list of those components which were included in the ASME Section XI Repair and Replacement Program. Copies of the individual Repair / Replacement evaluation sheets are filed with the MWO Packages and are available for review at the site.

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1. Owner: Georgia Power Caapeny,333 Ph Ave., NE, P.O. Box 4545, Aslames, Ga 30302 2. Plant: Edwin i Heksi Ninclear Plans, Rie. I Box 27s, Bexley, Gs 31513

3. Plana Urut 2 4. Owner Certi6 case of Ausimuusanom(ufreg) N/A 3. Canumercial Service Date 09/05n9 6. Nanianal Board Na ror Unia N/A ATTACHMENT TO THE OWNER'S DATA REPORT REFAIR AND REPLACEMENT

SUMMARY

El UNIT 2 FALL 1995 MPL Section XI DC Number Class Description Evaluation M W O/DC R Number Pressure Test 2Bil Ill Install shroud support system The core shroud stabilizer design has 2-95-02853/94-052- N/A VT-1, VT-3 consisting of 4 tic rod assemblies and been submitted to the NRC per letter wedges to ensure shroud structural dated 7-3-95. The design will ensure integrity if welds H1 through H8 fail. shroud integrity upon weld failure.

Welds HI through H8 are subject to Note. in NRC letter dated 9-25-95, cracking due to IGSCC. NRC approved this repair.

2B21-F010B 1/1 Install new disc to facilitate proper Exact iMat disc will be used , 2-95-03015 9503996 VT-1, VT-3, allignmentofhingepins. Also failure is attnbuted to semce system Operating Pressure change pressure seal (bonnet) from wear. The new i-r'= - --- --t seal is an (N-416-1) old metal style to new grafoil style. equivalent i@= --+ ^ and the new .

cover to be installed is also. This is an upgrade ofparts forimproved sema.

2B21-F010B 1/1 Replace valve components including The- , - - = used for the 2-95-03257 95-04419 VF-1, VT-3, hinge pins, disc, pressure seals, replanent of the disc, hinge pins, Operating Pressure spring gudes, and bushing bearing pressure seals, spring guides, and Test, N-416-1 inserts. bushing bearing inserts are exact replacement parts from an apprmed vendor.This failure is attnbuted to normal system wear. This is a LLRT valve thus it is evaluated for wear on an established cycle designed to predict urnamepenhle result prior to valve failure. Therefore this is a suitable repair.

2B21-F013H 1/1 Remove valve and send to Wyle Labs Valve is to be repaired under 2-95-00177 2-94-02476 VT-3, VF-1, for testing and repair as neassary appreoved maintenance program at Operating Pressure Wyle Labs. The removal, testing and Test repair of this valve is a standard

,,.,~e; measure, and is an

= --j- -i method for ensuring proper valve operation.

2B2I-MSRV-R62 1/1 Remove snubber R62 and reinform This work is being performed under an 2-95-00141/94-016 N/A None wide beam. approved DCR. No failure has occurred. This is being done as part of 88

1. Owner- Ocorgia Power Cornpany. 333 Piedmore Ave., NE, P.O. Box 4545, Atlanta, Ga 30302 2. Plant; Edwin IIlatch Nuclear Plant, Rie I Box 278 Baxicy,Ga 31513

3. Plant t.1mt 2 4. Owner Certifu:ste of Authorustion (if req.) N/A 5 Commercial Service Date 09/05n9 6. National Board No. for Unit N/A ATTACHMENT TO THE OWNER'S DATA REPORT REPAIR AND REPLACEMENT

SUMMARY

UNIT 2 FALL 1995 g

MPL Section XI DC Number Class Description Evaluation MWO/DCR Number Pressure Test the reevaluation of snubbers.

2B31 1/1 lastall 2 new 4 inch decon ports This modification is evaluated and 2-95-1654/2H91-03 N/A Volumetric, approved under the DCR. O Surface, VT, VT-l, VT-3, Operating Pressure Test (N-416-1) 2B31-F052A I/1 Valve had seat and disc damage Replace with like kind valve meeting 2-95-03469 R2 95-04701 Surface, VT, which is attributed to service induced specifications of orginal valve. Operating Pressure wear. Test, N-416-1 2C41-F029A/B 2/2 Replace flanged relief vahts as This replacement is being performed 2-94-00633/93-5041 N/A Surface, Visual, specified by MDC 93-5041. under an approved MDC for Hydrostatic Pressure improvement of system reliability. Test.

Suitability evaluation is covered by MDC 93-5041. No service induced failure involved. Valves are being replaced due to poor reliability, maintenance history and availability of replacement parts and 53 hts of existing relief valves.

2C51 1/1 Install new ECP/LPRM in the vessel No failure occurred. The LPRM 2-95-02111/93-059 N/A Operating Pressure to monitor the effectiveness of the assembly is fabricated in accordris.cc Test Hydrogen injection System for with class I material.

protecting the core of the reactor vessel. Assemblyisflangedtothe bottom of vessel.

2El1 2/2 Cut and cap piping to remove RHR Due to valve leakage RHR steam 2-95-02301/2H94-0 N/A VT, Volumetric, steam condensing mode. This is a condensing mode will be removed. All 32 Surface, Operating eight inch valve. aspects of this work has been evaluated Pressure Test, and approved by DCR 2H944)32. N-416-1 2El1 2/2 Cut and cap piping to remove RHR Due to vaht leakage RHR steam 2-95-02300/2H94-0 N/A VT, Volumetric, steam condensing mode. condendng mode will be removed. All 32 Surface, Operating aspects of this work has been evaluated Pressure Test, and approved by DCR 2H94-032. N-416-1 M

h I. Owner. Georgia Power Company,333 Picenora Ave NE.RO Dox 4545, Atlanta, Ga 30302 2. Ptars: 1%mn I Ilatch Nuclear Ptara, Rae. I Dos 278. Baxley,Ga 315I3

3. Plans Urut 2 4 Owner Certificane of Authoruption (dreg) N/A 5. Commercial Sernce Date 09/05/79 6. National Board No. for Unit N/A ATTACHMENT TO THE OWNER'S DATA REPORT REPAIR AND REPLACEMENT

SUMMARY

g UNIT 2 FALL 1995 MPL Section XI DC 1

Number Class Description Evaluation MWO/DCR Numeber Pressure Test 2El1-C001B 2/2 Replace pump assembly with rebuilt Work is being performed under a 60 2-93-03154 2-94 41605 System Operability ,

assembly from warehouse. This month PM program Noinsenice Surveillance assembly includes bolting. failure involved. R/R evaluation written to document new pump assembly installation.

2ElI-F005B 3/3 Replace valve disc and hanger The disc is being replaced in order to 2-95-00312 N/A Operating Pressure install an anti-rotation spud on the Test disc. 'Ihe hanger is being replaced as ,

a preventative measure. To be replaced with like kind components.

No failures have occurred.

2El1-F007B 2/2 Replace valve per DCR 2H95-056 Due to excessive wear on the 2-9543163/2H95-0 N/A Volumetric, VT, 2El 1-F007B valve internals, the valve 56 Operating Pressure will be replaced with a new anchor (N416-1) darling valve. This is a 4 inch valve.

2EIl-F015B 1/1 Drill hole in the upstream side of the NRC Generic Ixtter 89-10 2-95-02849/2H94-0 N/A VT-3, VT-1, flex wedge disc of 2El1-F005A to recommends that safety related motor 34 Operating Pressure climinate potential valve pressure operated valves be able to function Test, N-416-1 locking. cither opening or closing when subjected to the maximum differential pressure across the valve during normal operation and abnormal events within the design basis of the plant.

The modification to the valve will meet the requirements of Genenc letter 89-10 and will preside increased margin to operate during a design basis event. This modification willincrease MOV capability and improve system reliability by precluding the possibility ofvalve pressure locking. A failure has not occurred, thus a failure evaluation is not required.

90

1. Owner: Georgia Power Company. 333 Picenors Ave, NE, P.O. Box 4545, Atlanta, Ga 3o302 2. Plant: Edvnn I flatch Nuclear Plans, Rie. I Box 278, Baxley,Ga 31513

3. Plant Unit 2 4. Owner Certificate of Authorization (if req ) N/A 5. Commercial Service Date 09/05n9 6. National Board Na for Unit N/A ATTACHMENT TO THE OWNER'S DATA REPORT REPAIR AND REPLACEMENT

SUMMARY

g UNIT 2 FALL 1995 MPL Section XI DC Number Class Description Evaluation MWO/DCR Number Pitssuit Test i'

2El1-F018C 2/2 Replace and relocate vahr Replace valve with a like kind. Failure 2-95-01390 95-4091 Volumetric, cause is attributed to service in a harsh R3/95-5040 Surface, Operating environment. Vahe was originally Pressure Test installed close to an cibow which (N-416-1) ,

resulted in turbulent flow. This MDC relocates the valve to a more favorable location.

2El1-F028A 2/2 Replace stem, disc, disc guides, and NRC Generic Letter 89-10 2-95-01972/2H94-0 N/A Operating Pressure yoke on valve 2El1-F028A. recommends that safety related motor 34 Test operated valves (MOV)be able to function either opening or closing when subjected to the maximum differential pressure across the uhr during normal operation and abnormal events within the design basis of the plant.' 'Ihe modification to the valve will meet the requirements of Generic letter 89-10 and will provide ,

increased margin to operate during a design basis event. The new components will meet the design, material, and constmetion standards applicable to the RHR system. This modification willincrease MOV ,

capability and imprme system reliability.

2El1-F023B 2/2 Replace stem, disc, disc guides, and NRC Generic Letter 89-10 2-95-01971/2H94-0 N/A Operating Pressure l yoke on vahr 2 Ell-F028B. recommends that safety related motor 34 Test operated valves (MOV) be able to

• function either opening or closing when subrected to the maximum differential pressure across the valve during normal operation and abnorn l events within the design basis of the plant The moddication to the vahr 91

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1. Owner: Georgia Power Company,333 Piedrnant Ave., NE, P.O. Box 4545, Atlanta, Ga 30302 2. Ptars: EdwuiI Hatch Nuclear Plant, Rie. I Box 27s, Baxley, Ga 31513

3. Plans Unn 2 4. Owner Certificate of A ; 4.(if reg) N/A 5. Corroneraal service Date 09/05n9 6. National Board No. for (Jnit N/A ATTACHMENT TO THE OWNER'S DATA REPORT REPAIR AND REPLACEMENT

SUMMARY

g UNIT 2 FALL 1995 MPL Section XI DC Number Class Description Evaluation MWO/DCR Namiber Pressure Test will meet the requirements of Generic Letter 89-10 and will provide increased margin to operate during a design basis event. The new l components will meet the design, material, and construction standards applicable to the RHR system. *lhis modification will increase MOV capability and imprme system reliability. ,

2El1-F029 2/2 Nozzle of relief valve is being Machine cut is estimated to require 2-94-03597 95-04101 Operating Pressure ,

machine cut. Replace disc. removal of no more that 0.005", Test, Seat Leakage  ;

therefore no weld buildup is required. Test Machine cut of this nozzle is to remove a small defect and is an acceptable method of repair. Due to defect in the disc it will be replaced  ;

with an exact replacement. The seat .

leakage was found during seat leakage test, this test was repeated after repair ofvalve to verify defect remm21.

1 2El1-F030D 2/2 Machine nozzle of nhe and replace Repair is to remove scratches on disc 2-944)3601 R1 9504187 Surface, VT,  !

disc which were a result ofleakage. Found Operating Pressure during 42SV-SUV-004-0S. During Test (N-416-1) repair welding of a new nipple for ,

valve reststallation was neaary i 2El1-F045 2/2 Grind out flaw and blend in with Per evaluation by Structural Integrity 2-95-02863 9503563 MT .

vahe body. Do not exceed 1/4" Associates Inc. this is not a seniced depth without further evaluation. induced flaw. Flaw enluation determined this to be orginal construction flaw. This evaluation is to document that metal removal at these ,

locations, no greater than 1/4" depth is acceptable. MT must be performed 92

1. Owner Georgia Power Company,333 Piedmora An. NE, P.O. Box 4545, Atlanta, Ga 30302 2. Plant- Edwm I listch Nuclear Ptars, Rie. I Dox 278, Baxley,Ga 31513

3. Plant Urut 2 4. Owner Catificate of Authoruatum (if reg.) N/A 5. Comrnercial service Date 09/05/79 6. National Daard No. for Unit N/A ATTACHMENT TO THE OWNER'S DATA REPORT REPAIR AND REPLACEMENT

SUMMARY

g UNIT 2 FALL 1995 MPL Section XI DC Number Class Description Evaluation MWO/DCR Number Pressure Test after metal removal to document flaw removal. No pressure testing required.

2El1-F046B 2/2 Replace hinge pin, Bonnet studs. The above replawment parts are exact 2-92-03614 R1 2-92-03505 Operating Pressure pipe caps, and polish seat. equivalent components. The valve was Test operational and functional, however replacements parts will enhance continued performance of the valve.

2El1-F111 2/2 Vahe disc is worn, needs to be This valve disc is attributed to normal 2-95-02990 R2 9503938 Operating pressure replaced. system wear. He disc is to be test replaced using like kind disc. This will not be a life of plant repair. This is a LLRT valve this it is evaluated for wear on an established cycle designed to predict ungable results prior to ,

valve failure. Therefore this is a suitable repair. His is a 2 inch vahe.

2El1-F123 A 2/2 Replace valve per weld iso. Valve As stated in description failure is due 2-95-01427 R3 9503 % 3 Surface, Operating bonnet was replaced with Class 3 to craft. Valve is to be replaced with a Pressure (Code Case Bonnet and error was caught prior to Class 2 valve per approved utiding N-416-1) returning valve to service Craft procedure.

damaged valve while correcting this error, thus the need for the replacing of entire valve.

2EIl-F3078A 2/2 Remove blank flange and replace His blank flange is being installed 2-94-02569/94-5035 N/A Visual. Operating with blank flange specified in MDC under MDC 94-5035 and it's Pressure Test.

94-5035. Note: reliefvalve removed suitability was evaluated by that MDC.

last outage under a TMM and a blank flange installed.

2El1-F3078B 2/2 Remove blank flange and repla his blank flange is being installed 2-94-2570/94-5035 N/A Visual, Operating with specified blank flange in MDC under MDC 94-5035 and it's Pressure Test.

94-5035. Note: Reliefvalve was suitability was evaluated by that MDC.

removed last outage under a TMM.

2El1-RilR-224 2/2 Replace snubber with Lisega strut. This replacement replaces a snubber 2-95-2212/94-5071 N/A VT-3 93

I. Owner: Georgia Power Company. 333 Picenorn Ave NE. P.O. Box 4545, Atlanta, Ga 30302 1 Ptars: Edwm I Hatch Nuclear Plant. Rte. I Box 278, Bar!cy. Ga 31513

3. Plant Umt 2 4. Owner Certificate of Authoruation (ifreg) N/A 5. Commercial Service Date 09'0509 6. National Doord Na for Unit N/A ATTACHMENT TO THE OWNER'S DATA REPORT REPAIR AND REPLACEMENT

SUMMARY

g UNIT 2 FALL 1995 MPL Section XI DC Number Class Description Evaluation MWO/DCR Number Pnssurt Test No inservice failure has occurred. with a Lisega strut. It is part of the snubber reduction program. Reference MDC 94-5071 for evaluation.

2El1-RHR-H700 2/2 Modify existing snubber in order to meet the requirements of 2-95-l%2/2H94-03 N/A VT-3 Generic Letter 89-10, DCR 94-034 4 replaces the yoke with one with shorter dimensions. Since the new yoic has shorter dimensions, the snubber will be lowered according to the new height.

The new components and modification to the snubber will meet the design, material, and construction standards applicable to the RHR system. No failure has occured at this time.

2El1-RHR-il707 2/2 Modify existing snubber. In order to meet the requirements of 2-95-01%3/2H94-0 N/A VT-3 Generic Letter 89-10, DCR 94-034 34 replaces the yoke with one with shorter dimensions. Since the new 3cke has shorter dimensions, snubber 1El1-RHR-H707 will be lowered according to the new height. The new components and modification to the snubber will meet the design, material and construction standards applicable to the RHR system.

2El1-RHR-H714A/ 2/2 Remove existing PSA-100 snubber This work is being performed under an 2-954)0515/94-5071 N/A VT-3 2El1-RHR-H714 and replace with apprmtd MDC. Suitabilityis rigid strut. addressed via the MDC 94-5071. No service induced failure is imohtd.

This is a snubber reduction program activity.

2El1-RilR-il7ISA/ 2/2 Remove existing PSA-100 snubber This work is being performed under an 2-95-00513/94-5071 N/A VT-3 and replace with rigid strut. apprmed MDC. Suitability is addressed via the MDC 94-5071. No 94

l. Owner: Georgia Power Company 333 Pacenora Ave. NE, P.O. Box 4545, Antarna, Ga 30302 2.Ptart. Edwin i Hasda Nudear Plan, Rie. I Dux 278. Baxley, Ga 315 I3

3. Ptera Uret 2 4. Owner Certafscane of.' (if reg) N/A 5. Comineraal Service Date 09/0509 6. National Board Na for Unit N/A ATTACHM ENT TO THE OWNER'S DATA REPORT REPAIR AND REPLACEMENT

SUMMARY

UNIT 2 FALL 1995 El MPL Section XI DC Number Class Description Evaluation MWO/DCR Number Pressure Test senice induced failure invohtd.

2ElI-RHR-R228 2/2 Replace snubber with Lisega strut. This replacement is being done as part 2-95-02211/94-5071 N/A VT-3 This is part of the snubber of the snubber reduction program. No replacement program. No actual failure has occurred at this time.

failure has occurred at this time on Reference MDC 94-5071 for the snubber. evaluation of replacement.

2El1-RHR-R82 2/2 Torque wedge anchor bolts an base Torque of anchors is normal 2-94-01261 R2 2-94 01163 VT-3 plate of support. maintenance actisity. Note: This work was in conjunction with hanger replacement work presiously documented) 2El 1-RHR-R82 B31.1/ Replace strut hanger assembly due to Replacement of hangers are normal 2-94-01261 R2 2-94-01148 VT-3 2 spherical bearing failure. maintenance actisities. Cause of failure is not known.

2E21-CS-R82B 2/2 Snubber had high drag during testing The snubber willbe replaced with an 2-95-2570 N/A VT-3 due to normal wear. This snubber identical unit, replacement is per will be replaced. approved plant procedures.

2E21-F005A Ill Drill hole in the upstream side of the NRC Generic Ixtrer 89-10 2-95-02845/2H94-0 N/A VT-3, VT-1, flex wedge disc of 2 Ell-FD05A to recommends that safety related motor 34 Operating Pressure climinate potential valve pressure operated valves be abic to function Test locking. either opening orclosing when subjected to the maximum differential pressure across the valve during normal operation and abnormal events within the design basis of the plant.

The moddication to the valve will meet the requirements of Generic letter 89-10 and will provide increased margin to operate during a design basis event. This modification willincrease MOV capability and improve system reliability by precluding the possibility of vahe 95

l. Owner Georgia Power Company,333 Piedmont Ave NE, P.O. Box 4543, Atlarsa, Ga 30302 2. Ptar:t: Edwin I flatch Nuclear Plant. Rte. I Box 278, Baxley,Ga 31513

3. Plant Umt 2 4. Owner Certaficate of Authoruation (if req ) N/A 5. Commercial service Date 09S509 6. National Board No. for t.fmt N/A ATTACHMENT TO THE OWNER'S DATA REPORT REPAIR AND REPLACEMENT

SUMMARY

g UNIT 2 FALL 1995 MPL Section XI DC Number Class Description Evaluation MWO/DCR Number Pressure Test pressure locking. A failure has not ,

occurred, thus a failure evaluation is not required.

2E21.F005B 1/1 Drill hole in the upstream side of the NRC Generic Letter 89-10 2-95-02846/2H94-0 N/A VT-3, VT-1, flex wedge disc of 2E21-F005B to recommends that safety related motor 34 Operating Pressure eliminate vaht pressure locking. operated vahes (MOV) be able to Test function either opening or closing when subjected to the maximum differential pressure across the vahe during normal operation and abnormal ennts within the design basis of the plant. The modification to the valve will meet the requirements of Generic Letter 89-10 and will provide increased margin to operate during a design basis event. The new components will meet the design, material, and construction standards applicable to the RHR system. This modification willincrease MOV capability and improve system reliability.

2E21-F012A 2/2 Vaht to be replaced. Valve is bolted This vaht is an identical repia ment. 2-94-3611 2-95-2491 Operating Pressure in. The original valve could not have its Test set pressure adjusted.

2E21-F012B 2/2 Replace Valve Existing valve failed leakage test. 2-93-02393 R1 2-94-00825 Surface Hydrostatic Replacement valve is identical to Pressure Test original valve. Cause of failure does not appear to be service induced, but rather vahe being degraded over time due to maintenance activities.

Specifically in the seat area. Valve replacement will be in iso.-d a with applicable code and plant approved 96

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I. Owner: Georgia Power Cangany,333 Piedmass Ave NE, P O. Box 4545. Atlesma, Ga 3o3o2 2. Ptera: Edwm I flardi Nuclear Plana,Ibe. I Box 27s, Baxley,Ga 31513

3. Plasa Unsa 2 ( Owner Ccmficane of." " :-- ----(if req ) N/A 3. 8' J service Dane 09/0509 6. National Board No. for Usut N/A ATTACHMENT TO THE OWNER'S DATA REPORT REPAIR AND REPLACEMENT

SUMMARY

ASMU UNIT 2 FALL 1995 MPL Section XI DC~

Number Class Description Evaluation MWO/DCR Number Pressure Test imxalures.

2E2I-F015A I/I Drill hole in the upstream side of the . NRC Genenc Letter 89-10 2-95-02847/2H94-0 N/A VT-1, VT-3, flex wedge disc of 2E21-F015A to recommends that safety related motor 34 Operating Pressure climinate valve pressure locking. operated valves (MOV)be able to Test i ' Also replace bolts for bonnet. function either opening or closing when subpected to the maximum ddferential pressure across the valve during normal operanon and abnormal events within the design basis of the plant. 'Ihe modification to the valve will meet the requirements of Generic Letter 89-10 and will provide increase *I margin to operate during a design basis event. The new

,- -_ will meet the design,

, material, and constructum standards applicable to the RHR system. This modification willincrease MOV capability and improve system reliability. In addition bonnet bolts were found to be galled and corroded.

Reason for this could not be determined.

2E21-F019A 2/2 Replace disc and o-ring gland. Disc and o-ring gland will be replaced 2-94 4 1108 2-94 4 0772 Operating Pressure with exact . ;2 - --- :_ Test 2E21-F036A 2/2 Replace and Relocate check valve. Check valve was originally installed 2-94-02522 2-94-00797 Surface, with the discharge of the valve butted Rl/95-5038 Vohunetnc, up to an ebow which r=ee= the valve Operating Pressure to wear due to turbulent flow Test (N-416-1) conditions.

2E21-F036A 2/2 Replace all valve internals including Internals are being replaced due to 2 93-4176 RI 2-94-00797 Operating Pressure the disc. wear. Wearisofnormaloperating Test nature.

97

I. Owner. Georgia Power Company,333 Pie & noes Ave, NE, P.O. Dox 4543 Atlanta,Ga 30302 2. Plant Edwin iIlasch Nuclear Plant, Rte. I Dox 278. Baaley. Ga 3I513

3. Plant tJnet 2 4 Ownee Certakste of."d_4.(dreq ) N/A 5. Cemen::al Service Date o$o3/79 6. Nat anal Board No. for Unit N/A ATTACHMENT TO THE OWNER'S DATA REPORT REPAIR AND REPLACEMENT

SUMMARY

g UNIT 2 FALL 1995 MPL Section XI DC Number Class Description Evaluation MWO/DCR Number Pressure Test 2E32 1&2/I Remove piping and supports Piping is being removed as specified 2-94-00661/88-106 N/A Suface, Hydrostatic

&2 associated with MStV LCS in the by DCR. Suitability evaluation will be Pressure Test Steam Chase as specified by DCR performed during approval of DCR 88-106.88-106. No senice induced failure involved. MSIVleakagecontrol system removal is to eliminate a design inconsistency.

2E41 2/2 Replace restricting orifices D001 and Evaluation for suitability has been 2-94-699/2H93-036 N/A Surface, Operating D002 and associated piping. evaluated during the DCR process No Pressure Test.

insenice failure invohtd.

Pqh =- =t is for pressure reduction past isolation valve.

2E41 2/2 Replace and fabricate a new HPCI This replacement is being performed 2-94-700/2H93-036 N/A Surface, Visual, turbine exhaust drain pot stilling under an approved DCR for Hydrostatic Pressure well, as specified by DCR 93-036. improvement of system operation. Test.

Suitability evaluation is cowred by DCR 93-036. No senice induced failure involved.

2E41-F001 2/2 Replace valve disc due to normal The sept. uwnt discis being supplied 2-95-00130 2-94-02299 Operating Pressure wear. Also replace stem, studs / nuts, by the manufacturer with a stellite 6 Test inner bonnet stem outer bonnet facing. This is expected to improve

( pressure seal. the reliability of the valve. The studs and nuts are being replaced as a good practi , they have not failed.

l 2E41-F006 2/2 Relocate 2E41-F006 valve upstream This work is being pe formed by DCR 2-9344997/2H92-1 N/A VF, RT, UT, ofexistinglocation. Replaceold 92-164. Material suitability has been 64 Surface, and vahe location with pipe spool. evaluated by the DCR. Hydrostatic Pressure l Test.

2E41-f006 2/2 Drill hole in the upstream side of the NRC Generic Letter 89-10 2-95-02844/2H94-0 N/A Operating Pressure flex wedge disc of 2E41-F006 to i"- =- -- h that safety related motor 34 Test climinate potential valve pressure operated valves (MOV) be able to locking. function either opening or closing when subjected to the maximum 98

1. Owner- Georgia Power Company,333 Piedrnons Ave NE, P.O. Dox 4545, Atlarna,Ga 30302 2. Plant: Edwin i Hatch Nuclear Plant, Rie. I Box 278, Baxley Ga 31513 3 Plant Urut 2 4. Owner Certificate of Authoruation (if req ) N/A 5. Conunercial Service Date 09/05/79 6. National Daard No. fa Uret N/A ATTACHMENT TO THE OWNER'S DATA REPORT REPAIR AND REPLACEMENT

SUMMARY

UNIT 2 FALL 1995 g

MPL Section XI DC Number Class Description Evaluation MWO/DCR Numtwr . Pressure Test differential pressure across the valve during normal operation and abnormal events within the design basis of the plant. The modification to the valve will meet the requirements of Generic letter 89-10 and will prmide increased margin to operate during a design basis event. *ntis modification willincrease MOV capability and improve system reliability by precluding the possibility ofvalve pressure locking. A failure has not occured.

2E41-HPCI-H99 2/2 Relocate strut support and replace This work is being performed by DCR 2-93-04997/9H92-1 N/A VF-3 strut per DCR 2H92-194 92-164. Material suitability has been 64 evaluated by the DCR.

2E51-F013 2/2 Drill hole in the upstream side of the NRC Generic letter 89-10 2-95-02843/2H94-0 N/A VT-3, VF-1, flex wedge disc of 2El1-F005A to recommends that safety related motor 34 Operating Pressure eliminate potential valve pressure operated valves be able to function Test, N-416-1 naking. cither opening or closing when subjected to the maximum differential pressure across the valve during normal operation and abnormal events within the design basis of the plant.

The modification to the valve will meet the requirements of Genenc letter 89-10 and will provide increased margin to operate during a design basis event. This modification willincrease MOV capability and improve system reliability by precluding the possiblity ofvalve pressure locking. A failure has not occurred, thus a failure evaluation is not required.

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+

1. Owner. Georgia Power Company.333 Piedmons Ave, NE P.O. Box 4545, Atlassa, Ge 30302 2. Plant EdwuiI liasch Nuclear Plant, Rie. I Box 278, Baxley, Ga 3I513

3. Plans thut 2 4. Owner Certif'scate of Authoruarma 6f reg) N/A 5. Comniercial service Dese 09A)3/79 6. Nahonal Board No. for Unit N/A ATTACHMENT TO THE OWNER'S DATA REPORT ,

REPAIR AND REPLACEMENT

SUMMARY

UNIT 2 FALL 1995 g

MPL Section XI DC Neunber Class Description Evaluation MWO/DCR Nussber Pressure Test 2E51-F021 2/2 valve plug is worn and flats rounded This failure is attributed to system 2-95-00370 N/A Surface, VT, wear. The plug will be replaced with Operating Pressure like kind parts. Test 4

2E51-F045 2/2 Replace the existing Rockwellvalve NRC Generic Letter 89-10 2-95-2067/2H94-03 N/A RT, VT-3, FT, witha Anchor /Darlingspecia sw ==-:--is that safety related MOVs 4 Operating Pressure contour plug valve per DCR 94-034. be able to function either opening or Test (N-416-1) closing when subrected to the maximum differential pressure across i the valve during normal operation and abnormal events within the design basis of the plant. The modification to the valve will meet the requirements of GL 89-10 and will provide increased margin to operate during a design i basis event. The new components will meet the design, matenal and construction standards applicable to the RCIC system. This modification willincrease MOV capability and improve system reliability.

2G11-F004 2/2 Replace valve. This valve wear is The iu -- =- :: of this valve will be 2-95-03085 R1 95-04130 Volumetnc, attributed to normal system wear. with a like kind valve. Surface, VT, Operating Pressure Test, N-416-1 2G31 1/1 Prefab bottom head drain assembly No failure has occuned. Piping 2-95 42595 N/A Surface, Volumtric, for incore monitoring maternal being installed is per pipe Operating Pressure class DCA and willbe welded and (Code Case inspected per 42EN-EME-012-OS. N-416-1), VT 2G31 1/1 Install new bottom head drain line No failure occurred. The piping 2-95-02122/93-059 N/A VT,$urface, assembly line assembly to monitor material being installed is per pipe Operating Pressure the effectiveness of the Hydrogen class DCA and will be welded and Test (N-416-1)

Injection System for protecting the inspected per 42EN-EME-012-05.

bottom region of the reactor vessel.

This assembly is 2 inch and under.

100

1. Oumer: Georgia Power Company,333 Piedmont Ave. NE, P.O. Box 4545, Atlanta, Ga 303o2 2. Plant: Edwin I IIakh Nuclear Plata, Rie. I Dox 278, Baxley, Ga 31313

3. Plant Urut 2 4. Ovmer Certd'wate of Authoruation (irreg) N/A S. Commercial Service Date 09/0509 6. National Board No. fa tJnit N/A NITACHMENT TO THE OWNER'S DATA REPORT REPAIR AND REPLACEMENT

SUMMARY

UNIT 2 FALL 1995 MPL Section XI DC Number Class Description Evaluation MWO/DCR Number Pressuit Test 2N11-F003 2/2 Per MWO valve had a bad packing Replacement parts are identical parts 2-93-02169 RI 2-93-01753 Operating Pressure leak, upon imestigation bonnet obtained from the warehouse. All Test stuffing box was severely pitted due work is done per approved plant to normalinservice wear. procedures.

2P11-A001 2/2 Replace bolting in flanges on piping Bolting being used is an approved 2-93-4766 N/A Visualleakage .

specified on MWO. replacement for bolts being removed. check Cause of failure appears to be corrosion and possible stress.

2P42-F083 B31.1/ Replace relief valve 2P42-F083. It was determined by procurement 2-93-03018 N/A Operating Pressure 2 Vahe failed leakage and set pressure review services (PRS) that existing Test.

test. Valve is bolted in. relief valve 2P42-F083 was a Non-ASME code vahe. IST inspection plan boundary diagram drawings identify the valve as being ASME section XI class 2. Per PRS existing valve is being replaced with an identicalvalve. The new valve was determined to be an acceptable replacement and willbe upgraded by commercial grade dedication plan number CGDP No. 94-0021. Existing vahe was degraded due to maintenance attempting to repair so as to past leakage test. Replacement will be performed in accordance with applicable approved plant picaduis.i 2T52 M C/2 Install new penetration per DCR No failure has occurred. New cables 2-95-01348/2H94-0 N/A Volumetnc,94-013 need to be pulled and there was no 13 Surface, Pnematic more room in existing penetrations. pressure test.

101

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1. Owner: Georma PowerCommenv.333 Pieshnce Ave NF.P.O. Bar 4545. Adanta.Ooornia 30302 .

2. Plant: E4 win I. Hatch Nuclear Ptart Rouis 1. Box 278. BaJdsv.oA 31$13,

3. PlamUnit1 4. Owner casts 6cene of Authorussion (ifreg) h

5. CcamercialServiosDese 0945/79 6. National Board Na for Unit N/A Code Case and Alternative Testing Summary for Hatch Unit 2, Fall 1995 Outage Code Case No. Iltle i

Case N-98 Ultrasonic Examination-Calibration Block Tolerances, Section XI.

Case N-416-1 Alternative Pressure Test Requirement for Welded Repairs or Installation of Replacement Items by Welding, Class 1, 2 and 3, Section XI, Division 1.

Case N-460 Alternative Examiaation Coverage for Class 1 and Class 2 Welds, Section XI, Division 1.

Case N-461 Alternative Rules for Piping Calibration Block Thici: ness, Section XI, Division 1.

Case N-491 Alternative Rules for Ext;nination of Class 1,2,3, and MC Component Supports of Light-Water Cooled Power Plants, Section XI, Division 1.

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