L-09-197, Twelfth Inservice Inspection Summary Report

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Twelfth Inservice Inspection Summary Report
ML092240487
Person / Time
Site: Perry FirstEnergy icon.png
Issue date: 08/05/2009
From: Bezilla M
FirstEnergy Nuclear Operating Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
FOIA/PA-2010-0209, L-09-197 P0059-0012
Download: ML092240487 (331)


Text

{{#Wiki_filter:FENOC PerryNuclear Power Station 10 Center Road FirstEnergyNuclear Operating Company Perry,Ohio 44081 Mark B. Bezilla 440-280-5382 Vice President Fax: 440-280-8029 August 5, 2009 L-09-197 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001

SUBJECT:

Perry Nuclear Power Plant Docket No. 50-440, License No. NPF-58 Perry Nuclear Power Plant Twelfth Inservice Inspection Summary Report In accordance with the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI, "Inservice Inspection," 1989 Edition, Article IWA-6000, the Perry Nuclear Power Plant Twelfth Inservice Inspection Summary Report (Form NIS-1) is enclosed. This report documents the inservice examination activities conducted from return to commercial operations following the eleventh refueling outage until completion of the twelfth refueling outage. There are no regulatory commitments contained in this submittal. If there are any questions, or if additional information is required, please contact Mr. Thomas A. Lentz, Manager- Fleet Licensing, at 330-761-6071. Sincerely, Mark B. Bezilla

Enclosure:

FirstEnergy Nuclear Operating Company Perry Nuclear Power Plant Twelfth Inservice Inspection Summary Report cc: NRC Region III Administrator NRC Resident Inspector NRC Project Manager Authorized Nuclear Inservice Inspector Ohio Department of Commerce, Boiler Inspection Section kX'

FirstEnergy Nuclear Operating Company Perry Nuclear Power Plant Twelfth Inservice Inspection Summary Report

Page 1 of 2 FORM NIS-I OWNERS REPORT FOR INSERVICE INSPECTIONS As required by the provisions of the ASME Code Rules

1. Owner FirstEnergy Nuclear Operating Company, 76 South Main Street, Akron, OH 44308 (Name and Address of Owner)
2. Plant Perry Nuclear Power Plant, 10 Center Road, Perry, OH 44081 (Name and Address of Plant),
3. Plant Unit 1 4. Owner Certificate of Authorization (if required) N/A
5. Commercial Service Date 11/18/87 6. National Board Number for Unit N/A,
7. Components Inspected (only the systems with Class I and 2 components are listed in following table)

Manufacturer Component or Manufacturer or Installer National Appurtenance or Installer Serial No. PNPP MPL No. Board No. Rx Vessel GE/CBIN T-49 1B13 15 Rx Vessel GE/A&ES 1B13 1B13 64077 Nuclear Boiler System GE/A&ES 1B21 1B21 64084 Nuclear Boiler System Pullman Power Products 1B21 IB21 109 Reactor Recirculation System GE/A&ES 1B33 1B33 64076 Reactor Recirculation System Pullman Power Products 1B33 1B33 119 CRD Hydraulic Control System Pullman Power Products ICU1 IC 1 92 Standby Liquid Control System Pullman Power Products 1C41 1C41 108 Containment Atmosphere Monitoring *Johnson Controls 1D23-0064-F . ID23. . 008 Residual Heat Removal System Engineers & Fabricators Company 1E12 1E12 1621 Residual Heat Removal System Pullman Power Products 1E12 1E12 83 Containment Spray System Pullman Power Products 1E15 IE15 105 Low Pressure Core Spray System Pullman Power Products IE21 1E21 85 High Pressure Core Spray System Pullman Power Products 1E22 1E22 86 Leak Detection System Johnson Controls 1E51-0068-F 1E31 15 MSIV Leakage Control System Pullman Power Products 1E32 1E32 104 Reactor Core Isolation Cooling System Pullman Power Products 1E51 IE51 84 Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8Y in. x II in., (2) information in items I through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form. This Form (E00029) may be obtained from the Order Dept., 22 Law Drive, Box 2300, Fairfield, NJ 07007-2300

FORM NIS-I (Back)

8. Examination Dates 5/14/07 to 5/13/09
9. Inspection Period Identification: Third Period
10. Inspection Interval Identification: Second
11. Applicable Edition of Section XI 1989 Addenda None
12. Date/Revision of Inspection Plan: Rev 13, PNPP Inservice Examination Program Plan, dated 1/23/09
13. Abstract of Examinations and tests. Include a list of examinations and tests and a statement concerning status of work required for the Inspection Plan.

See attached summary report P0059-0012*

14. Abstract of Results of Examinations and Tests.

See attached summary report P0059-0012*

15. Abstract of Corrective Measures.

See attached summary report P0059-0012*

  • Report is 198 two-sided pages in length.

We certify that a) the statements made in this report are correct b) the examinations and tests meet the Inspection Plan as required by the ASME Code, Section XI, and c) corrective measures taken conform to the rules of the ASME Code, Section XI. Certificate of Authorization No. (if applicable) N/A Expiration Date N/A Date 7 e4/l,

  • Signed FENOC By 2 bD/tit /:L, ./

Owner CERTIFICATiE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Ohio and employed by Hartford Steam Boiler of Hartford, CT have inspected the components described in this Owner's Report during the period 5/14/07 to 5/13/09 , and state that to the best of my knowledge and belief the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the inspection plan and as required by the ASME Code, Section XI. B5' signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in the Owner's 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. 1- *w'&

  • Commissions NB9330 "N", "I", & "A", Ohio Commission Inspector's SignaturPJ National Board, State, Province, and Endorsements Date1!Ic

Page 2 of 2

1. Owner FirstEnergy Nuclear Operating Company, 76 South Main Street, Akron, OH 44308 (Name and Address of Owner)
2. Plant Perry Nuclear Power Plant, 10 Center Road, Perry, OH 44081 (Name and Address of Plant)
3. Plant Unit 1 4. Owner Certificate of Authorization (if required) N/A
5. Commercial Service Date 11/18/87 6. National Board Number for Unit N/A
7. Components Inspected (only the systems with Class I and 2 components are listed in following table)

Manufacturer Component or Manufacturer or Installer National Appurtenance or Installer Serial No. PNPP MPL No. Board No. Integrated Leak Rate System Pullman Power Products IE61 IE61 120 Fuel Transfer System General Electric 1F42 1F42 64079 Reactor Water Cleanup System GE/A&ES 1G33 1G33 64075 Reactor Water Cleanup System Pullman Power Products IG33 1G33 100 Fuel Pool Cleaning System Pullman Power Products 1G41 IG41 95 Suppression Pool Drain and Cleanup System Pullman Power Products 1G42 1G42 96 Suppression Pool Makeup System Johnson Controls 1G43-0065-F I G43 019 Containment Vessel Purge System Pullman Power Products 1M14 IM14 113 Drywell Vacuum Relief System Pullman Power Products 1M16 IM16 115 Containment Vacuum Relief System Pullman Power Products IM_17 IM_17 87 Combustible Gas Control System Pullman Power Products 1M51 1M51. .......... 106 Main Steam System Pullman Power Products IN11 1N11 111 Main, Reheat, and Miscellaneous Drains Pullman Power Products IN22 IN22 112 Feedwater System Pullman Power Products 1N27 1N27 89 Condenser Transfer and Storage System Pullman Power Products 1PI 1 1PI 1 102 Mixed Bed Demineralizer Water Sys. Pullman Power Products 1P22 1P22 73 Nuclear Closed Cooling System Pullman Power Products IP43 1P43 101 Containment Chilled Water System Pullman Power Products 1P50 1P50 103 Service Air System Fisher Controls 6393471 1P51 6170 Instrument Air System Pullman Power Products 1P52 1P52 74 Post Accident Sampling System Johnson Controls IP87 IP87 034 Containment System Newport News NNI-OS-02 1T23 N/A

REPORT NO. P0059-0012 INSERVICE INSPECTION

SUMMARY

REPORT FOR PERRY NUCLEAR POWER PLANT (PNPP) UNIT #1 LOCATED AT: 10 Center Road Perry, Ohio 44081 OWNER: FirstEnergy Nuclear Operating Company 76 South Main Street Akron, Ohio 44308 REACTOR SUPPLIER: General Electric Corporation 175 Curtner Avenue San Jose, California 95125 NRC DOCKET NUMBER: FACILITY FULL POWER LICENSE: CAPACITY, Mwe: 1305 COMMERCIAL OPERATION DATE: November 18, 1987 INSPECTION INTERVAL: November 18, 1998 - May 17, 2009 INSPECTION PERIOD: Third (Nov 18, 2005 - May 17,. 2009) REFUELING OUTAGE: RF012 DOCUMENT COMPLETED: July 9, 2009

REPORT NO. P0059-0012 ABSTRACT Perry Nuclear Power Plant (PNPP) Unit #1 was shutdown for approximately eleven and a half weeks to refuel the reactor vessel [Refueling Outage 12(RFOl2)] and perform plant maintenance commencing February 23, 2009. During this time period, and during the preceding operating cycle, inservice examinations were performed to comply with plant Technical Specifications and the 1989 Edition of ASME Section XI with no Addenda. ASME Section XI requires reporting of examination results for Class 1 and 2 pressure retaining components and their supports. This report summarizes the results of Class I and 2 examinations, and also Class 3 and Augmented examinations, which were performed in accordance with the schedules within PNPP's Inservice Examination Program Plan (ISEP), Revision 13. Automated ultrasonic examinations were performed on the upper course; reactor pressure vessel dissimilar metal nozzle to safe-end welds (previously Category B-F, now Risk-Informed R-A). These included five Feedwater (N4) nozzles, two Core Spray (N5) nozzles and three Low Pressure Core Injection (N6) nozzles. These examinations met the new ASME Section XI, Appendix VIII, Supplement 10 requirements. Existing flaws in N6A and N6C, first evaluated as a part of the BWRVIP guidance UT data review under Condition Report (CR)'08-47166, were again recorded and evaluated under CR 09-56393. Routine Section XI volumetric, surface and visual examinations were performed on Class 1, 2 and 3 piping systems and pressure retaining components. Class 1 piping weld examinations included application of Risk Informed ISI (reference Relief Request IR-049). In-vessel examinations consisted of the required Code visual examinations along with augmented visual examinations of numerous vessel interior components. Augmented ultrasonic examinations were also performed on the 20 Jet Pump Hold-Down Beams. Baseline visual examinations were performed on the Steam Dryer. The baseline exams identified minor indications on two Lifting Rod to Lifting Eye Barrel tack welds, one Upper Brace to Bank A End Panel weld, and within the Support Ring; reference CR's 09-54923, 09-55345 and 09-54661. The augmented visual and ultrasonic examinations were primarily conducted in accordance with the Boiling Water Reactor Vessel and Internals Project (BWRVIP) inspection guidelines.. Minor jet.pump.wedge wear was found on jet pump 6 and 13 and evaluated as acceptable for operation through RFOI3 (refer to CR 09-54819). Minor Wedge Rod wear was also found on a number of Jet Pumps; refer to CR 09-55400. Follow-up examinations of the vessel interior crud deposits found during RFO9 were performed and the crud deposits were found to be essentially unchanged (refer to CR's 03-01995 & 05-01928). Follow-up examinations were also performed on the SHSAM bolts for the anti-rotation pin wear found in RFO9. SHSAM #2 & 8 were modified this outage under Engineering Change Package 06-0021, Order 200081398. A follow-up Condition Report, 09-55364 was written document the condition going forward into Cycle 13 (also refer to CR's 03-02831 & 05-01794). A surveillance sample holder (SSH-2) was also found to have a bent bail handle; refer to CR 09-55513. RFOI2 was the second refueling outage of the third Inspection Period within Perry's second 10-Year inservice Inspection Interval. With the completion of the Cycle 12 and RFO12 examinations, 100% of the examinations scheduled for the third period are-done. The examinations resulted in a complete and acceptable program in that all indications were evaluated for acceptance in accordance with ASME Section XI, all required corrective actions and/or evaluations were completed, and the required completion percentages were met. 2

REPORT NO. P0059-0012 CONTENTS PAGE

1.0 INTRODUCTION

2.0 REFUELING OUTAGE DURATION 4------------------------------------- 3.0 CODE REQUIREMENTS 4------------------------------------- 4.0 INSPECTION 4------------------------------------- 5.0 CERTIFICATIONS 4------------------------------------- 5.1 Personnel 5------------------------------------- 5.2 Equipment and Materials 7----------------------------------7 Thermometers - -------------------------------------------- 7 Magnetic Particle Equipment 7-----------------------------7 Magnetic Particle Materials 7-----------------------------7 Ultrasonic Flaw Detectors 7-------------------------------7 Ultrasonic Couplants 7------------------------------------7 Transducers 8------------------------------------- 6.0 CALIBRATION STANDARDS i------------------------------------ 7.0 PROCEDURES AND INSPECTION PLANS -------------------------------- 12 8.0 RELIEF REQUESTS ----------------------------------------------- 13 9.0 SCHEDULE CHANGES ---------------------------------------------- 16 10.0 EXAMINATION

SUMMARY

RESULTS ----------------------------------- 17 11.0 NIS-2/NR-1 ------------------------------------------------------ 18 APPENDICES A. CYCLE 12 & RFOI2 EXAMINATIONS RESULTS

SUMMARY

--------------             22
  • Cycle 12 & RFO12 Scheduled Inservice Examinations -------- 23
          " Cycle 12 & RFO12 Preservice Examinations            --------------- 63 B. CYCLE 12 & RFO12 NIS-2/NR-1 FORMS          ------------------------- 68 LAST PAGE       --------------------------------------------------------- 198 3

REPORT NO. P0059-0012

1.0 INTRODUCTION

The information provided herein is supplied to document compliance with ASME B&PV Code, Section XI requirements for reporting inservice inspection results for Class 1 and Class 2 pressure retaining components and their supports. Examination results of Class 3 and Augmented components and their associated supports are included in this report as supplemental information. This report covers inservice inspection activities performed from Perry Nuclear Power Plant (PNPP)'s return to commercial operation after refueling outage RFOII through the completion of RFO12. Included in this report are the following:

              "   Personnel and Equipment Listings
              "   Examination Results Summaries
              "   NIS-2/NR-1 Reports
              "   Other Pertinent Information 2.0 REFUELING OUTAGE DURATION The Perry Nuclear Power Plant, Unit #1, was shutdown for RFO12 from February 23, 2009 to May 23, 2009. The plant returned to commercial operation on May 13, 2009, at 13:02.      This is noted as the time when the generator was synchronized to the grid.

3.0 CODE REQUIREMENTS The inservice inspections were conducted in accordance with the requirements of ASME B&PV Code, Section XI, Division 1, 1989 Edition, no Addenda, with Code Cases N-307-3, N-416-3, N-457, N-460, N-461-1, N-491-2, N-498-4, N-509, N-513-2, N-522, N-524, N-526, N-532-4, N-546, N-552, N-566-2, N-568, N-578 as applied in PNPP's Risk-Informed Class 1 Piping program, R-586-1, N-592, N-598, N-599, N-601, N-613-1, N-623, N-624, N-6W7, N-648-1, N-652-1, N-663, N-664, N-695 and N-700. 4.0 INSPECTION Inspection activities were conducted by Authorized Nuclear Inservice Inspection personnel from the Hartford Steam Boiler Company. 5.0 CERTIFICATIONS Personnel, equipment, and transducer certifications were maintained as required by code and procedures. This section identifies the personnel and equipment utilized in the performance of inservice examinations during Cycle 12 operations and RFOl2. Certification records for personnel and equipment are kept on site and are available for review. 4

REPORT NO. P0059-0012 5.1 Personnel Nondestructive Examination (NDE) personnel were qualified and certified to perform specific non-destructive examinations in accordance with PNPP or approved vendor procedures as verified by PNPP personnel and the Authorized Nuclear Inservice Inspector. The following is a listing of personnel responsible for the performance of the NDE activities related to ISI during Cycle 12 operations and RFOI2: ISI NDE PERSONNEL Andrie, Bryan NA NA NA II+ Blood, Eric NA NA NA . II++ Blum, William III** III III NA Bohn, Joseph NA NA NA Boyd, Rodney NA NA NA II++ Bryan, Timothy II* NA NA NA Bryd. James NA NA NA II++ Buck, George III** II II III Burton, Chad II*** NA NA NA

    .Catron, Earnest                      III**       NA         NA      NA Cave, Peter                           NA          IIL        IIL     II Clare, John                           NA          NA         NA      II+

Crawford, Timothy NA NA NA II++ Devito, Michael NA IIL IIL II Drews, Michael NA NA NA II++ DuBose, George III^ III III NA Duncan, Michael NA NA. NA II++ Duron, Robert II^ NA NA NA Erbacher, Lester NA NA NA II Erickson, Scott III** III III III Fish, Cody II*** NA NA NA Fish, Karen II^ NA NA NA Fish, Ken II*** NA NA . NA Fish, Kevin II*** NA NA NA Fitzgerald, Michael NA NA NA II++ Franklin, Sean NA NA NA II+ Green, Jerry NA NA NA II... Hancock, David II** II II II Herman, Dustin NA NA NA II++ Hess, S. Rodney NA NA NA II... Holloway, Mark NA NA NA II++ Huhe, Troy II** II II NA Hurley, Melvin NA IIL NA II Joffe, Christopher NA NA NA II++ Joffe, Nicholas NA NA NA II++ Johnson, Gary NA IIL IIL II Jopko, Steve NA IIL NA II Kemp, Michael NA NA NA III++ Lesnjak, Damijan II II IIL II Lynch, Norbon NA NA NA II+ Matthys, Russell NA NA IIL II McCain, Samuel NA NA NA II++ Messenger, John NA NA NA III Muhson, Dewey III** III III III Musgrove, Floyd NA NA NA II+++ Neau, David NA NA . NA III++ 5

REPORT NO. P0059-0012 ISI NDE PERSONNEL (Continued) Ott, William NA IIL NA II Owens, Johnny NA NA NA II+ Pattterson, John NA NA NA II+ Phelps, Antoninette NA NA NA II+ Phillips, David NA NA NA II++ Phillips, Donald NA NA NA II... Powell, Richard NA IIL IIL II Rachal, Andre II** NA NA NA Richardt, Joseph NA NA NA II+ Roth, Scott NA NA NA II+ Rude, Jan NA NA NA II++ Seng, Tony II*** NA NA NA Shearer, Levi NA NA NA II Shipes, Kenneth NA IIL NA II Siever, Michael NA NA NA II++ Snyder, Steve II** II II II Starnes, Jason NA NA NA II++ Stefanelli, Frank NA NA NA II++ Strong, Michael NA NA NA II++ Subido, Nicholas II*** NA NA NA Tepsick, Michael NA NA NA III Todd, Eugene NA NA NA II+ Trout, Keith NA NA NA II++ Urban, Michael NA NA NA II++ Wasko, Shawn NA NA NA II++ Whitaker, Robert NA NA NA III++ Williams, Larry NA NA NA II+ Winney, Ryan NA NA NA II++* Wirtz, Charles NA NA IIL III Wolf, Ronald NA NA NA II+ Zaharewicz, Kurt NA NA NA I1+ + - Limited to VT-2 only ++ - Limited to in-vessel VT-i and VT-3 examinations only +++ - Limited to VT-3 only

  • - Limited to thickness and contour examinations only
    • - PDI qualified personnel for manual and/or automated UT
    - Limited to automated UT data acquisition only
    - Limited to Phased Array Jet Pump Beam UT examinations only 6

REPORT NO. P0059-0012 5.2 Equipment and Materials The equipment and materials used during the performance of the non-destructive examinations were certified and/or calibrated in accordance with site procedures or approved vendor procedures and verified by the Quality Assurance Department and the Authorized Nuclear Inservice Inspector. The following is a listing of NDE equipment and materials used for the performance of the NDE work activities related to ISI during Cycle 12 operations and RFO12: THERMOMETERS

           -OMEGA             450 Digital             LS0Z0103A OMEGA             450 Digital             L80Z0103B OMEGA             450 Digital             L80Z0103D OMEGA             450 Digital             L8O103N OMEGA             450 Digital             L70M0_19F OMEGA             450 Digital             L70M0019J MAGNETIC PARTICLE EQUIPMENT Parker          .B-300 AC Yoke           PAR-ACMT-049 Parker           B-300 AC Yoke           PAR-ACMT-058 MAGNETIC PARTICLE MATERIALS Magnaflux              1 Gray Powder     I           8118 ULTRASONIC FLAW DETECTORS PANAMETRICS                Epoch 4               061487310 PANAMETRICS                EPOCH 4               081579202 PANAMETRICS                EPOCH 4               081577402 Zetec+             MICRO TOMOSCAN              133892 Zetec+             MICRO TOMOSCAN             18121-07 Zetec+             MICRO TOMOSCAN            228337-03
   + Used for Auto DM weld exams.

ULTRASONIC COUPLANTS Sonotech Ultragel II 92125 7

REPORT NO. P0059-0012 TRANSDUCERS APPROVED FOR USE FOR MANUAL EXAMS Harisonic 3251 A10 .50 10.0 MHz 0 Harisonic 6869 A10 .50" 10.0 MHz 0 KBA 00C520 Comp-G .375" 2.25 MHz N/A KBA 00CT34 Comp-G .375 1.5 MHz N/A KBA ooMPX8 Comp-G .50" 1.5 MHz N/A KBA OOMXB4 Comp-G .50" 2.25 MHz N/A KBA 01DXNH Comp-G .375" 2.25 MHz N/A KBA 01F4WN Comp-G .375" 5.0 MHz N/A KBA 01FC6J Comp-G .375" 5.0 MHz N/A KBA 01FC6L Comp-G .375" 5.0 MHz N/A KBA 01FYW9 Comp-G .375" 5.0 MHz N/A KBA 01FYWD Comp-G .375" 5.0 MHz N/A KBA O1HIWP Comp-G .375" 2.25 MHz N/A KBA O1H2MF Comp-G .375" 1.5 MHz N/A KBA. 01H2MH Comp-G .375" 1.5 MHz N/A KBA O1H2MJ Comp-G .375" 1.5 MHz N/A KBA 01H6D1 Comp-G .375" 1.5 MHz N/A KBA 01H6D2 Comp-G .375" 2.25 MHz N/A KBA 01H6D6 Comp-G .375" 2.25 MHz N/A KBA 01J9H1 FDCP-XDCR .50" 2.25 MHz 0 KBA 01JBOM Comp-G .5" 5.0 MHz N/A KBA 01JBON Comp-G .5" 5.0 MHz N/A KBA 01JBOP Comp-G .5" 5.0 MHz N/A KBA 01JB58 Comp-G .25" 2.25 MHz N/A KBA 01JB59 Comp-G .25" 2.25 MHz N/A KBA O1JB5B Comp-G .25" 2.25 MHz N/A KBA 01JB5C Comp-G .25" 2.25 MHz N/A KBA 01JBR1 Comp-G .25" 5.0 MHz N/A KBA 01JBR3 Comp-G .25" 5.0 MHz N/A KBA 01JBR4 Comp-G .25" 5.0 MHz N/A KBA O1JBR5 Comp-G .25" 5.0 MHZ N/A KBA O1JBRK Comp-G .5" 5.0 MHz N/A KBA 01JBRL Comp-G .5" 5.0 MHz N/A KBA 01JCTO Comp-G .25" 5.0 MHz N/A KBA 01JCTK Comp-G .5" 2.25 MHz N/A KBA O1JCTL Comp-G .5" 2.25 MHz N/A KBA O1JHFT Comp-G .5" 2.25 MHz N/A KBA 01JL02 Comp-G .25" 2.25 MHz N/A KBA 01JNKV Comp-G .5 1.5 MHz N/A KBA 01JNKX Comp-G .5 1.5 MHz N/A KBA 01JNKY Comp-G .5 1.5 MHz N/A KBA 01JNVP FDCP-XDCR .375" 3.5 MHz 0 FHP KBA 01JNVR FDCP-XDCR .375" 3.5 MHz 0 FHP KBA O1JPIV Comp-G. .5 1.5 MHz N/A KBA O1JP5X FDCP-XDCR .50" 3.5 MHz 0 F-HP KBA 01JP5Y FDCP-XDCR .50" 3.5 MHz 0 F-HP KBA 01JP61 FDCP-XDCR .25" 5.0 MHz 0 KBA 01JP62 FDCP-XDCR .25" 5.0 MHz 0 KBA 01JP68 FDCP-XDCR .375" 5.0 MHz 0 KBA 01JP6B FDCP-XDCR .375" 5.0 MHz 0 KBA O1JP6J FDCP-XDCR .50" 2.25 MHz 0 KBA O1JP6L Comp-G .5" 5.0 MHz N/A KBA 01JP6M Comp-G .5" 5.0 MHz N/A 8

REPORT NO. P0059-0012 KBA OlJPWC FDCP-XDCR .25" 2.25 MHz 0 KBA 01JPWD FDCP-XDCR .25" 2.25 MHz 0 KBA 01JR8J FDCP-XDCR .375" 2.25 MHz 0 KBA O1JR8K FDCP-XDCR .375" 2.25 MHz 0 KBA O1L7WV Comp-G .250" 1.5 MHz N/A KBA O1L7WW Comp-G .250" 1.5 MHz N/A KBA O1L7WX Comp-G .250", 1.5 MHz N/A KBA O1L7WY Comp-G .250" 1.5 MHz N/A KBA O1L7XO Comp-G .250" 1.5 MHz N/A KBA 01LJC5 FDCP-XDCR .25" 3.5 MHz 0 KBA 01LJC7 FDCP-XDCR .25" 3.5 MHz 0 KBA O1P7DH FDCP-XDCR .375" 10.0 MHz 0 KBA 574613965 MSEB 2 (; 011) 2.0 MHz 0 mm KBA 574614023 MSEB 2 (1 0l1) 2.0 MHz 0 mm KBA 5746220467 MSEB-4 3.5,x 10 4.0 MHz 0 KBA 5746220492 MSEB-4 3.5 x 10 4.0 MHz 0 KBA SE0082 Comp-G .5" 2.25 MHz N/A Panametrics 284242 AI1S .50" 10.0 MHz 0 Panaxnetrics 288670 AI1S .50" 10.0 MHz 0 TRANSDUCERS APPROVED FOR USE FOR AUTOMATED EXAMS RTD 00-339 "45Tl.5-Aust ELL(16 x 2.0 MHz 45 10)mm RTD 00-343 TRL2-Aust 2(ilx18) mm 2.0 MHz 60 RTD 00-351 70°TRL2-Aust 2(10 X 2.0 MHz 70 18)mm RTD 00-354 70°TRL2-Aust 2(10x18) mm 2.0 MHz 70 0 RTD 02-234 °TRL-2 Aust. 2(1 o10) mm 2.0-.MHz 0 RTD 02-235 0' TRL-4 2(;1 o10) nun 4.0 MHz 0 Aust RTD 03-175 TRL2-Aust 2 (7x10) nmm 2.0 MHz 45 RTD 03-176 TR L 2-Aust 2(7x10) mm 2.0 MHz 45 RTD 03-186 425TRL2-Aust 2(8x14) mm 2.0 MHz 42 RTD 03-337 45 0 TRL1-Aust 2(10x18) mm 1.0 MHz 45 RTD 03-338 45°TRL2-Aust 2(lix18) mm 1.0 MHz 45 RTD 03-678 456 TRL1-Aust 2(20X34).mm 1.0 MHz 45 RTD 03-679 60°TRLI-Aust 2(27X34) mm 1.0 MHz 60 RTD 03-681 45°TRLI-Aust 2(15x25) mm 1.0 MHz 45 RTD 03-682 45°TRLI-Aust 2(15x25) mm 1.0 MHz 45 RTD 03-683 6 0 °TRL2-Aust 2(15x25) mm 1.0 MHz 60 RTD 03-684 60'TRL2-Aust 2(15x25) mm 1.0 MHz 60 RTD 04-281 60°TRL2-Aust 2(7 x 10)mm 2.0 MHz 60 RTD 04-282 60 0 TRL2-Aust 2(7 x 10)mm 2.0 MHz 60 RTD 04-284 450TRL2-Aust 2(7 x 10) mm 2.0 MHz 45 RTD 04-286 45°TRL2-Aust 2(7 x 10)rm 2.0 MHz 45 RTD 04-287 70°TRL2-Aust 2(7x10) rmn 2.0 MHz 70 RTD 04-288 70°TRL2-Aust 2(7x10) mm 2.0 MHz 70 RTD 04-289 70°TRL2-Aust 2 (7xi0) imm 2.0 MHz 70 RTD 04-290 70°TRL2-Aust 2(7x10) mam 2.0 MHz 70 RTD 04-292 42°TRL2-Aust 2(8 x 14)mm 2.0 MHz 42 9

REPORT NO. P0059-0012

     &3,'t   '3/4R"t RTD       04-294    45°TRL2-Aust     2(8 x 14)mm    2.0  MHz    45 RTD       04-296    45*Ti.5-Aust      (16 x 10)mm   1.5  MHz    45 RTD       04-298    45°TI.5-Aust      (24x17) mm    1.5  MHz    45 0

RTD 04-303 45 TRL2-Aust 2(i0x18) mm 2.0 MHz 45 RTD 04-307 70'TRL2-Aust 2(i0x18) mm 2.0 MHz 70 RTD 04-314 60°TRL1-Aust 2(10xl8)mm 1.0 MHz 60 RTD 04-315 6 0 °TRL1-Aust 2(10 X 1.0 MHz 60 18)mm RTD 04-317 6 0 °TRLI-Aust 2(10x18) mm 1.0 MHz 60 RTD 04-318 45 0 TRL2-Aust 2(15 X 2.0 MHz 45 25)mm 0 RTD 04-319 45 TRL2-Aust 2(15 X 2.0 MHz 45

25) mm

.RTD 04-322 60*TRL2-Aust 2(15 X 2.0 MHz 60 25)mm RTD 04-323 60°TRL2-Aust 2(15 X 2.0 MHz 60 25)mm RTD 04-324 70'TRL2-Aust 2(15 X 2.0 MHz 70 25)mm RTD 04-325- 70*TRL2-Aust 2(15 X 2.0 MHz 70 25)mm RTD 04-327 70*TRL2-Aust 2(15 X 2.0 MHz 70 25)rmm RTD 04-331 45°TRL1-Aust 2(15 X 1.0 MHz 45

25) rm 0

RTD 04-336 6 °TRL1-Aust 2(15 X 1.0 MHz 60 25)mm 0 RTD 04-337 6 °TRL1-Aust 2(15.X 1.0 MHz 60 25)mm RTD 04-341 45 0 TRL1-Aust 2(20 x 1.0 MHz 45 34)rmm RTD 04-342 45°TRL1-Aust 2(20 x 1.0 MHz 45

34) rm 0

RTD 04-344 6 °TRL1-Aust 2(20x34) mm 1.0 MHz 60 RTD 04-347 60°TRL1-Aust 2(20 x 1.0 MHz 60 34)mm RTD 04-429 450 TRL1-Aust 2(15x25) mm 1.0 MHz 45 RTD 05-1054 "600 TRL2-Aust 2(15x25) mm 2.0 MHz 60 RTD 05-1055 60* TRL2-Aust 2(15x25) mm 2.0 MHz 60 RTD 05-139 45' TRL1-Aust 2(20 X 34) 2.0 MHz 45 mm RTD 05-141 450 TRL2-Aust 2(15x25) mm 2.0 MHz 45 RTD 05-144 600 TRL1-Aust 2(20 X 34) 2.0 MHz 60 mm RTD 05-146 600 TRL2-Aust 2(10xl8)mm 2.0 MHz 60 RTD 05-147 600 TRL2-Aust 2(7x10) mm 2.0 MHz 60 RTD 05-159 45°TRL1-Aust 2(10x18) mm 1.0 MHz 45 RTD 05-160 450 TRL1-Aust 2(10x18) umm 1.0 MHz 45 RTD 05-174 45' TRL2-Aust 2(15x25) mm 2.0 MHz 45 RTD 05-175 600 TRL2-Aust 2(7xi0) mm 2.0 MHz 60 RTD 05-176 70' TRL2-Aust 2(7x10) mm 2.0 MHz 70 RTD 06-502 00 TRL-2 Aust 2(0 o10) mm 2.0 MHz 0 RTD 06-505 45 0 T 1.5-Aust (24x17) mm 1.5 MHz 45 RTD 06-506 45°T 1.5-Aust (24x17) mm 1.5 MHz 45 0 RTD 06-508 42 TRL2-Aust 2(8x14) mmm 2.0 MHz 42 RTD 98-144 45 0 T-1.5 Aust (16x10) mm 1.5 MHz 45 RTD 98-154 .45°T-1.5 Aust (24x17) mm 1.5 MHz 45 RTD 98-156 456T-1.5 Aust (24x17) mm 1.5 MHz 45 RTD 98-158 45'T 1.5-Aust (24 x 17)mm 1.5 MHz 45 RTD 98-161 45°TRL2-Aust 2(10x18) mm 2.0 MHz 45 RTD 98-163 45 0 TRL2-Aust 2(10X18)mm 2.0 MHz 45 10

REPORT NO. P0059-0012 6.0 CALIBRATION STANDARDS Ultrasonic calibration standards approved for use for ISI related work activities during Cycle 12 operations and RFO12 are as listed below: CAL-DPTH-071 CAL-DPTH-073 CAL-DPTH-080 CAL-DPTH-57 CAL-IIW2-002 CAL-IIW2-012 CAL-IIW2-016 CAL-IIW2-028 CAL-IIW2-030 CAL-IIW2-050 CAL-IIW2-055 CAL-PDI-001 CAL-PDI-002 CAL-PDI-003* CAL-RHOM-004 CAL-RHOM-004 CAL-RHOM-008 CAL-RHOM-015 CAL-RHOM-051 CAL-RHOM-058 CAL-RHOM-082 CAL-RHOM-085 CAL-RHOM-093 CAL-RHOM-095 CAL-RHOM-099 CAL-RHOM-101 CAL-RHOM-103 CAL-RHOM-125 CAL-RHOM-126 CAL-STEP-096 CAL-STEP-120 CAL-STEP-138 CAL-STEP-163 CAL-STEP-168 CAL-STEP-173 CAL-STEP-179. CAL-STEP-189 CAL-STEP-190 CAL-STEP-191 CAL-STEP-192 CAL-STEP-195 GE-JPBEAM-BLK PY-1 . 5-RHR PY-10-80-CS PY-12-40-CS PY-127-1-RPV PY-12-XXI-SS PY-14-XX1-CS-F PY-18-40-CS PY-20-120-CS PY-4-80-SS PY-IR-RHR PY-SE-BI-3 PY-STUD-LPCS-2.25-CS PY-VALVE-XX1-CS PY-VALVE-XX2-CS 11

REPORT NO. P0059-0012 7.0 PROCEDURES AND INSPECTION PLANS The examination procedures and inspection plans used during Cycle 12 operations and RFO2 were as follows: Perry NDE Procedures:

                   ~
            .PROCEDU:E~                                ,TITLE           ,,

NQI-0952 9 Radiographic Operations and Examinations NQI-0942 11 Magnetic Particle Examination NQI-0944 11 Ultrasonic Examination (General Procedure) NQI-1042 13 Visual Examination Ultrasonic NDE Inspection Plans Used with NQI-0944: NDE-002 7 Ultrasonic Instrument Linearity Verification NDE-008 13 Manual Ultrasonic Examination of Ferritic Piping Welds NDE-012 5 Straight Beam Ultrasonic Examination of Bolts and Studs Procedure for Ultrasonic Examination of Stainless Steel NDE-018 11 (Austenitic) Piping Welds for Intergranular Stress Corrosion Cracking NDE-019 5 Ultrasonic Examination of Flued Head Penetration Attachment Weld, NDE-027 Ultrasonic Examination of Residual Heat Removal (RHR) System Heat Exchanger Nozzle Welds and Inner Radius Exams NDE-030 2 Manual Ultrasonic Examination of Valve Body Welds NDE-033 1, Ultrasonic Examination of-Vessel to Skirt Weld NDE-035 0 Ultrasonic Examination of Base Metal adjacent to Socket Welds 12

REPORT NO. P0059-0012 GEH NDE Procedures: GE Written Practice for Qualification of NDE Personnel: 386HA480 / R.20 Certification of Nondestructive Test Personnel Procedure for Training and Qualification of Personnel for GE Energy, Nuclear Specialized NDE Applications GE Procedure for IVVI & BWRVIP Required Exams Procedure for Invessel Visual Inspection (IVVI) of BWR 6 RPV Internals Procedure for Automated Ultrasonic Examination of Jet GEH-UT-547 R.1 Pump Beams with Phased Array Technique in Boiling Water Reactors GE NDE Procedures: DDR 07-Procedure for Ultrasonic Examination of Dissimilar GE-UT-209 / R.18 Metal Welds, and Nozzle to Safe-End Welds 08-05 Procedure for Automated Ultrasonic Examination DDR 07-GE-UT-244 / R.3 Tomoview Analysis of Weld Overlaid Austenitic Piping 17 Welds Procedure for the Performance of Straight Beam GE-UT-605 R.3 Examinations 8.0 RELIEF REQUESTS Due to geometric, metallurgical, and physical limitations, some of the items scheduled for examination during RFO12 received partial examinations. Within the limitations, examinations. were completed to the-greatest extent practical. For those Code exams in which the examination coverage achieved was less than 90%, relief requests have been submitted and approved. Additionally, where it has been determined that conformance with any other examination requirements of ASME Section XI is impractical; PNPP has requested relief from the examination requirements. The following listing summarizes all the relief requests thathave been submitted to and approved by the NRC for PNPP's second 10-year Inspection Interval: 13

REPORT NO. P0059-0012 RRý NO/REV. SYSTEM.*:ý .. TY .EREL1-EF.`]: CATEG ITEM NO IR-001 R-2 Reactor Pressure Vessel Partial Exams B-A B1.21 Bi.22 Bl.40 B-D B3.90 B3.100 B4.11 IR-007 R-1 Residual Heat Removal Partial Exams B-K-I BI0.10 Low Pressure Core Spray High Pressure Core Spray Reactor Core Isolation-Cooling Feedwater Reactor Water Cleanup Main Steam IR-009 R-1 Reactor Pressure Vessel Partial Exams B-O BI4.10 IR-012 R-2 Main Steam Partial Exams C-C C3.10 Residual Heat Removal C3.20 High Pressure Core Spray Feedwater IR-013 R-1 High Pressure Core Spray No Exams C-G C6.10 Low Pressure Core Spray Residual Heat Removal IR-015 R-1. Reactor Water Cleanup Partial Exams C-C C3.20 Residual Heat Removal Low Pressure Coolant-Injection IR-018 R-1 Residual Heat Removal Partial Exams B-K-I B10.10 IR-019 R-1 Control Rod Drive Partial Exams C-C C3.20 Residual Heat Removal High Pressure Core Spray IR-021 R-4 Main Steam No Exams D-B D2.20 Emergency Closed Cooling Emergency Service Water IR-023 R-i All with Snubbers Alternate Tech- N/A Sampling Plan Spec IR-024 R-1 Reactor Pressure Vessel Partial Exams B-F B5.10 IR-025 R-I Main Steam Alternative B-K-I B10.10 Exams IR-026 R-1 Main Steam Alternative- C-C.- C3.20 Feedwater Exams IR-027 R-1 Standby & HPCS Diesel Alternative D-B D2.20 Fuel Oil Exams IR-030 R-1 Reactor Pressure Vessel Alternate Exam B-A B1.11 for Circ. Shell Welds IR-032 R-0 Containment Substitute App E-D E5.10 J test for VT-3 E5.20 IR-034 R-0 Containment Inspect new N/A N/A coating IAW coating program 14

REPORT NO. P0059-0012 RELIEF REQUESTS CONTINUED RRNORE

           -     --     SSTM                TYPE RELIEF  -:,.j  CTEG!, -  ITEM- NO.

IR-035 R-0 Containment Pre-removal N/A N/A coating inspection IR-037 R-0 Containment Delete E-C N/A successive exam for repairs IR-038 R-0 Containment Alternative to E-G E8.20 torque and tension test IR-039 R-0 Containment Alternative to N/A N/A VT-3 lighting and resolution IR-040 R-0 Containment Alternate UT N/A N/A thickness IR-041 R-0 Containment Alternate N/A N/A Repair Records IR-042 R-0 Reactor Vessel Alternate B-H B8.10 Examination IR-043 R-1 Reactor Water Cleanup Alternate B-M-I B12.30 Categorization IR-044 R-0 Reactor Vessel Use of Code B-A B6.10 Case N-627 IR-045 R-0 Reactor Vessel Use of Code B-A Bl.30 Case N-623 BI.40 IR-046 R-0 Reactor Vessel Alternate B-A BlI:0 Length Sizing B1.20 Criteria IR-048 R-0 N/A Alternate UT N/A N/A Annual Training Requirements IR-049 R-0 Class 1 Piping Risk-Informed B-F & All Application B-J IR-053 R-0 Re-rating for Class 3 Allow use later N/A N/A systems Edition and Addenda IR-054 R-0 Class 1 Piping Alternate B-D B3.90 Examination B3.100 Population IR-055 R-0 Class 1 Piping No Exam R-A R1.16 IR-056 R-0 Reactor Vessel Alternate B-N-2 B13.40 Examination IR-057 R-0 Reactor Vessel Partial Exam B-A BI.30 PT-001 R-1 Various non-isolable Alternate C-H C7.30 (from the RPV Boundary) System and C7.70 Class 2 Components Inservice Tests PT-006 R-1 All Pressure Retaining Use of Code B-P All for Components within the ISI Case N-546 C-H Press. Boundary D-A, Testing B & C PT-007 R-1 Class 3 Safety Relief Alternate D-A Dl.10 Valve Discharge Piping Hydrostatic Test 15

REPORT NO. P0059-0012 Notes:

1. Relief Requests IR-016, IR-017, IR-022, and PT-003 were withdrawn in the I't Inspection Interval; IR-004, IR-005, IR-006, IR-008, IR-010, IR-011, IR-014, IR-020, IR-028, IR-029, IR-031, PT-002, PT-004 and PT-005 were withdrawn in the 2 nd Inspection Interval; IR-002, IR-033, IR-050, IR-051 and IR-052 were superseded by the approval of Code Cases N-307-3, N-599, N-695, N-663 and N-613 respectively; and IR-036, IR-047 and PT-008 were withdrawn without ever being approved.
2. For those Cycle 12 and RFO12 Code required examinations where the examination coverage was limited, the applicable relief request is referenced in the "remarks".column of the Examinations Results summary (Appendix A) for the particular examination item.

9.0 SCHEDULE CHANGES Scheduling changes were made during RFOI2 to facilitate the examinations, or to account for unforeseen physical or schedule interferences, or radiological conditions. These changes differ from the schedule in Revision 13 of PNPP's Inservice Examination Program (ISEP). The changes, which will be incorporated in the next revision to the ISEP, are as follows:

                                                       .         ~sb42:  1:

IE12-0336 Weld 1E12-0336 is a 12" Class 2, Category C-F-2, Item C5.51 weld that was scheduled for examination in RFOI2 under Order 200173621. It is the valve IE12-FO50A to pipe weld. It is located in the Steam Tunnel. It is also within the High Energy Pipe Break Exclusion Region (HEPBER) . Upon un-insulating it, it was found that there is a banded and glued wall penetration seal for Penetration PAB-3067 that is on the toe of the weld. Additionally, there is very little space between the valve and the penetration which will make removal of the boot seal difficult. Finally, the weld is an area with a dose rate of up to 280 mR/hr. As an equivalent substitution, weld 1E12-0580 will be examined. It is also a 12" Class 2, Category C-F-2, Item C5.51 weld that is located within the HEPBER. It is located in room 620-03 (RHR Bravo), does not scaffolding, does not require insulation removal, and is an area with a dose rate of only 70 mr/hr. Document Change Request (DCR) Notification 60052453.2 was generated to update the ISEP and the Technical Assignment File for HEPBER, TAF 81871. 1B13-JPRB-P5/P6 These welds were added to the scope due to IBI3-JPRB-PI3/PI4 Jet Pump Main Wedge Wear found on JP06 & IBI3-JPRS6-P5/P6 JP13 in accordance with BWRVIP-41. IB13-JPRS6-PI3/Pl4 IBI3-JPRS8-P5/P6 IB13-JPRS8-P13/P14 IBI3-JPTW-P05 lBI3-JPTW-PO6 IBI3-JPTW-PI3 IBI3-JPTW-PI4 16

REPORT NO. P0059-0012 SCHEDULE CHANGES CONTINUED IEI2-BO01D-SB2-WA Welded attachment 1E12-B001D-SB2-WA Is a Class 2, Category C-Cc, Item C3.10 that was scheduled for examination under order 200173680. Due to the radiological conditions in the area, this welded attachment was replaced, as an equivalent substitution with !EI2-BO01D-SB3-WA. 1E12-F0010-IS 20" Gate Valve 1E12-F0010-IS is a Class 1, Category B-M-2, Item C12.50 (Valve Grouping

                              # XI per ISEP) that was added to the examination scope due to emergent valve repair under order 200365416. ISEP requires an internal VT-3 any time a valve in this grouping is opened due to maintenance, 1 valve once per Interval.

1E12-F0019-IS 6" Check Valve 1E12-F0019-IS is a Class 1, Category B-M-2, Item C12.50 (Valve Grouping

                              # XIV per ISEP) that was originally scheduled for examination due to Preventive Maintenance Order 200280448. That order was removed from the scope of RFO12 and the valve was not dissembled therefore the internal VT-3 of IE12-F0019-IS is deleted from RFOI2.

IE12-F0067A-IS 24" Gate Valve is a Class 1, Category B-M-2, Item C12.50 (Valve Grouping # VIII per ISEP) was scheduled for examination due to Corrective Maintenance Order. 200005691, ECP 03-0011 and therefore the internal VT-3 of valve was scheduled for examination in RFOI2. 10.0 EXAMINATION

SUMMARY

RESULTS RFO2 was the last refueling outage of Perry's second 10-Year Inservice Inspecti'n Interval and it marked the completion of the" third inspection period. Not including pressure testing VT-2 exams that are completed every period, completion percentages at the end of the second period are reported as follows: CATEGORY REQUIRED COMPLETION %1 ACTUAL COMPLETION % B-A item B1.30 only 100 100 B-A other than B1.30 100 100 B-D 100 100 B-F N/A See Note 2 N/A B-G-1 100 100 B-G-2 100 100 B-H N/A See Note 3 N/A B-J N/A See Note 2 N/A B-K-l N/A See Note 3 N/A B-K of CC-N-509 100 100 B-0 100 100 C-A & B 100 100 C-C N/A See Note 3 N/A C-C of CC-N-509 100 100 C-D 100 100 C-F-2 100 100 17

REPORT NO. P0059-0012 C-G 100 100 D-A 100 100 D-B N/A See Note 3 N/A D-C N/A See Note 3 N/A D-A of CC-N-509 100 100 E-A 100 100 F-A N/A See Note 4 N/A F-A of CC N-491 100 100 R-A 100 100 Notes: (1) The required completion percentages reflect the end of interval requirements of Tables IWB-2412-I, IWC-2412-1, IWD-2412-1, IWE-2412-1 and IWF-2412-I. (2) The Class 1 piping weld exams of Categories B-F and B-J were replaced by Risk Informed Category R-A in accordance with Relief Request IR-049. (3) The integral attachment exams of Categories B-H, B-K-l, C-C, D-A, D-B, and D-C have been replaced by Categories B-K, C-C and D-A of Code Case N-509. (4) The component support examinations of Category F-A have been replaced by Category F-A of Code Case N-491. Cycle 12 and RFOI2 examinations resulted in a complete and acceptable program in that all indications were evaluated for acceptance in accordance with ASME Section XI, IWA-3000, all corrective measures or evaluations were completed, and the Inspection Program B percentage completion requirements of Subsections IWB through IWF were met. Appendix "A" is a computer-generated summary of the Cycle 12 and RFO12 examination results. Component identifications (Mark Nos.) and order of appearance may differ slightly from that listed in. Revision 13 of PNPP's Inservice Examination Program. The differences are to accommodate the database software program. Original examination data reports are on file and available for review at the site. 11.0 NIS-2/NR-1. Repairs, replacements and modifications are carried out in accordance with PNPP's Nuclear Repair & Repair (non-nuclear) Manual, which meets regulatory requirements and quality standards. Compliance of the work is delineated on NIS-2/NR-I Forms. The following is a listing of NIS-2/NR-I forms applicable to this report (Class 1 and 2 only) which have been completed since PNPP's last summary report: NR-1/NIS-2 FORMS 18

REPORT NO. P0059-0012 NR-1/NIS-2 FORMS CONTINUED S N*O/. MPL:.O.-. DSCRIPTION/COMMENTS.  :: CAiSS PG. Reactor Pressure Vessel (1B13) Cycle 12 & RFOI2 Reports (con't): 1B13-054 1B13-D0008 -Replaced 20 CRDMs and 8 cap screws each 1 70 at locations 26-47, 10-23, 30-27, 22-31, 30-35, 06-47, 42-31, 50-47, 10-47, 14-27, 30-23, 34-55, 26-31, 10-39, 10-11, 14-35, 18-31, 42-07, 46-11 and "8-35. Main Steam (IB21) System Cycle 12 .& RFO2 Reports: IB21-385 1B21 Re-rated design pressure for piping, 2 92 1P57 Doc-Only ECP 06-0022 1B21-405 1B21-H453 Replaced hydraulic snubber with like 1 93 snubber along with bracket assy 1B21-406 1B21-H452 Replaced hydraulic snubber with like 1 94 snubber and installed a load stud and 2 jam nuts. 1B21-407 1B21-H472 Replaced hydraulic snubber with like 1 95 snubber along with bracket assy IB21-408 IB21-H447 Replaced hydraulic snubber with like 1 96 snubber along with bracket assy 1B21-409 IB21-H462 Replaced hydraulic snubber with like 1 97 snubber along with bracket assy 1B21-410 1B21-H490 Replaced hydraulic snubber with like 1 98 snubber 1B21-411 IB21-H446 Replaced hydraulic tandem snubbers with 1 99 like snubbers 1B21-412 IB21-H491 Replaced hydraulic snubber with like 1 100 snubber along with bracket assy IB21-413 1B21-F0041E Replaced SRV with like SRV 1 101 1B21-414 1B21-F0041C Replaced SRV with like SRV 1 103 IB21-415 IB21-FO041G Replaced SRV with like SRV 1 105 1B21-416 1B21-F0051A Replaced SRV with like SRV 1 107 121-417 1B21-F0041A Replaced SRV with like SRV. 1 109 1B21-418 1B21-F0047G Replaced SRV with like SRV 1 il1 1321-419 1B21-F0051C Replaced SRV with like SRV 1 113 IB21-420 1B21-FO051G Replaced SRV with like SRV 1 115 1B21-421 1B21-F0047C Replaced SRV with like SRV 1 117 1B21-422 1B21-F0028C Rebuilt MSIV using a new poppet 1 119 1B21-423 1B21-F0022B Rebuilt MSIV and replaced 1 cover stud 1 122 and nut 1B21-424 IB21-F0032B Remove and reinstall test connection 1 124 IB21-425 1B21-F0032A Remove and reinstall test connection 1 126 Reactor Recirculation (1B33) System Cycle 12 & RF012 Reports: 1B33-130 1B33-C0001A Replaced pump seal cartridge assembly 1 128 1B33-131 IB33-G7066A Replaced E-Systems hydraulic snubber 1 130 with like snubber IB33-132 IB33-G7070A Replaced E-Systems hydraulic snubber 1 132 with like snubber 1B33-133 1B33-F0067B Rebuilt valve using 3 new body to bonnet 1 134 studs and nuts 1B33-134 1B33 Replaced piping.flange fasteners, 11 1 136 studs and 31 nuts 1B33-135 1B33-C0001B Replaced pump seal cartridge assembly 1 137 Standby Liquid Control (0&1C41) System Cycle 12 & RFO2 Reports: IC41-039 lC41-F0029A Replaced relief valve with like valve 2 139 19

REPORT NO. P0059-0012 NR-1/NIS-2 FORMS CONTINUED

  • .SYSN:' .. ML-.NO.  : DESCRLPTTIN/CObdb)MMENTS. *:.:" I.-CLASS PG Residual Heat Removal (1E12) System Cycle 12 & RFO12 Reports:

1E12-304 lEI2-F0063C Replaced 8" check valve with like valve 2 141 1E12-305 IE12-H0588 Modified support per ECP 09-0246 by 2 143 moving to a new elevation and re-welding 1E12-306 1E12-F0063B Replaced 8" check valve with like valve 2 144 1E12-307 IEI2-F0063A Replaced 8" check valve with like valve 2 146 IE12-308 1E12-F0086 Replaced 6" check valve with like valve 1 148 1E12-309 1E12-F0084B Rebuilt check valve using new spring and 2 150 disk IE12-310 IE12 Modifications made for the ADHR system, 2 153 ECP 04-0270-01, used the following: 8' of 8" pipe, 12" x 8" reducing tee, 8" 150# gate valve and 8" elbow IE12-311 IE12 Modifications made for the ADHR system, 2 155 ECP 04-0270-01, used the following: 10" pipe, 10" gate valve, sway struts (S/N 2006-126, -128, -138, -140, & -143), 3/4" plate, 10"' 900 elbow and tee, 1/2", plate, load stud and jam nut along with snubber (SIN 04616493/072) Low Pressure Core Spray (lE21) System Cycle 12 & RFO12 Reports: IE21-040 1E21-H0022 Permanently removed support 1E21-H0022 2 161 1E21-H0024 and modified snubber 1E21-H0024 into a rigid strut per ECP 04-0270-01 1E21-041 1E21-F0018 Replaced relief valve with like valve 2 162 1E21-042 1E21-C0002 Replaced water leg pump 2 164 IE21-043 IE21 Modifications made for the ADHR system, 2 166 ECP 04-0270-01, used the following: 12'

                             - 10" pipe (2 diff          Ht V's), 2 - 150# 10" gate vlv's, 2 - 300# 10" gate vlv's, 1 24"xlO" weldolet, 2 - 24" flanges, 1 sway strut      (S/N 2006-116 & 117),          1" plate , 24" pipe & tee, 40 studs and 80 nuts High Pressure Core Spray     (1E22)     System Cycle 12 & RFO12 Reports:-

1E22-074 1E22-F0035 Replaced relief valve with like valve 2 J1 7 2 Reactor Core Isolation Cooling (IE51) System Cycle 12 & RFO12 Reports: IE51-147 IE51-F0066 Installed new disk on check valve along 1 174 with 2 - 1 & 3/8" studs and 4 nuts 1E51-148 IE51-H0072 Replaced hydraulic snubber with like 1 176 snubber IE51-149 1E51-F0061 Replaced check valve with like valve 2 177 along with C.S. pipe/angle IE51-150 IE51-H2074 Replaced mechanical snubber with like 1 179 snubber 1E51-151 1E51 Replaced RCIC head spray piping 1 180 fasteners; 3 studs and 8 nuts on flange

                             #1 ih      Reactor Water Cleanup (1G33) System Cycle 12 & RFO2 Reports:

IG33-172 1G33-F0040 Replaced 6" 1500 # gate valve with like 2 181 valve 1G33-173 1G33-F0039 Replaced 6" 1500# gate valve with like 2 184 valve 20

REPORT NO. P0059-0012 NR-1/NIS-2 FORMS CONTINUED SY/O.MLN~DESCRIPTION/CObd2ýNTS *CAS PG Local Panels and Racks (IH221 System Cycle 12 & RFOI2 Reports: 1H22-005 I 1H22-H2761 1Replaced mechanical snubber with like 2 187 snubber Containment Vacuum Relief (1M17) System Cycle 12 & RFO2 Reports: 1M17-008 IM17-H0002 Replaced tandem mechanical snubbers with 2 188 1M17-H0003 like snubbers 1M17-009 1M17-H0004 Replaced tandem mechanical snubbers with 2 189 1M17-H0005 like snubbers IM17-010 1M17-H0008 Replaced tandem mechanical snubbers with 2 190 1M17-H0009 like snubbers 1M17-011 1M17-H0011 Replaced tandem mechanical snubbers with 2 191 1M17-H0012 like snubbers Combustible Gas Control (IM51) System Cycle 12 & RFO12 Reports: IM51-028 IM51-FO1OB (Corrected Copy of 1M51-028) Replaced 36 2 192 body to bonnet nuts on valve IM51-029 1M51-F010A Replaced 36 body to bonnet nuts on valve 2 193 Main, Reheat, Extraction, and Misc. Drains (IN22) System Cycle 12 &.RFOI2 Reports: 1N22-067 IN22-H0089 Replaced mechanical snubber with like 2 194 snubber IN22-068 1N22-H0148 Replaced mechanical snubber with like 1 195 snubber Feedwater (1N27) System Cycle 12 & RFO2 Reports: 1N27-049 1N27-F0828 Added vent valve, piping, tubing and 2 196 supports per ECP04-0091. 1N27-050 1N27-F0559A Removed and reinstalled 1-3/4" test 1 197 connection from 20" check valve Condensate Transfer and Storage (IPII) System Cycle 12 and RF012 Reports: IPlI-011 IPII-F0060 Replaced 12 studs and 24 nuts on valve 2 198 Copies of the NIS-2/NR-I forms are c6ntained in Appendix "B" and the corresponding starting page numbers are provided in the above table. 21

PEPORT NO. P0059-012 APPENDIX A "CYCLE 12 & RFO12 EXAMINATION RESULTS

SUMMARY

INSERVICE INSPECTION

SUMMARY

REPORT FOR PERRY NUCLEAR POWER PLANT (PNPP) UNIT 1 22

REPORT NO. P0059-012 First.Energy Nuclear Operating Company Perry Nuclear Power Plant ISI Summary Report No. P0059-0012 Second Interval, Third Period, Second Outage (RFO12) Cycle 12 and RFO12 Inservice Examinations Prepared by: Ar-42e ingineer EI Date:

                                                                          -7 Reviewed by:                      tAuthorize           Date:

Authorized Nuclear Inservice Inspectocr Wednesday, July 08, 2009 Page 1 of 40 23

REPRT NO. P0059-012 ASME IDof Component Examined Category Description of Component ASME Exam Size - Sched. - ISI Dwg. No. Item No. Method Exam Report No. Status Remarks 1B13-CG B-Kc UT 0944-09-E044 NRI No relevant indications. BOTTOM HEAD TO SKIRT 810.10 N/A N/A 305-006-104 1B13-CG B-Kc MT 0942-09A-010 ACC None BOTTOM HEAD TO SKIRT B10.10 N/A N/A 305-006-104 IB13-N4A-KB R-A A-UT 1Q800-09003 SAT Achieved 100% code coverage and 4 fabrication flaws FW NOZZLE N4A TO SAFE-END- DM R2.11 identified were sized and evaluated per Table IWA-Weld 3514.2 and found to be acceptable. 12' 1.16" 305-006-108 1B13-N4B-KB R-A A-UT 1Q800-09002 SAT Achieved 100% code coverage and no relevant FW NOZZLE N4B TO SAFE-END - DM R2.11 indications were recorded. Weld 12' 1.16' 305-006-108 1B13-N4C-KB R-A A-UT 1Q800-09-006 SAT Exam of the pre-existing weld-overlay which recorded 2 FW NOZZLE N4C TO SAFE-END - DM R2.11 previously identified indications were exhibited no Weld significant change and the original crack which does not 12' 1.16" 305-006-108 appear to have changed since application of the overlay. 1813-N4D-KB R-A A-UT 1Q800-09-025 SAT Achieved 100% code coverage, no relevant indications FW NOZZLE N4D TO SAFE-END - DM R2.11 were recorded. Weld 12' 1.16" 305-006-108 IB13-N4F-KB R-A A-UT 1Q800-09004 SAT Achieved 100% code coverage and no relevant FW NOZZLE N4F TO SAFE-END - DM R2.11 indications were recorded. Weld 12' 1.165 305-006-108 1813-N5A-KB R-A A-UT 1Q800-09-026 SAT Achieved 100% code coverage and no relevant LPCS NOZZLE N5A TO SAFE-END - R1.14 indications were recorded. DM Weld 12' 1.125" 305-006-109 1B13-N5B-KB R-A A-UT 1Q800-09-027 SAT Achieved 100% code coverage and no relevant HPCS NOZZLE N5B TO SAFE-END - R1.14 indications recorded. DM Weld 12" 1.125' 305-006-109 1B13-N6A-KB R-A A-UT 1Q800-09-028 UNSAT Achieved 100% code coverage. Recorded relevant RHR NOZZLE N6A TO SAFE-END - DM R1.14 indications, 1which was unacceptable per IWB-3514.2 Weld and was evaluated under CR 09-56393. Also reference 12" 1.125' 305-006-109 CR 08-47166. 1B13-N6B-KB. R-A A-UT 1Q800-09-029 SAT Achieved 100% code coverage, recorded a relevant RHR NOZZLE N6B TO SAFE-END - DM R1.14 indication which was evaluated acceptable per IWB-Weld 3514.2. 12" 1.125" 305-006-109 Wednesday, July 08,2009 Page 2 of 40 24

REPORT NO. P0059-012 ASME IDof Component Examined Category Description of Component ASME Exam Size - Sched. - ISI Dwg. No. Item No. Method Exam Report No. Status Remarks 1B13-N6C-KB R-A A-UT 10800-09-031 UNSAT Achieved 100% code coverage, recorded a relevant RHR NOZZLE N6C TO SAFE-END - R1.14 indication which was sized and evaluated per IWB-DM Weld 3514.2 and found to be unacceptable. Itwas evaluated 12" 1.125" 305-006-109 under 09-56393. Also refer to CR 08-47166. 1B13-N11-KA B-E VT-2 1Q800-09-262 SAT VT-2 completed as a part of ISI-B21 -T1 300-1, no CORE DIFFERENTIAL PRESSURE B4.11 evidence of leakage identified. NOZZLE V N/A 305-006-104 1B13-N12A B-E VT-2 1Q800-09-263 SAT VT-2 completed as a part of ISI-B21-T1 300-1, no INSTRUMENTATION NOZZLE B4.13 evidence of leakage identified.

1. N/A 305-006-106 1B13-N12B 8-E VT-2 10800-09-264 SAT VT-2 completed as a part of ISI-B21-T1300-1, no INSTRUMENTATION NOZZLE B4.13 evidence of leakage identified.
1. N/A 305-006-106 1813-N12C B-E VT-2 10800-09-265 SAT VT-2 completed as a part of ISI-B21-T1300-1, no INSTRUMENTATION NOZZLE B4.13 evidence of leakage identified.
1. N/A 305-006-106 1B13-N12D B-E VT-2 1Q800-09-266 SAT VT-2 completed as a part of ISI-B21-T1300-1, no INSTRUMENTATION NOZZLE B4.13 evidence of leakage identified.

1" N/A 305-006-106 1B13-N13A B-E VT-2 1Q800-09267 SAT VT-2 completed as a part of ISI-B21-T1 300-1, no INSTRUMENTATION NOZZLE B4.13 evidence of leakage identified.

1. N/A 305-006-106 1B13-N13B B-E VT-2 10800-09-268 SAT VT-2 completed as a part of ISI-B21-T1300-1, no INSTRUMENTATION NOZZLE B4.13 evidence of leakage identified.
1. N/A 305-006-106 1B13-N13C B-E VT-2 1Q800-09-269 SAT VT-2 completed as a part of ISI-B21-T1300-1, no INSTRUMENTATION NOZZLE B4.13 evidence of leakage identified.
1. N/A 305-006-106 1B13-N13D B-E VT-2 1Q800-09-270 SAT VT-2 completed as a part of ISI-B21-T1300-1, no INSTRUMENTATION NOZZLE 134,13 evidence of leakage identified.

1" N/A 305-006-106 1B13-N14A B-E VT-2 1Q800-09-271 SAT VT-2 completed as a part of ISI-B21-T1300-1, no INSTRUMENTATION NOZZLE B4.13 evidence of leakage identified.

1. N/A 305-006-106 Wednesday, July 08, 2009 Page 3 of 40 25

REPORT NO. P0059-012 ASME IDof Component Examined Category Description of Component ASME Exam Size - Sched. - IS!Dwg. No. Item No. Method Exam Report No. Status Remarks 1B13-N 146 1B13-N14B B-E VT-2 1Q800-09-272 SAT VT-2 completed as a part of ISI-B21-T1 300-1, no INSTRUMENTATION NOZZLE B4.13 evidence of leakage identified. 1V N/A 305-006-106 1B13-N14C B-E VT-2 1Q800-09-273 SAT VT-2 completed as a part of ISI-B21-T1300-1, no INSTRUMENTATION NOZZLE B4.13 evidence of leakage identified. I" N/A 305-006-106 1B13-N14D B-E VT-2 10800-09-274 SAT VT-2 completed as a part of ISI-B21-T1300-1, no INSTRUMENTATION NOZZLE B4.13 evidence of leakage identified.

1. N/A 305-006-106 1B13-N18-KA B-E VT-2 1Q800-09-275 SAT VT-2 completed as a part of ISI-B21-T1300-1, no LIQUID CONTROL NOZZLE B4.11 evidence of leakage identified.
  • 1" N/A 305-006-104 1B13-CRD-NZ B-E VT-2 1Q800-09-276 SAT VT-2 completed as a part of ISI-B21-T1300-1. CR 09-177 CONTROL ROD DRIVE NOZZLES B4.12 58823 was generated to document leakage identified.

N/A N/A 305-006-110 1B13-ICP-NZ B-E VT-2 1Q800-09-277 SAT VT-2 completed as a part of ISI-B21-T1300-1, no 53 INCORE INSTRUMENTATION B4.13 evidence of leakage identified. NOZZLES N/A N/A 305-006-111 1B13-CSHP-P1 X-A EVT1 1Q800-09-040 SAT P1, Best Effort Exam, 0% EVT-1 Coverage. Minor HP CORE SPRAY THERMAL SLEEVE X3.11 Scratches and Punch Marks from Fabrication noted, TO FLOW DIVIDER WELDS (2) NRI's. PlA, 25% Coverage, Additional 15% Coverage 10' 120 305-006-113 >30<60 Degrees, NRI's. 1B13-CSHP-CW-P3a X-A EVT1 1Q800-09-038 SAT 45% Coverage, Additional 5% Coverage >30<60 HP CORE SPRAY COUPLING TO X3.10 Degrees. ScratchNoted 3 O'clock RHAZ, NRI. HORIZONTAL PIPE 6- 40 305-006-113 1B13-CSHP-CW-P5 X-A EVT1 1Q800-09-039 SAT 50% Coverage, Additional 5% Coverage >30 <60 HP CORE SPRAY UPPER RISER PIPE X3.10 Degrees. Many Scratches, NRIs. TO COUPLING 6- 40 305-006-113 1B13-CSHP-CCW-P2 X-A EVTI 1Q800-09-032 SAT 45% Coverage, Additional 5% Coverage >30<60 HP CORE SPRAY FLOW DIVIDER X3.11 Degrees for the P2 and P2A welds. No indications. REDUCER WELDS 6- 120/40 305-006-113 1B13-CSHP-CCW-P3b X-A EVT1 1Q800-09-033 SAT 45% Coverage, Additional 5% Coverage >30<60 HP CORE SPRAY HORIZONTAL PIPE X3.11 Degrees. No indications. TO COUPLING

6. 40 305-006-113 Wednesday, July 08, 2009 Page 4 of 40 26

REPORT NO. P0059--012 ASME IDof Component Examined Category Description of Component ASME Exam Size- Sched.- ISI Dwg. No. Item No. Method Exam Report No. Status Remarks 1B13-CSHP-CCW-P3a X-A EVT1 1Q800-09-030 SAT 45% Coverage, Additional 5% Coverage >30<60 HP CORE SPRAY COUPLING TO X3.10 Degrees. No indications. HORIZONTAL PIPE 6" 40 305-006-113 1B13-CSHP-CCW-P5 X-A EVT1 10800-09-036 SAT 50% Coverage, Additional 10% Coverage >30<60 HP CORE SPRAY UPPER RISER PIPE X3.10 Degrees. Draw Beads Seen Below Weld, Grinding TO COUPLING Marks, Scratches in Exam Area, NRIs. 6" 40 305-006-113 1B13-CSHP-CCW-P6 X-A EVT1 1Q800-09-037 SAT 50% Coverage, Additional 5% Coverage >30<60 HP CORE SPRAY COUPLING TO X3.11 Degrees, Draw Beads Near Weld, NRrs. LOWER RISER PIPE 6" 40 305-006-113 1B13-CSHP-CCW-P4c I. X-A EVT1 .1Q800-09-034 SAT 50% Coverage, Additional 15% Coverage >30<60 HP CORE SPRAY LOWER RISER X3.11 Degrees, Scratches and Minor Gouges inExam Area - PIPE TO ELBOW NRI's. 6' 40/120 305-006-113 1B13-CSHP-CCW-P4d X-A EVT1 1Q800-09-035 SAT 85% Coverage, Additional 5% Coverage >30<60 HP CORE SPRAY ELBOW TO X3.11 Degrees. Many Draw Beads, All Examined - NRI's. SHROUD FLANGE

  • 6" 120/40 305-006-113 1B13-CSLP-CW-P3a X-A EVT1 1Q800-09-043 SAT 45% Coverage, Additional 5% Coverage >30 <60 LP CORE SPRAY COUPLING TO X3.10 Degrees. Scratches and Stains Noted, NRIs.

HORIZONTAL PIPE 6" 40 305-006-113 1B13-CSLP-CW-P5 X-A EVT1 1Q800-09-044 SAT 50% Coverage, Additional 10% Coverage >30 <60 LP CORE SPRAY UPPER RISER PIPE X3.10 Degrees. Discolorations, Stains and Scratches Noted, TO COUPLING NRI's. 6" 40 305-006-113 1B13-CSLP-CCW-P3a X-A EVT1 1Q800-09-041 SAT 45% Coverage, Additional 10% Coverage >30 <60 LP CORE SPRAY COUPLING TO X3.10 Degrees. Scratches, Rub Marks, NRI's. HORIZONTAL PIPE 6" 40

  • 305-006-113 1B13-CSLP-CCW-PS X-A EVT1 1Q800-09-042 SAT 45% Coverage, Additional 10% Coverage >30 <60 LP CORE SPRAY UPPER RISER PIPE X3.10 Degrees. No indications.

TO COUPLING 6" 40 305-006-113 1B13-CSS-7-$2 X-A EVT1 1Q800-09-049 SAT 35% Coverage, Additional 5% Coverage >30<60 CORE SPRAY SPARGER TEE TO X3.20 Degrees for welds identified as S2-R and S2-L, no SPARGER PIPE WELDS (2) indications. 5" - 305-006-115 1B13-CSS-7-$4, SAT 45% Coverage, Additional 10% Coverage >30<60 X-A EVT1 1Q800-09-050 CORE SPRAY SPARGER PIPE TO X3.20 Degrees 090 Degree Side, 50% Coverage Additional END CAP WELDS (2) 5% Coverage >30<60 Degrees 270 Degree Side.

5. - 305-006-115 Scratches and Minor Gouges - NRI's.

Wednesday, July 08, 2009 Page 5 of 40 27

REPORT NO. P0059-012 ASME IDof Component Examined Category Description of Component ASME Exam Size - Sched. -. ISI Dwg. No. Item No. Method Exam Report No. Status Remarks 1613-CSS-7-SB 1813-CSS-7-SB X-A VT-1 1Q800-09-051 SAT SB 75%, SB-020 - 75%, S-032 75%1, SB-050 - CORE SPRAY SPARGER BRACKETS X3.22 70%, SB-069 - 75%, SB-081 - 75%, SB-280 - 75%, SB-293 - 75%, SB-311 - 75%, SB-342 - 75%. All - NRI's. N/A N/A 305-006-116 1B13-CSS-353-$2 X-A EVT1 1Q800-09-045 SAT 40% Coverage, Additional 5% Coverage >30 <60 CORE SPRAY SPARGER TEE TO X3.20 Degrees for welds identified as S2-L and S2-R. No SPARGER PIPE WELDS (2) indications. 5- - 305-006-115 1B13-CSS-353-S3ab X-A VT-1 1Q800-09-046 SAT 50% Coverage and no indications. CORE SPRAY SPARGER SPRAY X3.21 NOZZLE WELDS (2 EA NOZZ)

5. - 305-006-115 1B13-CSS-353-$4 X-A EVT1 10800-09-047 SAT 1B13-CSS-353-S4-090 (90 Degree Side) Coverage CORE SPRAY SPARGER PIPE TO X3.20 45% Additional 10% Coverage >30 <60 Degrees. 1B13-END CAP WELDS (2) Css-353-$4-270 (270 Degree Side) Coverage 60%,

5" - 305-006-115 Additional 5% Coverage >30 <60 Degrees. No indications. 1B13-CSS-353-SB X-A VT-1 1Q800-09-048 SAT SB-0 -75%, SB-020 - 75%, SB-049 70%, Movement CORE SPRAY SPARGER BRACKETS X3.22 CCW of Sparger, NRI's. SB-068 - 75%, SB-081 -55% Movement of Sparger, NRI. SB-280 - 80%, SB-292 - N/A N/A 305-006-116 75%, SB-310 - 75%, gouges, NRI. SB-329 -75% Weld Bead Overlap - NRI's. SB-341 - 75%. All - NRI's. 1B13-CSS-WA B-N-2 VT-3 1Q800-09001 SAT Exams actually performed in RFO9 under 1Q800 CORE SPRAY PIPING BRACKET B13.30 021. WELDED ATTACHMENTS N/A N/A 305-006-114 1B13-GRSB-WA B-N-2 VT-3 1Q800-09-059 SAT 100% coverage on welds WA-0 and WA-180, no GUIDE ROD SUPPORT BRACKET B13.30 indications. WELDED ATTACHMENTS N/A N/A 305-006-101 1913-UPPER-INT X-A VT-3 IQ800-09-066 SAT 100% coverage, CR 09-5541: Nas generated to VESSEL INTERIOR ABOVE FW X6.15 document no change' in crud }uild-up. SPARGERS N/A N/A 305-006-101 1913-IRM-32/29 X-A VT-3 1Q800-09-052 SAT 100% coverage, no indications. IRM INSTRUMENT DRY TUBE E X2.10 N/A N/A 305-006-117 1B13-IRM-32/37 X-A VT-3 1Q800-09-053 SAT 100% coverage, no indications. IRM INSTRUMENT DRY TUBE F X2.10 N/A - N/A 305-006-117 1B13-IRM-48/13 X-A VT-3 1Q800-09-054 SAT 100% coverage, no indications. IRM INSTRUMENT DRY TUBE G X2.10 N/A N/A 305-006-117 Wednesday, July 08, 2009 Page 6 of 40 28

REPORT NO. P0059-012 ASME IDof Component Examined Category Description of Component ASME Exam Size - Sched.- ISI Dwg. No. Item No. Method Exam Report No. Status Remarks 1B13-IRM-48/53 X-A VT-3 1Q800-09-055 SAT 100% coverage, no indications. IRM INSTRUMENT DRY TUBE H X2.10 N/A N/A 305-006-117 1B13-JPA-P3/P4 X-A VT-3 1Q800-09-080 SAT 100% coverage, no indications. JET PUMP NOZZLE TO MIXER X1.30 ASSEMBLY. N/A N/A 305-006-126 1B13-JPA-P13/P14 X-A VT-3 1Q800-09-081 SAT 100% coverage, no indications. JET PUMP NOZZLE TO MIXER X1.30 ASSEMBLY N/A N/A 305-006-126 1B13-JPHDB-P1 X-A UT 1Q800-09005 SAT 100% coverage, no relevant indications. JET PUMP 1 HOLD DOWN BEAM X1.10 N/A N/A 305-006-125 1B13-JPHDB-P2 X-A UT 1Q800-09-007 SAT 100% coverage, no relevant indicatons. JET PUMP 2 HOLD DOWN BEAM X1.10 NIA N/A 305-006-125 1B13-JPHDB-P3 X-A UT 1Q800-09-008 SAT 100% coverage, no relevant indications. JET PUMP 3 HOLD DOWN BEAM X1.10 N/A N/A 305-006-125 1B13-JPHDB-P4 X-A UT 10800-09-009 SAT 100% coverage, no relevant indications. JET PUMP 4 HOLD DOWN BEAM X1.10 N/A N/A 305-006-125 1B13-JPHDB-P5 X-A UT 1Q800-09-010 SAT 100% coverage, no relevant indications. JET PUMP 5 HOLD DOWN BEAM X1.10 N/A N/A 305-006-125 1B13-JPHDB-P7 X-A UT 1Q800-09-011 SAT 100% coverage, no relevant indications. JET PUMP 7 HOLD DOWN BEAM X1.10 N/A N/A 305-006-125 1B13-JPHDB-P8 X-A UT 1Q800-09-012 SAT 100% coverage, no relevant indications. JET PUMP 8 HOLD DOWN BEAM X1.10 N/A N/A 305-006-125 1B13-JPHDB-P9 X-A UT 1Q800-09-013 SAT 100% coverage, no relevant indications. JET PUMP 9 HOLD DOWN BEAM X1.10 N/A N/A 305-006-125 Wednesday, July 08, 2009 Page 7 of 40 29

REPORT NO. P0059-012 ASME IDof Component Examined Category Description of Component ASME Exam Size- Sched.- ISI Dwg, No. Item No. Method Exam Report No. Status Remarks 1B13-JPHDB-P10 X-A UT 1Q800-09-014 SAT 100% coverage, no relevant indications. JET PUMP 10 HOLD DOWN BEAM X1.10 N/A N/A 305-006-125 1B13-JPHDB-P11 X-A UT 1Q800-09-015 SAT 100% coverage, no relevant indications. JET PUMP 11 HOLD DOWN BEAM X1.10 N/A N/A 305-006-125 1B13-JPHDB-P12 X-A UT 1Q800-09-016 SAT 100% coverage, no relevant indications. JET PUMP 12 HOLD DOWN BEAM X1.10 N/A N/A 305-006-125 1B13-JPHDB-P13 X-A: UT 1Q800-09-017 SAT 100% coverage, no relevant indications. JET PUMP 13 HOLD DOWN BEAM X1.10 N/A N/A 305-006-125 1B13-JPHDB-P14 X-A UT 1Q800-09-018 SAT 100% coverage, no relevant indications. JET PUMP 14 HOLD DOWN BEAM X1.10 N/A N/A 305-006-125 1B13-JPHDB-P15 X-A UT 1Q800-09-019 SAT 100% coverage, no relevant indications, JET PUMP 15 HOLD DOWN BEAM X1.10 N/A N/A 305-006-125 1B13-JPHDB-P16 X-A UT 1Q800-09-020 SAT 100% coverage, no relevant indications. JET PUMP 16 HOLD DOWN BEAM X1.10 N/A NI/A 305-006-125 1B13-JPHD8-P17 X-A UT 1Q800-09-021 SAT 100% coverage, no relevant indications. JET PUMP 17 HOLD DOWN BEAM X1.10 N/A N/A 305-006-125 1813-JPHDB-P18 X-A UT 1Q800-09-022 SAT 100% coverage, no relevant indications. JET PUMP 18 HOLD DOWN BEAM X1.10 N/A N/A 305-006-125 1B13-JPHDB-P19 X-A UT 1Q800-09-023 SAT 100% coverage, no relevant indications. JET PUMP 19 HOLD DOWN BEAM X1.10 N/A N/A 305-006-125 1B13-JPHDB-P20 X-A UT 10800-09-024 SAT 100% coverage, no relevant indications. JET PUMP 20 HOLD DOWN BEAM. X1.10 N/A N/A 305-006-125 Wednesday, July 08, 2009 Page 8 of 40 30

REPORT NO. P0059-012 ASME IDof Component Examined Category Description of Component ASME Exam Size - Sched. - ISI Dwg. No. Item No. Method Exam Report No. Status Remarks 1B13-JPLAW-POI X-A VT-3 1Q800-09-068 SAT 100% coverage, no indications. JET PUMP SENSING LINE X1.20 ATTACHMENT WELDS NIA N/A 305-006-125 1B13-JPLAW-P02 X-A VT-3 1Q800-09-069 SAT 100% coverage, no indications. JET PUMP SENSING LINE X1.20 ATTACHMENT WELDS N/A N/A .305-006-125 1B13-JPLAW-P03 X-A VT-3 1Q800-09-070 SAT 100% coverage, no indications. JET PUMP SENSING LINE X!.20 ATTACHMENT WELDS N/A N/A 305-006-125 1B13-JPLAW-P04 X-A VT-3 1Q800-09-071 SAT 100% coverage, no indications. JET PUMP SENSING LINE X1.20 ATTACHMENT WELDS N/A N/A 305-006-125 1B13-JPLAW-P05 X-A VT-3 1Q800-09-072 SAT 100% coverage, no indications. JET PUMP SENSING LINE X1.20 ATTACHMENT WELDS N/A N/A 305-006-125 1B13-JPLAW-P06 X-A VT-3 1Q800-09-073 SAT 100% coverage, no indications identified however FME JET PUMP SENSING LINE X1.20 was discovered inthe area. See CR 09-55507. ATTACHMENT WELDS N/A NIA 305-006-125 1B13-JPLAW-P07 X-A VT-3 IQ800-09-074 SAT 100% coverage, no indications identified however FME JET PUMP SENSING LINE X1.20 was discovered in the area. See CR 09-55507. ATTACHMENT WELDS N/A N/A 305-006-125 1B13-JPLAW-P08 X-A VT-3 1Q800-09-075 SAT 100% coverage, no indications. JET PUMP SENSING LINE Xl.20 ATTACHMENT WELDS N/A N/A 305-006-125 1B13-JPLAW-P09 X-A VT-3 103800-09-076 SAT 100% coverage, no indications. JET PUMP SENSING LINE X1.20 ATTACHMENT WELDS N/A N/A 305-006-125 1B13-JPLAW-PlO X-A VT-3 1Q800-09-077 SAT 100% coverage, no indications. JET PUMP SENSING LINE X1.20 ATTACHMENT WELDS N/A N/A 305-006-125 IB13-JPRB-P5/P6 X-A EVT1 1Q800-09-078 SAT Examined RB-I &RB-2 b-d welds on JP05 and RB-1 & JET PUMP RISER BRACE WELDS (8) X1.40 RB-2 a-c welds on JP06 welds due to expanded scope from JP06 wedge wear and achieved 50 - 60% N/A N/A 305-006-125 coverage. No indications Wednesday, July 08, 2009 Page 9 of 40 31

REPORT NO. P0059-012 ASME IDof Component Examined Category Description of Component ASME Exam Size- Sched. - ISI Dwg. No. Item No. Method Exam Report No. Status Remarks 1B13-JPRB-P13/P14 1B13-JPRB-P13/P14 X-A EVT1 1Q800-09-079 SAT Examined RB-1 &RB-2 b-d welds on JP13 and RB-1 & JET PUMP RISER BRACE WELDS (8) X1.40 RB-2 a-c welds on JP14 welds due to expanded scope from JP13 wedge wear and achieved 50 - 60% N/A N/A 305-006-125 coverage. No indications 1B13-JPREW-PI1/P12 X-A EVT1 1Q800-09-082 SAT 80% coverage on RS-1, 40% coverage on RS-2. No JET PUMP RISER ELBOW WELDS (2) X1.70 indications. N/A N/A 305-006-126 1B13-JPREW-P13/P14 X-A EVT1 1Q800-09-083 SAT 90% coverage on RS-1, 40% coverage on RS-2. Non-JET PUMP RISER ELBOW WELDS (2) X1.70 relevant indications noted. N/A N/A 305-006-126 1B13-JPREW-P15/P16 X-A EVT1 10800-09-084 SAT 90% coverage on RS-1, 40% coverage on RS-2. Non-JET PUMP RISER ELBOW WELDS (2) X1.70 relevant indications noted. N/A N/A 305-006-126 1B13-JPRS3-P1/P2 X-A EVT1 10800-09-085 SAT 48% coverage and no indications. JET PUMP RISER PIPE TO X1.71 TRANSITION PIECE WELD N/A N/A 305-006-126 1B13-JPRS3-P3/P4 X-A EVT1 1Q800-09-086 SAT 35% coverage and no indications. JET PUMP RISER PIPE TO X1.71 TRANSITION PIECE WELD N/A N/A 305-006-126 1B13-JPRS3-P5/P6 X-A EVT1 1Q800-09-087 SAT 47% coverage and non-relevant indications noted. JET PUMP RISER PIPE TO X1.71 TRANSITION PIECE WELD N/A N/A 305-006-126 1B13-JPRS3-P7/PB X-A EVT1 10800-09-088 SAT 30% coverage and non-relevant indications noted. JET PUMP RISER PIPE TO X1.71 TRANSITION PIECE WELD N/A N/A 305-006-126 1B13-JPRS3-P9/P1O X-A EVT1 10800-09-089 SAT 30% coverage and no indications noted. JET PUMP RISER PIPE TO X1.71 TRANSITION PIECE WELD N/A N/A 305-006-126 1B13-JPRS6-P51P6 X-A EVT1 1Q800-09-090 SAT 80% coverage on the RS6/7 bracket weld on the JP06 JET PUMP RISER PIPE TO X1.72 side, examined due to main wedge wear on JP06. No RESTRAINER BRACKET WELDS (2) indications. N/A N/A 305-006-126 1B13-JPRS6-P13/P14 X-A EVT1 1Q800-09-091 SAT 70% coverage on the RS6/7 weld, JP13 side exam due JET PUMP RISER PIPE TO X1.72 to main wedge wear on JP13. Non-relevant Indications RESTRAINER BRACKET WELDS (2) noted. N/A N/A 305-006-126 Wednesday, July 08, 2009 Page 10 of 40 32

REPORT NO. P0059-012 ASME Category IDof Component Examined Description of Component ASME Exam Size - Sched. - ISI Dwg. No. Item No. Method Exam Report No. Status Remarks 1B!3-JPRS8-P5/P6 X-A EVTI 1Q800-09-092 SAT 50% coverage on RS-8 and RS-9, non-relevant JET PUMP RISER PIPE TO RISER X1.72 indications noted. Exam due to scope expansion from BRACE YOKE WELDS (2) main wedge wear on JP06. N/A N/A 305-006-125 1B13-JPRS8-P13/P14 X-A EVT1 1Q800-09-093 SAT 45% coverage on RS-8, 50% coverage on RS-9, non-JET PUMP RISER PIPE TO RISER X1.72 relevant indications noted. Exam due to scope BRACE YOKE WELDS (2) expansion from main wedge wear on JP13. NIA N/A 305-006-125 1B13-JPTW-P05 X-A VT-1 1Q800-09-094 EVAL Setscrew gaps (JPSS1) were examined on VS &SS for JET PUMP RESTRAINER ADJUSTING X1.50 JP05. Gap noted on VS, refer to CR 09-55819-01. Tack SCREW TACK WELDS welds (JPSS2)were examined VS &SS, 50 100% N/A N/A 305-006-125 coverage with no Indications. 1B13-JPTW-P06 X-A VT-1 1Q800-09-095 SAT Setscrew gaps (JPSS1) were examined on VS &SS for JET PUMP RESTRAINER ADJUSTING X1.50 JP06. No gap noted. SCREW TACK WELDS N/A N/A 305-006-125 1B13-JPTW-P13 X-A VT-1 1Q800-09-096 EVAL Setscrew gaps (JPSS1) were examined on VS &SS for JET PUMP RESTRAINER ADJUSTING X1.50 JP13, Gaps noted on both sides, refer to CR 09-55819-SCREW TACK WELDS 01. Tack welds (JPSS2) were examined VS &SS, N/A N/A 305-006-125 100% coverage with no indications. 1B13-JPTW-P14 X-A VT-1 10800-09-097 EVAL Setscrew gaps (JPSS1) were examined on VS &SS for JET PUMP RESTRAINER ADJUSTING X1.50 JP14. Gaps noted on both sides, refer to CR 09-55819-SCREW TACK WELDS 01. Tack welds (JPSS2) were examined VS &SS, N/A N/A 305-006-125 100% coverage with no indications. 1B13-JPWD-P1/P2 X-A VT-1 1Q800-09-1 00 EVAL 100% Coverage on both P01 and P02, minor rod wear JET PUMP RESTRAINER BRACKET X1.51 observed. See CR 09-55400. WEDGE BEARING SURFACE N/A N/A 305-006-125 1B13-JPWD-P3/P4 X-A VT-1 1Q800-09-101 EVAL 100% Coverage on both P03 and P04, minor rod wear JET PUMP RESTRAINER BRACKET X1.51 observed. See CR 09-55400. WEDGE BEARING SURFACE N/A N/A 305-006-125 1B13-JPWD-P5/P6 X-A VT-1 1Q800-09-098 EVAL 100% Coverage on both P05 and P06, minor rod wear JET PUMP RESTRAINER BRACKET X1.51 observed. See CR 09-55400. Wedge wear noted on WEDGE BEARING SURFACE JPWD-P06, see CR 09-54819. N/A N/A 305-006-125 1B13-JPWD-P7/P8 X-A VT-1 1Q800-09-102 EVAL 100% Coverage on both P07 and P08, minor rod wear JET PUMP RESTRAINER BRACKET X1.51 observed. See CR 09-55400. WEDGE BEARING SURFACE N/A N/A 305-006-125 1B13-JPWD-P9/P10 X-A VT-1 1Q800-09-103 EVAL 100% Coverage on both P09 and P10, minor rod wear JET PUMP RESTRAINER BRACKET Xl.51 observed. See CR 09-55400. WEDGE BEARING SURFACE N/A N/A 305-006-125 Wednesday, July 08, 2009 Page 11 of 40 33

REPORT NO. P0059-012 ASME Category IDof Component Examined Description of Component ASME Exam Size - Sched. - ISI Dwg. No. Item No. Method Exam Report No. Status Remarks 1B13-JPWD-P11/P12 X-A VT-1 1Q800-09-104 EVAL 100% Coverage on both P11 and P12, minor rod wear JET PUMP RESTRAINER BRACKET X1.51 observed. See CR 09-55400. WEDGE BEARING SURFACE N/A N/A 305-006-125 1B13-JPWD-P13/P14 X-A VT-1 1Q800-09-099 EVAL 100% Coverage on both P13 and P14, minor rod wear JET PUMP RESTRAINER BRACKET X1.51 observed. See CR 09-55400. Wedge wear noted on WEDGE BEARING SURFACE JPWD-P13, see CR 09-54819. N/A N/A 305-006-125 1B13-JPWD-P15/P16 X-A VT-i 1Q800-09-105 EVAL 100% Coverage on both P15 and P16, minor rod wear JET PUMP RESTRAINER BRACKET X1.51 observed. See CR 09-55400. WEDGE BEARING SURFACE N/A N/A 305-006-125 1B13-JPWD-P17/P18 X-A VT-1 1Q800-09-106 EVAL 100% Coverage on both P17 and P18, minorrod wear JET PUMP RESTRAINER BRACKET X1.51 observed. See CR 09-55400. WEDGE BEARING SURFACE N/A N/A 305-006-125 1B13-JPWD-P19/P20 X-A VT-1 1Q800-09-107 EVAL 100% Coverage on both P19 and P20, minor rod wear JET PUMP RESTRAINER BRACKET X1.51 observed. See CR 09-55400. WEDGE BEARING SURFACE N/A N/A 305-006-125 1B13-LPRM-SAMP X-A VT-3 1Q800-09-056 SAT LPRM-08-25, 08-33, 24-57, 32-09 and 48-49 were LPRM INSTRUMENT DRY TUBES 10% X2.11 examined, 100% coverage with no indications. SAMPLE N/A N/A 305-006-117 11B13-SD-AHI X-A VT-1 1QBOD-09-108 SAT 100% coverage, non-relevant indications noted. HOOD TO BANK HORIZ END PANEL X4.12 WELD, TOP NIA N/A 305-006-129 1B13-SD-AH2 X-A VT-1 1Q800-09-109 SAT 100% coverage, non-relevant indications noted. BANK LOWER VERT END PANEL TO X4.12 BANK BOTTOM PANEL WELD, 0 DEG N/A NIA 305-006-129 1B13-SD-AH3 X-A VT-1 1Q800-09-110 SAT 100% coverage, non-relevant indications noted. HOOD END PLATE TO UPPER X4.12 SUPPORT RING WELD, 0 DEG SIDE N/A N/A 305-006-129 1B13-SD-AH4 X-A VT-1 1Q800-09-111 SAT 100% coverage, non-relevant indications noted. HOOD TO COVER PLATE WELD X4.12 N/A N/A 305-006-129 1B13-SD-AH5 X-A VT-1 1Q800-09-112 SAT 100% coverage, non-relevant indications noted. HOOD END PLATE TO UPPER X4.12

  • SUPPORT RING WELD, 180 DEG SIDE N/A N/A 305-006-129 Wednesday, July 08, 2009 Page 12 of 40 34

REPORT NO. P0059-012 ASME IDof Component Examined Category Description of Component ASME Exam Size- Sched.- ISI Dwg. No. Item No. Method Exam Report No. Status Remarks 1B13-SD-AH6 X-A VT-1 10800-09-113 SAT 100% coverage, non-relevant indications noted. BANK LOWER VERT END PANEL TO X4.12 BANK BOTTOM PANEL WELD, 180 N/A N/A 305-006-129 1B13-SD-AHS1 X-A VT-1 10800-09-114 SAT 100% coverage, non-relevant indications noted. HOOD TO HOOD STIFFENER WELD, 0 X4.12 DEG SIDE N/A N/A 305-006-129 1B13-SD-AHS2 X-A VT-1 1Q800-09-115 SAT 100% coverage, non-relevant indications noted. HOOD TO HOOD STIFFENER WELD, X4.12 180 DEG SIDE N/A N/A 305-006-129 IB13-SD-AVI X-A VT-1 1Q800-09-116 SAT 100% coverage, non-relevant indications noted. BANK VERT END PANELS TO X4.12 OUTLET PLENUM END PANEL WELD, N/A N/A 305-006-129 1B13-SD-AV2 X-A VT-1 1Q800-09-117 SAT 100% coverage, non-relevant indications noted. BANK VERT END PANELS TO HOOD X4.12 END PLATE WELD, 0 DEG SIDE N/A N/A 305-006-129 1B13-SD-AV3 X-A VT-1 1Q800-09-118 SAT 100% coverage, non-relevant indications noted. HOOD TO HOOD END PLATE WELD, 0 X4.12 DEG SIDE N/A N/A 305-006-129 1B13-SD-AV4 X-A VT-1 1Q800-09-119 SAT 100% coverage, non-relevant indications noted. HOOD TO HOOD END PLATE WELD, X4.12 180 DEG SIDE NýA N/A 305-006-129 1B13-SD-AV5 X-A VT-1 10800-09-120 SAT 100% coverage, non-relevant indications noted. BANK VERT END PANELS TO HOOD X4.12 END PLATE WELD, 180 DEG SIDE N/A N/A 305-006-129 1B13-SD-AV6 X-A VT-1 1Q800-09-121 SAT 100% coverage, non-relevant indications noted. BANK VERT END PANELS TO X4.12 OUTLET PLENUM END PANEL WELD, N/A N/A 305-006-129 1B13-SD-BH3 X-A VT-1 1Q800-09-122 SAT 100% coverage, non-relevant indications noted. HOOD END PLATE TO UPPER X4.12 SUPPORT RING WELD, 0 DEG SIDE N/A N/A 305-006-129 1B13-SD-BH5 X-A VT-1 1Q800-09-123 SAT 100% coverage, non-relevant indications noted. HOOD END PLATE TO UPPER X4.12 SUPPORT RING WELD, 180 DEG SIDE N/A N/A 305-006-129 Wednesday, July 08, 2009 Page 13 of 40 35

REPORT NO. P0059-012 ASME IDof Component Examined Category Description of Component ASME Exam Size - Sched.. ISI Dwg. No. Item No. Method Exam Report No. Status Remarks 1B13-SD-BV2 X-A VT-1 1Q800-09-124 SAT 100% coverage, non-relevant indications noted. BANK VERT END PANELS TO HOOD X4.12 END PLATE WELD, 0 DEG SIDE N/A N/A 305-006-129 1B13-SD-BV3 X-A VT-1 1Q800-09-125 SAT 100% coverage, non-relevant indications noted. HOOD TO HOOD END PLATE WELD, 0 X4.12 DEG SIDE N/A N/A 305-006-129 1B13-SD-BV6 X-A VT-1 1Q800-09-126 SAT 100% coverage, non-relevant Indications noted. HOOD TO HOOD END PLATE WELD, X4.12 180 DEG SIDE N/A N/A 305-006-129 1B13-SD-BV7 X-A VT-1 1Q800-09-127 SAT 100% coverage, non-relevant indications noted. BANK VERT END PANELS TO HOOD X4.12 END PLATE WELD, 180 DEG SIDE N/A N/A 305-006-129 1B13-SD-CH3 X-A VT-1 1Q800-09-128 SAT 100% coverage, non-relevant indications noted. HOOD END PLATE TO UPPER X4.12 SUPPORT RING WELD, 0 DEG SIDE N/A N/A 305-006-129 1B13-SD-CH5 X-A VT-1 IQ800-09-129 SAT 100% coverage, non-relevant indications noted. HOOD END PLATE TO UPPER X4.12 SUPPORT RING WELD, 180 DEG SIDE N/A NIA 305-006-129 1B13-SD-CV2 X-A VT-1 1Q800-09-130 SAT 100% coverage, non-relevant indications noted. BANK VERT END PANELS TO HOOD X4.12 END PLATE WELD, 0 DEG SIDE N/A N/A 305-006-129 1B13-SD-CV3 X-A VT-1 1Q800-09-131 SAT 100% coverage, non-relevant indications noted. HOOD TO HOOD END PLATE WELD, 0 X4.12 DEG SIDE N/A N/A 305-006-129 1B13-SD-CV6 X-A VT-1 10800-09-132 SAT 100% coverage, non-relevant indications noted. HOOD TO HOOD END PLATE WELD, X4.12 180 DEG SIDE N/A N/A 305-006-129 1B13-SD-CV7 X-A VT-1 1Q800-09-133 SAT 100% coverage, non-relevant indications noted. BANK VERT END PANELS TO HOOD X4.12 END PLATE WELD, 180 DEG SIDE N/A N/A 305-006-129 1B13-SD-CP-90 X-A VT-1 1Q800-09-134 SAT 100% coverage, non-relevant indications noted. COVER PLATE TO UPPER SUPPORT X4.12 RING WELD, 90 DEG SIDE N/A N/A 305-006-128 Wednesday, July 08, 2009 Page 14 of 40 36

REPORT NO. P0059-012 ASME IDof Component Examined Category Description of Component ASME Exam Size - Sched.- ISI Dwg. No. Item No. Method Exam Report No. Status Remarks 1B13-SD-CP-270 X-A VT-1 1Q800-09-135 SAT 100% coverage, non-relevant indications noted. COVER PLATE TO UPPER SUPPORT X4.12 RING WELD, 270 DEG SIDE N/A N/A 305-006-128 1B13-SD-DC1-H X-A VT-1 1Q800-09-136 SAT 100% coverage, indications noted were captured under DRAIN CHANNEL 1 TO UPPER X4.12 the Upper Support Ring (1B13-SD-USR) exam point. SUPPORT RING HORIZ WELD N/A N/A 305-006-128 1B13-SD-DC2-H X-A VT-1 1Q800-09-137 SAT 100% coverage, indications noted were captured under DRAIN CHANNEL 2 TO UPPER X4.12 the Upper Support Ring (lBt3-SD-USR) exam point SUPPORT RING HORIZ WELD N/A N/A 305-006-128 1B13-SD-DC3-H X-A VT-1 1Q800-09-138 SAT 100% coverage, indications noted were captured under DRAIN CHANNEL 3 TO UPPER X4.12 the Upper Support Ring (1B13-SD-USR) exam point SUPPORT RING HORIZ WELD N/A N/A 305-006-128 1B13-SD-DC4-H X-A VT-1 1Q800-09-139 SAT 100% coverage, non-relevant indications noted. DRAIN CHANNEL 4 TO UPPER X4.12 SUPPORT RING HORIZ WELD N/A N/A 305-006-128 1B13-SD-DC5-H X-A VT-1 1Q800-09-140 SAT 100% coverage, indications noted were captured under DRAIN CHANNEL 5 TO UPPER X4.12 the Upper Support Ring (1B 13-SD-USR) exam point SUPPORT RING HORIZ WELD N/A N/A 305-006-128 1B13-SD-DC6-H X-A VT-1 1Q800-09-141 SAT 100% coverage, non-relevant indications noted. DRAIN CHANNEL 6 TO UPPER X4.12 SUPPORT RING HORIZ WELD N/A N/A 305-006-128 1B13-SD-DC7-H X-A VT-1 1Q800-09-142 SAT 95% coverage, non-relevant indications noted. DRAIN CHANNEL 7 TO UPPER. X4.12 SUPPORT RING HORIZ WELD N/A N/A 305-006-128 1B13-SD-DC8-H X-A VT-1 1Q800-09-143 SAT 100% coverage, non-relevant indications noted. DRAIN CHANNEL 8 TO UPPER X4.12 SUPPORT RING HORIZ WELD N/A N/A 305-006-128 1B13-SD-DC-V1 X-A VT-I 1Q800-09-144 SAT 100% coverage, non-relevant indications noted. FIRST VERTICAL WELD OF DRAIN X4.12 CHANNEL 1 N/A N/A 305-006-128 1B13-SD-DC-V2 X-A VT-1 1Q800-09-145 SAT 100% coverage, non-relevant indications noted. SECOND VERTICAL WELD OF DRAIN X4,12 CHANNEL 1 N/A N/A 305-006-128 Wednesday, July 08,2009 Page 15 of 40 37

REPORT NO. P0059-012 ASME IDof Component Examined Category Description of Component ASME Exam Size - Sched. - ISI Dwg. No. Item No. Method Exam Report No. Status Remarks 1813-SD-DC-V3 X-A VT-1 10800-09-146 SAT 100% coverage, non-relevant indications noted. FIRST VERTICAL WELD OF DRAIN X4.12 CHANNEL 2 N/A N/A 305-006-128 1B13-SD-DC-V4 X-A VT-i 1Q800-09-147 SAT 100% coverage, non-relevant indications noted. SECOND VERTICAL WELD OF DRAIN X4.12 CHANNEL 2 N/A N/A 305-006-128 1B13-SD-DC-V5 X-A VT-1 IQ800-09-148 SAT 100% coverage, non-relevant indications noted. FIRST VERTICAL WELD OF DRAIN X4.12 CHANNEL 3 N/A N/A 305-006-128 1B13-SD-DC-V6 X-A VT-i 1Q800-09-149 SAT 100% coverage, non-relevant indications noted. SECOND VERTICAL WELD OF DRAIN X4.12 CHANNEL 3 N/A N/A 305-006-128 1B13-SD-DC-V7 X-A VT-1 1Q800-09-150 SAT 100% coverage, non-relevant indications noted. FIRST VERTICAL WELD OF DRAIN X4.12 CHANNEL 4 N/A N/A 305-006-128 1B13-SD-DC-V8 X-A VT-1 1Q800-09-151 SAT 100% coverage, non-relevant indications noted. SECOND VERTICAL WELD OF DRAIN X4.12 CHANNEL 4 N/A N/A 305-006-128 1B13-SD-DC-V9 X-A VT-1 1Q800-09-152 SAT 100% coverage, non-relevant indications noted. FIRST VERTICAL WELD OF DRAIN X4.12 CHANNEL5 N/A N/A 305-006-128 1B13-SD-DC-V10 X-A VT-1 1Q800-09-153 SAT 100% coverage, non-relevant indications noted. SECOND VERTICAL WELD OF DRAIN X4.12 CHANNEL5 N/A N/A 305-006-128 1B13-SD-DC-V11 X-A VT-1 1Q800-09-154 SAT 100% coverage, non-relevant indications noted. FIRST VERTICAL WELD OF DRAIN X4.12 CHANNEL 6 N/A N/A 305-006-128 1B13-SD-DC-V12 X-A VT-1 1Q800-09-155 SAT 100% coverage, non-relevant indications noted. SECOND VERTICAL WELD OF DRAIN X4.12 CHANNEL 6 N/A N/A 305-006-128 1B13-SD-DC-V13 X-A VT-1 10800-09-156 SAT 100% coverage, non-relevant indications noted. FIRST VERTICAL WELD OF DRAIN X4.12 CHANNEL 7 N/A N/A 305-006-128 Wednesday, July 08, 2009 Page 16 of 40 38

REPORT NO. P0059-012 ASME IDof Component Examined Category Description of Component ASME Exam Size- Sched.- ISI Dwg. No. Item No. Method Exam Report No. Status Remarks 1B13-SD-DC-V14 X-A VT-1 1Q800-09-157 SAT 100% coverage, non-relevant indications noted. SECOND VERTICAL WELD OF DRAIN X4.12 CHANNEL7 N/A N/A 305-006-128 1B13-SD-DC-V15 X-A VT-1 1Q800-09-158 SAT 100% coverage, non-relevant indications noted. FIRST VERTICAL WELD OF DRAIN X4.12 CHANNEL8 N/A N/A 305-006-128 1B13-SD-DC-V16 X-A VT-I 1Q800-09-159 SAT 100% coverage, non-relevant indications noted. SECOND VERTICAL WELD OF DRAIN X4.12 CHANNEL 8 N/A N/A 305-006-128 1B13-SD-DH3 X-A VT-1 10800-09-160 SAT 100% coverage, non-relevant indications noted. HOOD END PLATE TO UPPER X4.12 SUPPORT RING WELD, 0 DEG SIDE N/A N/A 305-006-129 IB13-SD-DH5 X-A VT-1 1Q800-09-161 SAT 100% coverage, non-relevant indications noted. HOOD END PLATE TO UPPER X4.12 SUPPORT RING WELD, 180 DEG SIDE NIA N/A 305-006-129 1B13-SD X-A VT-3 1Q800-09-162 SAT 100% coverage for welds DC-V01 through V16, some STEAM DRYER DRAIN CHANNELS X4.10 non-relevant indications noted. N/A N/A 305-006-119 1B13-SD-DV2 X-A VT-1 1Q800-09-163 SAT 100% coverage, non-relevant indications noted. BANK VERT END PANELS TO HOOD X4.12 END PLATE WELD, 0 DEG SIDE N/A N/A 305-006-129 1B13-SD-DV3 X-A VT-1 1Q800-09-164 SAT 100% coverage, non-relevant indications noted. HOOD TO HOOD END PLATE WELD, 0 X4.12 DEG SIDE N/A N/A 305-006-129 1B13-SD-DV6 X-A VT-1 1Q800-09-165 SAT 100% coverage, non-relevant indications noted. HOOD TO HOOD END PLATE WELD, X4.12 180 DEG SIDE N/A N/A 305-006-129 1B13-SD-DV7 X-A VT-1 1Q800-09-166 SAT 100% coverage, non-relevant indications noted. BANK VERT END PANELS TO HOOD X4.12 END PLATE WELD, 180 DEG SIDE N/A N/A 305-006-129 1B13-SD-EB-30 X-A VT-1 1Q800-09-167 SAT 75% coverage, non-relevant Indications noted. EARTHQUAKE BLOCK AT 30 DEG TO X4.12 UPPER SUPPORT RING WELDS N/A N/A 305-006-128 Wednesday, July 08, 2009 Page 17 of 40 39

REPORT NO. P0059-012 ASME IDof Component Examined Category Description of Component ASME Exam Size- Sched.- ISI Dwg. No. Item No. Method Exam Report No. Status Remarks 1B13-SD-EB-90 X-A VT-1 1Q800-09-168 SAT 95% coverage, non-relevant indications noted. EARTHQUAKE BLOCK AT 90 DEG TO X4.12 UPPER SUPPORT RING WELDS N/A N/A \ 305-006-128 1B13-SD-EB-150 X-A VT-1 1Q00-09-169 SAT 75% coverage, non-relevant indications noted. EARTHQUAKE BLOCK AT 150 DEG X4.12 TO UPPER SUPPORT RING WELDS N/A N/A 305-006-128 1B13-SD-EB-210 X-A VT-1 1Q800-09-170 SAT 100% coverage, non-relevant indications noted. EARTHQUAKE BLOCK AT 210 DEG X4.12 TO UPPER SUPPORT RING WELDS N/A N/A 305-006-128 1B13-SD-EB-270 X-A VT-1 1Q800-09-171 SAT 90% coverage, non-relevant indications noted. EARTHQUAKE BLOCK AT 270 DEG X4.12 TO UPPER SUPPORT RING WELDS N/A N/A 305-006-128 1B13-SD-EB-330 X-A VT-1 1Q800-09-172 SAT 95% coverage, non-relevant indications noted. EARTHQUAKE BLOCK AT 330 DEG X4.12 TO UPPER SUPPORT RING WELDS N/A N/A 305-006-128 1B13-SD-EH1 X-A VT-1 1Q800-09-173 SAT 100% coverage, non-relevant indications noted. HOOD TO BANK HORIZ END PANEL X4.12 WELD, TOP N/A N/A 305-006-129 1B13-SD-EH2 X-A VT-1 1Q800-09-174 SAT 100% coverage, non-relevant indications noted. BANK LOWER VERT END PANEL TO X4.12 BANK BOTTOM PANEL WELD, 0 DEG N/A N/A 305-006-129 1B13-SD-EH3 X-A VT-1 1Q800-09-175 SAT 100% coverage, non-relevant indications noted. HOOD END PLATE TO UPPER X4.12 SUPPORT RING WELD, 0 DEG SIDE N/A N/A 305-006-129 1B13-SD-EH4 X-A VT-1 1Q800-09-176 SAT 100% coverage, non-relevant indications noted. HOOD TO COVER PLATE WELD X4.12 N/A N/A 305-006-129 1B13-SD-EH5 X-A VT-1 1Q800-09-177 SAT 100% coverage, non-relevant indications noted. HOOD END PLATE TO UPPER X4.12 SUPPORT RING WELD, 180 DEG SIDE N/A N/A 305-006-129 1B13-SD-EH6 X-A VT-1 10800-09-178 SAT 100% coverage, non-relevant indications noted. BANK LOWER VERT END PANEL TO X4.12 BANK BOTTOM PANEL WELD, 180 N/A N/A 305-006-129 Wednesday, July 08, 2009 Page 18 of 40 40

REPORT NO. P0059-012 ASME IDof Component Examined Category Description of Component ASME Exam Size- Sched.- ISI Dwg. No. Item No. Method Exam Report No. Status Remarks 1B13-SD-EHS1 X-A VT-1 10800-09-179 SAT 100% coverage, non-relevant indications noted. HOOD TO HOOD STIFFENER WELD, 0 X4.12 DEG SIDE N/A N/A 305-006-129 1B13-SD-EHS2 X-A VT-1 1Q800-09-180 SAT 100% coverage, non-relevant indications noted. HOOD TO HOOD STIFFENER WELD, X4.12 180 DEG SIDE N/A N/A 305-006-129 1B13-SD-EV1 X-A VT-1 10800-09-181 SAT 100% coverage, non-relevant indications noted. BANK VERT END PANELS TO X4.12 OUTLET PLENUM END PANEL WELD, N/A N/A 305-006-129 1B13-SD-EV2 X-A VT-1 10800-09-182 SAT 100% coverage, non-relevant indications noted. BANK VERT END PANELS TO HOOD X4.12 END PLATE WELD, 0 DEG SIDE NIA N/A 305-006-129 1B13-SD-EV3 X-A VT-1 1Q800-09-183 SAT 100% coverage, non-relevant indications noted. HOOD TO HOOD END PLATE WELD, 0 X4.12 DEG SIDE N/A NIA 305-006-129 1B13-SD-EV4 X-A VT-1 1Q800-09-184 SAT 100% coverage, non-relevant indications noted. HOOD TO HOOD END PLATE WELD, X4.12 180 DEG SIDE N/A N/A 305-006-129 1B13-SD-EV5 X-A VT-1 1Q800-09-185 SAT 100% coverage, non-relevant indications noted. BANK VERT END PANELS TO HOOD X4.12 END PLATE WELD, 180 DEG SIDE N/A N/A 305-006-129 1B13-SD-EV6 X-A VT-1 1Q800-09-186 SAT 100% coverage, non-relevant indications noted. BANK VERT END PANELS TO X4.12 OUTLET PLENUM END PANEL WELD, N/A N/A 305-006-129 1B13-SD-HDA-S X-A VT-1 1Q800-09-187 SAT 100% coverage, non-relevant indications noted. 'A' HOLD-DOWN STUD X4.12 N/A N/A 305-006-128 1B13-SD-HDB-S X-A VT-1 1Q800-09-188 SAT 100% coverage, non-relevant indications noted. 'B'HOLD-DOWN STUD X4.12 N/A N/A 305-006-128 1B13-SD-LA1 X-A VT-1 1Q800-09-189 SAT 80% coverage, non-relevant indications noted. UFTING ROD TO UPPER SUPPORT X4.12 RING WELD N/A N/A 305-006-130 Wednesday, July 08,2009 Page 19 of 40 41

REPORT NO. P0059-012 ASME IDof Component Examined Category Description of Component ASME Exam Size - Sched.- ISI Dwg. No. Item No. Method Exam Report No. Status Remarks 1B13-SD-LA2a X-A VT-1 10800-09-190 SAT 100% coverage, non-relevant indications noted. LOWER BRACE TO BANK A END X4.12 PANEL WELD, TOP &BOTTOM N/A N/A 305-006-130 1B13-SD-LA2b X-A VT-1 1Q000-09-191 SAT 80% coverage, non-relevant indications noted. LOWER BRACE PLATE TO PLATE X4.12 WELD, TOP &BOTTOM N/A N/A 305-006-130 1B13-SD-LA3a X-A VT-1 IQ800-09-192 SAT 100% coverage, non-relevant indications noted. UPPER BRACE TO BANK A END X4.12 PANEL WELD, TOP & BOTTOM N/A N/A 305-006-130 1B13-SD-LA3b X-A VT-i . 1Q800-09-193 SAT 90% coverage, non-relevant indications noted. UPPER BRACE PLATE TO PLATE X4.12 WELD, TOP &BOTTOM N/A N/A 305-006-130 1B13-SD-LA4 X-A VT-1 1Q800-09-194 EVAL 100% coverage, relevant indication on the 90' side tack LIFTING ROD TO LIFTING EYE X4.12 weld. Refer to CR 09-54923. BARREL TACK WELDS N/A N/A 305-006-130 1B13-SD-LA5S X-A VT-1 1Q800-09-195 SAT 100% coverage, non-relevant indications noted. LIFTING ROD EYE BARREL TO X4.12 LIFTING EYE WELDS, BOTH SIDES N/A N/A 305-006-130 1B13-SD-STRUCT X-A VT-3 1Q800-09-221 SAT 95% coverage on the 90° &2700 sides, non-relevant STEAM DRYER STRUCTURAL X4.11 indications noted. N/A NIA 305-006-119 1B13-SD-LB1 X-A VT-1 1Q800-09-196 SAT 85% coverage, non-relevant indications noted. LIFTING ROD TO UPPER SUPPORT X4.12 RING WELD N/A N/A 305-006-130 1B13-SD-LB2a X-A VT-1 1Q800-09-197 SAT 100% coverage, non-relevant indications noted. LOWER BRACE TO BANK AEND X4.12 PANEL WELD, TOP &BOTTOM N/A N/A 305-006-130 1B13-SD-LB2b X-A VT-1 1Q800-09-198 SAT 80% coverage, non-relevant indications noted. LOWER BRACE PLATE TO PLATE, X4.12 WELD, TOP &BOTTOM N/A N/A 305-006-130 1B13-SD-LB3a X-A VT-I 1Q800-09-199 EVAL 100% coverage, relevant indication on the 900 side of UPPER BRACE TO BANK AEND X4.12 the weld. Refer to CR 09-54661. PANEL WELD, TOP &BOTTOM N/A NIA 305-006-130 Wednesday, July 08, 2009 Page 20 of 40 42

REPORT NO. P0059-012 ASME IDof Component Examined Category Description of Component ASME Exam Size - Sched. - ISI Dwg. No. Item No. Method Exam Report No. Status Remarks 1B13-SD-LB3b X-A VT-1 1Q800-09-200 SAT 100% coverage, non-relevant indications noted. UPPER BRACE PLATE TO PLATE X4.12 WELD, TOP & BOTTOM N/A N/A 305-006-130 1B13-SD-LB4 X-A VT-1 1Q800-09-201 SAT 100% coverage, non-relevant indications noted. LIFTING ROD TO LIFTING EYE X4.12 BARREL TACK WELDS N/A N/A 305-006-130 1B13-SD-LB5 X-A VT-1 1Q800-09-202 SAT 100% coverage, non-relevant indications noted. LIFTING ROD EYE BARREL TO X4.12 LIFTING EYE WELDS, BOTH SIDES N/A N/A 305-006-130 1B13-SD-LCI X-A VT-1 1Q800-09-203 SAT 100% coverage, non-relevant indications noted. LIFTING ROD TO UPPER SUPPORT X4.12 RING WELD N/A N/A 305-006-130 1B13-SD-LC2a X-A VT-1 1Q800-09-204 SAT 100% coverage, non-relevant indications noted. LOWER BRACE TO BANK AEND X4.12 PANEL WELD, TOP &BOTTOM N/A N/A 305-006-130 1B13-SD-LC2b X-A VT-1 10800-09-205 SAT 100% coverage, non-relevant indications noted. LOWER BRACE PLATE TO PLATE X4.12 WELD, TOP &BOTTOM NIA N/A 305-006-130 1B13-SD-LC3a X-A VT-1 1Q800-09-206 SAT 100% coverage, non-relevant indications noted. UPPER BRACE TO BANK AEND X4.12 PANEL WELD, TOP &BOTTOM N/A N/A 305-006-130 1B13-SD-LC3b X-A VT-i 1Q800-09-207 SAT 100% coverage, non-relevant indications noted. UPPER BRACE PLATE TO PLATE X4.12 WELD, TOP &BOTTOM N/A N/A 305-006-130 1B13-SD-LC4 X-A VT-1 1Q800-09-208 SAT 100% coverage, non-relevant indications noted. LIFTING ROD TO LIFTING EYE X4.12 BARREL TACK WELDS N/A N/A 305-006-130 1B13-SD-LC5 X-A VT-1 1Q800-09-209 SAT 100% coverage, non-relevant indications noted. LIFTING ROD EYE BARREL TO X4.12 LIFTING EYE WELDS, BOTH SIDES N/A N/A 305-006-130 1B13-SD-LDI X-A VT-1 1Q800-09-210 SAT 95% coverage, non-relevant indications noted. LIFTING ROD TO UPPER SUPPORT X4.12 RING WELD N/A N/A 305-006-130 Wednesday, July 08, 2009 Page 21 of 40 43

REPORT NO. P0059-012 ASME IDof Component Examined Category Description of Component ASME Exam Size - Sched. - ISI Dwg. No. Item No. Method Exam Report No. Status Remarks 1B13-SD-LD2a X-A VT-1 1Q800-09-211 SAT 80% coverage, non-relevant indications noted. LOWER BRACE TO BANK AEND X4.12 PANEL WELD, TOP &BOTTOM N/A N/A 305-006-130 1B13-SD-LD2b X-A VT-1 1Q800-09-212 SAT 80% coverage, non-relevant indications noted. LOWER BRACE PLATE TO PLATE X4.12 WELD, TOP &BOTTOM N/A N/A 305-006-130 1B13-SD-LD3a X-A VT-1 1Q800-09-213 SAT 100% coverage, non-relevant indications noted. UPPER BRACE TO BANK AEND X4.12 PANEL WELD, TOP & BOTTOM N/A N/A 305-006-130 1813-SD-LD3b X-A VT'-I 1Q800-09-214 SAT 80% coverage, non-relevant indications noted. UPPER BRACE PLATE TO PLATE X4.12 WELD, TOP &BO'TOM N/A N/A 305-006-130 1B13-SD-LD4 X-A VT-1 1Q800-09-215 EVAL 100% coverage, relevant indications on both tack welds. LIFTING ROD TO LIFTING EYE X4.12 Refer to CR 09-54923. BARREL TACK WELDS N/A N/A 305-006-130 1B13-SD-LD5 X-A VT-1 1Q800-09-216 SAT 100% coverage, non-relevant indications noted. LIFTING ROD EYE BARREL TO X4.12 LIFTING EYE WELDS, BOTH SIDES N/A N/A 305-006-130 1B13-SD-LG-0 X-A VT-i IQ800-09-217 SAT 100% coverage, non-relevant indications noted. LOWER GUIDE TO LOWER SUPPORT X4.12 RING WELDS, 0 DEG SIDE N/A N/A 305-006-128 1B13-SD-LG-180 X-A VT-1 1Q800-09-218 EVAL 100% coverage, relevant indication from bent guide LOWER GUIDE TO LOWER SUPPORT X4.12 bracket Refer to CR 09-54923. RING WELDS, 180 DEG SIDE N/A N/A 305-006-128 1B13-SD-MC X-A VT-1 1Q800-09-219 SAT 100% coverage, non-relevant indications noted. MANWAY COVER WELD, 270 DEG X4.12 SIDE N/A N/A 305-006-128 1B13-SD-TB1 X-A VT-1 1Q800-09-220 SAT 100% coverage, non-relevant indications noted. TIE BAR I AND ITS BANK X4.12 ATTACHMENT WELDS N/A N/A 305-006-128 IB13-SD-TB2 X-A VT-1 1Q800-09-222 SAT 100% coverage, non-relevant indications noted. TIE BAR 2 AND ITS BANK X4.12 ATTACHMENT WELDS N/A N/A 305-006-128 Wednesday, July 08,2009 Page 22 of 40 44

REPORT NO. P0059-012 ASME Category IDof Component Examined Description of Component ASME Exam Size - Sched. - ISI Dwg. No. Item No. Method Exam Report No. Status Remarks 1B13-SD-TB3 X-A VT-1 1Q800-09-223 SAT 100% coverage, non-relevant indications noted. TIE BAR 3 AND ITS BANK X4.12 ATTACHMENT WELDS N/A N/A 305-006-128 1B13-SD-TB4 X-A VT-1 1Q800-09-224 SAT 100% coverage, non-relevant indications noted. TIE BAR 4 AND ITS BANK X4.12 ATTACHMENT WELDS N/A N/A 305-006-128 1B13-SD-TB5 X-A VT-1 1Q800-09-225 SAT 100% coverage, non-relevant indications noted. TIE BAR 5 AND ITS BANK X4.12 ATTACHMENT WELDS N/A N/A 305-006-128 1B13-SD-TB6 X-A VT-1 1Q800-09-226 SAT 100% coverage, non-relevant indications noted. TIE BAR 6 AND ITS BANK X4.12 ATTACHMENT WELDS N/A N/A 305-006-128 1B13-SD-TB7 X-A VT-1 1Q800-09-227 SAT 100% coverage, non-relevant indications noted. TIE BAR 7 AND ITS BANK X4.12 ATTACHMENT WELDS N/A N/A 305-006-128 1B13-SD-TB8 X-A VT-1 1Q800-09-228 SAT 100% coverage, non-relevant indications noted. TIE BAR 8 AND ITS BANK X4.12 ATTACHMENT WELDS N/A N/A 305-006-128 IB13-SD-TB9 X-A VT-1 1Q800-09-229 SAT 100% coverage, non-relevant indications noted. TIE BAR 9 AND ITS BANK X4.12 ATTACHMENT WELDS NIA N/A 305-006-128 1813-SD-TBIO X-A VT-1 1Q800-09-230 SAT 100% coverage, non-reevant indications noted. TIE BAR 10 AND ITS BANK X4.12 ATTACHMENT WELDS NIA N/A 305-006-128 1B13-SD-TBl1 X-A VT-1 1Q800-09-231 SAT 100% coverage, non-relevant indications noted. TIE BAR 11 AND ITS BANK X4.12 ATTACHMENT WELDS N/A N/A 305-006-1.28 1B13-SD-TB12 X-A VT-1 1Q800-09-232 SAT 100% coverage, non-relevant indications noted. TIE BAR 12 AND ITS BANK X4.12 ATTACHMENT WELDS N/A N/A 305-006-128 1813-SD-TB13 X-A VT-1 1Q800-09-233 SAT 100% coverage, non-relevant indications noted. TIE BAR 13 AND ITS BANK X4.12 ATTACHMENT WELDS N/A N/A 305-006-128 Wednesday, July 08,2009 Page 23 of 40 45

REPORT NO. P0059-012 ASME IDof Component Examined Category Description'of Component ASME Exam Size- Sched. - ISI Dwg. No. Item No. Method Exam Report No. Status Remarks 1B13-SD-TB14 X-A VT-1 1Q800-09-234 SAT 100% coverage, non-relevant indications noted. TIE BAR 14 AND ITS BANK X4.12 ATTACHMENT WELDS N/A N/A 305-006-128 1B13-SD-TB15 X-A VT-1 1Q800-09-235 SAT 100% coverage, non-relevant indications noted. TIE BAR 15 AND ITS BANK X4.12 ATTACHMENT WELDS N/A N/A 305-006-128 1B13-SD-TB16 X-A VT-1 1Q800-09-236 SAT 100% coverage, non-relevant indications noted. TIE BAR 16 AND ITS BANK X4.12 ATTACHMENT WELDS N/A N/A 305-006-128 1B13-SD-TB17 X-A VT-i 1Q800-09-237 SAT 100% coverage, non-relevant indications noted. TIE BAR 17 AND ITS BANK X4.12 ATTACHMENT WELDS NIA N/A 305-006-128 1B13-SD-TB18 X-A VT-i 1Q800-09-238 SAT 100% coverage, non-relevant indications noted. TIE BAR 18 AND ITS BANK X4.12 ATTACHMENT WELDS NIA N/A 305-006-128 1B13-SD-TB19 X-A VT-I 1Q800-09-239 SAT 100% coverage, non-relevant indications noted. TIE BAR 19 AND ITS BANK X4.12 ATTACHMENT WELDS N/A N/A 305-006-128 1B13-SD-TB20 X-A VT-1 1Q800-09-240 SAT 100% coverage, non-relevant indications noted. TIE BAR 20 AND ITS BANK X4.12 ATTACHMENT WELDS N/A N/A 305-006-128 1B13-SD-TB21 X-A VT-1 1Q800-09-241 SAT 100% coverage, non-relevant Indications noted. TIE BAR 21 AND ITS BANK X4.12 ATTACHMENT WELDS N/A N/A 305-006-128 1B13-SD-TB22 X-A VT-1 1Q800-09-242 SAT 100% coverage, non-relevant indications noted. TIE BAR 22 AND ITS BANK X4.12 ATTACHMENT WELDS N/A N/A 305-006-128 1B13-SD-TB23 X-A VT-I 1Q800-09-243 SAT 100% coverage, non-relevant indications noted. TIE BAR 23 AND ITS BANK X4.12 ATTACHMENT WELDS N/A N/A 305-006-128 1B13-SD-TB24 X-A VT-1 1Q800-09-244 SAT 100% coverage, non-relevant indications noted. TIE BAR 24 AND ITS BANK X4.12 ATTACHMENT WELDS N/A N/A 305-006-128 Wednesday, July 08, 2009 Page 24 of 40 46

REPORT NO. P0059-012 ASME IDof Component Examined Category Description of Component ASME Exam Size- Sched. - IS Dwg. No. Item No. Method Exam Report No. Status Remarks 1B13-SD-TB25 X-A VT-1 1Q800-09-245 SAT 100% coverage, non-relevant indications noted. TIE BAR 25 AND ITS BANK X4.12 ATTACHMENT WELDS N/A N/A 305-006-128 1B13-SD-TB26 X-A VT-1 1Q800-09-246 SAT 100% coverage, non-relevant indications noted. TIE BAR 26 AND ITS BANK X4.12 ATTACHMENT WELDS N/A N/A 305-006-128 1B13-SD-TB27 X-A VT-1 1Q800-09-247 SAT 100% coverage, non-relevant indications noted. TIE BAR 27 AND ITS BANK X4.12 ATTACHMENT WELDS NIA N/A 305-006-128 1813-SD-TB28 X-A VT-1 1Q800-09-248 SAT 100% coverage, non-relevant indications noted. TIE BAR 28 AND ITS BANK X4.12 ATTACHMENT WELDS N/A N/A 305-006-128 1B13-SD-TB29 X-A VT-1 10800-09-249 SAT 100% coverage, non-relevant indications noted. TIE BAR 29 AND ITS BANK X4.12 ATTACHMENT WELDS N/A N/A 305-006-128 1B13-SD-TB30 X-A VT-1 1Q800-09-250 SAT 100% coverage, non-relevant indications noted. TIE BAR 30 AND ITS BANK X4.12 ATTACHMENT WELDS NIA N/A 305-006-128 1B13-SD-TB31 X-A VT-1 1Q800-09-251 SAT 100% coverage, non-relevant indications noted. TIE BAR 31 AND ITS BANK X4.12

  • ATTACHMENT WELDS N/A N/A 305-006-128 1B13-SD-TB32 X-A VT-1 10800-09-252 SAT 100% coverage, non-relevant indications noted.

TIE BAR 32 AND ITS BANK X4.12. ATTACHMENT WELDS N/A N/A 305-006-128 1B13-SD-USR X-A VT-1 1Q800-09-253 EVAL 100% coverage. CR 09-55345 generated for minor axial UPPER SUPPORT RING ACCESSIBLE X4.12 and circumferential indications. SURFACES, INCL RING TO SKIRT N/A N/A 305-006-128 1B13-SHSAM X-A VT-3 1Q800-09-067 EVAL 100% coverage, relevant indications and wear were SHROUD HEAD STUD ASY MOD X6.14 noted and SHSAM #2 &8 were modified via ECP 06-LOCKING PINS 0021. Refer to CR 09-55364. N/A N/A 305-006-119 1B13-SRM-16/21 X-A VT-3 1Q800-09-057 SAT 100% coverage, non-relevant indications noted. SRM INSTRUMENT DRY TUBE B X2.10 N/A N/A 305-006-117 Wednesday, July 08, 2009 Page 25 of 40 47

REPORT NO. P0059-012 ASME IDof Component Examined Category Description of Component ASME Exam Size - Sched. - ISI Dwg. No. Item No. Method Exam Report No. Status Remarks 1B13-SRM-40/45 IB13-SRM-40/45 X-A VT-3 10800-09-058 SAT 100% coverage, non-relevant indications noted. SRM INSTRUMENT DRY TUBE D X2.10 N/A N/A 305-006-117 1B13-SSH-1 X-A VT-3 IQ800-09-060 SAT 100% coverage, non-relevant indications noted. SURVEILLANCE SAMPLE -X6.10 HOLDER/SPECIMEN NIA N/A 305-006-127 181 3-SSH-2 X-A VT-3 1QB00-09-061 SAT 100% coverage, relevant indication on a bent bail SURVEILLANCE SAMPLE X6.10 handle was noted. Refer to CR 09-55513. HOLDER/SPECIMEN N/A N/A 305-006-127 1B13-SSH-3 X-A VT-3 IQB00-09-062 SAT 100% coverage, non-relevant indications noted. SURVEILLANCE SAMPLE X6.10 HOLDER/SPECIMEN NIA N/A 305-006-127 11B13-SSH-WA-1 B-N-2 VT-1 1Q800-09-063 SAT 85% coverage, non-relevant indications noted. SAMPLE HOLDER, WELDED B13.20 ATTACHMENT NIA N/A 305-006-127 1B13-SSH-WA-2 B-N-2 VT-1 1Q800-09-064 SAT 100% coverage, non-relevant indications noted. SAMPLE HOLDER, WELDED B13.20 ATTACHMENT N/A N/A 305-006-127 1B13-SSH-WA-3 B-N-2 VT-1 1Q800-09-065 SAT 100% coverage, non-relevant indications noted. SAMPLE HOLDER, WELDED B13,20 ATTACHMENT N/A N/A 305-006-127 1B21-F0041A-IS B-M-2 VT-3 1Q800-09-258 SAT As-found exam of SRV that is being replaced in RFO12. SRV, INTERNAL SURFACE B12.50 (GROUPING NUMBER I) 10" N/A 305-605-101 1B21-F041A-B B-G-2 VT-1 1Q800-09-257 SAT Examined 12 studs upon removal of existing SRV, 10 SRV BOLTING, 12 EACH B7.50 were cut to facilitate removal. 10" NIA 305-605-101 1B21-G101D F-A VT-3 1042-09-044 SAT None RIGID GUIDE (WA) MPL 1B21G7033 F1.G 26" N/A 305-605-104 1B21-H0074 F-A VT-3 VT-09-0778 SAT None MECHANICAL SNUBBER F3.SN (WA)(TANDEM) 12" N/A 305-605-116 Wednesday, July 08, 2009 Page 26 of 40 48

REPORT NO. P0059-012 ASME IDof Component Examined Category Description of Component ASME Exam Size- Sched.- ISI.Dwg. No. Item No. Method Exam Report No. Status Remarks 1B21-H0074-WA D-Ac VT-1 1042-09-038 SAT None INTEGRAL ATTACHMENT D1.20 MECHANICAL SNUBBER 12" N/A 305-605-116 1B21-H101D(A) F-A VT-3 1042-09-039 SAT None VARIABLE SPRING MPL 1B21G7056 F1.SP 26' N/A 305-605-104 1821-H101D(B) F-A VT-3 1042-09-040 SAT None VARIABLE SPRING MPL 1B21G7057 FI.SP 26" N/A 305-605-104 1B21-H0423 F-A VT-3 VT-09-0781 SAT None MECHANICAL SNUBBER F3.SN 10" N/A 305-605-112 1B21-SI04D F-A VT-3 VT-09-0624 SAT None HYDRAULIC SNUBBER MPL F1.SN 1B21G7083 26" N/A 305-605-104 1B33-0109 R-A UT 0944-09-E046 GEO Previously recorded geometry noted with essentially no 12" PIPE TO ELBOW R3.ND changes. 12" .575' 305-602-103 1B33-010O. R-A UT 0944-09-E047 NRI None ELBOW SEAM, DOWNSTREAM R3.LS 12" .575" 305-602-103 1B33-0109-U R-A UT 0944-09-E048 NRI None PIPE SEAM, UPSTREAM R3.LS 12" .575" 305-602-103 1B33-0110 R-A UT 0944-09-E049 GEO Previously recorded geometry noted with essentially no 12" ELBOW TO PIPE R3.ND changes. 12" .575" 305-602-103 1B33-0110-D R-A UT 0944-09-E050 NRI None PIPE SEAM, DOWNSTREAM R3.LS 12' .575" 305-602-103 1B33-0110-U R-A UT 0944-09-E051 NRI None ELBOW SEAM, UPSTREAM R3.LS 12' .575" 305-602-103 Wednesday, July 08, 2009 Page 27 of 40 49

REPORT NO. P'0059-012 ASME IDof Component Examined Category Description of Component ASME Exam Size- Sched. - ISl Dwg. No. Item No. Method Exam Report No. Status Remarks 1B33-F0067A-IS B-M-2 VT-3 1Q800-09-254 SAT Interior accessible by wedge pin replacement ECP 03-24" GATE VALVEINTERNAL B12.50 0011, corrective maintenance order 200005691. SURFACE (GROUPING NO.V11i) N/A N/A 305-602-102 1B33-H301A F-A VT-3 1042-09-050 SAT None CONSTANT SUPPORT, PUMP, MPL FI.40 1B33G7013A N/A N/A 305-602-102 1B33-H303A F-A VT-3 1042-09-051 SAT None CONSTANT SUPPORT, PUMP, MPL FI.40 1B33G7015A N/A N/A 305-602-102 1B33-H304A F-A VT-3 1042-09-052 SAT None CONSTANT SUPPORT, PUMP, MPL FI.40 1B33G7016A N/A N/A 305-602-102 1C41-0001 R-A UT 0944-09-E038 NRI No counterbore was observed. SWEEPOLET TO 12" PIPE. R2.ND 12" 80 305-691-101 1C41-0001 R-A UT 0944-09-E037 NRI No interfering conditions or indications observed. SWEEPOLET TO 12" PIPE. R2.ND 12" 80 305-691-101 1C41-H0056 F-A VT-3 1042-09-045 SAT None RIGID STRUT F1.ST 1.5' N/A 305-691-101 IC41-H0059 F-A VT-3 1042-09-047 SAT None RIGID GUIDE F1.Gs 1.5" N/A 305-691-101 1C41-H5004 F-A VT-3 1042-09-046 SAT None RIGID SUPPORT FI.R 1.5" N/A 305-691-101 lC41-H5005 F-A VT-3 VT-09-0783 SAT None MECHANICAL SNUBBER F1.SN 1.5" NIA 305-691-101 1E12-0029 C-F-2 UT 0944-09-E019 NRI None 18" PIPE TO 24" X24 X18" TEE C5.51 18' 40 305-641-101 Wednesday, July 08,2009 Page 28 of 40 50

REPORT NO. P0059-012 ASME IDof Component Examined Category Description of Component ASME Exam Size - Sched.- ISI Dwg. No. Item No. Method Exam Report No. Status Remarks 1E12-0108A C-F-2 UT 0944-09-E006 NRI None 24" FLANGE TO PIPE C5.51 24" 40 305-641-101 1E12-0131 C-F-2 UT 0944-09-E020 GEO Previously recorded geometry noted with essentially no 18" PIPE TO ELBOW C5.51 changes. 18" 40 305-641-110 1E12-0145 C-F-2 UT 0944-09-E023 NRI None 20" PIPE TO INLET NOZZLE HEAT C5.51 EXCHANGER B001A 20" 40 305-641-111 1E12-0151 C-F-2 UT 0944-09-E026 NRI Previously detected geometry noted at below recording 20" X18" REDUCER TO 18" PIPE C5.51 levels. 18" 40 305-641-118 1E12-0160 C-F-2 UT 0944-09-E027 NRI None 20' PIPE TO HEAT EXCHANGER C5.51 B001C INLET NOZZLE 20" 40 305-641-118 1E12-0330 C-F-2 UT 0944-08-EOO1 NRI None 12" PIPE TO ELBOW C5.51 12" 40 305-642-119 1E12-0389 C-F-2 UT 0944-09-E031 NRI Previously recorded root geometry observed at below 12" PENETRATION P113 PROCESS C5.51 recordable levels. PIPE TO PIPE 12" 40 305-642-126 1E12-0402 R-A UT 0944-09-E032 NRI None 12' ELBOW TO PRB 2044 PROCESS R2.ND PIPE 12" 80 305-642-126 1E12-0455 C-F-2 UT 0944-09-E025 NRI None PIPE TO 18' ELBOW C5.51 18" 40 305-641-105 1E12-0580 C-F-2 UT 0944-09-E041 NRI None 12" VALVE F053B TO PIPE C5.51 12" 100 305-642-132 1E12-0968 C-F-2 UT 0944-09-E036 NRI Previously detected geometry noted at below recording 10" X10" X 10" TEE TO 10" PIPE C5.51 levels. 10" 80 305-641-112 Wednesday, July 08, 2009 Page 29 of 40 51

REPORT NO. P0059-012 ASME IDof Component Examined Category Description of Component ASME Exam Size- Sched. - ISI Dwg. No. Item No. Method Exam Report No. Status Remarks tE12-BOO1A-003 C-A UT 0944-09-E024 GEO Examined 0' to 1800. Scan performed across weld SHELL CYLINDER #3 TO SHELL HEAD C1.20 crown. Previously recorded indications were observed with essentially no changes. NIA N/A 305-641-121 1E12-B001A-064 C-B MT 0942-09A-008 ACC None SHELL HEAD TO INLET NOZZLE NK- C2.21 N4 20" N/A 305-641-121 1E12-BOOIA-004 C-B UT 0944-09-E028 NRI None SHELL HEAD TO INLET NOZZLE NK- C2.21 N4 20" N/A 305-641-121 IE12-BOO1A-004-IR C-B UT 0944-09-E021 NRI None INLET NOZZLE NK-N4 INNER RADIUS C2.22 20' N/A 305-641-121 1E12-B001A-SB3-SP F-A VT-3 1042-09-014 SAT None RIGID, HEAT EXCHANGER SUPPORT F1.40 (WA) N/A N/A 305-641-121 1E12-B001A-SB4-SP F-A VT-3 1042-09-015 SAT None RIGID, HEAT EXCHANGER SUPPORT F1.40 (WA) N/A N/A 305-641-121 1E12-B001D-SB3-WA C-Cc MT 0942-09A-007 ACC None HEAT EXCHANGER SUPPORT C3.10 BRACKET WELDED ATTACHMENT N/A N/A 305-643-123 1E12-C002A-004 C-G MT 0942-09A-004 ACC None HEAD FLANGE TO HEAD SHELL C6.10 N/A N/A 305-641-120 1E12-C002A-005 C-G MT 0942-09A-005 ACC None 18" DISCHARGE FLANGE TO 18" C6.10 DISCHARGE PIPE N/A N/A 305-641-120 1E12-C002A-010 C-G MT 0942-09A-006 ACC None HEAD SHELL LONGITUDINAL SEAM C6.10 N/A N/A 305-641-120 1E12-F0010-IS B-M-2 VT-3 1042-09-074 SAT None 20' GATE VALVE, INTERNAL B12.50 SURFACE (GROUPING NO. XI) 20" N/A 305-642-117 Wednesday, July 08, 2009 Page 30 of 40 52

REPORT NO. P0059-012 ASME IDof Component Examined Category Description of Component ASME Exam Size - Sched. - ISI Dwg. No. Item No. Method Exam Report No. Status Remarks 1E12-F0019-SEAM B-M-1 UT 0944-09-E030 NRI Single sided exam due to component configuration. 6"CHECK VALVE BODY WELD B12.40 (GROUPING NO. XII) 6" N/A 305-642-122 1E12-F0042B-SEAM B-M-1 UT 0944-09-E033 NRI 100% Coverage, Valve Stem observed, similar to 12" GATE VALVE BODY WELD B12.40 previous data. (GROUPING NO. XII) 12" N/A 305-642-137 1E12-H0016 F-A VT-3 VT-09-0779 SAT None MECHANICAL SNUBBER F1.SN 12' N/A 305-642-125 1E12-H0292 F-A VT VT-08-0008 SAT None MECHANICAL SNUBBER F2.SN 24" N/A 305-641-101 1E12-H0378 F-A VT-3 VT-08-0013 SAT None MECHANICAL SNUBBER F2.SN 18" N/A 305-642-102 1E12-H0390 F-A VT-3 1042-09-041 SAT None VARIABLE SPRING (WA <.75" T) F2.SP 20" N/A 305-642-101 1E12-H0499 F-A Vr-3 1042-08-006 SAT None VARIABLE SPRING F2.SP 18' N/A 305-641-106 1E12-H0662 F-A VT-3 1042-08A-002 SAT None RIGID STRUT F2.ST N/A N/A 305-641-108 1E12-H0681 F-A VT-3 VT-08-0009 SAT None MECHANICAL SNUBBER F2.SN N/A N/A 305-641-103 1E12-H0772 F-A VT-3 VT-09-0485 SAT None MECHANICAL SNUBBER F2.SN 12" N/A 305-642-126 1E12-H0786 F-A VT-3 1042-09-065 SAT None RIGID STRUT F1.ST 12" N/A 305-642-125 Wednesday, July 08, 2009 Page 31 of 40 53

REPORT NO. P0059-012 ASME IDof Component Examined Category Description of Component ASME Exam Size- Sched. - ISI Dwg. No. Item No. Method Exam Report No. Status Remarks 1E21-0033 C-F-2 UT 0944-09-E022 NRI Previously recorded geometry noted with essentially no 14 X12" REDUCING ELBOW TO 12" C5.51 changes. PIPE 12" 40 305-705-108 1E21-0053 C-F-2 UT 0944-09-E018 NRI Previously detected geometry noted at below recording 16" FLANGE TO 16"X 14" REDUCER C5.51 levels. 16" 40 305-705-102 1E21-CO01-007 C-G MT 0942-09A-001 ACC None 24' SUCTION FLANGE TO 24" C6.10 SUCTION PIPE 24" N/A 305-705-113 IE21-COO1-008 C-G MT 0942-09A-002 ACC None 24" SUCTION PIPE TO HEAD SHELL C6.10 N/A N/A 305-705-113 1E21-CO01-010 C-G MT 0942-09A-003 ACC None HEAD SHELL LONGITUDINAL SEAM C6.10 N/A N/A 305-705-113 1E21-C001-17B C-D UT 0944-09-EO10 NRI None LPCS PUMP, STUD #17 C4.30 N/A N/A 305-705-113 1E21-CO01-17B C-D UT 0944-09-EO01 NRI None LPCS PUMP, STUD #17 C4.30 N/A N/A 305-705-113 1E21-CO01-18B C-D UT 0944-09-E002 NRI None LPCS PUMP, STUD #18 C4.30 N/A N/A 305-705-113 1E21-CO01-18B C-D UT 0944-09-EOII NRI None LPCS PUMP, STUD #18 C4.30 N/A NIA 305-705-113 1E21-C001-19B C-D UT 0944-09-E012 NRI None LPCS PUMP, STUD #19 C4.30 N/A N/A 305-705-113 1E21-CO01-19B C-D UT 0944-09-E003 NRI None LPCS PUMP, STUD #19 C4.30 N/A N/A 305-705-113 Wednesday, July 08, 2009 Page 32 of 40 54

REPORT NO. P0059-012 ASME IDof Component Examined Category Description of Component ASME Exam Size - Sched. - ISI Dwg. No. Item No. Method Exam Report No. Status Remarks 1E21-CO01-20B C-D UT 0944-09-E004 NRI None LPCS PUMP, STUD #20 C4.30 N/A N/A 305-705-113 1E21-C001-20B C-D UT 0944-09-E013 NRI None LPCS PUMP, STUD #20 C4.30 N/A N/A 305-705-113 1E21-C001-21B C-D UT 0944-09-E005 NRI None LPCS PUMP, STUD #21 C4,30 N/A N/A 305-705-113 1E21-C001-21B C-D UT 0944-09-E014 NRI None LPCS PUMP, STUD #21 04.30 N/A N/A 305-705-113 1E21-C001-22B C-D UT 0944-09-E015 NRI None LPCS PUMP, STUD #22 C4.30 N/A N/A 305-705-113 1E21-C001-22B C-D UT 0944-09-E007 NRI None LPCS PUMP, STUD #22 C4.30 N/A N/A 305-705-113 1E21-C001-23B C-D UT 0944-09-E00B NRI None LPCS PUMP, STUD #23 04.30 N/A N/A 305-705-113 1E21-C001-23B C-D UT 0944-09-E016 NRI None LPCS PUMP, STUD #23 C4.30 N/A N/A 305-705-113 1E21-C001-24B C-D UT 0944-09-E017 NRI None LPCS PUMP, STUD #24 C4.30 N/A N/A 305-705-113 1E21-C001-24B C-D UT 0944-09-E009 NRI None LPCS PUMP, STUD #24 C4.30 NIA N/A 305-705-113 1E21-FOO05-SEAM B-M-1 UT 0944-09-E029 NRI 100% Coverage, observed valve stem non-relevant 12" GATE VALVE BODY WELD B12.40 indication similar to previousdata. (GROUPING NO. XVI) 12" N/A 305-705-113 Wednesday, July 08,2009 Page 33 of 40 55

REPORT NO. P0059-012 ASME IDof Component Examined Category Description of Component ASME Exam Size - Sched.- ISI Dwg. No. Item No. Method Exam Report No. Status Remarks 1E21-H0005 F-A VT-3 1042-09-037 SAT None RIGID STRUT Fi.ST 12" N/A 305-705-111 1E21-H0023 F-A VT-3 1042-09-013 SAT None ANCHOR (WA) F2.A 16" N/A 305-705-103 1E21-H0026 F-A VT-3 VT-08-0011 SAT None MECHANICAL SNUBBER (WA <.75" T) F2.SN 24" N/A 305-705-101 1E21-H0062 F-A VT-3 VT-08-0012 SAT None MECHANICAL SNUBBER F1.SN 12" N/A 305-705-108 1E21-H0080 F-A VT-3 1042-08-003 SAT None RIGID STRUT (WA <.75 T) F2.ST 24" WA 305-705-101 1E21-H0089 F-A VT-3 1042-08-004 SAT None VARIABLE SPRING F1.SP 12' N/A 305-705-108 1G33-0101 R-A UT 0944-09-E045 NRI None 4" PIPE TO BENT PIPE R3.ND 4" 80 305-671-107 IG33-H0206 F-A VT-3 1042-09-063 SAT None VARIABLE SPRING F1.SP 4' N/A 305-671-107 1G33-H0211 F-A VT-3 1042-09-064 SAT None RIGID STRUT F1.ST

3. N/A 305-671-102 1G41-B001A-SP F-A VT-3 1042-09-027 SAT None ANCHOR, HEAT EXCHANGER (WA) F1.40 N/A N/A 305-654-108 1G41-BOOIA-WA D-Ac VT-1 1042-09-028 SAT None INTEGRAL ATTACHMENT HEAT D1.10 EXCHANGER ANCHOR N/A N/A 305-654-108 Wednesday, July 08, 2009 Page 34 of 40 56

REPORT NO. P0059-012 ASME IDof Component Examined Category Description of Component ASME Exam Size - Sched.- ISI Dwg. No. Item No. Method Exam Report No. Status Remarks 1G41-H0005 F-A VT 1042-08-009 SAT None RIGID ROD F3.R 10" N/A 305-655-117 1G41-H0033 F-A VT-3 1042-09-025 SAT None RIGID GUIDE F3.G 6" N/A 305-655-110 1G41-H0113 F-A VT-3 1042-08-007 SAT None RIGID STRUT F3.STm 10" N/A 305-655-109 1G41-H0163 F-A VT-3 1042-08-010 SAT None RIGID STRUT F3.STm 10" N/A 305-655-111 1G41-H0223 F-A VT-3 1042-08-011 SAT None RIGID GUIDE F3.G 8a N/A 305-651-101 1G41-H0266 F-A VT-3 1042-08-012 SAT None RIGID STRUT F3.ST 10" N/A 305-655-113 1G41-H0282 F-A VT-3 1042-09-026 SAT None RIGID STRUT F3.ST 10" N/A 305-651-103 1G41-H0291 F-A VT-3 1042-08-013 SAT None RIGID GUIDE F3.G 4" N/A 305-654-105 1G41-H0373 F-A VT-3 1042-08-014 SAT None RIGID STRUT F3.STm 10" N/A 305-655-115 1G41-H0425 F-A VT-3 1042-09-030 SAT None ANCHOR (WA) F3A 10" NIA 305-654-102 1G41-H0425-WA D-Ac VT-1 1042-09-029 SAT None INTEGRAL ATTACHMENT ANCHOR D1.20 10" N/A 305-654-102 Wednesday, July 08, 2009 Page 35 of 40 57

REPORT NO. P0059-012 ASME IDof Component Examined Category Description of Component ASME Exam Size- Sched. - ISI Dwg. No. Item No. Method Exam Report No. Status Remarks 1G41-H0450 F-A VT-3 VT-09-0590 &96 SAT None MECHANICAL SNUBBER (TANDEM) F3.SN 12" N/A 305-654-101 1G42-H0005-WA D-Ac VT-3 1042-08-005 SAT None INTEGRAL ATTACHMENT RIGID., D1.20 GUIDE 10' N/A 305-655-101 1G42-H0016 F-A VT-3 1042-08-015 SAT None RIGID STRUT F3.ST 10" N/A 305-655-101 IN11-H0222-WA C-Cc VT-I 1042-09-048 SAT None, INTEGRAL ATTACHMENT RIGID C3.20 GUIDE 28' N/A 305-605-110 1N22-0062 @ X-B VT-1 1042-09-042 SAT None 2" PIPE TO ELBOW X10.11 2' 160 305-121-101 1N22-0062 @ X-B UT 0944-09-E034 NRI None 2" PIPE TO ELBOW X10.11 2' 160 305-121-101 1N22-0063 @ X-B UT 0944-09-E035 NRI None 2" ELBOW TO PIPE X10.11 2" 160 305-121-101 1N22-0063 @ X-B VT-1 1042-09-043 SAT None 2' ELBOW TO PIPE X10.11 2" 160 305-121-101 1N27-0025 C-F-2 UT 0944-09-E039 NRI None 20" X20" X 14" TEE TO 20" PIPE C5.51 20" 120 305-082-104 1N27-0025A @ X-B UT 0944-09-E040 NRI Previously detected geometry noted at below recording 20" X20" X 14" TEE TO 14" X 12' X10.10 levels. REDUCER 14" 120 305-082-104 1N27-P414-SP F-A VT-3 1042-09-049 SAT None ANCHOR, PEN TO SHIELD BLDG (WA) N/A 305-082-104 Wednesday, July 08, 2009 Page 36 of 40 58

RElPORT NO. P0C39-012 ASME IDof Component Examined Category Description of Component ASME Exam Size - Sched. - ISI Dwg. No. Item No. Method Exam Report No. Status Remarks 1N27-P414-WA B-Kc MT 0942-09A-009 ACC None P414 FLUED HEAD FITTING TO B10.20 PROCESS PIPE ATTACH WLD 20" N/A 305-082-104 1N27-P414-WA @ X-E UT 0944-09-E042 NRI 0" Exam, no relevant indications. P414 FLUED HEAD FITTING TO X1 0.20 PROCESS PIPE ATTACH WLD 20' N/A 305-082-104 1N27-P414-WA @ X-E UT 0944-09-E043 NRI Previous non-relevant Indications recorded at same P414 FLUED HEAD FITTING TO X10.20 sweep location and lower amplitude were observed at PROCESS PIPE ATTACH WLD below the recording criteria and no longer recordable 20" N/A 305-082-104 due to new wedge/angle used to perform the exam. 1P45-H0025 F-A VT-3 1042-08-017 SAT Notification 600507788 generated for the degraded RIGID GUIDE F3.G coatings. 16" N/A 305-792-106 1P45-H0115 F-A VT-3 1042-09-012 SAT Notification 600521767 written to addressed rusted U-RIGID GUIDE F3.G Bolt on the guide. 16" N/A 305-792-107 1P45-H0138 F-A VT-3 1042-08-008 SAT None RIGID GUIDE F3.G 16" N/A 305-792-103 1P45-HO159 F-A VT-3 1042-09-035 SAT Notification 600522690 generated to clean and re-paint ANCHOR (WA) F3.A hanger and attachment. 24' N/A 305-792-104 1P45-H0159-WA D-Ac VT-1 1042-09-036 SAT Notification 600522690 generated to clean &re-paint INTEGRAL ATTACHMENT ANCHOR D1.20 hanger and attachment 24" N/A 305-792-104 1P45-H0357 F-A VT-3 1042-09-031 EVAL Notif 600521857 written for relevant operable indication RIGID STRUT (WA) F3.ST due to strut having no free movement 16" N/A 305-792-103 1P45-H0357-WA D-Ac VT-1 1042-09-032 SAT None INTEGRAL ATTACHMENT RIGID D1.20 STRUT 16" N/A 305-792-103 1P45-H0408 F-A VT-3 1042-09-033 SAT None RIGID GUIDE F3.Gs 8" N/A 305-791-101 Wednesday, July 08, 2009 Page 37 of 40 59

REPORT NO. P0059-012 ASME IDof Component Examined Category Description of Component ASME Exam Size- Sched. - ISI Dwg. No. Item No. Method Exam Report No. Status Remarks 1P45-H0622 F-A VT-3 1042-09-034 SAT None RIGID STRUT F3.ST 8" N/A 305-792-109 1P47-H0291 F-A VT-3 1042-0-016 SAT None RIGID STRUT F3.ST 6' N/A 305-002-111 CLASS 1,PIPING B-P VT-2. 1Q800-09-278 SAT Pressure testing accomplished by various ISI PIPING-SYSTEM LEAKAGE TEST B15.50 Instructions. N/A N/A 305-NO-DWG CLASS 1, PUMPS B-P VT-2 1Q800-09-279 SAT Pressure testing accomplished by various ISI PUMPS-SYSTEM LEAKAGE TEST B15.60 Instructions. N/A N/A 305-NO-DWG CLASS 1, VALVES B-P VT-2 1Q800-09-280 SAT Pressure testing accomplished by various ISI VALVES-SYSTEM LEAKAGE TEST B15.70 Instructions. N/A N/A 305-NO-DWG CLASS 1,PR COMP B-P VT-2 1Q800-09-281 SAT Pressure testing accomplished by various ISI REACTOR VESSEL-SYSTEM B15.10 Instructions. LEAKAGE TEST N/A N/A 305-NO-DWG CLASS 2, PIPING C-H VT-2 1Q800-09-282 SAT Pressure testing accomplished by various ISI SYSTEM PRESSURE TEST C7.30 Instructions. N/A N/A 305-NO-DWG CLASS 2, PRESS VESS C-H VT-2 1Q800-09-283 SAT Pressure testing accomplished by various SI SYSTEM PRESSURE TEST C7.10 Instructions. N/A N/A 305-NO-DWG CLASS 2, PUMPS C-H VT-2 10800-09-284 SAT Pressure testing accomplished by various ISI SYSTEM PRESSURE TEST C7.50 Instructions. NIA N/A 305-NO-DWG CLASS 2, VALVES C-H VT-2 1Q800-09-285 SAT Pressure testing accomplished by various ISI SYSTEM PRESSURE TEST C7.70 Instructions. NIA N/A 305-NO-DWG CLASS 3, PR COMP D-A VT-2 10800-09-286 SAT Pressure testing accomplished.by various ISI SYSTEM PRESSURE TEST D1.10 Instructions. N/A N/A 305-NO-DWG Wednesday, July 08,2009 Page 38 of 40 60

REPORT NO. P0059-012 ASME IDof Component Examined Category Description of Component ASME Exam Size - Sched. - ISI Dwg. No. Item No. Method Exam Report No. Status Remarks CLASS 3, PR COMP D-B VT-2 1Q800-09-287 SAT Pressure testing accomplished by various ISI SYSTEM PRESSURE TEST D2.10 Instructions. N/A N/A 305-NO-DWG CLASS 3, PR COMP D-C VT-2 1Q800-09-288 SAT Pressure testing accomplished by various ISI SYSTEM PRESSURE TEST 03.10 Instructions. N/A N/A 305-NO-DWG 1T23-EXTERIOR E-A GVIS 1042-09-024 SAT Minor surface rust EXTERIOR EL 599-757 AZ 0-360 E1.11 N/A N/A 305-503-EXT 1T23-INTERIOR E-A GVIS 1042-09-075 SAT Ctmt Integrity OK; CRs 09-51721 &51967 initiated due INTERIOR EL 574-757 AZ 0-360 E1.11 to degraded coatings. N/A N/A 305-503-INT 1T23-013-I E-A VT-3 1042-09-016 SAT No structural degradation; CR 09-51721 generated for INT EXCEPT ST &FILTER RM EL 642- E1.12 coatings degradation. 6.p ' z 0-90 (4%) N/A N/A 305-503-113 1T23-014-I E-A VT-3 1042-09-017 SAT No structural degredation; CR 09-51721 generated for INT EXCEPT FUEL STOR PIT EL 642- E1.12 coatings degredation. 690 AZ 90-180 (3%) N/A N/A 305-503-114 1T23-015-1 E-A VT-3 1042-09-018 SAT No structural degredation; CR 09-51721 generated for INTERIOR EL 642-690 AZ 180-270(6%) E1.12 coatings degredation. N/A N/A 305-503-115 1T23-016-1 E-A VT-3 1042-09-019 SAT No structural degredation; CR 09-51721 generated for INT EXCEPT STEAM TUNNEL EL 642- E1.12 coatings degredation. 690 AZ 270-360 (5%) N/A N/A 305-503-116 1T23-017-1 E-A VT-3 1042-09-020 SAT No structural degredation; CR 09-51721 generated for INT REFUEL FLOOR TO DOME EL 690- E1.12 coatings degredation. 727 AZ 0-90 (4%) N/A N/A 305-503-119 1T23-018-1 E-A VT-3 1042-09-021 SAT No structural degredation; CR 09-51721 generated for INT REFUEL FLOOR TO DOME EL 690- 'E1.12 coatings degredation. 727 AZ 90-180 (4%) N/A N/A 305-503-120 IT23-019-1 E-A VT-3 1042-09-022 SAT No structural degredation; CR 09-51721 generated for INT REFUEL FLOOR TO DOME EL 690- E1.12 coatings degredation. 727 AZ 180-270 (4%) NIA N/A 305-503-121 Wednesday, July 08, 20D9 Page 39 of 40 61

REPORT NO. P0059-012 ASME IDof Component Examined Category Description of Component ASME Exam Size - Sched.- ISl Dwg. No. Item No. Method Exam Report No. Status Remarks 1T23-020-1 E-A VT-3 1042-09-023 SAT No structural degredation; CR 09-51721 generated for INT REFUEL FLOOR TO DOME EL 690- E1.12 coatings degredation. 727 AZ 270-360 (4%) NIA NIA 305-503-122 Table Notes:

1. Status codes are "SAT', "UNSAT" or "EVAL" for visual exams. For surface exams they are "ACC" for acceptable, "REJ" for rejectable and" INFO" for exams that require additional information. For ultrasonic exams they are "IND" for indication, "GEO" for geometry, and "NRI" for no recordable indications along with "SAT", "UNSAT" or "EVAL" for vendor UT datasheets.
2. The above exam listing is all the inservice examinations that were performed during Cycle 12 or RFO12 in accordance with Perry's Inservice Examination Plan (ISEP).

Wednesday, July 08,2009 Page 40 of 40 62

REPORT NO. P0059-012 First Energy Nuclear Operating Company Perry Nuclear Power Plant ISI Summary Report No. P0059-0012 Second Interval, Third Period, Second Outage (RFO12) Cycle 12 and RFO12 Preservice Examinations Prepared by: ,,_ _ _ _ _ _ _ Date: 7 / ISI Engineer I Reviewed by: -Authrize Date: __ ._,____/ Authorized NuclearlInservice Inspector,"Q Wednesday, July 08, 2009 Page 1 of 5 63

REPORT NO. P0059-012 ASME IDof Component Examined Category Description of Component ASME Exam Size - Sched. - ISI Dwg. No. Item No. Method Exam Report No. Status Remarks 1B13-N8-B B-G-2 VT-1 1Q800-09-259 SAT Examined 3 studs &8 nuts which were replaced on this RPV HEAD SPRAY NOZZLE N8 TO B7.10 bolted connection, heat numbers D145 and TBX for FLANGE BOLTING studs and nuts, respectively. N/A 305-006-103 1B21-F0041A-fS B-M-2 VT-3 1042-09-011 SAT Examination of replacement safety relief valve, Ser No. SRV, INTERNAL SURFACE B12.50 160884. (GROUPING NUMBER I) N/A 305-605-101 1B21-F041A-B B-G-2 vr-1 1042-09-055 SAT Examined 12 replacement studs, nuts and washers, SRV BOLTING, 12 EACH B7.50 heat number 590A. N/A 305-605-101 1B21-F041C-B B-G-2 VT-I 1042-09-054 SAT Examined 12 replacement studs, nuts and washers, SRV BOLTING, 12 EACH B7.50 heat number K745. N/A 305-605-103 1B21-F041E-B B-G-2 VT-1 1042-09-056 SAT Examined 12 replacement studs, nuts and washers, SRV BOLTING, 12 EACH B7.50 heat number OG84. N/A 305-605-101 1B21-F041G-B B-G-2 VT-1 1042-09-058 SAT Examined 12 replacement studs, nuts and washers, SRV BOLTING, 12 EACH B7.50 heat number K745. N/A 305-605-103 1B21 -F047C-B B-G-2 VT-I 1042-09-057 SAT Examined 12 replacement studs, nuts and washers, SRV BOLTING, 12 EACH B7.50 heat number K745. N/A 305-605-103 1B21-F047G-B B-G-2 VT-I 1042-09-059 SAT Examined 12 replacement studs, nuts and washers, SRV BOLTING, 12 EACH B7.50 heat number K745. N/A 305-605-103 1B21-F051A-B B-G-2 VT-1 1042-09-060 SAT Examined 12 replacement studs, nuts and washers, SRV BOLTING, 12 EACH B7.50 heat number K745. N/A 305-605-101 1821-FO51C-B B-G-2 VT-1 1042-09-061 SAT Examined 12 replacement studs, nuts and washers, SRV BOLTING, 12 EACH B7.50 heat number K745. N/A 305-605-103 1B21-F051G-B B-G-2 VT-1 1042-09-062 SAT Examined 12 replacement studs, nuts and washers, SRV BOLTING, 12 EACH B7.50 heat number K745. N/A 305-605-103 Wednesday, July 08,2009 Page 2 of 5 64

REPORT NO. P0059-012 ASME IDof Component Examined Category Description of Component ASME Exam Size. Sched. - ISI Dwg. No. Item No. Method Exam Report No. Status Remarks 1B2 1-H0046 F-A VT-3 VT-09-0808 SAT Pre-service exam of replacement snubber Ser No. MECHANICAL SNUBBER F3.SN 43347. N/A 305-605-115 1B21-H0446 F-A VT-3 VT-09-0865 SAT Pre-service exam of replacement snubber Ser No. HYDRAULIC SNUBBER (WA < .625" T) F1.SN 30800103/005. (TANDEM) N/A 305-605-106 11B21-H0447 F-A VT-3 VT-09-0867 SAT Pre-service exam of replacement snubber Ser No. HYDRAUUC SNUBBER F1.SN 30800103/008. NIA 305-605-106 1B21-H0452 F-A VT-3 VT-09-0868 SAT Pre-service exam of replacement snubber Ser No. HYDRAULIC SNUBBER F1.SN 02615163/002. N/A 305-605-106 1821-H0453 F-A VT-3 VT-09-0869 SAT Pre-service exam of replacement snubber Ser No. HYDRAULIC SNUBBER FI.SN 30800103/006. N/A 305-605-106 1821-H0462 F-A VT-3 VT-09-0870 SAT Pre-service exam of replacement snubber Ser No. HYDRAULIC SNUBBER FI.SN 30800103/00Z N/A 305-605-106 1821-H0472 F-A VT-3 VT-09-0871 SAT Pre-service exam of replacement snubber Ser No. HYDRAULIC SNUBBER F1.SN 30700524/016. N/A 305-605-106 1B21-H0490 F-A VT-3 1Q800-09-261 SAT Pre-service exam of replacement snubber Ser No. HYDRAULIC SNUBBER F1.SN 30800103/007. N/A 305-605-106 1B21-HO491 F-A VT-3 VT-09-0873 SAT Pre-service exam of replacement snubber Ser No. HYDRAULIC SNUBBER FI.SN 30800103/010. N/A 305-605-106 1B33-F067B-B B-G-2 VT-1 1Q800-09-256 SAT Pre-service exam of bolting replaced during 24" VALVE BOLTING B7.70 implementation of ECP 03-0011, order 200005691. N/A 305-602-104 1B33-S371A F-A VT-3 VT-09-0828 SAT Pre-service exam of replacement snubber Ser No. 060. HYDRAUUC SNUBBER, PUMP F1.40 MOTOR, MPL 1B33G7066A N/A 305-602-102 Wednesday, July 08, 2009 Page 3 of 5 65

REPORT NDY. P0059-012 ASME IDof Component Examined Category Description of Component ASME Exam Size - Sched. - ISI Dwg. No. Item No. Method Exam Report No. Status Remarks 1833-S375A F-A VT-3 VT-09-0845 SAT Pre-service exam of replacement snubber Ser No. 059. HYDRAULIC SNUBBER, PUMP (WA) F1.40 MPL 1B33G7070A N/A 305-602-102 1E12-H0118 F-A VT-3 1042-09-066 SAT Pre-service exam of new support for ECP 04-0270-01, ANCHOR (WA) F2.A order 200199139. N/A 305-642-119 1E12-H0293 F-A VT-3 VT-09-0847 SAT Pre-service exam of replacement Snubber per ECP HYDRAULIC SNUBBER (TANDEM) F2.SN 0270-01, order 200199137. N/A 305-641-101 1E12-H0309 F-A VT-3 VT-09-0822 SAT Pre-service exam of replacement Snubber per ECP HYDRAULIC SNUBBER F2.SN 0270-01, order 200199137. N/A 305-642-105 1E12-H0364 F-A VT-3 1042-09-069 SAT Pre-service exam of new support for ECP 04-0270-01, RIGID STRUT F2.ST order 200199137. N/A 1 305-642-114 1E12-H0790 F-A VT-3 1042-09-071 SAT Pre-service exam of new support for ECP 04-0270-01, HYDRAULIC SNUBBER &RIGID F2.SN order 200199139. STRUT N/A 305-641-105 1E21-0044A C-F-2 UT 0944-09-E052 GEO Geometric indication (root) recorded. Pre-service exam 14" PIPE TO 14' X10" REDUCING TEE C5.51 due to additional weld added to ISI population from ADHR mod, ECP 04-0270-01, order 200199135. 40 305-705-105 IE21-H0024 F-A VT-3 1042-08A-001 SAT Pre-service exam insupport of ECP 04-0279-01. RIGID STRUT F2.ST N/A 305-705-102 IE51-0001-B B-G-2 VT-1 1Q800-09-260 SAT Pre-service exam of 1 replacement nut on this bolted 6* FLANGE BOLTING B7.50 connection, heat number TBX. NIA 305-631-108 11E51-H0072 F-A VT-3 V'-09-0874 SAT Pre-service exam of replacement snubber, Ser No. HYDRAULIC SNUBBER F1.SN 30800103/009. N/A 305-631-108 A1N22-H0148 F-A VT-3 VT-09-0815 SAT Pre-service exam of replacement snubber Ser. No. MECHANICAL SNUBBER FI.SN 24405. N/A 305-121-101 Wednesday, July 08, 2009 Page 4 of 5 66

REPORT NO. P0059-012 ASME IDof Component Examined Category Description of Component ASME Exam Size. Sched.- ISI Dwg. No. Item No. Method Exam Report No. Status Remarks 1G40-H0008 1G40-H0008 F-A VT-3 1Q800-09-255 SAT Pre-service exam of new support installed under ECP RIGID STRUT (TANDEM) F2.ST *04-0270-01, order 200199135. N/A 305-246-103 1G40-H0024 F-A VT-3 1042-09-072 SAT Pre-service exam of new support for ECP 04-0270-01, RIGID STRUT F2.ST order 200199139. N/A 305-246-101 1G40-H0025 F-A VT-3 1042-09-067 SAT Observed out-of-spec pin-to-pin setting, initiated CR 09-RIGID STRUT (TANDEM) F2.ST 56656. Reworked via ECP 04-0270-01 revision 20, order 200199137. N/A 305-246-102 1G40-H0026 F-A VT-3 1042-09-068 SAT Pre-service exam of new support for ECP 04-0270-01, RIGID STRUT (TANDEM) " F2.ST order 200199137. N/A 305-705-103 1G40-H0027 F-A VT-3 1042-09-070 SAT Pre-service exam of new support for ECP 04-0270-01, RIGID STRUT F2.ST order 200199139. N/A 305-246-101 1G40-H0028 F-A VT-3 1042-09-073 SAT Pre-service exam of new support for ECP 04-0270-01, RIGID STRUT (TANDEM) F2.ST order 200199139. N/A 305-641-106 Table Notes:

1. Status codes are "SAT", "UNSAT" or "EVAL" for visual exams. For ultrasonic exams they are "IND" for indication, "GEO" for geometry, and "NRI" for no recordable indications.
2. The above exam listing is all the preservice exams that were performed during Cycle 12 or RFO12 due to repair/replacement activities.

Wednesday, July 08, 2009 Page 5 of 5 67

REPORT NO. P0059-012 APPENDIX B "CYCLE 12 & RFO12 NIS-2/NR-1 FORMS" INSERVICE INSPECTION

SUMMARY

REPORT FOR PERRY NUCLEAR POWER PLANT (PNPP) UNIT 1 68

S.EPORT NO. P0059-012

                                                                                                                 -      653 NIS-2!NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As required by the Provisions of the ASME Code Section XI IPNPP No. 9308 Rev. 9/11/00                                                                                          NOI-1741
1. Owner: FIRSTENERGY CORP. Date 12/14/07 10 Center Road. Perry, Ohio 44081 Sheet 1 of 1
2. Plant: Perrv Nuclear Power Piant (PNPP) Unit 1 10 Center Road. Perry, Ohio 44081 200283212 (Repair Org. P.O. No., etc.)

3, Work Performed By: FIRSTENERGY Nuclear Ooerating Company PNPP Type Code Symbol Stamp NR 10 Center Road. Perry. Ohio 44081 Authorization No. 33 Expiration Date 9/28/08

4. Identification of System: Reactor and Internals 1B13
5. (a) Applicable Construction Code: ASME Section III Class 1 ,1974 Edition NAMJE/SECTION/DIVISION/CLASS winter 19 75 Addenda Code Case(s) 'N207, N272, 1361-2, 1644-4, 1728 (b) Construction Code used for repairs, modifications, or replacements: 1974 W 1975 Edition Addenda Code Case(s)

(c) ASME Code Section XI applicable for Inservice Inspection: 1989 none none Edition Addenda Code Case(s). (d) Applicable Edition of Section XI Utilized for Repairs, Modification, or Replacements: 198,__9 19 none Addenda none Code Case(s) (e) Design Reiponsibilities FIRSTENERGY CORP.

6. Identification of Components Repaired, Modified, or Replacement Components Name of Name of Manufacturer Nat. j Other Year Repair, ASME Component Manufacturer Serial No. Board ID. Built Replacement, Code No. or Modification Stamped piping General Electricr 11313 64077 N/A 1984 Replacement 1985 system

_ __ _ _ _.1 __ _

7. Description of Work: Installed eight new capscrews and slotted washers at CRDM flanoe at location 42-31 Heat number 255A.
8. Test Conducted: Hydrostatic- E] Pneumatic- [ Nominal Operating. Pressure- El Other- E]

Pressure N/A psi Test Temperature N/A degrees F Code Case(s) N/A 69

       " NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back)
!PNPP No. 9308 Rev. 9/11/00                                                                                                       NQI-1741
9. Remarks:

NO NAMEPLATE.STAMPING PERFORMED DUE TO THE INTERFACE CONTROLS OF RA-2370 BEING IN EFFECT AND JURISDICTIONAL AUTHORITY CONCURRENCE HAVING BEEN RECEIVED. Note: Attach all applicable Manufacturer's Data Reports. Supplemental sheets such as lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded on the front of this form. CERTIFICATE OF COMPLIANCE I, Michael J Tepsick , certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and to the National Board Inspection Code "NR" rules. National Board Certificate of Authorization No. 33 to use the "NR stamp expires 28 Seot. , 20 08 Date 14 Dec. 20 07 Signed FENOC-PNPP " ,/.. -7 QC Tech. (name of repairorganization) (authorizedrepresentative) (title) CERTIFICATE OF INSPECTION/INSERVICE INSPECTION I, Thomas G Laps holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HSB CT. of Hartford, Conn. have inspected the repair, modification or replacement described in this report on

  • 20 0 f and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section X1 of the ASME Code and the National Board Inspection Code 'NR' rules.

By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or oss of any kind arising from or connected with this inspection. Date 20 -- Signed Fi-t'ý1

                                                                      .Ž")/_ Commissions       NB 9330 "N' "I" A" Ohio Comm.

(inspector)o'- ,, (National Board (include endorsements), andjurisdiction,and no.)

REPORT NO. P0059-012

                                                                                                  !B13-054 NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As required by the Provisions of the ASME Code Section XI PNPP No. 9308 Rev. 9/11100                                                                                          NQ1.1741
1. Owner: FIRSTENERGY CORP. Date 5/15/09 10 Center Road, Perry, Ohio 44081 Sheet 1 of ___
2. Plant: Perry Nuclear Power Plant (PNPP) Unit 1 10 Center Road, Perry, Ohio 44081 see attached chart (Repair Org. P.O. No., etc.)
3. Work Performed By: FIRSTENERGY Nuclear Operating Comoany PNPP Type Code Symbol Stamp NR 10 Center Road. Perrv. Ohio 44081 Authorization No. 33 Expiration Date 2/28/2011
4. Identification of System: 1B13 Reactor and Internals
5. (a) Applicable Construction Code: ASME SECTION IIICLASS 1 1974 Edition NAMEJSECTlON/DIVISION/CLASS WINTER 19 75 Addenda Code Case(s) N207. 1361-2, 1728, 1644-4, N272 (b) Construction Code used for repairs, modifications, or replacements: 1974 W75 N/A Edition Addenda Code Case(s)

(c) ASME Code Section XI applicable for Inservice Inspection: 1989 NONE N/A Edition Addenda Code Case(s) (d) Applicable Edition of Section XI Utilized for Repairs, Modification, or Replacements: 1989 . N/A 19 N/A Addenda N/A Code Case(s) (e) Design Responsibilities First Energy Corp

6. Identification of Components Repaired, Modified, or Replacement Components Name of Name of Manufacturer Nat. Other Year Repair, ASME Component Manufacturer Serial No. Board ID. Built Replacement, Code No. or Modification Stamped PIPING GENERAL 1813 64077 1B13D000 1984 REPLACEMENT YES r

SYSTEM ELECTRIC

7. Description of Work: Replaced 20 control rod drives and 1" cap screws see attachment for details.
8. Test Conducted: Hydrostatic- E) Pneumatic- El Nominal Operating Pressure- [D Other- E]

Pressure 1025 psi Test Temperature 123 degrees F Code Case(s) N/A 70

NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back) PNPP No. 9308 Rev. 9/11100 NQ1- 1741

9. Remarks:

NO NAMEPLATE/STAMPING PERFORMED DUE TO THE INTERFACE CONTROLS OF RA-2370 BEING IN EFFECT AND JURISDICTIONAL AUTHORITY CONCURRENCE HAVING BEEN RECEIVED. Note: Attach all applicable Manufacturer's Data Reports. Supplemental sheets such as lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded on the front of this form. CERTIFICATE OF COMPLIANCE I, JOHN W. MESSENGER, certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and to the National Board Inspection Code "NR' rules. National Board Certificate of Authorization No. 33 to use the 'NR stamp.ex ires 28 Sept. 20 2011 Date 15 MAY 20 09 Signed FENOC-PNPP "C Tech. (name of repairorganization) (._-authorizedrepresentative) (title) CERTIFICATE OF INSPECTION/INSERVICE INSPECTION I, Thomas G Laos holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by . HSB CT. of Hartford, Conn. have inspected the repair, modification or replacement described in this report onM x-1. 20'.ý*. nd state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, conceming the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property dama

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

Date 2b D Signed commissions C NB 9330 "N" "r'A" Ohio Comm. finspec oO (National Board (include endorsements), andjurisdiction,and no.)

REPORT N3. P0059-012 NIS-2/NR--i 1313-054 PAGE 3 OF Z19

1. Owner FIRSTENERGY CORP 10 CENTER ROAD. PERRY. OH 44081
2. Plant: Perry Nuclear Power Plant (PNPP) Unit one 10 Center Road. Parry, Ohio 44081 WO # See below.

(RepairOrg. P.O. No., etc.)

3. Work Performed By: FIRSTENERGY NUCLEAR OPERATING COMPANY (PNPP) Type Code Symbol Stamp NR 10 Center Road, Perry, Ohio 44081 Authorization No. 33 Expiration Date 9/28/2011
4. Identification of System: 1B13 REACTOR AND INTERNALS
5. (a) Applicable Construction Code: ASME SECTION III NB 1974 Edition WINTER 19 75 Addenda Code Case(s) N207,1361-2.1728,1644-4,N272 (b) Applicable Edition of Section X1Utilized for Repairs or Replacements: 19 898 19 NO Addenda
6. Identification of Components Repaired, Modified, or Replacement Components WONUMBER CORE NEW CRDM SIN NTA-iBER OF ET -NUMBERS OF LOCATION CAPSCREWS NEW CAPSCREWS 200316015 , 26-47 A2257. 8 255A 200316011 10-23 A-3997 8 255A 200316023 30-27 A4006 8 255A 200316022 22-31 A4115 9 255A 200316018 30-35 A4216 8 255A 200316014 06-47 A4250 8 255A 200285923 42-31 A4483 8 255A 200316016 50-47 A4537 8 255A 200316004 10-47 A4582 8 255A 200316010 14-27 A4647 8 255A 200316024 30-23 A4676 _ 255A 200319782 34-55 A5237 8 255A 200319801 . 26-31 A5385 8 255A 200316008 10-39 A.5414 8 255A 200352463 10-11 A-5468 8 255A 200316017 14-35 A5572 8 255A 200316019 18-31 A5583 8 255A 200316026 42-07 A5695 8 255A 200316025 46-11 A5703 8 255A 200319788 18-35 A.5720 [ 8 255A 71
        /         "Sheet                                                                                                                         1 of 2 FOkM-N-2.Ffwr:CE.RT!CATE HOLDERS' DATA REPORT FOR NUCLFA.R PART AN"D APURTENA.NCESO i 16:' .

As r*tquired by the Provision of the ASME Code Rules, Scfion i1. Div. I

                                                      .                                                                         ~!rY/,!*'/2 -7 y.',D L (z)M--ufncruxed by-            General Electric Company,                     Castle Rayne Rd.,                  Wilmington,              N.C.

Manxr and adad-- of ftPT Ce-tlte Holder) (b) Maoufmaccred fo'" General Electric Company, San Jose, California (N-EBG) (Name and addre, r N Cardflcate Holder for coaxplat-d nuclear coiponenfl 7-2 Ilentflcatlon-Certlflcate Holder's Serial No. of Part A2257 NeerIl Bd. No. Dr-wing Prepared by D. L. Paterson (a) Constructed According to Drnwing No. 768E534G_00 (b) eControl Rod Drive, Model #7RDB144DG001 (c) Applicable Al-4E.C98e: Scrion *I, Edicion _.174. 94 Addendaddche W'75 No.7 136_36- -2____ 1

3. Remi-ics: Standard.ýpart for use with Reactor. Hydrostatically tested at 1820 psi.

(Brxief dv-scrition of service for whitch coponet wme desined)c Total number of sheets - 2 We ccrdfy chat die-s4rsemens made in this report are correct and this vessel paze or appurtenance its defined in the Code con-forms to the rules plf,.dstructioa of the A9-.E Code Section 1I. (The applicable Desi.iSpeciflcation and Stress Report are not the responsibility of the NPT Certificate Holder for parts. Kn NPT Certif-i---te Bolder for appudseancaa ih rcponsible for urnishing a separate Design Specification znd Stress Report if the appunenamce is not included In the cobrponent, Desiss Speciication and Stress RPor.l)

                                          . Sind
                                              . pB K,  o          GE,   -N7EPD-rbID                           BA'
                                                 ....            (--er~icmH~dn (NPTCerro=csf Hoiden)                   01u~oiz~~on*o.NPT N-!151 Ccr.ifica.e of Authorizaziob 'oiten             S(eptemb--*r        75,. 1-981]         Certificate of       uhorizacian No.           TT__-1_51 CERTIFICATION OF DESIGN FOR APPURTENANCE (when applicable)

Design formationon-..le GE, NEPD-WMM-QA, Castle Hzayne Rd., Wilminaton,: N'.C. 22A5556, Rev. Z Stress

      ... .          rpor Iysis          on file Re      GE,        NEPD,    Sarr Jose,        Calif.

22A4912, Rev. Design .specificadoxs- certified by B. N. Sridhhar Prof. Eng. Stare Calif Reg. N.18345 4 Str.ss analysis reparfcertified by B. N. Sridhar Pof E.g. Sca-c Calif Reg. No 183 5 CERTIFICATE OF SHOP INSPECTION 1, the undernigned, holding a valid cormisxioo issued.by the National Board oi Boiler ='d Pressure Vessel Inspectors and/or the Scate.or Pro'ince of North Carolina and employed byDepartment of Labor of State- of North Carolina have inspected the pare of x pressure ressel described in this Partial Data Re~pdat on, 8/26/ 191 8 and state that to the best o my knowledge antd belief, the NFT Certificate Holder has constructed this part In accordance with the ASME Code Section ttl. By signing thi-s-certificare, neither the Inspector nor his employer malces any waranty, expressed or implied, concern-log the part. described in this Partial Data Report. Furthermore. neither the Inspector nor his employer shall be liable in arry marrer for any personal inj-ury or property damage or a loss of *aybind trising troca or connected with this inspection.

                        .Date    81261              19     81
           -______"____"      _                                          Commissions                     1.0. 723,PA.WC1766, oHIO Kspieor'se 9gnseeorv                                                              N.0lom     eoa-d. Stete. Provinos ad Nlo.

[10/771 This form EB00,40) may be obtained from the Order Dent.. ASMS. 345 E. 47th St.. New York, N.Y. 10017

REPORT NO. P0059-012 S-Sheet 2 of 2 FORM N.2'NPT CER!TICATE SOLDERS' DATA REPORT FOR NTJCLFEAR PART AND APPURTE.NANCES . 7, j u2

                   .  '--As
                       .--     required by the Provision of the ASME Code Rules, Section M11.Div. I L. (=)M      /-
            --         T    General Electric Company,               Castle Rayne Rd.,                 Wilrngron, N.C.

(NHne aD addr= of NPT Certncuat HoJder) (W)Mmuf ctured for General El-ectrc Comprany, San Jose, Califor-nia (N\-3CG) (Nnme nad addrtacnN C-rO*cra* HEider. for 'omulet-d nmeercomponoen 2- Identir-cation-Cert~cate Holder's Serial No. ofrxst A2257 Ntr'l BM.No. _ D. L. Peterson (a) Coastruczed Acc&Ddimg to Dr-uwing No. 768E53AG001 Drewing Prepmr-ed (b) Description pfJ3-rinspected Control Rod Drive, Model #7RflB144DG001 N207 (c) Appli-cable SMI-5o,-eserionni, Uiorin 27i Adden Ca-e No. 1361-W2 Cl:as 1* Cap 166.9274P. (1 67A23.43). SA18Z - F316 Code weld-, 3/8 thick' 1 1/16 OD R5OYPI02

2. Indicatar-.Pipe 156B9313Pl SA312-TP316 3/4* sch 405-seamless pipe 0... l:*
                 . ':all thickness - -.

1.065_max, d-ia. .

3. Plug l59AT176PI SA182-F304 1/4 thick x 0.812 OD
4. Flange -]g9D6lOPl (719E474)
          .SAI 82-F304 3.37 thihk x 9 5/8 DO neck I1-716 thick x 5.0 0D 2.875T-w: '

5..Base 137C5311PI XM-_19_A$M4E SA479-3.0 0D x 884 .10

6. Ring'F-Mnge 114BSI22P2 SA182-F304 1"..thick x 5.00D x 1.75 TO
7. Cap-Sc-ew 117C4516P2 SAl. 93-6 CONTROL OD DRIVE 6 ea. i/2 dia. on 4 1/8 bolt'circle DWG - 768E534
8. Plug 175A7961Pl 9. Nut 137C3934PI MI-19 SA479 SA18Z7F304 0.38 thick x 1.307 dia.

1.30 thick x 2.62 dia. GC.I 72

                                                          -                                                                                                   Sheet 1 of .2              oz/

FORM N-2 NFT CERTIFICATE HOLDERS' DATA REPORT FOR NUCLEAR PART .AND APPUR.TENANCES* As requircd by the Provision of the ASME Code Rules, Section Ill, Div. I

1. (P) nufa ed by. General Electric Company, Castle Hay-ne Rd., Wi-lngton, N.C.

(Name and addresof XaT Cerflncata Holder) ( cm*r*-d for General Electric Company, San Jose, California (TEBG) Slame4 address ofN Creorai, Holder for omipleted nucleare orienot 2- "Idensdfcation-Certilfcate Eolder's Serial No. of Part A3997 Nat'l BkL No. 768.534GO01 D. L. Peterson Wn Constracred A-ccording to Drawiag No.________ Drawing Prepared by (h) Description 0f P I d Control Rod Drive, Model #7RD3!44DG001 (cý Applicable ASMECode:Section II, Edition 94 W'75 1361-2 1 Ediron..~,Addenda dare -,___ Cese No- ____Class______

 -      mrt-        Standard part for use w-ith. Reactor.-                                             ydrostatically tested at 1820 pai.

CEHot d-it..erpeof -,i.sjo. for vhla), emepoet ... deoic-d)

  • Total ntunber of sheets - 2 we certify thatb te stct=e5s made in this report are correct and this vessl part or appurtenance as defined in the Code con-forms to the rules of coseerocrIon of the AS'E Code Section 111.

(The applicable Design Speciflcation and Stress Report are not the responsibility of the NI'T Certificate Holder for parts. An NPT CeretI-icate Holder for appurt-naace=s is rcspcnsible for furniisýing a separate Dcsign Soccificadon and S-rras Report if the appurtcnzac is not included in the component Design Specification and Stress Report.) S8/26/ 81 GE, NEPD-WD-tNPr CcrdMnote Holden Certificate of Arorizarion Expires Septmber TS, ..T-98 eeict of A oizzzion No- _______ ____ CERTIFICATION OF DESIGN FOR APPURTENANCE (when applicable) Design in.ormntionpon file., GE, NEPD-WMD-OA, Castle Hayne Rd., Wilminqton.. N'.C, 22A5556, Rev.. 2 Stess analysis report no file at GE, NERD, San Jose, Calif. 22A4912, Rev. 2 Design specifications certified ry B. N. Sridhar Prof. Eng. State Ca Iif Reg. No.1 8 3 4 5 Scress analysis report certified by _. N. Sridhar Prof.. Eng. Srate Calif Reg N.8345 CERTIFICATE OF SHOP INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel lxspeceors and/or the State or Province of.,0rth Carolina and employed byDeaartmert of Labor of State of North Carolina have inspected the part of a pressure vessel described in this Partl..aLts Report on 8/26/ 19' l ad state that to the best of wy Icn.oiedLe and belief, the NMT Certificate Holder has constructed this part in accordance with the ASME Code Section I. By signing this certificatc. neithet the inspector nor his employee makes any -arrmany, expressed or implied, concern-Inc the part described In this Partial Data 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 *ay kind arising from or connected with this inspection. Date 8f/2/ 19 81

                               .-          al..                                                                                  N.C. 723,PA.W.1766, OHIO..

aioaO ac-1 seard. stat., provinc, and Na.

 *Cwpiela~aoljI   .h--. Ia t.oro,   lII.  ,n t.,   .       d-ie    a. ny
                                                                       ,b.     -td P-   idea    MI) *La, is 5*'
  • 1t", (2) ifomako*i in ito-ao 1-2 0 this

REPORT NO. P0059-012 Sheet 2 of 2 FORM N-2 NTT CERTFICA&TE HOLDERS' DATA REPORT FOR NUCLEAR PART AND A.PPURTENANCESo As required by the Provision of tbc.ASME Code RuIls, S~cnioan-l, Div. I

1. (m)* .nuEac-u4 6y General Electric Company, Castle Ha1ae Rd., Wilmington, N.C.

(Nam. sod add-t. oNNPT C.*ef.ete i*1re£) (6) a=ure*= d for General Electric Company, San Jose, California (=)C-(Name and addrte a N Ce-ricate Holder fw cossctcd nuclear copom t(roD

2. Ident1icati*n-Certiflcate Holder's Serial No. ofP2prt A3997 -,Nat'l BA. No.

768F53LG001 Drzwing Prapeaed by D. L. Peterson (a) Constructed According to Drawing No-(b) Descripcoi of Pa [msp~cm Control Rod Drive, Model #7RDBl44DG00i S*E"d Sio75 N207 (M) ApplicablAEC=:Smo1, Editi.on 914.-, Adcdnd- date k .. C Czs r. 1361-2 Clzss o-s I

1. Cap 166B9274PI (167A2343)

SA182 - F316 3/8 thick x 1 1/15 OD

2. Indicator Pipe 16529313PI SA312-TP316 3/4 sch 40-seamless pipe 0.113. wall thickness 1.065 max. dia.

3- Plug 159AII76PI SA182-F304 1/4 thick x.0.31l OD

4. Flange 919D610Pl (719E474)
          .SAM8-F304 3.37 thick x 9 5/8 OD neck 1 1/16 thick x 5.0 0D 2.875 ID 5.. Base 137C5311PI XM-19 ASME SA479.

3.0 00D x .884 ID

6. Ring Flange 114B5122P2 SA182-F304 I" thick x 5.0 00 x 1.75 ID
7. Cap Screw 117C4516P2 SA193-86 CONTROL R0D DRIVE 6 ea. 1/2 dia. on 4 1/8 bolt circle DWG - 768E534
8. Plug 175A7961PI XM-19 SA479 SA182-F304 1.30 thick x 2.62 dia.

0.38 thick x 1.307 dia. 73

                                          .                                                                                               ~~Shiest    i     of 2           .-   o L

FORIM N-2ZNFT CERTIFICATE HOLDE DATA REPORT FOR.UCLEAR PART AND ASPeRTT-N.oNCE.

                                                                         "S' Div. I the ASME Code Rules. Section Ill-As required by the Provision of
      .(              .      "       Gemeral        Electric        Comoauy,           Castle Hayone Rd.,                 Wili=.-gton,            N.C.

(NA~,and .4dý e MPT Cznoc.axe huL-nt (b) &iujcc=z= 4., General Klectr+/-c Company, San Jose, California (NEBG) M&Cil and5addMý tc fNCeMft=te Hold- f= rospi-se a-k-o oas~

2. Identfilcation-Ce-rticaie Hiolder's Ser~iz No of Part A4006 4&006 A65 Nat-1 Bd. N~o.____________
                                                                                                                                .L         Ptro (W) Coasracered A=odi=            ; t   Drtt=i g No. 768_534G                   _01 Drairrg Prepared by S:                 of P=                       Control Rod Drive,                   Model #7PDBI44DG00l iNdU/
                                                       , Editri      1974        ,         -          W'75              C zse         1361-2 oC1s_-

(c) A sPiiichi©AS24ECode:Sea-twiz

3. Re-k= Standard part for use with Reactor. Eydrrostatically rested at 1320. psi.
  • Total number (f sheets - 2 Vce c ertify thut the stane=:mus rca~d in this teP=-t ae correctr amd t~his Teaszel plit r W Zpiurtensce osdefined in the Code con-fElaz. to the rules of conrructia cd the ASAE Code sac:io ill (Tbe applicable Desi= Specflcato and Strew Report am not the resprnbttlly of the NPT Cerflcate *Holder for pa-s. An NPT C_-atif-iesre Holder for .p-=ro=nces is rtsporsibit for frutrhion a 3e-m=se Desin Specd.fi*.son sod Strsas R*.p-t if the -,neo=znce is noc included In the comD=net Deslr Seciffcadtoa and SW Repori) 7/20 19 81 -- siczxdBy GE, .D D- J & ._ {i (NPTCe-sfics .Hsddsr Septenber 15, 1981 C--mic=or of .juthorizacicc NPT IN-1191 C-rtiFicate of Atdboricnion E=,i-CERMFF CATION OF DESIGN FOR APPURTENAiNCE (when epp~lica-le)

GE, NEFDD--*A, Castla Hay-ne Rd., Wilor~ngrou, N.C. 22A5556, Rev. -t Screz analyzin rpcot a= file =G:. NEPD--w-D-OA. Castle Havne Rd. , Wilanlaton, N.C. 22A4912, Rev. 2 1j . Demign 3peifiction c=rtiF-id by. B. N. Sridhar . Scre Prof. tog.acc ý c.,.84 z-ni -sis repor ce-tilBed 3. N. N SrIdhar by P.of P -o.E Eu; -S 5=,eC&if e2 Re.

e. No345 No.

CERMFICATE OF SHOP INSPECTION

            . the undersigned, holding a Vli6d coornis*aso i-s=ed by the Nocional Board of Boiler sod Pressure VTssel Lospecor*-

anao/or the Sc=re or P.-oimce of North Carolina mad e=*lyd byDeoarmLenr of Labor of State. of North. Carolina hze inpected the p.r of a pressure vessel described in this r.W Data Repot7/20 on 198_. and state that to the bes c m.y k=owledan and belief. the XPT Certlficate Holder has consrr',cted this pman in accordance with the ASM.E Code'Section Ill. By siz ing 0 this cie-.iticare, neither the Inspe=tror or his employer makes imy anrraoy, e:pri-ss.ed cc ,,ispoied, concc.-,- Icg 'the part described In this Partial Data Report. Furthertrore, neither (he Inspector nor his employer shall. be liable in say mamner for my persmoa.l injury or property damage or a losa of =so kild riezing from or conacc-zed

  • irhthis inspect X.L 7/20 81 8o-N. i, 723,PA, . , C1766,:QH tfAs6-irr- :iascat'w Namtiona- ord. 3Ttat, P-...o -od a..

(I VIM) Thisfelt IDWAQ4elutsy-beamznuraiedorSAre ,S~~j5iS* New Y~cc!rrr. --X. 1C017

REPORT NO. P0059-0!2 Sheer 2 of 2 FORM N-2 NFT CERTIFICATE HOLDERS' DATA REPORT FOR NUCLE.R PART AND A.PPURTENANCES-94+~> ~7 As required by the Provision of the ASME Code Rules. Section 111. Div. I ILi -l. (Mn)Mn.facctxd by -Geaeral Eleccric Company, Castle Havne Rd., Wilm.io..on, N.C. (Hame and addxýa v( NfT CermOncate Holder) (b) Manuiscrurcc foz General Electric Company, San Jose, California (HNEBG) (Na-, and add:m of N Cerftlaczte Holder for completed nuclear componnot

2. Identifcation-Certifcate Holder's Serial N o. of Par A4006 N.,'I Bd. No.

D. L. Peterson (a) Conocructed According to Drz-m ng No. 768R513L 001 Drawing Prcparcd by (b) Description of Part Inspected Control Rod Drive, Model 07RDBI44DG001 N207 (c) Applicable ASM E Code: S ecEion Ill,EdiEio n 1974 ,_Addn_ _de W_75 ,_czscNo. ..1361-2 Cl _ _

1. Cap 166B9274PI (167A2343)

SA182 - F316 Code weld 3/8 thick x 1 1/16 OD P.50YP102

2. Indicator Pipe 166B9313PI 0 SA312"-TP316, 3/4 sch 40-seamless pipe 0.113 ',all thickness 1.065 max. dia. Reactor vessel thimble I
3. Plug 159A1176PI I SA182-F304 L 1/4 thick x 0.812 OD3 4- Flange 919D610Pl (719E474) Code eld
           .SA182-F304                                                              -R.50YP102 3.37 thick x 9 5/8 00                                                                      8.

neck 1 1/16 thick x 5.0 0D 2.875 ID

5. Base 137C5311P1 XM-19 ASME SA479 -

3,0 0D x .884 ID I

6. Ring Flange 11485122P2 SAl82-F304 Code weld 1" thick x 5.0 00 x 1.75 ID - " Pifnypfl n
7. Cap Screw 117C4516P2 SA193-86 CONTROL. ROD DRIVE 6 ca. 1/2 dia. on 4 1/8 bolt circle DUG - 768E534
8. Plug 175A7961PI 9. Nut 137C5934P1
                                                                                                   'MI-l9 SA479 SA182-F304 0.38 thick x 1.307 dia.                                                               1.30 -. iir- x2.62 74
                                          -                                                                                                Sheet 1 ot' 2
               -FORIM      N-2 NP`T CLIRIIFCATE HOLDERS' DATA REPORT FOR AMCLEA-R PART AND A-PVRTz-N.A-NCZS-Aurcqufrcd by the Provision of the ASME Code Rules. Sceddon Ml. Div. I9~iJ L (n                 -- =ib           Cvene-ral Ellectric              Co~oan-y,        Cast-le Eayme Rd. ,                 W+/-.Imngtaa" N.C.

r Geme-ral fb)o M1ectric Conman-y, San jose, Cal-ifornia (NM-3) An 2ztn (N=M L2e(Cm-tdcate if Ocddýroro~nfseg ==Jeu co=ý 768ES34rG001 D2. L. Paterson (n) Conc.-nc=ed Acn--ord=;; to Dr--4ing No. _ Drawing Prepared b-/ (b)Desdpd~~Control Pod Drive, bfodel #7ElBL4-4DGOOE Wc Appiiczhle ASKE Code. Edirian Elcionn, Add,=a d~c ,Cae No._1- - 1=

          .Rcas-       Standard part for use with Reac-tor.                                    HydrostatLca-lly tested at 1820 Da+/-.
  • Total. number of sheets - 2 Ve ectrify rhacthe srsrtem,= mjkdL in this report are- correct afad this Vessel pert or ==port==ancr zandc~eS,1~ in the Code con.-

forin to the rules ýLf eonso'ctioa of the A-'iýIE Co3de S-crion 11T. M~e applicmble Desiz Specilcation and Stress Re-por are not the re pordblillti of the XT. Certitlcale Holder for pax-m. Ax NPI' Certi-iczte: Holder for appurtcasmcca is r conibfc for furni:-hiog a sepn-Atc .Deini Speeifirzrion tad Stress RprtT if 'be a.tren i o Included Inethe coaepookent De~sten Spectffcajion andi SUTisa Repo-r*.) _2/24 in~d CE, G NEP-r,1D-- 1984 offa IP T N- I 15 eriiaeof An~zhori~xtion Eanires. ~ .~e'5 94Cfcn rixsaic= No.________ CERMFICATION OF DESiGN FOR APPURTENANCE (when aplp- hle) Desig ormirono file GENERAL ELEMTRIC CO., SAN JOSE, CALIFORNIA 2945556, R~ev. Z.° s-*, =,,r~s -*:=,.*.ai *GENERAL ELECTIRI'C M4*,. SAN JOS.E, .CALIFORNIA 22A4912, Rev. 2 ' Deeign speciirsew.ns e by B. N. Sr:dhar Proi.. Stare Calif Reg.N._8345 sMeS3 aMaiysra reporCti~ B. . N SrLca Prof- Eng- Scurc Ca.4:L Reg. No.ý 4 CERTIFICATE OF SHOP INSECTION I, the amdermnigeil, holding a yalid cc="s;ion issa-tL by the Natona.1 Boerd of Boil=r and Preas-ue Yeasel Iaxe=-rr ed./or the St=e or Pro:inceof North Carolina" ad =.ay,*d byDaoarumat of Labor of State of North Carolina hmýeCinapee-ted the part of a pressure vansel described in Chis arutla Data Fteprt on-. 2/24 _ ,"88zasmt. that to the b.e ofm knowledze and belief, the NFT Certlicae"Holder has .crmstrcted this Part in accordance wih the ASM.E Code Section i.

       . By alxng this certificxne, neither the In-pecror nor his employer mlhes 4ny arrm-cty, =pressed c c                                            ied, concern-ini the part described In this Partial Data Report. Furthermore., neither the lnspector nor his employer shail be li&bze- in ay- manne*r for ay personal injury or prert7. desage or 2 loss of any kind arisin; froor or coamc-ecd Wich Chia itaEpecdron.

2/24 83 3 Dat Ct -- 1 as ona 723,PA.WC1766, OHIO ~.n Ia4aa-ror's Si~ss~sw. ' ?CatiaaI Sao-e. Stata, ?roaeisa. -d MOs. 5

           ~1aaa2i t.*Uir     lasS Of !a-4, .aksbvx or draOwnxX =      beozaod proa'ida (0 1)   L- 5%

NW' 2 11" (2) iL.-Lda In Lt.. 1-2 Ms sthl This form lEOOOaAW miry ba obtinind from the Order DeM., ASME. 34S E.47 th St.. New Yorie. N.Y. Dal17

REPORT NO. P0059-012 Sheet 2 of 2 FORM N-2 NI'T CERTIFICATE HOLDERS' DATA REPORT FOR NUCLE.AR PART AND .APPURTENANCES3 As required by the Provision of the ASME Code Rules, Section II, Div. I ((C

   . (-)*              b. General Electric            Company        Castle Hayn-e Rd.,                  Wilmnzton,             N.C.

(N-e .. d .ddr--. of liFT C=-nCtO-e Hold--) (b) Mnufcrurcd for. General Electric Company, San Jose, California (MG) N.,e wid addr-, otX Cer"l~col. Hoer fo1op wpoletvdtucIeur :*ma-opacnt

2. Ideoetifation-CertMflrate Holdez's Seria] No. of Part M115 N 'i Bi. No.

(a) Conatemcmd According to Drzwing No- 7687B53GO01 Drawing Preppred b, D. L. Peterson (6) Descripcion of Pz- Insptc-ted Control Rod Drive, Model 67iDBl44DG001 N207 (c) Applicabie A94E Codc: Sccion III, Edikio 1974 Addcndadate W'75 CzseNo. !361-2 Cjass 1

1. Cap 166B9274PI (167A2343)

SAl82 - F316 Code weld-- 3/8 thick x 1 1/16 DD P5OYP102

2. Indicator Pipe ]66B9313PI .2 Ir SA31 2-TP316 3/4 sch 40-seamless pipe /

Q,13 %.,all thickness 1.065 max. dia. Reactor vessel thimble

3. Plug 159A1176P-i SA182-F304 1/4 .hi.ck x 0.812 OD .-
4. Flange 919D61OP1 (719E474) Code wel d
            .SA182-F304                                                                 -P.5YPI 2_--L<

3.37 thick x 9 5/BO0D neck 1 1/16 thick x 5.00D 2.875 ID Base 137CS311PI XM-19 ASME SA479 - 3.0OD x .884 ID "

6. Ring Flange 11415122P2 SA182-F304 -- Code weld I' thick x 5.0 0D x 1.75 ID PsnYPi1nP
7. Cap Screw 117C4516P2 SAl 93-86 CON1TROL ROD DRIVE 6 ea. 1/2 die. on 4 1/8 boltcircle DWG - 768E534 I.

8.- Plug 175A7961Pi 9. Nut 137C5934PI " XM-19 SA479 SA182-F304 0.38 thick x 1.307 dia. 1.30 thick x 2.62 d-4 75

Sheet 1 Of 2 2r2

                      . FORM NT.-   .NFTr        CERTIFCATE HOLDERS' DAT.A. REPORT FOR NUCLEAR PART AND AFYtJRTENANCS-.

As required by the Provision of the .ASl{E Code Rules. Secrion IIH. Div. I L (z) = General _lectric Company, Castle Hay-ne Rld., Wilmington, N.C. (Lab~am& dac.2 fNr Cnle H.Idcrc SGeneral Electric Company, San Jose., California (NE:CG) Mace- dd= am alnel Ho~ridot5ere~e c ta4cdea,

           '.       -'A421                                                                                                6 768&E534GO0l                                             -             D. L.         Petarson (a)     C_=crn~c4 Accrd___to________                      o6                                    aming Prepared 67 1

(b) D--*. o* P-

  • Control Rod. Drive, Modeal i7RDIB44DG001 (c) A;p*Li-*eA*~eIS Ft -didoeTE974n -- eioiIdiioe
  • A- __ W'75 C&=.No_ 1361-2

_ Cl&=s . Standard part: far usa with. Reactor, HydrostaticallT tested at 1820 psi. (oE~ra eoate-+/-rioa= t -wcv o which caxc aspco

  • Total rneber of sheets -

Ve c-ifr dmarthe- sraremn me= in.ri repore- corrcrt -4 dhis veszcl pacr or pp*n=-mrnce as defined in the- Cod= coi-. Gon de th Mica of coa=Metina. of the- A -1:1E C11etinIL (The applcable Desian- Spedilcation. and Stre. Report are, not the r-po.nzibility of the. N'r Cerdiflcate Hodear1or pmtL An NFT Ceti-i*eJ Hodad for xppurtrc i3 responsible- for furniching- a scpmae Design Specification amd. Stres Re=p if the- r is' not. Lancluded xr. tlie component D~eal=n- Specifleatinn and- Sftrrn- Report-) 0---- 6/23 ~.81 GE_,. NXPD-WMID -______________

                                                                                                )N~r CefW.iiHeICM

____________________._A~horiazei*, No. __I__________ Crifaimc of Ahoriza E=-pin -,- September- 15, 1981 C=-dficz=r of. ________________ CERTIFICATION OF DESIGN FORAPPURTENANCE (whber epplicable) Desmi'gfor*ainoon file . GE,'NEPD-WMD10-A, Castle Hayne Rd., Wilninaton, W.C. 22A5556, Rev. Z srr- sli.r ou M n GE, NE.D, San Jose, Calif. 22A4912, Rev. 2 De:xip =pecificadoon cercified by B IT1 Srid~har .Pmo. nS.Stx:eCa-lif Reg. N___3_5" S~= **y.i *c*..i**3m . Ng. Srldhar ,- E. ,zCali~f ""_,' 3 ____835 Srz,ý=a analyxis reporr cýertifiecd N.___________________ Prof. En.Stre____ RKesNo.

                                                                           -     CERýFCATE OF SHOP- INSPEeTION t,   the undarmigmed, holding a raLid conanissiom isnued by che Na=ional Board.of Boiler and Pre-asre Vessel Inspecntrs and/or the Sarne or Province of N0orth CarolLna                                               uad mplcyed ýyDepaz-mant. of Labor of               State of North Carolina                                                      hue inspected the part of & premare, vessel deseribed in this patnil Daa Reort o and bebef. the NPT Certiticati Holder has canitucted this Part In accordance with the ASME Code Section 10.

6/2 198. Catd= that to the betofrr ~naw lefte By signing this certificate, neicher the Inspector nor his employ mt--kes may warrnt'y, expressed or implied, concear-Ina the part described In this PartiaL Data Report. Furthermore. neither the Inspector nor his employer, shall be liable in =y- manner for any personal injury or prprtrdemnsage or a loss of =ny hind zrising. Erco oo connected with dais inspec-=on. Dat 6 2:ý 81 ___________ C o ~ Xt R7,PAaMne.SraPr1dea la U.V..r 1U,...n. ,- .i r~5 m -,eaC).. .5 I (7 19~r- 1..aS.t. -d N...OO1 .. o... 2St1P It * -77 fUC -. k. -h- - fA or-7(Id.mfl I. b I- t.. L) U. ix Orde I (2)aI

                                                                                                                                                .                 348 .      7-2                         .0091 (I1G[77)                                                     This form (EDOD4O)rny be obtained from tha Order Daot.. ASME. 34S E. 47th St-. Naw York. N.Y. 10017

REPORT NO. P0059-012

  • *.. ... "Sheet 2 of 2 FORM .N-2 NPT CERTIFICATE HOLDES' DATA REI'ORT FOR TJCLE._R PART &".D .J URTENANCES-As re-quird by the Provision of the ASME Code Rules, Section III, Div. I M-=la*--e__u-Gener~l.

t.(6 Electric Coanany, Castle Eayne Rd., t'i2 in*ton. N.C. J(N* a= ado-*a lIST Crt-rfl~.au Holder) (6) Mt--imcru.-d fat Genera.! Electric Company, San Jose, California (1ýG) (Ný ~badd4 of m Cenfficate HcddT for compe.e=n4s~ 2.ldnnea c -Cs.*rti~eae Holders Sertal.No. of P.,- A4216 --

  • ar Bd. No.

rminoed A.-oroin& m Drawing No. 7 853& QQ1 DrzD..Pr . ..D... L. Peterson (m) Cone (b) Dez=ipcion of Pamr Inzpected Control Rod Drive, Model #t7!DB144DG001 "7 "7 N207 (c) .ddczbadaLWE Code: Sadari= , Edia;-. IV. ., **dae.Q5 .d' C--teNo. 1361-2 Cizzs I

1. Cap 16689274PI (167A2343)

SA182 - F316 Code weld---_ 3/8 thick x 1 1/16 OD P.5YPI02

2. Indicator Pipe 166B9313PI I SA312-TP31G 3/4- sch 40-seamless pipe 0.113 wall thickness 1.06a max. dia. Reactor vessel thimble 3'. Plug 159AlI76PI SA,18-F304 L 1/4 thick x 0.812 0D
4. FTange 919D610PI (719E474) Code weld
               -SA1I82-F304                                                                - POYP102f 3.37 thick x 9 5/8 OD neck 1 1/16 thick x 5.0 OD 2.875 ID
5. Base 137C5311P1
  • XM-19 ASM4E SA479-3
                 .00D x .884 ID                                              -
5. Ring Flange 11485122P2 SA182-F304 Code weld I' thick x 5.0 00 x 1.75 ID D;nyPin2
7. Cap Screw'II7C4516P2 SAl93-B6 CONTRQL ROD DRIVE 6.ea. 1/2 dia. on 4 1/8 bolt'circle DWG - 768E534
8. Plug 175A7961P1 9. Nut 137C5934P!

SAl82-F304 XM-19 SA479

             .0.38 thick x 1.307 dia.                                                                  1.30 thick x 2.62 d-ia.

00213 76

Sheet lof 2 F0 FORM N-2 NTPI CERT CIATE BOLDERS' DATA REPORT FOR NUCLEAR PART AND A.PURt'4NAJ4CE*SO As required by the Provision of ,he ASME Code Rules. Section I11. Div. I

      .(e).          .c-e     b         General G              Electric       Company,          Castle Eayne Rd.,                  Wilng--n,                  N.C.

Mt=~ =d d~-.(X?,~ T C~eOleotc Holder, (b) Ma=fmc--*.e for General E-ectric Company, San Jose, California (N-E3C) (No.=d aed d .r cdo,-onnoe: Hiold-r lee e=Ictv.d scear eePesee 2- l~e lt;cni-Crt1flczte Holder' seria. No.o A4250 N .d. N4o. Drem-ig Prcpnre4 by D. L. Peterson (a) Czo=m=sr=ed A =ordimg to Drzohima No. 768EF-534&GO01 Control Rod Drive, Hodel #TRDBI44DG00l

          )                                               ,           1974                              W75         _1361-2                            e
                            ~AE     Cde:

(e~ Aplicb~e intditi 197 a 7 Cesa 140. ____ Clzz______ "3. Re --- Standard Dart for use vith Reactor. Eydrostatical17 tested at 1820 pei.

  • Total number of sheets - 2 We certify that the nr~ewmcar meda in this rayr mre co-rrect. aod th.ia ,'ene pzrtr ur "0 -eoece asdefimed in the C-de cuo-forrs to che rales of ao s~octi=~ o4 the A.9IE e fSectiou III.

(The applcable De!ni= Specification and St:rem Repot are not the resonsibility of the XFT Ce-.tflc*w Holder for parts. AnfT CeX-f-i:zt Hokfar for 2vpurtrnao is respon*ible for hur shing i 3se-tsuc De*zir Spec-ific*aonxod Srts eport if the snrten.=c= is not ltaciudell In the cvraronent Design SpeciMatlco and SL-ess Report)

            'ae____________              19    -     Si~med Certificu.te of .Authorizo                 E---ea         September         15,    1981          Cc=              *.frLi,-Zo'-C            No. NT N-1l51 CERT7FICATION OF DESIGN FOR APPURMTENANCE (when applicable)

Design imormaion onfile GE, NE.D-ýD--QA, Castla Hayzne -M., WTlz'*lgton, N.C. 22A5336, Rev. 2-Sre==a analtrxi. repom . file . G-4. 1j'D-WMD-QA, Castle Rayne R-.d. Jil-m-ngton, N.C. 22A491.2, Rev. 2 Design W*-*rmerio* c-.-f'ied by .B. N. Sridhar pro.f. .1sS.... Calif 8--3&5 Streas soiysis. rr-et certified 3B. U. Srdhar o. i.,. , Calif Re;. CEriMFICATE OF SHOP ItSPECTON I. the undersigmed, holding 1 vLid comniss=icr imnsed by the Narional Boird of Boiler and Prcm=re Vess.eL nzpec-.ors

    "-doe the Store or Province o Norrth Carol-nla                              and emploied            2De2arrSent of Labor of              State of lorth               Carolima                       hhave in=pectcd rtse p"n. of a prezsure Tessal described in uis Pmarital !MCAFte:>om on                                                  7/23                          iS1.andstate.-at to the best of my lowiesde and bellf, t-he NP Certificate Hoider has c*.stIucted this par In accordance with the ASME Code Section lII.

B- signxing this certificzme,' niýeiher tie Inspector nor his emcployer make.3easy .rrsny- * =;prmazes- or inmticd. cooce.-- lniz the part described Il this ?itartal Data Report. Furthermore. oelther the Inspector nor his emPloY-er shall be liable in any Motnexr for =y personal inj'r-7 or prop-rty d=nage or L loss of xy kind arising from or co=necied itch *his inspectiona. Dar., 7/23 19 81 NC. 723,PAU C1766, OHIO

                         .e,        r    5                                     Comm3-.io                                             1.t.. Pt-            -    Me G                                .                                                                4--           .atir..,                       .

tSrn e cr Y ('*o-m7 Thin ico.-n lESO4QreOr,- o cotoad-~il ".-rr Cooer~it.i'..-,i 7-, --- lSt.. 'Jew "err. N.Y. (OO17

REPORT NO. P0059-012 Sheet 2 of 2 7 FOR.Mf N-2 NPT CERTIFICATE HOLDERS' DATA, PEPORT FOR 'N-UCLEAR PART AND APPURTENANCES, 1'- / As required by the Provision of the ASMfE Code Rules. Scctiun Ill. Div. I

1. ).n) arcturced b General Electric Company, Castle -Ra5~e Rd., Wjnlinczon, N.C.

(Name .. d adde of NPT Cer. lcste Holder) (b)Mancfac=Eed for. General Electric Company, San Jose, Califor-nia (IN=,-.G) (NM ne and addres o* N CertilCate Holder for comlveted nuclear component)

2. Identificaton-Certificate Holder's Serial No. of P-ort A4250 NoVl Bd. No.

D. L. Pe-terson 7685F 35CA00I Drawing Preparxd by (r) Constructed According to Drist-g No. (b) Description of Pert Inspected Control Rod Drive, Model #7RDB144DG001 1 (c) Applicable ASME Code. S*cdon L,1*,Ediion 1974 W 75 , Cse N207 Addc____ a date as,*qo 1361-2 Class

1. Cap 166B9274P1 (167A2343)

SA182 - F316 Code wel d---. 3/8 thick x 1 1/16 OD P50YPI02 IQ

2. Indicator Pipe 16689313P1 SA312-TP316 3/4 sch 40-seamless pipe 0.113 wall thickness 1.065 max. dia. Reactor I Ratrvessel thimble I
3. Plug 159A1176PI I SA182-F304 L.

1/4 thick x 0.812 DO

4. Flange 919061OPI (719E474) Code weld -
          .SA182-F304                                                                    --., 0YPI02 3.37 thick x 9 S/8 0D neck 1 1/16 thick x 5.0 0D 2.875 ID
5. Base 137C5311PI XM-19 ASME 5A479 3.0 OD x .884 ID
6. Ring Flange 114BS122P2 SAl82-F304 Code weld PSoYPI02 I" thick x 5.0 0D x 1.75 ID P5OYPlO2
7. Cap Screw 117C4516P2 SAl93-86 CONTROL ROD DRIVE 6 ea. 1/2 dia. on 4 1/8 bolt circle DWG - 768E534
8. Plug 175A7961Pl 9. Nut 137C5934P!
                                                                                                      ýN-19 SA479 SA182-F3D4 1.30 tiiak = 2-62 diA.

0.38 thick x 1.3.07 dia. 77

Sheet 1 of 2 -q4' FOMSzN-2 Nr-r CERTIFICATE HOLDERS' DATA REPORT FOR MJUCL-A.R PART AND ALFRTE.NANCES . As rnouir-d by the Provision of the ASME Code Rulis. Sertion 111.Div. I

   .        .             -    y-Generai Electric Company,                             Castle Hayna Rd.,                 Wilming-on,             N.C.

(b) -or General Electric Coopany, San Jose, California (NP_BG) (NEaszd zddrs_ rfN Ce-ofleste 140kdr for ranfoiete a-iee c=ný=o'

   . Idet8zn-Cs*r-Acate Holdev's SetialNo. ofPart                                 A4483                         N (a)     C==ixncted Accoziing =o Dre'smnl No. 76F54O1                                  Dre-ial Prc=pared by              D       .Ptro Control Rod Drive,                              #7RDB144DG001
                                                                                                        #odal 1974                                W'75                         1361-2 (c) A-z-o ic-e ASE CoJd: Secri*               III, Ediri'                     Aoa_==                          , Cn-e Noý_C__-_                    _

3 .,-,,. Sjandard part for use with Raact*r. Hydrostatica!ly tested at 1820 psi.

  • Total number of sheets - 2 Wecer~fy chor: the szz~ec-3r -4ed to rhiz r~ are cx-nrect C.~

hia veMSel p=r or pZ.U oc s eie ndi oeco for."s t the rules of oo:xsrmc-= of the ASiE e Secton Ii. (eb-e aplicable Design Specfl*calon -- d St rM l;oort are not te respooslbliltY of tbe MPT Certilcte Holder for pa:--& An N.T CerOl-icue Hfoldier foe zippwurenancza is responsible for furrdshing a %epsiarwe Deaign Spci_;5ndoo and Striss Rapozt if the aprcn is not -tocuded In Lbe component Deslam SPeCIfl+/-estin and SoESmSenrL) 7/23 81 GE, ',*-D-W1'KD-QA ______________ 19 - Siged B Ce ofificte of Aucb-i= t E=pj-es Sentember 15, 1981 C-rcircmm oif Lhorizsion. No. nPT N-LLS CEWIFICAT1ON OF DESIGN FOR APPURTENANCE (when applic+/-ie) Dczar~i,*fotmadon oa file CGH, Nh'*D-*fDA, Castle Hay-ne Rd., WilmIngton, N.C. Z2L5556, Rev. 2-Sa-ess ,mlysix repo a File = GZ_ ZD-WMQ-OA, Castle EaT-ne Rd. , Wilmi.-n4agon. N.C.

       .2A491_2, Rev. 2 Desiga speciii-aions, cer.ified, by              3. N. Sridhar                                             Eng. St.e Calif      L     ER. N     -345 S[r-sw- asxl           reprce*iqed               3. N. Sridhar                                      PrL          =.Ste Calif            Reg.            _o.18345 CERIFI-%CTE OF SHOP INSPECTION

[,the underzij-ned, holding a valid coteteizzooa i=sued by d-e Nazionzl Board of Boiler ind Pressue Vessel 1nspectors

     'ed/or the       Scare of pmr,,-to- a      North Carolina                 ad Proptored byDeparr--Ment of Labor of             Stare     of North Carolina                               ha"      insqp-eted the part of & pressure vessel dscri6bed in t.is 7/23                           is - an d-. ztsex    tat to the besto-f m -7 IzowleJd ce eand beief. the NPT Certil.cate Holder h-. cooz'icted this Part in accordance with the ASME Code Setcton LEI.

BY sining this certificace, aeicher the sot his am nosp,*tor nsl-es any wn..rcy-, expressed ar implie-d, conce-i-

                                                                                                -zlayr ins the Part described In this Partial Data Report. Furthermore.                                      ne!ther the Inspector nor his embployer shall be liable in my mtanner for ay persoosl injury or prope-'y damage or a loss of Lay kind &rising froa or cptsnac-ced
     ýith :his inspection.

Dare7/23 81 N.C. 723,?A.WC1766 1 OHIO 4-1o,-a Coard. stat.. P_-.- ad to ~

10l7T) 7 hh.forrn tE0004O ransy-b orrmnod ýrar;L Xý St. 'lie- Ior,- Nf.

Y- 00

REPORT NO. P0059-012 Sheet 2 of 2 FORý' N-2 NPT CERTIFICATE HOLDERS' DATA REPORT FOR XNUCLEAR PkRT AND APPURTENANCESC 0!7420

                                                                                                                                                         ,,7 As recaired by the Provision oF rhe A.SME Code RuIes. Sctzion III. Div. I
1. (a)M~nufaccLrcd by. General Electric Company, Castle Hayne Rd., Wilmington, N.C.

(Name aRd addreaa Of NKT CeUo CatLe Heol.dri (b) Manuf*ccred fox General Electric Company, San Jose, California (N'3G) MNare and add&,n of N Cera fci-e Holder (or comsplted nuclear comnoeao

2. identtfcation-Certifleate Holder's Serial No. o( Part A4483 Sd. No.

BNa'l D. L. Paterson 768E53LtGO01 Drawing Prepared byI [-) Constructed According to Dracing No. (b) Descripclon of Parc Inspecizd Control Rod Drive, Model #-7RDB144DGO01 N207

                                                                              , Ad d_                5     _d_          No .

sWe7 13 6 1 - 2 ClNs2 ( c) A notic on II I, E d c otin 1 9 7 4 a b le A SME C o d e : Se c ti

1. Cap 1-66B9274P1 "

(167A2343) SA182 - F316 Code vield 3/8 thick x 1 1/16 OD P50YP102

2. Indicator Pipe 16689313PI SA312-TP316 3/4 sch 40-seamless pipe 0.113 1,0655mx .;,.all thickness dia.

5max. dReactor. vessel thimble

3. Plug 159AI176Pl SA182-F304 L 1/4 thick x 0.812 OD
4. Flange 919D61OPI (719E474) Code ,aield
           .5A182-F304 3.37 thick x 9 5/8OD                                                                     'DO neck 1 1/16 thick x 5.0 00 2.875 1D
5. Base 137C5311P1 6 XM-19 ASME SA479 A .

3.0 0D x .884 ID

6. Ring Flange 11485122P2 SA182- F304 I" thick x 5.0 00 x 1.75 ID - PrnYpl2p
7. Cap Screw 117C4516P2 SAi93-B6 CONTROL ROD DRIVE 6 ea. 1/2 dia. on 4 1/8 bolt circle DWG - 768E534
8. Plug 175A7961PI 9. Nurt 137C5934P1 YM-19 5SA479 00880 SAl82-F304 1.30 t4,i 6c-x.2-a.22 dia 0.38 thick x 1.307 dia.

78

                                 -.     -                                                                   /3/2'     /~/6./~5-12-.Theec                 1 of 2
             ..,RUU N-2 C4PT CERTMFCAYE HOLDERS' DATA REP'ORT FOR NUCLEAR PART AND APPURTE-ANCBS, As required by the Provision of the ASME Code Rulei. SAecrion U1I.Div. I                                                         /~L
                        ~~          G.ýe-nera]. Ziectric Comony                         Castle Hay-na Rd.,                  W    "'ý-'  gton, NT.C.

t~LN a00ýda-em (~NP1 CUfcz1&cLHoidwn ('4- faýGeneral Electric Company, Saxi Jose, Califzornia (1'TZBG) tMta .2d a~oN Cerudcnt. Hodr od =ew ý

                             -- =Holder's Sertnl No- of Pan. _____________7.'                                                     14c..
                                              ~   D~i   ~768Z-534G0Q1                                         rpzdb               Drwo
                                                                                                                                    . L.       Feterson

(~ ~c~cmi i ~Control Rod Drive-, 'Modal &7hD3l44DG001 b~~AEC de eeire , 1974 W'75 L361-2I E Cod= *c' No.iý C111,__________ SLndr pKr oruewt eao-. Rdostatically tast~ed at 1820 pal. (3-1.1 "aoipU- f -.. ~oIo- -hioN -P- e - 41 STotal. onmber, of sh~eat3 - 2-Ve czrify thar the s~ia oeei hxreo recormret xnd:Ethim vasel perr or zppuoraaaocc z3. dcfined, in the Code-coo-cc=- ca: mw rules- oi comP~oetioa of the- ASME Cfodc Secricon Ill-Zhop-a=L-able DesIdn Socelflcatlan~. and Streu Report are- not. the. rfnr'oosibUltY of the ITP1 Cet-cOflent- Holder for parts An NFr Certif- =+/-e- Hiolder for 2ppurt=Lacre is respoes~bl for ftumisltin za separatc Desig,. Spcafcdor. and Stiress Report if the 2=purtMnce=c is not-aci uded. Urf the comoponentL D .S pecitication. and Srtz-sa Repom.j 12/30 19 ~ ZD-DQ (N7! CerdAlcte Hold=,, i~cr-of Anchorizerioa Epi- June 16, L981 Cnroficaor of kurhorizz;:ic;o_ MNETN. CEIMfFICAIION OF DESGN FOR APPURTENAtNCE (when. zpplicahie) DesiGE~ E'D~D--qACastle Hay-ne Rd., W1Ilminogron, N.C. 225.36,- Rev. 1 Snzz~ -axyiysi rnport. ca Fil atG. =XP-WMDO0A. Castle Rayne Rd., Wilm-ington. N.C. Z2A4912, Rev. 2 De-dia = cifi-kcsoas certifled by 3. 'L. Sr-idhar Prof. Eng. Scare Clf a.~~84 3 Sc=ss zaodsiyei r-poct crrtified S. B, N. Sridhar P-o.Fn.t Scr~CalJf Rex..N4o )8 Z CERTIFIC.kTE OF SHOP [NSPECTION

1. the undersigned!, holding x vmLid coaLashior issued by the Na.ionxJ Board of Boiler Lad Pressure Vessel Ens.e=eors and/or the Sacae or Province of North2 Carolina .ad c=pLoynd byDeoarmenr of Labor of Sa.CSta of Nor'th Carolina have iopecred the part of a prm=ur-e e:asel described in this 8 0 Partal Dlta Report ei 12/30 s 9 an.dtathat t te best tYInowledse rof and belief, the .PT Certdcate Holder has coi ,_-uteo this part In accr-diance ttiththe ASME Code Section I1.

BY igining thiz certifice=, neither the inspector nor his cral.oyer mak~e cy w.T.ancy. et=rcsd cc im-plied, concern-- ton the Part described In this Partial Oata Report. Furthermore. neither the Inspector nor- his em.ploYer-

  ýr-ad. low liable in any manner jar =y pers                     .aLinjur-y or pi'p-rry damage or a. loass oi my kina aristrng fro or connected witr- dhia inspec:ion.

12/30 80 Caasoi siana ~ 779 OAMWCLGO, OHIU. Z' 4S C~rnl71 o,1OO~myo~aan fhu romr u~_Dre 5A1.~ 4tntf.Ns ~r 10017

REPORT NO. P0059-012 Sheec 2 of 2 v'/ FORM N-2 ,NPT CERTICAZE HOLDERS' DATA REPORT FOR -NUCLEAR PART A1ND APFURTFLNA.NCES- .. As required by thc Provision of the ASME Code RuIts. Sctiorn £11. Div. I

        -          by  Ceneral G(=          F-acrr:c Com~any,        Casc! e *avne Fd. , W!1mi =-ton.                  N.C.

LN-. -I d&- 19 MPT Cý]3. HWIL-i ( - f, CGenera1 Eiectric Company, San Jose, Califor'-a (N=,G) S;--'--Ce.O.lc~tFHolder's SeriaL No. of Par: A4537 .- `1' Bd_ No. D. L.. Peterson 768=43A001 Dr=-:im Pp*=d by DL t (m) C=zmc*.*ed According to Dtr=ig Noý. (b)- =ipdon oi ?%z- l-s.ed Control Rod Drive, Model- J7RDM4LOGDO01 N207 t (c) App9TkSECo.Sc IEdri= .974 ,A*-d*= W 75' C No.. 1361-2 ChZi_, T.-. Cap. 1669274Pl (167A2343) SA182. - F316 3/8-thick x l 1/16 D' 2L fndicator- Pipe 16689313PT SA312-TP3"1I 3/4ý sch 40-seamless pipe. (.V13 v.'all thickness T.065. max. dia.

3. PIugF 159A1U7GP1 SAI 8Z-F304-1/4-thick x 0.812 O.
4. Flange 919DI0"PI (719E474)

_SA182-F304 3.37 thick x 9 5/8 OD neck 1 1/16 thick x 5.0 OD 2.875 ID S. Base 137CS311Pl SI XM-19 ASME SA479-3.0 00 x .884 iD

6. Ring Flange ll4B5122P2 SA182-F304 l" thick x 5.0 0D x 1.75 ID
7. Cap Screw ll17C4516P2 SAl 93-86 CONTROL ROD DRIVE 6 ea. 1/2 dia. on 4 1/8 bolz circle DWG - 768E534
8. Plug 17SA7961PI 9. Nur 137C5934P1 XM-19 SA479 SA182-F304
                                                                                   -    1-3a52ia 0.3a thicx x 1.307 dia.                                                             .. .. L  ~~h**
                                                                                                          =
  • Pi* .. *?.....

79

S.Sheet 1 of 2, FORN N-2 NPT CERTIFICATE HOLDERS' DATA REPORT FOR NUCLEAR PART AND .APPURTENA-NCES-As re uired by the Provision of the ASME Code Rules, Stctiou III, Div. I

1. (a) Mafamcmed by General Electric Company, Castle Hayne Rd., Wilmington, N.C.

(Name and addr-ss of NFT Certlcate- Holder) . (b) Ma.tfacrud'ifo CGeneral Electric Company, San Jose, California (N-EBG) (Vs, aa* addrm of N CerJttUCZt Holder for corolcimed nuclear coonponent'

2. ldentFlfcations-Cer'flcete.Holders Serii No. orf A4582 Nar'l Us. No.

(Z) Constructed According to Draving No. 768o34G00 r ped by .D. L. Peterson Control Rod Drive, Model #7RfDB144DG001 (b) Description of Pa-s Inspecte*d 1974- W 75 - 1361-2 1 (c) AppLicable AS4E Code: Section III, Edition - , Addenda d --- _il5 , CaeNo. 1361-2 Class

3. Remarb= Standard part for use with Reactor- Hydrostatically tested at 1820 p.s+/-.

(BRnt dencr-iplos of on-ic. f-or hlch emneoneat wa decicondl

  • Total number of sheets - 2 We certify. shat the srace-ocsrs made- in thds report are correct and this vessel part or appurtena=c as defined in'.te Code coo, fotes to the rules of coasarucion of the A-94E Code Section lIT.

(The applicable Design Specification and Stress Report are not the responsibility of the NPT Certificate Holder for parts. Aln NF'T Certlif-icxte Holder for a.ppurt'nnces is responsible for furnisýing a *cparato Design Spccificadon and Stress Report if the appurt"nancec is not. Included in the combponent Design Specification and Stress Report-) Datrt sig..t GE NP*ED-WMD" c o (NPTrCtieatiloe Holder) pirew September 15,.T981 Certific"te of hrizni*on N4 KPT W-115= Certificate of Authonz'rt CERTIFICATION OF DESIGN FOR APPURTENANCE (when applicable) Design inform -rion on filec GE, NEPD.-WMD-OA, Castle Ha yne Rd.., Wilmington., N.C. 22A5556, Rev. 2 -GE, NEPD, &an Jose, Calif. Stress analysis repoct owr file at________________ ________________ 22A4912, Rev. 2 Design speciiicadons certified by B. N. Sridhar Prof. Eng. State Calif Reg. No*8345 Stress analysis report cerified . B., N. Sridhar Pr. . Fag. &are Reg. No.1345 CERTIFICATE OF SHOP INSPECTION I, the undersigned, holding a valid coommission issued by the National Board of Boiler and Pressure Vessel Inspectors and/or. the Sctae or Province of* North Carolina and employed byDepartment of Labor of State of North Carolina . have inspected the part of % pressure vessel described in this P.artal Data Report n . 8f26/ 19 . and state that to the best of my knowledge and belief, the K'PT CertifIcate Holder has constructed this part In accordance with the ASME Code Section 13. By signing this certificate, neither the Inspector nor his employer makes may warsnry, expressed or implied, concer-n-ins the part described in this Partial Data Report. Furthermore. neither the Inspector nor his' employer shall be liable in any mianner for any personal injury or propaery damage or a loss of any kind arising from or connecred with this inspection. Dat

                                --81 6Y  --                       ' 1                                                              723,PA.WC176G
                                                                                                                              .G.                              j+ )4 Dt-8                                                                         Commission.                                             S
                                            "    inp*/*o*-a             Sh~atu*N-1-.1                                          Board, S~tat.      Province ýud No.
 *oPPiee=W~     sh-tl   ia foc If Li-,. nl,.,b.      -  d-.n.os      t   I-od   p-id-~     (1)   L=I. Un Pý    I 1", (2)  iLnrsntio  i, It-n   )-2  0   1

REPORT NO. P0059-012

       .....                                                                                                  'Sheet 2 of 2 FORM N-2 -N'PT CER=ICATE HOLDERS' DATA PEPORT FOR                             CLF-AR. P.ART .4ND AYPPJTZTFNA.NCES                 443 As reuimred by the Provision of the ASIME Code Rules, Section M. Div. I L (e)          cz-diy*     General Electric Compan7,                  Castle Hayne Rd.,                 Wilmigntom,          N.C.

(Nc. and ad-m ofNrT f CerfO*ate Ho*der) k)m~ufzcmre~d fat General Electric Company, San Jose, California (NEG) (Name mzd add,- a N CartIl.cat, Holder for -pletie nu-Je=r comp*.nuO

2. Identflection-Certife Holder's SeNo. o Part A4582 -V=I &4. No. "' _ _

(L) Consrucrted kccordimg -o Dw-ing Na- 768E513AG01 Drawing Prepmred by D.L. Peterson (b) Descriprion of Pen Inspecred Control Rod Drive, 1-fodel #7RDB!44DCGO0

                                                                                                                   ,_207 (c) AppticibieASMECode:S-czioottEditior           197..,        Addendzdeze           W75.         C.seNo.       1361-2 Clss        l1
1. Cap 16689274P1v( .

(167A2343) SA182 - F316 Code. weld* 3/8 thick x 1 1/16 OD. 000. 02

2. Indicator Pipe 16689313PI 2 I SA312-TP316 3/4 sch 40-seamless pipe {

0.113 wall thickness 1.065 max. dia- Reactor vessel thimble

3. Plug: 159AlI76P1 SA182.- F304 L 1/4- thick x 0.8120 D .

4.. Flange 919D61OPl (719E474) Code. weld

         .SA182-F304                                                                .- P,50YP102 3.37 thick x 9 5/8 0DD.

neck 1 1/16. thick x 5.00D O 2.875 ID 4-

5. Base 137C5311PI (

XM-19 ASME SA479: 3.0 0O x .884 ID .

6. Ring Flange 11485122P2 SA182-F304 Code -yeld I" thick x 5.0 00 x 1.75 ID P50YPI02
7. Cap Screw 117C4516P2 SA193-B6GOD CONTROL DRIVE 6 ea. 1/2 dia. on 4 1/8 bolt circle DWG - 768E534
8. Plug 175A7961PI "" 9. Nut 137C5934PI (.O,1 SA182-F304 x-i9 sA479 0.38 thick x 1.307 dia. -1.30 thLick x 2.62 daia.

Rn

Sheet 1 of 2 Z-2 000,-

                   '" <--2      N-,PT CEIZR             CA*TE HOLDERS' D&TA REPORT FOR NUCLEAR PART AND AP.                                                 -ANCESO As rcquirtd by the Provision of the ASME Code Rules. Section I1U.Div. I
                                  .,,     General FIeczric Company,                          Castle Haye P.d.,                Wilmington,            N.C.

(b) - fo General Zlentric Company, San Jose, California (TEBG) A4647 Z. idetlJ.05c2 t Holder.-% Sertal No. of--am

                            -Ce.,rt,_flce.                                     _        __                           N     l Bd. No.

S768F_534G00! by D. D L. P?-tarson P According to Dr-ing No- ...____________ Dra*ig P:epd (a) C*n=ucse-Control Rod Drive, Model #7RDE144DC-00! (b) Dencriptio=. of Pem. Ip==e'et ed (c)1974 , edu e W'75 CaeNo. 1361-2

3. ? emarzz: Standard part for use witli Reactor. EydxrostaticalJ.y tested at 1620 pai.
  • Total ntnber of sheets - 2 Ve oerrnfy d inrhim revooe- ame nrszharreee and 6oreccsi -eI perrt r .9purnnozce .sdefined in the C-ode coo-fomst the roles oi cncsrrcri~of athe A&%4Edodc Section III.

(The applicable DeelS- 3>-icftlan and Sac-e Report 2re not the rcs;;;nibtItY of the .PT CertifczEe Holder for P-arts An NPT Crc-ti!- ic=Ie Holde for a x*rn-tca= is r-spocrs*blc fcT fornizhina a Design SoecficLdoo and St-rs R7-port if Ehe zpj*rt=e.,ce is not

                                                                                          -epnr-z_

Included In the compnoent Desn SeecMcadon and Stress Pfttort)

   ...t.-                  7/23            19-81          Signed        GE,    NEPD-dD--QA wsFr ce u           -n B   (/
                                                                                                                                   -         w        -

Seutember 15, 1981 ,T N* N-1153, C-rrifienre of Akuciacion e=pires CERIFICAMNON OF DESIGN FOR APPURTENANCE (wke, iepplicable) GE, iEFD-ZMD-OA, Castle HayL-e Rd., Wilmington, N.C. 22A_,5_6, lev.2.. Srre-3 sux~ysix e=e fil n GZ.NP-bDO. Castle Fa'Vne Rd., Wlw-mington, IN.C . 22A4912, Rev. 2 Dein3encirtious. cc.=ied by B- '.I. Sr--dhar ?Tof. E-n, S~noe Calif Rc&Xoý9-* CER7'FICATE OF SHOP INSFECTION I, the-cin*rsigse, holding a nisid commission isued by te (-ztionai Board of Boiler =-d Prest're Yen=se Inspec-ors

            /           sm of p* ',

St North Carolina DeDarr-Men: of Labor of State of North Carolina h.ve inspe the part of a pressre -e=sel desribed in this PartL Daa Rpor an 7/23 19U.. annd sta.ethat to the bes of my lznowledee and beflef, the s Certificate Holder has constructed this pazx In accordance with the .ASV.E Code Seclon Iai. By signing thisx crrificae, n-either the InspccTr nor his employer maokes =oy ýnrrzscy; expressed or iMplied-, concer,- Ing the part described In this Partial Data Report. Furthermore. neither the Inspector nor his employer shall be liable in my cnonen for mny per=msol injury or property das-age or a losz of soy kind arizing from or connec-ed

       -irh (him insp=c-ioa.

D- 7/2,3 19 81 6 PCNL. 72V7 KWC176 , OHIO

                                                  ~'9 ~On'~' ~p~t    5 Nsio-cs   anard.. 3tst., P-n,'nao      -d No.

nlom)h Thu isoYomIE COG401 rm t~eootamcnod .aorr- ý- Crcer'O-bt2 ',trySt.. NeW I m -Nr.Y. 1O1 cc

REPORT NO. P0059-012 Shaee 2 of 2 7 ly :*:* / , FORM N-2 NT CERTIFICATE HOLDERS' DATA RE-PORT FOR N"UCLEAR PART .ND APPLURTE*NANCES-

                             .ks rcquirnd by týt ?Tovision of zhe .ASME Cod- RuJcs. Ser:-ion 1H. Div.

I. (a)M nuf*c.urcd by General Electric Company, Castle {avne Rd., WN-ngt .C. (b) MenufEcmred for General Electric Company, San Jose, California (N-EBG) lHa.me sad a~dfr.,* of N CettlfltAle Hii*--r fa- eoamlet--d nudes: eomnponenu*

2. Identfication-Certircate Holder's Serial No. of Part A4647 Na:'l Bd. No.
0. L. Peterson (e) Constructed According to Drawing No. 768E53LG00O Drawing Prcpsed by (N) Description of Par Inspec:ed Control Rod Drive, Model f,7RDBI44DG001 N207 (c) .ppLicablc A.MECode: Secdon II, Edition 1974 , Addenda..re W75., CaseNo. 1361-2 Class
       ,    Cap 166B9274P-(167A2343)

SA182 - F316 Code weld 3/8 thick x 1 1/16 OD PSOYPI02 I

2. Indicator Pipe 166B9313PI 0 I SA312-TP316 3/4 sch.40-seamless pipe 0.113 .all thickness 1.065 max. dia. Reactor vesselI thimblessel I
3. Plug 159A1176PI t .

SA182-F304-1/4 thick x 0.812 0D

4. Flange 9190610PI (719E474) Code weld
           .SA182-F304                                                                    .-. 50YP102 3.37 thick x 9 5/8 0D                                                                              8.

neck 1 1/16 thick x 5.000D 4 2.875 ID

                                                                                                                 .5Q ..

5, Base 137CS311P1 XM-1 9 ASME SA479 30 00D x .884 ID

6. Ring Flange 114BS122P2 /

SA182-F304 L Code weld I" thick x 5.0 00D x 1.75 ID P50YP102

7. Cap Screw 117C4516P2 SA193-8& CONTROL ROD DRIVE 6 ea. 1/2 dia. on 4 1/8 bolt circle DWG - 768E534 8, Plug 17SA7961PI 9. Nut 137C5934Pi SA182-F304 XM-19 SA479 0.38 thick x 1.307 dia. 1.30+cl x- 22_ ia . 00715 81

Sheet 1 of 2 FORM* 2 NIFT CERTIFICATE HOLDERS' DATA REPORT FOR .N-OUC-LER PART AND .A-PPELTENA!NCES* As required by the Provision of the ASME Code Rules_. Section Ill. Div. I

1. bY GCenEral Ele~ctric Company, Castle H-ay-ne Rd. , Wilm-:ngton, N.C.

(Nan =~ d~KF a~leaijoler,kP (b) Idaoo e fo- I General. Electric Company, San Jose, California (i'TEBG) 2, Idoctflnciar-Certflcaef Hold er's Serizl No. of Part A467 6 Bd- MO. 768ES34G001 D. L. Peterson (n) Coamsrrscred A-ccozdiri0 to Drnorsrg Nc.________ Dro-imr, Prepsnod by (b) Dencripri=on P=* Lk d Control Rod Drive, Model M72DBi44DG00! (c) A*lcehe A-q.ECede:&ev-ieaaI, Ediroo 1974 , A.i4=odad-c W'75 - C-eNm. 1361-2 Cl=z-3 - Stazdard -part for use w-ith Reactor. Hydrostatically tested at 1820 psi. (aA0io deon-ipei- f( -vriee (- hkleh doeiiceo4

                                                                                                                              -~ne~t Total nunber of sheets -                       2 Ve certify thori the store~s~rz rtednz [is dt-im mepar nre correct rd thisz vessel Pert or. mopturzaanco a- clefimod iz the Code con-foreexs to the jroles of caosorctica of dsez kaiý-Ceýdc Sccrio .s                   iI (Th amplcazble Destsin Specificarlau and Sa-ess Reprst ame m-o the respoosibjility of tme XPT CeOr fleerc Holder for parmr An XFT! Cer11-irere Ho~lker far a7Vprertences is respapeibic for fu                  sbiioima s-parore Deoirp Spe -flee-on -- d Stress KmeLtr if the 2pp neancc is no(

tacluded1 toEe como002nt Desi-, Smcfc~hadrn anod Stra- Report-)A 17/23 981 Gie E, NUID-WlDf-QA s( MfPl' C.-t.5so Malt-) I Certificzte of Astsdsori-martirc t-=irz September 15. 1981 Cerofijcst of AZ NT N-1151 CERTIWICA'flN OF DES3GN FOR APPURTENANCE (when rpplicenbls) n1=mzoa zi ilem Demgn E, NKPD-;ZM-QA., Castle Hay-ne -Pd., Wilming-ton, N.C. 22A5.556, tevr.. 2 Screos onulymis report an aile or GE. WZZPD-WMD-O.A. Castle Fa-y-e Rd.. Rilmiazton. N. C 22A4912, Rev. 2 8 34 5 Dcsiga 2perificatiocss certticid by1 3. N'. Sridhar Prof. En 0 . Stot.,Cali! tc,..,4.1 1 3 45 St.-ena onelymiz report certfe .N Sidhar Fri o.seeaJifE a 0 o CERnFICATE OF SHOP INSPECTMON 1, the ,-dars*iit~-d, holding x valid comemis-mic is=ued by the NMrionl Board of Boiler end Preomire Vessel t*spectGa _d/or -the Stare of provin- a North Carolina ond m=plo-fd byDepartment of Labor of State of North Carolina ha.ve imr-pected the part of a prezzure weenal described in this P'armAj D~tS Report on7/23 _ I and sate that to the best of my lmo-led-e zM bellef,. =e NPST Cternficee Holder hes rcomsucted this Pan In accordance w*ltb the ASME Coe Section LU. By signing thi- certificere, neither the lna;ctor nor his cspLycr makes may 'arrenry, =:pr-.-seed or z-plied, concern-" Ina the pa-rt described In this PortIaJ Data Report. Furthermore. neither the Inspector nor his e'mployer shall be liable in eny mroetoe for =y personal injury or property dam.ae or a loss of =ny hind ari-ing from or cotnecred Vith this i;spection-I Date cl*4~~.9.* 421 7/23 . 19 81 _tial 723,RA.WC1766, OHI0. oN.C. 3-1-1 B-1m. P-L- -d N..nublisý Ie;...ooj.u U771o,,.. e..wo=oeJ.s 2sto. 401 a.,ol s fl** 0 2)lor-.0, I,; ,r5

REPORT NO. P0059-012 Sheer 2 of 2 FORM N-2 NTT CERTIFICATE hOLDEIRS' DATA REPORT FOR NUCLEAR PART AND .APPURTENANCES-As required by the Provision of the ASME Code Rules. Section [1. "Div. I

1. (a) Ma-ai=.md by. General Electric Co-oan7, Castle lqavne Rd., Wilminttom, N.C.

(b) M-nufmcz-ted for General Electric Company; San Jose, Calilforznia (NBG) (Mýrd addrý of.4 Cc-Adante Ho~d- Woc~voitQd n..clw cýD~oO 2- ridentm~atkm-Certflate Holder's Serial No. ofPr AA4676 N~l d No. __________ D. L. Peter-son (r) Co~smmted Accrding to Dc~ins No. 7 6 8F53 G'00 I Drovig'rep-ed by .L Ptro (!%)Descriio 0 of P,-rt Lo-pted Control Rod Drive, Model #7R DB!44DC-001 (c) Aoplti=mble A S9EC *:c-Sccion ELI,Edi.tion - 1974 W*.

                                                                , Add *'dmdxcScW'75N207               N. 13 125ls I. Cap 166B9274PI                                                                           (

(-Y7A2343) SA182 - F316 Code welId-- 3/8 -thick x 1 I/T6 0D R50YPlD2

2. Indicator Pipe 166B9313PI I 3A312-TP3]6 3/4 sch 40-seamless pipe 0.113 v:all thickness 1.065 max. dia. Reactor vessel F thimblL-
3. Plug 159A1176PI .

SA182-F304 " I 1/4 thick x 0.812 OD d

                                                                                         .3
4. Flange 919D610PI (719E474) Code wel i
           .SA182-F304                                                           -.R5OYPl1 02--<

3.37 thick x 9.5/8 00 " . neck 1 T/16 thick x 5.0 0D 2.875 IM 5.. Base- 137C5311P* XM-19 ASME 5A479 3.0 00D x .884 ID

5. Ring Flange 114B5122P2 SAI82-F304 ' Code weld I" thick x 5.0 0D x 1.75 ID P ,nYp1)?
7. Cap Screw 117C4516P2 SA193-86 COrITROL ýOD DRIVE 6 ea, 1/2 dia. on 4 1/8 bolt circle DWG - 76aE534
8. Plug 175A7961PI 9. Nut I_37C5934P! 00539 XM-19 SA479 SAI82-F304 0.38 thick x 1.307 dia. L-3 ic.-2S aa.

82

She~et 1 of 2 FORM N-2 NPT CERTIF!CATE NOLDE:S' DATA RE2PORT FOR NCLEAR PART AND APPURTENANCES' As required by the Provision of the ASME Code Rules, Section iMI, Div. I L ( M~nQzc-ured General Electric Comoany, Castle Eayne R., Wi! ,mingtton, N,C. (Naoe a&dad r of NnT CerfICLet Holder) (hi Manufctured for General Elfectric Company, San Jose, California (NEBG) (Name R*d zddo*e KNCetUncaLe Holder for comoleted ntueer comeonooao 2- Identificatlon-Certitcate Holder's Serial No. of Part _ ANs7 Nar'l Bd. No. 76SE534GO01 D. L. Peterson (c) Constructed According to Drawing No,,_____________ Drowing Prepared by________________ (b) D e .criptio n of P azzInspected Control Rod Drive, Model #7RDB144DG001 N u 1 9 (c) .ppLicxble A.UECoAerS-cti-1nI, Edition 1974" ___74 Addend.deze W'75 , Ca~seNo. 1361-21 1361-2 Class. S$tandard part for use w-ith Reactor. Hydrostatically tested at 1820 psi. (elro( deoeiprti5a of -eo,-cafor whioh -omp=ant was d-ioenod)

  • Total number of sheets - 2 We certiry that the sttementcas made i.n this report wre correct and this vessel pert or appur*enancc os defiecd na the Code con-forms to rhe- rules of 'conasucrion of the ASME Code Section I1I.

(The applicable Design Specification and Stress Report are not tŽhe responsibility of the NFT Certifcate Holder for part-- .A.- NPT Cernff-icac Holder for appurtenances is responsible for furnishing a separate Design Specification and Stress Report if the appurtenance is' not Included in the component Desian SpecifIcation and Stress Report-)

.)MC                              8/31-                81-                       CE,        E-Wi 19      -       Siged       ________________B" 12uv cetlelate Holder)

Ccrtificate of Authocizaciroi Eapire-s SepTember T5,.. -981 Cerificate of/Autrizion No. NPT N-I_51 CERTIFICATION OF DESIGN FOR APPURTENANCE (when applicable) Design intformdtiono0 ile . GE, NEPD-WMD'-OA, Castle. aavne- Rd.-, Wilminoton, W.C. 22A5556, Rev. 2 Srress analysis report on, ilc at GE, EPD.,'San" Jose, Calif. 22A4912, Rev. 2 Design specifications c=rtified by B. N. Sridhar Prof. Eng. State Calif Reg.Noj18345" 834 Stress. antlysis report ,rrIfied y. B. N. Sridhar Prof. Eng. ScnrenCa!if Reg. NooL 5 CERTIFICATE OF SHOP INSPECTION 1, the undersigned, holding & valid commission issued by the National Boe.rd of Boiler.and Pressu*e Vessel Inspectocs and/or the State or Province of North Carolina aod employed byDeDart1nent of Labor of State of North Carolina have inspected the part of a pressure veasel described in this partial DtaReponan 8/31 19 L. and state that to the best of my knowledze and belief, thie NPT Certificate Holder has constructed this part In accordance with the ASME Code Section ILl. By signing this certificate, neither the Inspector aor his employet makres any wa,-:anry, expressed or implied, concern-lit the part described in this Partial Data Report. Furthermore. neither the Inspector nor hLs employer shall be liable in ny manner for any personal injury or properry deimage or a loss of any kind arising from- ot coanecred with this inspection. Drce -78/31 19 81-NG 2Y G76)HG ftiapatio. slcetur. N.el Beard, Stat., ?e-oleoo and No.

 "'.,~,o    n.o....  .h¢o.t.      f.      1 i..,
                                        .orn        ..     ... o. draw     s... -y ..    -. p-id..    (t) L-  i.       11", (2)            i.Lort-   1-7
                                                                                                                                                        .-. 00                           _ki (o107)                                                         7 his form {EO0040lmay be obtained from the Order Dept., ASME, 345 E. 47th St.. New York, N.Y. 10017

REPORT NO. P0059-012

       .  .      .                                                                                                S h ee t 2 o" 2,           L3 F ORM N-2 NPT CERTIHFCA TE -HOLDERS' DATA REýORT FOR NUCLEA.R PART A-N'D A.PPURTENA.NCES*

As r-quired by the Provision of the ASME Code Rules, Section HI, Div. I

i. ()d by General Electric Company, Castle Ra*-ne Rd., Wjilmi2n,.-_j, N.C.

(Nae and ad6u, of NFT Cerficate Holder) (b) V.-u*facrrecd for General Electric. Company, San Jose, California (h-NG) (Nane an4 ddran oa N Certficate Holdrer fonpleted or nucdler comroonem

2. Identification-CerMlcrte Holder's Serial No. aPart A5237 'larl 3d. No.

D. L. Peterson (a) Co=srracred According to Drzwing No. 768E53AG0rn Drawing Prepared by (b) Description.o P=r Inspecmed Control Rod Drive, Model #7RDBl44DGO01 17 - N207.N295 (c) App~icicab A.SVE Cod c: Secri on 111, F-dirion. ...... Addenda draze W........C.., CsNo. 1361-2 Cbzs. 1

1. Cap 166B9274PI (1 67A2343)

SA182 - F316 Code weld---. 3/8 thick x 1 1/16 OD P:50YPI02

2. Indicator Pipe 166B9313PI SA312-TP316 3/4 sch 40-seamless pipe 0,113 wfll thickness 1.065 max. dia. Reactor vessel thimble I
3. Plug 159A1l76PI SA182-F304 L -*

1/4 thick x 0.812 OD

4. Flange 919D610PI (719E474) Code we.ld
           .SA182-F304                                                                .-e.50YPl02--                 ,

3.37 thick x 9 5/8 OD neck 1 1/16 thick x 5.0 0D 2.875 ID.

5. Base 137C5311P1 XH-19 ASME SA479.

3.0OD x .884 ID " \

6. Ring Flange 11485122P2 SA182-F304 Code weld I" thick x 5.0 0D x 1.75 ID P50YP102
7. Cap Screw 117C4516P2 SA193-86 CONTROL ROD DRIVE 6 ea. 1/2 dia. on 4 1/8 bolt'circle DWG - 768E534
8. Plug 175A7961PI 9. Nut 137C5934PI.

8.Plg 75791PM~-19 SA479 0)79 SA182-F304 1.-0 thi79 26da 0.38 thick x 1.307 dia. 1.30 thick x 2.62 die. 83

Sheet 1~ of FO)RM1N-2 .NPT CERTFIfCATE HOLDERS' DATA REPORT FOR NTJCLEAR PA-RT AND A-PPURTENANCES,

As .- required by the Provision of the ASME Code. Rules, Section III, Div. I
          * .. _.i:c.-red by        General              .lectric Company,                Castle Hayne Rd.,                 Wlmia.gon.                  N.C.

(Name and afN ot Cre~sotiaioder3 (b) Manufeacmred for General Electric Company, San Jose, Califomria (NEBG) (Natme and add- of N Ceraxicate Holder for :.mpleted nuclear cotoponent) 2- Identifcatlob-Certifc-ate Holder's Serial No. ofPart A-5385 Nmr'l Bd. No. 768E534G001 D. L.. Peterson (a) Constracredc Accoiding to Drawing No.__________ Drawing Prepared b (b) D Control Rod- Drive, Model #7RDB!44DC-001 94-inU1 2~ ~ *dto1974 W'75 136 N2U/ N295 (c) AppLicbceA ECodc:Sc ,Addenda dae, Case No. C] Lss

3. Kemosdis: Standard part for use with Reactor. Eydrostatically tested at 1820 psi.

3 ri dwsriptin ef .f -1.. for stick -p-nt deiged)

  • Total number of sheets - 2 We certify th=czrhe sta.em-ncs m-de inthis report re correct and this vessel part or mppiCt-eoance as defined in the Code con-forms to the rules of "construction of the A-WE Code Section alI.

(The applicable Desin Specification and Stress Report are'not the responsibility of the NFT Certificate Holder for parts. An NP)'" Certif-icame Holder for appurtcnancts is rcsponsiblc for furnishing a 3cparatE Design Specification and Strss Report if the appurtcnance is not Included In the component Desire Specifcation and Stress Report) [) _ 8/31 19 81 Siged GE, NEPD-W-t 13 B- -

                                .      ..- -                              W Ceeflma* Bolder)

Cetrificate of Aurhori7zariono NT N-1151 Cer CERTIFICATION OF DESIGN FOR APPURTENANCE (when pplicabie) Design informio.. on me at GE, NKEPD-WMD:OA, Castle Rayne- Rd 4iImi hoton. X".C. 22A5556, Rev*. 2-Stress analysis r4port on file at GEa 22A4912, Rev. 2 Design specifications certified by B. N. Sridhar - Prof. Eng.*Ste Ce.IL Reg.. - Stress 2nalysis report certified B. N. Sridhar Prof. Eng. State Caif Reg. No__8345 CERTIFICATE OF SHOP INSPECTION 1, the undersigned, holding a valid commission issued by the Narional ,oard of Boiler and Pressure Vessel Inspectors and/or the State or Province of Sorth Carolina and employed byDepartinent of Labor of State of North Carolina have inspected the p*at of z pressure vessel described in this Partial Data Report on 8/31 IssLL and state that to the best. of mr kno'wiedee and belief, the NPT Certificate Holder has constructed ahds part in accordance with the ASME Code Section Ull. By signing this certificate, neither the Inspector nor his employci makes any warr=nry, expressed or implied, concern-inz the Part described in this Partial Data 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 wich this inspction. Date .. n * , ./31 19 8___. D 8/ 1M 723,PA-W01766, OH1o A -Commissions .- a Signrur. otloaK 5..-I

                                                                                                                                -d. St2w.,   P-ovia. and Xo..L
         *5se~cm~e.~on--eoia-es    Lri-r. eketchet -, dr.inez             -ybe d poeid-     ix (I   tI-  1. 3A",  1", (2) ian             1,eo 1s-e    .      i (10/77                                            Triis form (ED0040Olmey be obtain~ed from The Order Dept.., ASME, 345 E. 47th St.. New York, N.Y. 10017

REPORT NO. P0059-012

  • :..* ,, '-Sheet 2 of 2 Oc/'

FORM N-2 NTT CE!RTIYCATE BOLDEERS' DATA REPORT FOR NrUCLEA-R PA.RT AND APPTJ*RTENANCES-As required by fhe Provision of the ASIVE Code Rules, Section DI.OIv. ( M-fa_-=-c-J by General Electric Company, Castle Haaie Rd., Wilmingtom, N.C. (Natne and addrc af N*T Certificate Ho*der) (5) Meooiecured fr General Electric Company, San Jose, Califo-na (Ni G) (Name and addre=ht-a C-"di*ate HoLder for co.Wk.ed nodear oonponenO

2. ldentificzdon-Certf.cate Holder's Serial No..of Part A5385 --- -Nri U. No.

768E53LLG001 Drrwing Prepared 5 0. L. Peterso (a) Cnsrmnczed According to Dewuing No. (b) Demcriprion of Part lnspe=ced Control Rod Drire, Model #7RDB144Dc000 9i4' N207 N295 (e) ApplicabieASMECode:section II, Edicion1.. , Addarad W75 - CaseNo. 1361-2 Clss 1

1. Cap 16639274PI (167A23431 SA182 - F316 Code weld 3/8 thick x 1 1/16 OD P5OYPlO0
2. Indicator Pipe 166B9313PI SA312-TP316 3/4 sch 40-seamless.pipe 0-.113 w'all thickness 1.065rmax. dia.

3.- Plug 159A1176PI SA182-F304 1/4 thick x 0.812 O0

4. Flange 919D610P1 (719E474)
            .SA1.82-F304 3.37 thick x 9 5/8 00 neck 1 1/16 thick x 5.0 0D 2.875 ID
5. Base 137C5311P1 XM-19 ASME SA479.

3.0 0D x .884 ID

6. Ring Flange 114B5122P2 SA182-F304 1" thick x 5.0 0D x 1.75 ID
7. Cap Screw 117C4516P2 SA1 93-86 CONTROL ýOD DRIVE 6 ea. 1/2 dia. on 4 1/8 bolt'circle DWG - 768E534
8. Plug 175A7961P1 9. Nut 137C5934PI 3oo744 SA182-F304 XR-19 SA479 0.38 thick- x 1.307 dia. 1.30 thick x 2.62 dia.

84

v Sheet 1 of 2 ~~~47

                                                                                                                                                                               )i@'?. / /

2 .NT CF-RIICATE HOLDERS' DATA REPORT FOR SNCLEAR PA£RT AND APMtiTE -IANCFS.- As required by the Provision of the ASME Code Rules. S-ction 111. Div. I V( =i==.-ed by Genera ZlEac=ric Comoany, Castle a-y-ne Rd., Wii=,ington, N.C. (Na .~Xn&5o Greis orQM~rCte ýAi~o1&- (bi .*a=*-e4 *r General Flectr+/-c Com.any, San Jose, Califcrnia (N-BCG) fr? oe rd Ad: CCX Ce'"fkcnte Ho~der f= eWcsv nncicor omoZorJ

2. Ids~cat5c*-Cerncata Holdee. sSecia No. ol rt.. A_54 14. , _________F__N___

(a) Corizmac:ed A-cording to Drzuin No. 76834G001 76SZ54GO01D_Drzwi-g Pr-epered by L. Peterson (S) Desiprin Pere Control Rod Drive, Model #7RDBl4-4DGOl (cl AppLicmk ASSIZECa .*-e*Secet-M, E'ditio' 1974 _1361-2 1

3. Res==- Standard part for use 'aith Reactor. Hydrostatically taszed at 120 psi.

(B'i.f d._'t+/-ois .1 of-,o

                                                                                      -..    (-    tO~o~t         tt         d..iCP               -
  • Total number of sheets - 2 Te certify dxat the szzz~mmts rode in thiz rzvocrt axe c=re.-si ad Cisis YCZSI pert Of putnveo defined. ja the Code coo.

,is=s to ris alea- oa cous--uc--' i of die AdE Code Se--cr IIL (The zao1Icable Des= SPo-aIC2Zin and Stress Retirt are not the responsibiLity of. the NP'" Certkcaw Holder fr pxa-,. An NPT Certlf-ite Holder for zrurt==mac= is retpoaible for fu.-hioiz g a sepaX.e Design Spelfioion zad Strnss Repor if the 2.DqL=teC is not Included in the conpooent DeL-.La SpeeinctIn and Stress Pepor) 7/23 81 G3, \MM-Z--QA~ 19 - Sigied - XFT N-l.1 52 Certificzte Of Auchori=oirs Expires Seutember 15, 1981 CeriMFICae of ora.aric No. _T_-1_- CER.TFICATION OF DES*GN FOR APPURTENANCE (whien wppliczafe) CGE, NEPD-r1D--QA, Castle sayne Rd., Wilmington, N.C. Demi~n ii an File 22A55336, Rev. 2, Sre-=a 005ly523 repsl' a fle G-8. N D--WD-OA, Castle HaveM RM., W,!]_LnS=ton. .N.C. 22A4912, Rev.. 2 83 43 Dezi.n specil*uriosa certifiaed B.. N. Sr4-dhar Pto. R.g. S..re Calif. Reg. NO. 83 4

        *ere&aa~lyirepo-e            x          i,      B. N. Srldhar                                                 .ta        C life                    10e.1No1 3 CERTIFICATE OF -SHOP [NSPECTMON I, the uýidersigred, holding a isiid con=iz-io=- i-a.ed by the N*Sionwl Boad of Bailer ed Pressure Vessel L=pecc_.or ed/or the Sare Of pjay,                 ol North Carolina                     ,Od eziployd byDeoar-zent of Labor of           State of North Carolina                                         hz~e inspe-ted rhe pArt of & preassure ýezmse describe-d in this PeriaTwfa,      Report on                                                  7/23                                1. and stae hxc to the be-s-, rmy IntwIed.e and belief. !he .?T Certflcate Hoeder hits cass-ructed this Part in accrdiance with the ASME Code Section In-By signing this certiGfcaze, neither the iaspecror nor his epiloyer m,,.s my vaersocy; expressed or implied, camice.--.

Ina the part described In this Partial Data Report. Furthermore, neither the Inspeclor nor his emDloyer shall be liable in eay miroer for my pero-adl injoqr or property demaie or a loss of any kinsd rizins t-ree or counect**d eith this irspectio. Dat . 7/23 19_81 O

        *Swl..nn5*0   '.p4tore o1 . i.,. Mt4O.                          ..  ,.daIii.             5        tt .4    1- e  B-1o.r~b
                                                                                                                               .oo    st.t.          tt      -d i 0fl7)                                           This I trn    EO)Ce4i rnarohe ontznoner                       ~t                 '21f'S.               e    YomeC-e
                                                                                                                                                                '. N.Y. 10017

REPORT NO. P0059-012 Sheet 2 of 2 i ,. o FORM N-2 NPT CERTIFICATE HOLDERS' DATA REPORT FOR NUTCLEAR PART AND k.PPIJRTENANCES*  ::

                              .As required by the_Provision of the ASVME Codt Rules. Section 1I1. Div. I
t. (a)Manoc~acd.by CGener-al Electric Company, Castle Hay-ne Rd. , Wil in.zon, NC.

(Na-e and addre- aN*T [ Cer-aScate Mnai-d (b) Mznuiacerad fot General Electric Compar.y, San Jose, California (N--G) (Name end addmre oatN Ce.tincate Holder for completed nuclear conponene)

2. Ident~lcatloo-CertIfcate Holder's Serial No. of Pa*rt-4 1 " NA54 B 'No.

D. 1.. Pete-rson 76&8F%53GO lI Drawing Prepared by . (a) Constsrcted According to DOa-ing No. (b) Dcscription of Pe.rt Inspected Control Rod Drive, Model #7RDBI44DG001 1 N207 (c) AtpLicable ASMECode:Sccrion1l, Edition 1974 Addendedare W 75 cascNo. 1361-2 Class  !

1. Cap 166B9274Pl (167A2343)

SA182 - F316 Code ,welds, 3/8 thick x 1-1/16 OD P.50YPI02

2. Indicator Pipe I.56B9313Pl I SA31 2-7P31 6 3/4 sch 40-seamless pipe 0.113 wall thickness 1.065 max. dia. Reactor'vessel thimble I
3. Plug 159A1176P1 1 SAI82-F304 L 1/4 thick x 0.812 00
4. Flange 919D610Pl (719E474) Code weld
          .5A182-F304                                                                   -..R-YP           -*2 3.37 thick x 9 S/800          D.

neck 1 1/16 thick x 5.0 OD 2.875 ID

5. Base 137C5311Pl XXH-1 9 ASME SA479 3.0 0D x .884 ID,
6. Ring Flange 1143512P2-/

SA182-F304 Code weld 1" thick x 5.0 00 x 1,75 ID "P50YP02

7. Cap Screw 117C4516P2 SA193-BS CONTROL ROD DRIVE 6 ea. 1/2 dia. on 4 1/8 bolt circle DWG - 768E534 8 Plug 175A7961PI 9. Nut 137C5934Pi SA182-F304 X-!9 SA479 0.33 thick" x 1.307 dia. .. 305 thick x 2.62 d.a.

85

saeer Lox z FORM N-2 NPT CERTIFICATE HOLDERS' DATA REPORT FOR NUCLE.AR PA.RT AND APPURTENANCES* As required by the Provision of the ASME Code Rules. Section I11, Div. I _.Lf.* ncurct by General Electric Company, Castle Hayne Rd., Wilmington, N.C. (Nama ad ddrase d NPr Certlkeatae Hdaer) (b) iannufacrur-d lor General Electric Company, San Jose, California (NEBG) IName San ddress of N Certtlcate Holder for c pleted nuclear component) 2 Identiflcatjon-Certiflcate Holder's Serial No. of Part ANar' Bd. No. (a) Constructed According to Drawing 76"E534GO01 D. L. Peterson No._768_534G001_" Dre-ing Prepaancd by (b) Description of P-* Control Rod Drive, Model #7RDBI44DG001 ()DsrpinoPatInspectedN U (c).A..ECode: Seion 1 1974 W'75 1361-2 Cc) A~ppicable It!E, E~dton A,ddenda de , case No - .. Class

3. Remark: Standard part for use with Reactor,. Hydrostatically tested at 1820 psi.
                                                           - (alafdasripton       t    -1.-l. 1o- -hiah  a-oopneottaa          dali~j.-*
  • Total numb'er of sheets - 2

_7* . . . We certify thatthe statements made in this report are correct mod this vessel po.rt or appurtenanc- as defined in the Code con-forms to the rules of construction of the ASME Code Section [i1. (The applicable Deslrn Specifieation and Stress Report are not the responsibtlilty of the NPT Certificate Holder for parts. An IPT Certtf-icatc Holder for appurtenances is responsible for furnishing a scparate Design Specification and Stre.s Report if the appurtenance is not Included in the component Desirn Specification and Stress Report.) Dtt 8/29 81 Signed GE, N'EPD-WMD" B (N" Certiicate .. "molder) Certificate of Authorizaticon 'Expires Sep-tem et- 1 5, 1981 'Certificate of juthorization No. ITN15 CERTIFICATION OF DESIGN FOR APPURTENANCE (when a'pplicable) Design inforrnoiori on file GE.,; NEPD-WMD-OA, Castle Hayne Rd._, Wilmington, N.C. 22A-5556, Rev. 2 ..

 .... Z2A9s..,             report o file at              GE, NEPD,           San Jose, Cal if.

22A4912, Rev. 2 Design specifications certified by E, N. Sridhar Prof. Eng, State Calif Rag. Np-183.45 4 Stress amalysis report certified by3. B N. Sridhar Prof. Eng. s*,te Calif Reg. No183 5 CERTIFICATE OF SHOP INSPECTION 1, the undersigned., holding a valid comasission issued by the National Board of Boiler and Pressure Vessel Inspectors and/or the State or Province of North Carolina and employed byDepartment of Labor of . State of North Carolina "have inspected the part of a pressure vessel described in this Partial Data Report on~ 8/29 1981 and slav. that to the best oftty ltnowteldze and belief, the NPT Certificate Holder has constructed this part In accordance with the ASME Code Section Ill.

          .By signing this certificate, neither the Inspector nor his employer ntakes any w=*arany, expressed or implied, concern-Ing the Part described In this Partial Data Repbrt. Furthermore. neither the Inspector nor his employer
     &hall"be liable in any seanner for any personal injury or property damage or a. loss of any kind arising from or connected with this inspection.

Date 141 P 8/29 19 81 Ka 731-AX16G,0HO 8j:3 aaLI00: toP~eitor'. sliata Nti.onal oard. Stat.. Praince. and Na. 1J.ta. .kataha~ a, ~~aa inC. ~aay ba o.a4 pa~nea It) .ioe is SN, a II'. (2) lato,-aatiae a Ita,,. I-) ea ibis (10/77) This form .(E00040) msy be obtained from the Order Dept., ASME, 345 E. 47th St., New York, N.Y. 10017

REPORT NO. P0059-012 ?. ' L . ' *-*Sheet 2 of 2

                  .PJ N-2 NPT CERT]FICATE SOLDERS' DATA REPORT FOR NUCLEAR PART AND APPURTENANCES-                                                .U As required by the Provision of the ASME Code Rules, Section III, Div. I
    , (a) Manufactrcd    by     General Electric             Company,      Castle Hay-ne Rd.,                 W!l!inigton,         N.C.
                                                                    "(Nme and addzo of N.T"rCerIcate Hulder)

(b) Manufacrured for General Electric Company', San Jose, California (NEBG) (Name and addej o0"N Certldate Holder for completýd uucleaz copooet.)

2. Identlrlcatlon-Certiflcate Holder's Serial No. of Part A5468 -Nat'l Bd. No.

768E53LGfl1 Drawing Prcpered by L. Peterson (a) Constructed According to Drawing No. (b) Description of Pare !nspec*ed Control Rod Drive, Hodel #7RDB144DG00l 1974. N207 (c) Applicable A.SE Code: Sccrioa tIl, Edition -, Addcnda date '-7

                                                                                              --                 No. 1361-2 Coss        2 I     Cap 16689274P-(167A2343)

SA182 - F316 Code weld 3/8 thick x 1 1/16 OD P050YPI02'

2. Indicator Pipe 166B9313Pl -

SA312-TP316 . 3/4.sch 40-seamless pipe 0.113 wall thickness

 *           ~1.065 max. dia..                                                               Reactor vessel thimble
3. Plug 159AI176PI --

SA182-F304- L 1/4 thick x 0.812 OD .3---

4. Flange 919D610P1 (719E474) Code weld .
              .SA182-F304                                                              .o*..5OYP102                       ,

3.37 thick x 9 5/8 0D neck 1 1/16 thick x 5.0 00 2.875 ID .

5. XM-1Base 9 137C5311P1 ASME SA479 ..

3.0 0D x .884 ID

6. Ring Flange 114BS122P2 SA182-F304 -Code weld I" thick x 5.0 0D x 1.75 ID P(9YPI02
7. Cap SEc'rew 117C4516P2 SAl93"-B6 CONTROL ROD DRIVE 6 ea. 1/2 dia. on 4 1/8 bolt'circle DWG - 768E534
                                                                      -9.                             Nut 137C5934P1
8. Plug 175A7961PI " XM.-19 SA479 SA182-F304 1.30 thick x 2.62 -la.

0.38 thick x 1.307 dia. 86

77. Sheet 1 of 2 /62 7 FORM S-2 NFT CER=_TICA HOLDE' DATA REPORT FOR UCLZR P.ART AND APPURTENANCES' As rcquir-d by the Provision of the A.SME Code Rules. Se,6on IIl. Div. I- __/_,-

                                .        General Electric Company,                           Castle Hayme Rd.,                     Wii'm4ngton,              N.C.

(Niame Wi .ddr~a~ si .N CiIems-,lz* Holdler, (b) .*4ufz¢zu.-d for General Electric Company, San Jose, California (N-EBC-) Oimoan dd orr of 1 Cerýisess, Holderfr -Mee4 ducleme -ýcilie~e Idemnflcatotn-Cer_'fcate Holder*' Seral! No. of Part A_5572N l B N. (n) C--a- d Artding to Dr-wins 'o. 768F534G001 Drsing Pr==trd D- L. Paterson of *Control Rod Drive, Model #7RDB144DGO00

                                                                            *1974                              W'75                             1361-2                        1 (c)     Apqlczh4e A.SE Cced:eSi            &     n in1, Edieion,                      Addendada.e,                         Case No.                      Cl0-t               _
3. Rc-=-az: Standard .art for use with Raactor. Eydrostattcall7 tasted at 1820 psi.

(Bridt d-1tmares of o.,-i.. for -hsic5 .o-p,.c mac

  • Total number of sheets - 2 Ve c:r-ixy LIh1t the z:r=*-ýe- s de in this r.port e corret ýrnd ,his ,e=sel p-.r or =pupurrnc- "S deFined iL the Code con.

forms to the raie3 of c*z=--c-,ico athe ,kASAE Code Sec.ioo I1_ (The aoolicable De0i:= Speciflcatlou and Stress Report are not Uie resr41bibilty o( tbe NPT Certiflnat Holder for parm. An NPT Ceretf-icxze Holder for appurttnanc= is rr*pootible for farmishin: z separate Digsn Specificanon sod S-esas Rzpor if the apFprteanc= ia not included In the component Desim Spec.flcncslo and SZt-es- Rla ,-'eL) 7/23_19 81 E, C<._ YZPD-WM-(QA (x~r Ced~ficft* Hold-m) By ( C f o NPT N-Ll31 Cerfitqc:*e of Auchoam.=rie Expires SeotEmber 15, 1981 Ctr.ifl==_i_- orcho-izac:a No. CER71FICATION OF DESIGN FOR APPUHTENANCE (when aopliczabe) on file atGE, .N=D-*M-QA, Castle Hayne Rd., W1*isizgzon, N.C. D'esign ilorrioz 22A%5556, Rev.. S22A5 3, r.--o e

  • G2. N-fD*WI-OA. Castle ZE=voe Rd., W!lmington, N.C.

22-4912, Rev. 2 Scce Prof En. al! 1 ,..j.283435 Design eificxtion cld ", B. IN. Sr!dhar ppf E.Sce~ Reg.No U. N. Sr"dbar Ca14F . ',.8343 CERTIMPCATE OF SHOP INSPECTION

   "=el/or the 1,S-nec   be or Proha.,

idrsinad, olinga ýi .North Carolina alidconvoisaoa isued and =pl.,,d by die byDeoarl-ent NAtcfarlBoard of Boiaef of andLabor Pressoorr Yezae Inspclor3 of State of North. Caro Lina hav¢e inspecte-d the part of a pressure vessel dezaicdin* :a"his F'rzr* Dam .Repom-cc 7/23 19 L__. and statre that to Le bes3t c( =o knowle~dze xnd befii. the N'(T Certificate Holder h.s constructed this part in accordance with the ASME Code Sectlon Ill. By signing this Cenieither the lpAer-=or nor his e-plooyr makes ty wrr-.y, erprme3d or ,-fieAd,conic-t.. In% the part described In this Partial Data Repor. Furthermore, aeither the Inspector nor his emplorer shall be liable in *my *manesfor any personsa inior7 or property damage or x loss of mny kind arising tr or- caaneczed with thii, inapec:ion. D.. .. ,- 7/23 19 81 .

                                                                                                                          *NiC. 723,PA.WC1766, QHJ'0 Con~sissias          Satoril Bo,-O L1us.*~~.                                            '~a       ~   o,. ro.~      t       *39*           '      e~n.*~.-

St-~, P-e,-i..- i X.. (0/771 Th is terms I E= 401 marp cc noonw frcrer;s O~rcer Di=_ý St.. Y rk .Y. (01

REPORT NO. P0059-012 Sheet 2 of 2.!p FOR-IMN-2 N'T CERTIFICATE BOLDERS' DATA REPORT FOR NUCLEAR PART AXD A2PURTENkNCES* I i As required by thc F-ovisiort of the ASIME Code Rules. Section III. Div. I -. (a). aurac:u4 by -e~nera 7_ec~ric El Coopany, Castle Rayne Rd., Wilmincccn, N.C. (Nae and addJ oi .NT Czr~tco . HoldenJ (b f earal Electric Company* San Jose, California (NJ-EG) (Nae a zddr, of N Cartcate Holder for c*amoled nuzlemr o-nm.p-

2. Idemflcatioa-Certflcate Holderls Serial No. &Part -L5572 a d. No.

D. L. Pet-rson 768753_OGOO1 Drawing ýPrrpe-ed by (a) Cozsmncced According co Dcr'wing No. (b) Descripotn of Pea Imospecred Control Rod Drive, Model #T7`RD3144DG001 N207 We) .Applicable AECode:eSecrionm111, Edition 1974 , Addcndzadmxe W'75 ,CzseNo. 1361-2 Cl-s. 1

       . Cap 166B9274PI (167A2343)

SA182 - F316 3/8 thick x I I/T6 OD

2. Indicator Pipe 166B9313Pl SA312--TP315 3/4 sch 40-seamless pipe 0.113 vlall thickness 1.055 max. dia.
3. Plug 159A1176PI SA182-F304 1/4 thick x 0.812 0D
4. Flange 91D610Pi (719E474)
         .SA182-F304-3.37 thick x 9 5/8 0D neck 1 1/16 thick x 5.0 0O 2.875 !D
5. Base 137C5311PI XA1-19 ASME SA479 3.0 0D x .884 ID
6. Ring Flange 114B5122P2 SAI82:-F304 I" thick x 5.0 00 x 1.75 1D
7. Cap Screw 117C4516P2 SAl93-86 CONTROL ROD DRIVE 6 ea. 1/2 dia. on 4 1/8 bolt circle DWG - 768E534 8.. Plug 175A7961P1 9. Nut 137C5934Pi SAI82-F304 DI-19 5A479 i--3Z thaicý_-m-7-I2 *di.

0.38 thick x 1.307 dia.

                                                                                                                                 -o r" SE 87

Sheet 1 of 2 FORM-, X-2 ,",PT CERTIFIC4.TE_ HOLDERS' DATA REPORT FOR XNUCLEAR PART ANqD APp?-TRN,AJCES - As rtuircd by the Provision of the ASME Code Rules. Section Ill. Div. I

                                                                                                                                                                  ;.. - ,_ i* A.---:*

1(.* - bT General Electric Company, Castle laynae Rd., Wilndngton, N.C. (N&ý ad oddý ot NT-Pr e~ fiio~d~, (k) .a,-fne,-d f., Generral Electric Company, San Jose, California (NEBG) (n.- and ýi Ncema~at [?: Hofezr fmrenlSd .iertfn 2_ Ic9;r,-.!acn--Ce,,c-Ee Holder's S*-ftI No. e* Part A558 Nel U. No. D--ing PepedL. Petero (a) Ccznoc:Ld Accoadinlg to Drýin-n No. 76DF.o34G001 (h) Dezcripcic-2 of Pan- Ec;ý=d Control Rod Drive, Model #7RDBl44DGO01 NZU[ Cc) A bIe A-E e: d~l, Edin_______1974 , Addenda a W'75 _

  • C=se No. C11l-2 Class _

Standard bart for~use with Reactor. Hydrostatically tested at 1820 psi.

  • Total number of sheets - 2 Ve cercify that the ste-=o=r=s -,"e in thin repor. xre e--rect nod dais vessel p*o-t or .pt-remacce acndefined in the Czde co.-

1ýn to th. rules of coat. r-ci of the A-IE Cdoe Secrion ILL (The aonsficsb!e DOotean Spzclftc-t-r anod Su t ee*rt are not thE r-PI:sibiIItY of the NP!' Certtfcame Holder for ;.re. AknNPX Cer-tf-imrzc Hoi4 far =rte=..ne,. i. reapo=ole" oq=r.hizg a separ*ate Dsico Spz--ficzzio a -t St-r-s RePot d1th*e t-osne is not Included Io t-e camponenst Desl=i spzctflcsnon aod Supno3 Rerrt-)

     )    .....        77/23_        19 81       iG5=t=d            GE,       NEFD-Wh-QA                     -          B'/.x.

am'? craaletaa kte3dsri Ce=tfic=t: of Airhorizstica EpirLn September 15. 1981 Cettificot of AL.- NPT N-ill! CERTIFICATION OF DESIGN FOR APPURTENANCE (when mpplicblhe) GE, HN-*D-t&M-QA, Castle Hay-ne Rd., Wilmington, N.C. 22A5556, Rev. 2 Stcre-- eelyvis report =o file r,.GZ. " - D-OA, Castle Ha-ne Rd., Wilmsncon. N.C. 22-k4912, Rev. 2 83 4 5 Desin :-:eiFu=naioos certified b7 B. N. Sridhar Pro. Fac. Stnte C-SJIla Reg. No-1 Sc*-*= artlymiz report c by B. N. Sridhcar Prof. E=U.. e Caif No18345 pep. . CERTIFICATE OF SHOP INSPECTION I, the uaderig-nýd, holding a md co-dt'i:" i=umed by the Notional Board of Boiler e=d Pre.-ssoe Vrsse lanspectors aad/or the State or Proincme

  • Noi-mh Carolina a,.d emloyed b.Depar-ment of Labor of State of North Carolina have inspected the par of a prc:strc we=f diencihd in this Farinl iMm Repon on 7/23 19U.- and sta.e Lhat to the best at m*v howle-de and býeilef. ahe NT Certiftcte Folder has cooroteucted this panj In accordance wilth tbe ASME Code Section 11. ,

By signing this certificaý, neither the Inspector nor his ermployer mnaes cmy *a*r-ary, erpresse-d ar inplied, coc-ert-Ino the part described In this Partial Data Report. Furthermore, neither the "onsteetor nor his emaloyer

   -hall be liable in ay manner for ay per-onal injury or properry damage or a loss of tar kind irsirg from or connected eith this inaperctin.

D~te_ 7/23 81__ so. ~~ ~ ~ ~ ~ o. . .. ~ ~* ~ f ~ -- 3-,d. Stt- P-t e..nd~S...t40 i ~~~ skthe ~"S.C!etsr.t [= - -- ý-Y- tt zz= At nit& z r77. -

REPORT NO. P0059-012 Sheet 2 or 2 FORI N-2 NPT CERTIFICATE BOLDERS' DATA R.EPORT FOR NUCLEAR P.kRT AND APPURTENANCES*

                            =As  required by the Provision of the ASME Code Rules. Section III. Div. I
j. (e) b4enuf'oc._d b, CGeneral Electric Company, Castle Fsyne Rd., Wilr-c+gton, N.C.

(Ncxeutnd ddae-u fNPT CeOldfete Holder) (b)Ma=2ufac-red fat General Electric Company, San Jose, Californmia (E-z3G) (Name o=d addrn o( N Cert ncnte Holder tor compeLoed nuclear raeppoentl Z. Ident fMcatio-Certtfcate Holder's serial No. ..of'._Part _ _______ Nac'l 5d. No. (rc) Coastrucced AccodinIg to Drzw.ng No. 768V53AG001 Drawing Pr-pt-red by D.L. Peterson (b) Description of P"mmlaspecced Control Rod Drive, Model #7RDB144DG001 N207 (M) Applicable AW.E Code: Scctionm [1, EdiCio 1974 Addcodedo:e W'75 C., No. 13612 Class Cap 166B9274P1 ." (167A2343) SA182 - F316' Code weld 3/8 thick. x 1 .1/16 OD . P.5OYPI02

2. Indicator Pipe 155B9313Pl . 2 SA312-TP316 3/4 sch 40-seamless pipe I 0.113 %'alTthickness 1-.O5. nax. dia. --"' " ...... Reacto.r vessel-7 . thimble I 3.. Pl'ug 1 59AlI 76Pl SA182-F304 . " L_ "

1/:thick x.0.812. OD

4. Flange- 919D610PI. (71.9E474) Code weld- I SA1 82-F304: .-P50YPI02 ,

3.37 thick x9 9'/8 00 S. , neck 1 1/16 thick x. 5.0 0D

          *2.875 ID                                                                                     4 5
5. Base 137C5311PI XM-I 9 ASME SA479 (

3.0 0D x .884 ID

    .6. Ring Flange 114B5122P2                                                                                                      \\bi SA782-F304                                                                                                       Code weld 1" thick x 5.0 0D x 1.7-5 ID                                                                                     P50YP102 7.. Cap Screw. 117C4516P2 SA193-B6 .                                                                                              CONTROL ROD DRIVE 6 ea. 1/2 die. on 4 1/8 bolt circle                                                                        DWG - 768E534
8. Plug 175A7961PI - --- " 9. Nut 137C5934P1 SA182-F304. XM-19 SA479 0.38 thick x.1-307 jdia. -

88

Sheet ! of 2 FORM N-2 NPT CERTMFCATE HOLDERS' DATA REPORT FOR NUCL&A-R PART AI{D APPURTEENANCFS- 3YL ty3 As requred by the Provision of the ASME Code Rules, Section III, Div. I L...(.e)ic.o-ed ~y -GeneralElectric Comapany, Castle Haynoe Rd., Wilmington, N.C. (Naaernmd addre of NPT Ceronate lold-r) (b) MmmuEr~crred for General Electric Company, San Jose, Califoraia. (-EEBG) (Neme Vnd addz of N Certtficate Holder for coarpleted nuclear com~ono

2. Idenitlication-Cerdfcate Holders Seril No. o*f!*r A5695 Hee'l Bd. No.

(m) Constructed According toDrewnig No. 7.SE534GOPI Drowing Prepared by D. L. Peterson (b) Description of Control Rod Drive, Model #7)RDBIU44DG001 974 Tdro W175 1361-21 (c) Applicable AStRECodet Section III, Edcion Addendadae W_7__, CaseNo. 13_1-2eClss_

3. Remp:os: Standard part for use with Reactor. Rydrostatically tasted at 1820 psi.

(]tif-d-iptLp.io of -i..-io for ýhUoh .- ep-ot -o doojosd)

  • TotaT number of sheets - 2 We certify rhat the statemcnts made in this report are correct and this vessel port or apparrn.nce as defined in the Code coo-forms to the rules of'conscracrion of the ASME Code Section III.

(The applicable Design Speclilcatlon and Strem Report are not the responsibility of the NPT Certificate Holder for parts. An NPT Certif-icate Holder for appsnrte-ances is responsible for turnishin.g a separse Design Specification and St-res Rc-port if the appurtenance is not -Included in the component Design Speciflcatlon and Stress Report) 8/31 19 81 Signed GE, N-ED-W1D-

                                                                  -Se~t~efllbHErTaJ98at                         erN1.3                    kubolazonN.

Cer-ificae- of Authoriarion Exoire- Certificate of N"7 CERTIFICATION OF DESIGN FOR APPURTENA1NCE (wke- applica6le)

       .Design informat.io on fl e                          GE,     NEPD-WMDI-OA,                 Castle Hayne- Rd.,                    Wilminaton., N.C.

5556, Rev., 2

      ..-S.ress ,nAlysis             repotrson file        E        G-E*,NEPDSan Jose.                            Calif.

22A4912, Rev. 2 Design specifications certified by B. N. Sridhar Prof. Eng. Sr.tae Calif Ret.NoiU45 SaeeS analysis ,po-e c=rtified . B. N. Sridhar Prof. Eng. State Calif Rg. No18345 CERTIFICATE OF SHOP INSPECTION 1, the undersigned, holding a valid commission ismued by the National Board of Boiler and Pressue Vessel Inspectors and/or the Stare or Province of North Carolina and employed byDepartment of Labor of State of North Carolina have inspecred the par of a pressure vessel described in this Partial Data Report on 8/31 IL5_j] and state that to the best of my knowledze and belief, the NPT Certificate Holder has conso-ucted this part In accordance with the ASME Code Section [II. By signing this certificate, neiher the Inspector nor his employer makes May w-rranry, expressed c implied, concern-. Ing the Part described In this Partial Data Report. Furthermore, neither the Inspector nor his employer

         $hall be liable in any mnanner for any personal injury or property dna.Lge or a loss of any kind arising from or connected with this inspection.

D"te 8/31 1 82 N.C. 723,PA.WC1766, NIHP. _ __ _ __ _ _ Commissionsa .

                    -   '5    e~oe00.ode--
                                /       cof     U~t,, akooks..O.                                                                               o Btt   d, St.trc     ? oa,.  .. d
     ,ho.o    :

eol J .1.oI* "O~ .k 5 . 00 1. , k0 mh- - eorh db .e -*S 7 -d. rIli~z-id-o (t) - ie 1 1'%"(7)} "o.--. oo It- 1-2 m ( (70MF7) This form (E000 40) may be obrined from the Order Dept., ASME, 345 E_ 47th St.., New York, N.Y. 10017

REPORT NO. P0059-012

  • 2 22 -oS opL/3 FORM N-2 NT CERTIFICATE HOLDERS' DATA R-EPORT FOR NUCLEAR PART AND A-PPTJRTENANCES, As required by the Pr-ovision of the ASME Code Rules. Section ill, Div. I
. (.) Mbnifcnd by            Genera! Electric Company,                   Castle HaTne Rd.,                 Wi-mincnon,         N.C.

(Naxe an addrý, of NPT Cordbcate HKoder) () fo General Electric Company, San Jose, California (7N4E3G) (Na.ra and addri= of N Cerdtiate Holder for caotpleted nu*aro" componenu

2. Identification-Certlflcate Holder's Serial5 o. of ?at Bd. No.

(e) Consetcted According to Drawing No. 768E53GOOI1 Dr;win- Prepar*d D. I. Peterson (S) Descripcion of Pae--Iaspered Control Rod Drive, Model #7RDB144DG001 197'4, i75 N207N295 (c) Applicable ASME Cod: Se-ction MI[,Editiza , Addeadzd=eW75, Case No. 1361-2 Cl.s 1

1. Cap 166.9274P1 (167A2343)

SA182 - F316 Code weld-3/8 thick x 1 1/16 OD P5OYP102

2. Indicator Pipe 166B9313PI (2 SA31 2-TP31 6 3/4 sch 40-seamless pipe 0.113 ;.,.all thickness
           ....065 max. da.                                                              Reactor vessel Sthimble*
3. Plug 159AI176Pl t SA182-F304 ' L_

1/4 thick x 0.812 0OD Flange 9l9D6lOPl (719E474)

4. .SA182-F304 Code weld
                                                                                      .,9, YPIO02*

3.37 thick x 95 /8 0O 8 , neck.l 1/16 thick x 5.0 00D 2.875 ID 4

                                                                                                               -5
5. Base 137C5311P1 .

XM-19 ASME SA479. -. . 3.0ODx .884 ID -7

6. Ring Flange 114BS122P2 SA182-F304 Code weld.

10 thick x 5.0 00 x 1.75 ID P5OYPI02 "

7. Cap Screw 117C4516P2 SAl 93-86 CONTROL FOD DRIVE 6 ea. 1/2 dia. on 4 1/8 boltcircle DVIG - 768E534
8. Plug 175A796.1 8.Plg..... " 9. Nut 137C5934P1 M-19 SA479 SA!82-F304 1.30 thick x 2.62 d~ia.

0.38 thick x 1.307 dia. 89

FORM N-2 NPT CErTIFCATE HOLDERS' DATA R.EPORT FOR NUCLEAR PART AND APPURTFEANCFS, As required by the Provision of the ASME Code Rules. Settioz Ill. Div. (sj~reby General Zlectric Company, Castle Rayne Rd. Wilmilagton, NC

                                 ~.General        Zlectric Compaixy, San jose, Cal* arnia                                   (NMEBC)

Z. idntfcz~an-Crfte Holdeei S-ctoI ?No.otPant A5703 Nee'I24. No..___________ ccCam=emrzed 1-czln D-i-j o 768E. 534G001 Drsýeing Pr-ae by 1.L Ptro (S) 'Descr-iptionof ?= 159e- Control Rod Drive, MKodel 7D44OQ (c) Applieshie AE Code: SeetioaMf.~ro 1974 ,Aad end.d WW7 5 , cý..4~.-Class_________ 3 cM=- Standard part for uase s-ith Reacat r. Ey-drostatically tested at 1820 za i. (SEhtta dan.rptiaa *f am..icv fto wi-are -pý-wan dcner-

                     *Total number           of sheets            -    2 Ut certify tb~t tise sream<!t3 -4d              Miade-i r=             cect W ame         and chis 'easel pact o aýtpaoreoa~nce "~ defimad to Line Code con,.

ft==:2 to the rules ol constrostion oa -drc A&4UE , ection 111. MTe applicable Desiti Specificatiou and Streom Rrect are not the resportssblifty o( the- '11>TCertifncate H~older for Parts .kn NI' Ces-tif. ictme Holdcr for 2mptm=:x&nc=s is reseaibi for ftrrnisihi a separate Desicrt Spcciiesdou resi Stress Acp~ort if die ippurtcenrcz is not included in the c-ormponent Desis Spo tftcadon anti Sts-ess Rep~omt) ... Dare - 7/23 ~ '.~ ByGl?-dl~ t-~ L 19 sinfca.ti;d,

                                                 -s Certific~at      ol Auic,eiarian Expire             -Seutember 1-5.             1981                               toizexicet a~i~of      No.. _____N-_____51 CE=TF1CA'fl1OM OF DESIGN FOR APPURTENANCE (when appliczhie)
                                       -. GE         rN2D-WXiD--QA,         Castle Rayne Rd.,                Vilm=Lingcon,          LIT.C.

22A.5556, Rev. :2 Scress uaxymia repor n u artGZ. NRPD-4ThD-C0A. Cas tile Rayne Rd, Wilmiflift on, N. C . 22A4912, Rev. 2 8 4 Dezi sa specicaions. ucercified by, B. N.- Sridhar Prof. Eze- Stare if pRe3 o-Screa. anaysis.repr ~n by B. N-. Sridhar Pro.Eg. ~a .Lif1- Re.N,Ic 83 1L3 f~C-ERWfICATE OF SHOP !NSPECT1ON

1. t~he uzxjes-3igned, holding a Yxijd coemtiseicon isaitd by dcb Sati~oox Board of Boiler and Pressue Vvsse xrpci c wialor the Scare or Province aj North. Carolina aad ctpa~ byDeoartment of Labor of State of North Carolina hkv ivxecc th paTo rsue sc ecia in hi Pardal Data Reoto 7/23 I&P.L . ad.,Lstetht Wothe berto my ., ezoIetdee and b-ilef, Lhe .NPT`Certificate Holder has coasýUctedl thits MMrIn accordance with the ASME Code Section 112.

3 y signing tbrix cer-ificsre meicher the laspecrgr mar his e-=ployer nalhes =y vzxrcy; espressed ar imjsliclA{ cvncers-Ing the part described in this3 partial Data Report. Furthermore. ocither the Insp)ector nor his temloayer shall 1e lixhLe in *my amnaeT lot any personal injusy or property doezace or x loss of Any kind arising fromntar anected wich cthis inspection. Date 72 981 _________________ 723;PA.MA17K6 Noztssos1.C. OHIO Tlhistor ItEodool rmey e' owtwaoa tronTrpaýOrcer oznt- Pt~bS. fJ~t Ne Y rt -YA. 100, 0OC d4

REPORT NO. P0059-012 Sheet 2 of 2 ,.1 FORM N-2*.*., CERTtFICATE HOLDERS' DATA REPORT FOR NUCLEAR PART AND APPURTENANCES' "rquired by the Provision of the.AS E Code Rulns. Se'ztion I. Div. I

1. (-) Manuactured by General Electric Company, Castle R--yne Rd., Wim-in-Rtoan, N.C.

(Name and ad -rse of Nnp Certlcate Holde.rl (b) M=nufacnurcd for Gener.al Electric C6=many, San Jose, California (NEBG) (Name and addza of N Cerdncnae Holder fow complleted nuclear component)

2. Identifcation-CerOflcate Holder's Serial No. of Part A-5703 Nar'l Bd. No.

D. D L. Peterson (a) Conscrncted ACcording to Drawing No. 76.E53GC-001 Drawing Pcpoprcd by (b) Descripcion of P. xlpns cced Control Rod Drive, Model #7PDB144DG001 N207 (c) Applicable ASN{E Codc: Scerion1,_EcLiclon 1974 , Addondadaze W'75_, C.seNo. 1361-2 Cle.s 1

        ,   Cap 166B9274P1                                                                            Codewel (l67A2343).

SA182 - F316 Code vielId----. 3/8 thi.ck. x.l 1/16 00 P50OYPI02

2. Indicator Pipe .166B9313PI SA312-7316 3/4 sch 40-seamless pipe 0.1)3 wall thickness 1.055 max. di.a.

Reactor vessel thimble 1

3. Plug 159Al176Pl SAI82-F304 1/4 thick x 0.812 0D
4. Flange 9190610P] (719E474) de we ld\
           .SA 82-F304 3.37 thick x 9...5/8 0D neck 1 1/16 thick x 5.0 0D 2.875 ID S. Base 137C5311PI XM-I 9 ASME SA47-9 3.0 00D x .884 ID
6. Ring Flange 11B5122P2 SA182-F304' - Code weld I" thick..x.5.0 00 x 1.75 ID.

P5OYPl12

7. Cap Screw117C4516P2 SAl93-B6 CONTROL ROD DRIVE 6 ea. 1/2 dia. on 4 1/8 bolt circle DWG - 768E534
8. Plug 175A7961P1 9. Nut 137C5934P1 XH-19 SA479 SA182-F304 -1. 30- ti-kic = -2ý 2 d_-ta. O 0.38 thick x 1.307 dia.

90

shelet Iof 217 FOR?&11N-42F CERWFc-iCA HOLDERS' DAT-A'-RPORT FORSTVCLEAP.Z PART ANfl-APFVWRTEA-NCES

                                   'Asre q ired by tde -Prov-       i~on of the ASME Code Rua Section III, Div*:

4 1I.C. 1- k-~ze-, Gem'-l~al Zelctric Company, Castle Esyn-e Rd. , WlmInngton, (gue-1 ddýc-1'a C=,z5cm~n 14.ir (~) GC-eral Eleotrlic Comoany, San Jose, Califo=mm CNMG) 2- dt ~~zaUcf. F-cidm- Sm 24o.i of_ A57 20 me 3di. No.-__________ (~C~ee~~cad~76a]7534GO01 D- . Petersom (b)D~c~ ~Contra! Rod flrive, Model P B3144D)GO0 ()~~~~ A ~ l~i ez~ *974- W'75 31-

                                                             ~diei      o~~AA'-4d.o d~e                           *C=;,    No-.                ma        ______

3Standard pzint for use writh Reactor. flydxroatatically tasted at 1820 pal.

                    *Total m       ~e=      of sheiats           -. 2.

2 Ve cmendiy dho the sr~emw- aa~ i-- 613 repcxe am correc=. and d~iia ,'e-sel ccr~~ - defined ia the Coda eon hame of cmumc-iom io the ASME Coder S-e-riom 11L c __ý ITho- aprilfcmbie 0;A, Speeifttic and Strb RHn~l 2me no. tfa rerp~mibIJit: of th* N.-1 Cz.r zc2.+/-a HoldE~r for pare- -an NFT CartS!- i=Lo Hol- for &p~E~e= is rm=soeýiloi fOr f~roshumua. a =prt-Dmigm SPez85 dnd Strlmn R1ePor if Lbn ts a=nn InClda In, the comr~ane Des1im- 5pecfincz and Stre Hepart-) 7/7 _j981ý - GM- , NBPD-1D- 3- ~ L - CtR=ICA71ON OF DESGN FOR-APPURTENANCE (when Lupiicnble) D~stýal GE, NEPO-W¶D-OA, Castle Hayne Rd., Wil~mingtom.. N.C.. 22A5556, Rev--a S=ý= =Aoymis reprco.rile 2c GE, NEPO, San Jose, Calif. Z2A.4912, Rev-. 2 oeo-igm ijd yB B -- N.- Srinid2i pj ý .. Calif Regj;:.93 1 saeez aoeiysjs reVm edb B. N. gridharxprl Eng. Se.zCal-rf RZ.)4. 834 CMRMFIC-ATE OF HifO- INSPECTION

1. che undersiged, hldiozng X Toiid CCQMi2Zion iZ3oed bly the' H-; Ed BOard of Boiler mad Preaaaaae Veanel Inz-pectes e sh'a rýc emo p-cjoc oj North Carolinia .- L e,,y byDepartmant of Labor of State ofE North~ Caroli4na haeizczdi dz- a o ajm~ descril:ed in chi's emi PmrdzialLta Peport on-- 7/7 _19 .1 arid state Matito M~ebes ofmy bnowledzm.

and belief. the NPT Cer~llcate Holder has cons~rocted this Part In Accoredanee with the ASME Code Section 111. By sirping this ceerificaa, =icfh41t che laexpe=nr his ecmplcrer tanites zory watrrsry, e--pmzsaed cc plied,c Ins the Part described In thibs Partial Data F-eport. i.Frthermore. neither the inspector nor his emploYer, calol I>- liable in x~m scaner for any perzcraml injuxy or p y',ýdooagc or a loss of may kind ariziztg frmi at ctmnecm-d w-ith this ionap~eeica. Dais- . /?.. 7 _ 19 81 C~mianioos N.C. 723TBA.C1766, OHIO io!~.Jioa.

                           .~of [.00            o.   ~=~oo ey          .004 0.-,4.      (1) -   1B*. IV% C21i1~U,         o,~.                    ~ZS<

(1o77lThis form (EDD(1ln)mW be otliuned from -di Order Dept.. ASAAE, 346 F 47m1 St-. New York- N.Y. 10017

REPORT NO. P0059-012

                  -                                                                                                                                            Sheet 2 of 2/

FOORm-N-2 N-PT CERTIFiCATE HOLDERS' DATA REPORT FOR NUCLEAR PART AND APPURTENANCES,

                                         -A5 required bWthe Provision of the ASME Code Rules, Secion IIl, Div. I L(a)M~aw-n=d by                  General Electric Company,                                               Castle Hay-ne Rd.,                  Wilmingtom,            N.C.
                                       -  .~..        -       -             -    .       -      .   (None and addre= ot NvT cerabcz&Holder)                  -

(b) M aufl.tured fr General Electric Coerany, San Jose, Cali-z--*o a (NE3G)

                               - -   .        .-                                        nat4Mda-eý of S            Oetic=eHoivderfor ýpe~emoenuclear tvmaeloen:)
2. Idenltifecs 5on-Certlcasele Bolder's Serial No. *P'axt, A5720 - 'd. No.

(e-.. ......... ... L. Peterson ()Canstmcted According t-- Drawing Nc. 768Sý53AC0OQ Dratring Prepared b b)De cniption of Pamt Ieepeceed- Control Rod Drive, Miodel #7RDB-144lG-60l.

                     .~)               "- ..                                            ~       "J                                                  *.             N207 Applicable.A-'WE Code:SeerzionEa1, Ed"cion (c)                                                                        1974                AddLdd.d            .e             C7rNo. 1361-2 cl.,                        I
          .      Cap ].)A.B9.274P 1 (I67A2343)                                                                                                            od       weld SAiJS2- ; F3 76                -.. -                                           -                                   Code weld---,-

3/8 thick x 1 1/16 0D P.50YPlO2

2. Indicator Pipe 166B9313PlI 3-/4 scr-40-seamless pipe - - *'

0-] 1_3, wall thickness ... . 1.065 max.. dia. Reactor vessel

                                                                                   *    -.-.-          .-....                        thimble-                   -                    ...
3. Plug 159A1176PI \
  • . - SAI-82--F30.4- ... ... - .... .. . L
  • ~~-1/4 thic~k--X--0.8-8i2 00-- . .

3.

4. Flange 9*l06lOP" (719E474) Code weld X 2SA1 8-.F3o4 . .. p,50YP1 02---<

37 3.-e-.":-Tk x-5'.9*./8 CD 0. ..... . -. 1D--1/ck-thck* x 5.000

                  - M 7 -__ __ " ; . $ "              .                       .....

3.0OD x .834 ID . -

6. Ring Flan~g-1.1l4B5122P2 - / ~ .
               -*SAl82-F304-.                                                              .     "                                           ......                     Code wel d I" thick x 5.0'00 x 1.75 ID                                                                                                                           POYPI 02
7. Cap Scr-,e-.T17-C4516P2 ....

SAI 93-B& .... .... " ... -.. .... CONTROL DDRIVE

                .6-ea,-.,l-/2.dia., .-on 4 1/8 bolt circle                                                       .

8.

      '           PV-T1SA79IC:PO                           ".       "-.-                   --               '                   "
                                                                                                                              .9.         Nut'      137C5934P1 SA1 82-F304                                                                                                             XH-19 SA479 0.38 thick                S~l 1 .307'dia.           8-F3041.30 ..                                                                        thick x 2.62 dia..

91

REPORT NO. P0059-012 11321,- 3cK§5 NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As required by the Provisions of the ASME Code Section XI PNPP No. 9308 Rev. 9/11/00 NO1-1741

1. Owner: FIRSTENERGY CORP. Date 10/24/07 10 Centef Road. Perry. Ohio 44081 Sheet 1 of 1
2. Plant: Perrv Nuclear Power Plarit (PNPP) Unit 1 10.Center Road, Perry. Ohio 44081 ECP 06-0022 (RepairOrg. P.O. No., etc.)
3. Work Performed By: FIRSTENERGY Nuclear Operating Company PNPP Type Code Symbol Stamp NR 10 Center Road, Perry, Ohio 44081 Authorization No. 33 Expiration Date 9128/08
4. Identification of System: NUCLEAR BOILER B21 / INSTRUMENT AIR P57
5. (a) Applicable Construction Code: ASME SECTION III CLASS 2 and 3 1974 Edition NAME/S ECTION/DIVISION/CLASS Winter 19 75 Addenda .Code Case(s) ..*N3,N32-4,N71-6,N71-9,N224-1.N225.N241,N242 N249 N272.N282.N413,1644-5.1728.

(b) Construction Code used for repairs, modifications, or replacements: 1974 W75 _ Edition Addenda Code Case(s) (c) ASME Code Section XI applicable for Inservice Inspection: 1989 NONE N/A Edition Addenda . Code C.. Case(s) (d) Applicable Edition of Section XI Utilized for Repairs, Modification, or Replacements: 1995 19 N/A Addenda N/A Code Case(s) (e) Design Responsibilities First EnerqV Corp

6. Identification of Components Repaired, Modified, or Replacement Components Name of Name of Manufacturer Nat. Other Year I Repair ASME Component Manufacturer Serial No. Board ID. Built Replacement, Code No. I_ or Modification Stamped Piping system Johnson Controls 1P57-0043-F 033 N/A 1985 REPAIR YES Piping system Johnson Controls 1B21-0070-F 001 N/A 1985 REPAIR YES Piping system PULLMAN 1 P57 110 N/A 1985 REPAIR YES POWER Piping system PULLMAN 1B21 109 N/A 1985 REPAIR YES POWER .
7. Description of Work: THE DESIGN DOCUMENT FOR THIS RERATING IS ECP-06-0022 THIS WAR A DOC-[MFNT ONIY DESIcN CHANGE WITH NO FIELD WORK;SEE REMARKS SECTION.
8. Test Conducted: Hydrostatic- Ei Pneumatic- E) Nominal Operating Pressure- E] Other- El Pressure N/A psi Test Temperature N/A degrees F Code Case(s) N/A 92

NIS-21NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back) PNPP Nc. 9308 Rev. 9/11100 NQI-17-41

9. Remarks: -rý e

A  ; es*: anbUI -l ýu, Ul u oI DoI

                                                           ý;

ll!II: ons- o

                                                                       ; +k e

DO 1 anII 14 or:7

                                                                                              *l a*1r suDD 1JbI I

v f em 1s 1 14 owns 1 ream o I 4: fl, 1P57F00524A/B valves to the air accumulator tanks is increased from 200 psio to 210 osia. Note: Attach all applicable Manufacturer's Data Reports. Supplemental sheets such as lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded on the front of this form. CERTIFICATE OF COMPLIANCE 1, Michael J Teosick certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section X1 of the ASME Code and to the National Board Inspection Code "NR" rules. National Board Certificate of Authorization No. 33 to use the "NR stamp expires 28 Sept. , 20 08 Date 24 Oct. 20 07 Signed FENOC-PNPP DC Tech. (name of repairorganization) (authorized representative) (title) CERTIFICATE OF INSPECTION/INSERVICE INSPECTION I, Thomas G Laps holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HSB CT. of Hartford. Conn. have inspected the repair, modification or replacement described in this report on 1ýAf 1%. 20 0 7 and state that to the best of my knowledge and belief, this repair, modification or replacement has been'completed in accordance with Section X1 of the ASME Code and the National Board Inspection Code 'NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from or connected with this inspection. Date .9 , 20 Q-r Signed " Commissions NB 9330 "N" "I" A" Ohio Comm. (inspector) 3 (National Board (include endorsements), and)urisdiction,and no.)

REPORT NO. P0659-012 NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As required by the Provisions of the ASME Code Section XI PNPP No. 930S Rev. 9/11/0O NQI-1741

1. OvvneE FIRSTENERGY CORP. Date 5-6-9
                        *10 Center Road. Pery. Ohio 44081                              Sheet 1            of    1
2. Plant: Perry Nuclear Power Plant (PNPP) Unit 1 10 Center Road. Perry. Ohio 44081 (Repair Org. P.O. No., etc.)
3. Work Performed By: FIRSTENERGY Nuclear Ooeratino Comoanv PNPP Type Code Symbol Stamp NR 10 Center Road. Perry, Ohio 44081 Authoirization No. 33 Expiration Date 09/28/20.11
4. Identification of System: NUCLEAR BOILER PROCESS 1B21
5. (a) Applicable Construction Code: ASME Section III Class 1 .1 974 Edition NAME'SECTION/OIVISION/CLASS WINTER 19. 75 Addenda Code Case(s) N272. 1644-5, 1728, N413 (b) Construction Code used for repairs, modifications, or replacements: 1974 W 1975 none Edition Addenda Code Case(s)

(c) ASME Code Section XI applicable for Inservice Inspection: 1989 none none Edition Addenda Code Case(s) (d) Applicable Edition of Section XI Utilized for Repairs, Modification, or Replacements: 1989 19 none Addenda none Code Case(s) (e) Design Responsibiities FIRSTENERGY CORP.

6. Identification of Components Repaired, Modified, or Replacement Components Name of Name of Manufacturer Nat. Other Year Repair, ASME Component Manufacturer Serial No. Board ID. Built Replacement, Code No. or Modification Stamped PIPING PULLMAN 1B21 N/A N/A 1985 Replacement YES SYSTEM POWER
7. Description of Work:. REPLACED SNUBBER S/N 97-614263-33 WITH SNUBBER S/N 30800103/006 ALSO INSTALLED FWD BRACKET ASSY HT# N2037-G/N4312. PLANT ID 1B21H453.
8. Test Conducted:" Hydrostatic- ] Pneumatic- E Nominal Operating Pressure-rE- Other- El Pressure N/A psi Test Temperature N/A degrees F Code Case(s) N/A 93

NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back) PNPP No. 93D8 Rev. 9/11/00 NQI-1741

9. Remarks:

NO NAMEPLATE/STAMPING PERFORMED DUE TO THE INTERFACE CONTROLS OF PART 3 SECTION 1.8.6 BEING IN EFFECT AND JURISDICTIONAL AUTHORITY CONCURRENCE HAVING BEEN RECEIVED. Note: Attach all applicable Manufacturer's Data Reports. Supplemental sheets such as lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded on the front of this form. CERTIFICATE OF COMPLIANCE I, Michael J Teosick , certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and to the National Board Inspection Code `NR' rules. National Board Certificate of Authorization No. 33 to use the "NR stamp expires 2B Sept. , 20 11 Date 6 MAY 20 09 Signed FENOC-PNPP _ OC Tech. O (name of repair organi-zaton) (authorized representative) (titis) CERTIFICATE OF INSPECTION/INSERVICE INSPECTION I, Thomas G. Laps holding a valid commission issued by The NationaleBoard of.Boiler and Pressuie Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HSB CT: of Hartford, Conn. have inspected the repair, modification or replacement described-in this report on ni`xŽ_7 20 Dq_ and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code 'NR' rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damageor I s of any kind arising from or connected with this inspection. Date _ 20 d) SignedT &"A , I Commissions NB 9330 "N" "I""A" Ohio Comm. (inspector)f- * (NationalBoard (include endorsements), and jurisdiction, and no.)

REPORT NO. P0059-012 NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As required by the Provisions of the ASME Code Section Xl PNPP No. 9308 Rev. 9/11100 NQI-1741

1. Owner: FIRSTENERGY CORP. Date 5-11-9 10 Center Road. Perry Ohio 44081 Sheet 1 of 1
2. Plant Perry Nuclear Power Plant (PNPP) Unit 1 10 Center Road. Perry. Ohio 44081 . 200280560 (Repair Org. P2O. No., etc.)
3. Work Performed By: FIRSTENERGY Nuclear Ooerating Comoany PNPP Type Code Symbol Stamp N.R 10 Center Road. Perry, Ohio 44081 Authorization No. 33 Expiration Date 09/28/2011
4. Identification of System: NUCLEAR BOILER PROCESS 1B21
5. (a) Applicable Construction Code: ASME Section III Class 1 .1974 Edition NAMIE/SECTION/DIVISION/CLASS WINTER 19 75 Addenda Code Case(s) N272, 1644-5, 1728. N413 (b) Construction Code used for repairs, modifications, or replacements: 1974 W 1975 none Edition Addenda Code Case(s)

(c) ASME Code Section XI applicable for Inservice Inspection: 1989 none none Edition Addenda Code Case(s) (d) Applicable Edition of Section XI Utilized for Repairs, Modification, or Replacements: 19 89 _ 19 none Addenda none Code Case(s) (e) Design Responsibilities FIRSTENERGY CORP.

6. Identification of Components Repaired, Modified, or Replacement Components Name of Name of Manufacturer Nat. Other Year Repair, ASME Component Manufacturer Serial No. Board ID. Built Replacement, Code No. . or Modification Stamped PIPING PULLMAN 11B21 NIA N/A 1985 Replacement YES SYSTEM POWER
7. Description of Work: REPLACED SNUBBER S/N 00-614813-002 WITH SNUBBER SIN 02615163/002 ALSO INSTALLED A LOAD STUD HT# MSP AND 2 JAM NUTS C OF C 1894,PLANT ID 1B21H452.
8. Test Conducted: Hydrostatic- [0 Pneumatic- El Nominal Operating Pressure- E] Other- [I Pressure N/A psi Test Temperature N/A degrees F Code Case(s) N/A 94

NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back) PNPP No. 9308 Rev. 9/11/00 NQI-1741

9. Remarks:

NO NAMEPLATE/STAMPING PERFORMED DUE TO THE INTERFACE CONTROLS OF PART 3 SECTION 1.8.6 BEING IN EFFECT AND JURISDICTIONAL AUTHORITY CONCURRENCE HAVING BEEN RECEIVED. Note: Attach all applicable Manufacturer's Data Reports. Supplemental sheets such as lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 of this report is included on each sheet, and'(3) each sheet is numbered and the number of sheets is recorded on the front of this form. CERTIFICATE OF COMPLIANCE I, Michael J Tepsick , certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and to the National Board Inspection Code "NR" rules. National Board Certificate of Authorization No. 33 to use the "NR stamp expires 28 Sept., 20 11 Date 11 MAY 20 09 Signed FENOC-PNPP 25 Z-zf zt DC Tech. (name of repairorganization) (authorizedrepresenta'tive) (title) CERTIFICATE OF INSPECTION/INSERVICE INSPECTION 1, Thomas G. Laos - holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HSB CT. of Hartford, Conn. have inspected the repair, modification or replacement described in this report on M 20 o09 and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of-any kind arising from or connected with this inspection. Date 417l-, 20 6 Signed s o4 Commissions NB 9330 "N" "I""A" Ohio Comm. Ts_ (NationalBoard (include endorsements), andjurisdiction, and no.)

REPORT N(D. P0059-012 NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As required by the Provisions of the ASME Code Section X1 PNIPP No- 930B Rev. 91/00 NQ1-1741

1. Owner FIRSTENERGY CORP. Date 5-12-9 10 Center Road. Perry. Ohio 44081 Sheet 1 of .1
2. Plant Perry Nuclear Power Plant (PNPP) Unit 1 10 Center Road Perrv Ohio 44081 200280563 (RepairOrg. P.O. No., etc.)
3. Work Performed By: FIRSTENERGY Nuclear ODerating Company PNPP Type Code Symbol Stamp NR 10 Center Road. Perry. Ohio 44081 Authorization No. 33 Expiration Date 09/28/2011 4.ý Identification of System: NUCLEAR BOILER PROCESS 16321
5. (a) Applicable Construction Code: ASME Section III Class 1 "1974 Edition NAMESECTION/DIVISION/CLASS WINTER 19 75 Addenda Code Case(s) N272, 1644-5. 1728, N413 (b) Construction Code used for repairs, modifications; or replacements: 1974 W 1975 none Edition Addenda Code Case(s)

(c) ASME Code Section XI .applicable for Inservice Inspection: 1989 none none. Edition Addenda Code Case(s) (d) Applicable Edition of Section XI Utilized for Repairs, Modification, or Replacements: 1989,__ 19 none Addenda none Code Case(s) (e) Design Responsibilities FIRSTENERGY CORP.

6. Identification of Components Repaired, Modified, or Replacement Components

{ Name of Name of Manufacturer Nat. Other .Year" Repair, ASME Component Manufacturer Serial No. Board ID. Built Replacement, Code No. . or Modification Stamped PIPING . PULLMAN 121 N/A N/A 1985 Replacement YES SYSTEM POWER Tea

7. Description of Work: REPLACED SNUBBER S/N 00-614883-001 WITH SNUBBER S/N 30700524/016 ALSO INSTALLED FORWARD BRACKETT ASSY HT# N2089/N1699. PLANT ID 11B211H472.
8. Test Conducted: Hydrostatic- - Pneumatic- 0 Nominal Operating Pressure- E Other- ]

Pressure N/A psi Test Temperature N/A degrees F Code Case(s) N/A 95

I- - -  : _ -- ,. -. - - . . . - - :-. - r . . . . 1 , z r :ý . - -- - ý- .'.- - ... -7

                                                                                                                                                                 ý - -- '

NIS-2[NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back) ?NPP No. 9308 Rev. 9/11/00 NQI-1741

9. Remarks:

NO NAMEPLATE/STAMPING PERFORMED DUE TO THE INTERFACE CONTROLS OF PART 3 SECTION 1.8.6 BEING IN EFFECT AND JURISDICTIONAL AUTHORITY CONCURRENCE HAVING BEEN RECEIVED. Note: Attach all applicable Manufacturer's Data Reports. Supplemental sheets such as lists, sketches, or drawings 'may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded on the front of this form. CERTIFICATE OF COMPLIANCE I, Michael J Teosick _ certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section X1 of the ASME Code and to the National Board Inspection Code "NR' rules. National Board Certificate of Authorization No. 33 to use the "NR stamp expires 28 Sept. 20 11 Date 12 MAY 20 09 Signed FENOC-PNPP - OC Tech. aXi'- (name of repairorganization) (authorzed representative) (title) CERTIFICATE OF INSPECTIONIINSERVICE INSPECTION 1, Thomas G. Laos holding a valid commission issued by The National Board of Boilea and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HSB CT. of Hartford, Conn. have inspected the repair, modification or replacement described in this report on 13 20 eq1 and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the work described in this report Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damag Iloss of any kind arising from or connected with this inspection. Date _ 13 i.20 0L! Signed Commissions NB 9330 "N""I""A" Ohio Comm.

                                                   "nspe-todr                                     (NationalBoard (include endorsements),

andjunsilction, ano no.)

REPORT NO. PO059-012 113 2~-1 d° NIS-2[NR-I OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As required by the Provisions of the ASME Code Section XI PNPP No. 9308 Rev. 9/I 1/00 NQI-1741

1. Owner. FIRSTENERrY CORP. Date 5-6-9 10 Center Road. Pert-v. Ohio 44081 Sheet 1 of 1
2. Plant: Perry NucleaK-Power Plant (PNPP) Unit 1 10 Center Road. Perry, Ohio 44081 200280557 (Repair Org. P.O. No., etc.)
3. Work Performed By: FIRSTENERGY Nuclear ODeratino Company PNPP Type Code Symbol Stamp NR 10 Center Road. Perry, Ohio 44081 Authorization No. 33 Expiration Date 09/28/2011
4. Identification of System: NUCLEAR BOILER PROCESS 1B321
5. (a) Applicable Construction Code: ASME Section III Class 1 ,1974 Edition NAMEJSECTJON/DIWVSJONICLASS WINTER 19 75 Addenda Code Case(s) N272, 1644-5, 1728, N413 (b) Construction Code used for repairs, modifications, or replacements: 1974 W 1975. none Edition Addenda Code Case(s)

(c) ASME Coda Section XI applicable for Inservice Inspection: 1989 none none Edition Addenda Code Case(s) (d) Applicable Edition of Section XI Utilized for Repairs, Modification, or Replacements: 198 __ 19 none Addenda none Code Case(s) (e) De9ign Responsibilities FIRSTENERGY CORP.

6. Identification of Components Repaired, Modified, or Replacement Components Name of Name of Manufacturer Nat. Other Year Rpi, ASME Component Manufacturer Serial No. Board ID. Built Replacement, Code No. or Modification Stamped PIPING PULLMAN 1121 N/A N/A 1985 Replacement YES SYSTEM POWER
7. Description of Work: REPLACED SNUBBER S/N 97-614263-30 WITH SNUBBER S/N 30800103/008 ALSO INSTALLED FWD BRACKET ASSY-HT# N2038/N4312. PLANT ID 1B21H447.

.8. Test Conducted: Hydrostatic- D Pneumatic- D] Nominal Operafing Pressure- F1 Other- fl Pressure N/A psi Test Temperature N/A degrees F Code Case(s) N/A 96

                                                                                                  .......................    ~                     .-

NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back) PN4PP No. 9308 Rev. 9/11/00 NQI-1741

9. Rema-ks:

NO NAMEPLATE/STAMPING PERFORMED DUE TO THE INTERFACE CONTROLS OF PART 3 SECTION 1.8.6 BEING IN EFFECT AND JURISDICTIONAL AUTHORITY CONCURRENCE HAVING BEEN RECEIVED. Note: Attach all applicable Manufacturer's Data Reports. Supplemental sheets such as lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded on the front of this form. CERTIFICATE OF COMPLIANCE I, Michael J Teosick , certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section Xl of the ASME Code and to the National Board Inspection Code 'NR" rules. National Board Certificate of Authorization No. 33 to use the "NR stamp expires 28 Se~t. 20 11 Date 6 MAY_, 20 09 Signed FENOC-PNPP _C Tech. (name of repair organization) (a uthori2edrepresentative) (title) CERTIFICATE OF INSPECTION/INSERVICE INSPECTION I, Thomas G. Laos holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HSB CT. of Hartford, Conn. have inspected the repair, modification or replacement described in this report an - 20 Oct and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code 'NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or irnplied, concerning the Work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from or connected with this inspection. Date 2_,20 _r Signed 64 -ý4 er (\4,'* Commissions NB 9330 "N" "I""A"Ohio Comm. (inspecto4r )T (NationalBoard (include endorsements), andjurisdiction,and no.)

REPORT NO. P0059-012 NIS-2fNR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As required by the Provisions of the ASME Code Section XI PNPP No. 9308 Rev. 9111/00 NOI-1741 1, Owner: FIRSTENERGY CORP. Date 5-6-9 10 Center Road. Perry. Ohio 44081 Sheet 1 of 1 2, Plant: Perry Nuclear Power Plant (PNPP) Unit 1 10 Center Road, Perry. Ohio 44081 200280562 (Repair Org. P.O. No., etc.)

3. Work Performed By: FIRSTENERGY Nuclear OoeratinO Company PNPP Type Code Symbol Stamp NR 10 Center Road. Perrv, Ohio 44081 Authorization No. 33 Expiration Date 09/28/2011
4. Identification of System: NUCLEAR BOILER PROCESS 1B21
5. (a) Applicable Construction Code: ASME Section III Class 1 1974 Edition NAME/SECTION/DIVISIONICLASS WINTER 19 75 Addenda. Code Case(s) N272, 1644-5, 1728. N413 (b) Construction Code used for repairs, modifications, or replacements: 1974 W 1975. none Edition Addenda Code Case(s)

(c) ASME Code Section Xi applicable for Inservice Inspection: 1989 none none Edition Addenda Code Case(s) (d) Applicable Edition of Section XI Utilized for Repairs, Modification, or Replacements: 1989 19 none Addenda none Code Case(s) (e) Desijn Responsibilities FIRSTENERGY CORP.

6. Identification of Components Repaired, Modified, or Replacement Components Name of Name of Manufacturer Nat. Other Year Repair, ASME Component Manufacturer Serial No. Board ID. Built Replacement, Code

_ _ No. or Modification Stamped PIPING PULLMAN 1B21 N/A N/A 1985 Replacement YES SYSTEM POWER . .. 7 Description of Work: REPLACED SNUBBER S/N 97-614263-27 WITH SNUBBER S/N 30800103/D02 ALSO INSTALLED FWD BRACKET ASSY HT# N2037-G/N4312. PLANT ID 1B21 H462.

8. Test Conducted: Hydrostatic- E) Pneumatic- [I Nominal Operating Pressure- E] Other- []

Pressure N/A psi Test Temperature N/A degrees F Code Case(s) N/A 97

NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back) PNPP No. 9308 Rev. 9/i 1/DO NO]-i741

9. Remarks:

NO NAMEPLATE/STAMPING PERFORMED DUE TO THE INTERFACE CONTROLS OF PART 3 SECTION 1.8.6 BEING IN EFFECT AND JURISDICTIONAL AUTHORITY CONCURRENCE HAVING BEEN RECEIVED. Note: Attach all applicable Manufacturer's Data Reports. Supplemental sheets such as lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded on the front of this form. CERTIFICATE OF COMPLIANCE 1, Michael J Teosick _, certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section Xl of the ASME Code and to the National Board Inspection Code "NR' rules. National Board Certificate of Authorization No. 33 to use the "4R stamp,,expires 28 SeZt., 20 11 Date MAY 20 09 Signed FENOC-PNPP OC Tech. (name of repairorganizationJ (authorized representative) (titie) CERTIFICATE OF INSPECTIONIINSERVICE INSPECTION I, Thomas G. Laos ,holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HSB CT. . of Hartford, Conn. have inspected the repair, modification or replacement described in this report on M"4.-7, 20 C93 and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from or connected with this inspection. Date 20 QýL Signed Commissions. NB 9330 "N""I""A" Ohio Comm. tinspector Q J (National.Board (include endorsements), andjurisdiction, and no.)

REPORT NO. P0059-012 NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As required by the Provisions of the ASIME Code Section Xl PNPP No, 930B Rev. 9/ 1/00 NQI-1741

1. Owner. FIRSTENERGY CORP. Date 5-5-9 10 Center Road. Perry. Ohio 44081 Sheet 1 of 1
2. Plant Perry Nuclear Power Plant (PNPP) Unit 1 10 Center Road. Perry, Ohio 44081 200280564 (RepairOrg. P.O. No., etc.)
3. Work Performed By: FIRSTENERGY Nuclear Operatino Comoany PNPP Tyfpe Code Symbol Stamp NLR 10 Center Road, Perry, Ohio 44081 Au:thorization No. 33 Ex piration Date 09/28/2011
4. Identification of System: NUCLEAR BOILER PROCESS 1821
5. (a) Applicable Construction Code: ASME Section III Class 1 1974 Edition NAME/SECTION/DIVISION/CLASS WINTER 19 75 Addenda Code Case(s) N272. '1644-5. 1728, N413 (b) Construction Code used for repairs, modifications, or replacements: 1974 W 1975 none Edition Addenda Code Case(s)

(c) ASME Code Section. X1 applicable for Inservice Inspection: 1989 none none Edition Addenda Code Case(s) (d) Applicable Edition of Section XI Utilized for Repairs, Modification, or Replacements: 19 89_ 19 none Addenda none Code Case(s) (e) Design Responýsibilities FIRSTENERGY CORP.

6. Identification of Components Repaired, Modified, or Replacement Components Name of Name of Manufacturer Nat Other Year Repair, ASME Component Manufacturer . Serial No. Board ID. Built Replacement, Code I No. I I I or Modification Stamped PIPING PULLMAN 1B21 N/A N/A 1985 Replacement YES SYSTEM POWER 7 Description of Work: REPLACED SNUBBER S/N 97-61"4263-25 WITH SNUBBER S/N 30800103/007 PLANT'ID 1B21 H490.
8. Test Conducted: Hydrostatic- ED Pneumatic- J1 Nominal Operating Pressure- F] Other- El Pressure N/A psi Test Temperature N/A degrees F Code Case(s) N/A 98

NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back) PNPP No. 9308 Rev. 9/11/00 DNQI-1741

9. Remarks:

NO NAMEPLATE/STAMPING PERFORMED DUE TO THE INTERFACE CONTROLS OF PART 3 SECTION 1.8.6 BEING IN EFFECT AND JURISDICTIONAL AUTHORITY CONCURRENCE HAVING BEEN RECEIVED. Note: Attach all applicable Manufacturer's Data Reports. Supplemental sheets such as lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded on the front of this form. CERTIFICATE OF COMPLIANCE I, Michael J Teosick certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and to the National Board Inspection Code "NR" rules. National Board Certificate of Authorization No. 33 to use the "NR stamp expires 28 Seat. , 20 11 Date 6 MAY 20 09 Signed FENOC-PNPP / -- OC Tech. (name of repair organization) . (authorizedrepresentative) (title) CERTIFICATE OF INSPECTIONIINSERVICE INSPECTION I, Thomas G. Laos holding axvalid commission issued by The National.Board of-Boiler-and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HSB CT. of Hartford, Conn. have inspected the repair, modification or replacement described in this report on - 20 0 and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code "NR rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from or connected with this inspection. Date J~1,20 Q5 Signed Zf M&I V "' Commissions NB 9330 "N" ""I""A"Ohio Comm. (nspectoq 1 U (National Board and (includeand jufisdiction, endo'sements), no.)

REPORT NO. P0059-012 NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As required by the Provisions of the ASME Code Section XI PNIPP No. 9308 Rev. 9/11/00 NQI-1741

1. Ownen FIRSTENERGY CORP. Date 5-5-9 10 Center Road. Pen-v, Ohio 44081 Sheet 1 of I
2. Plant: Perry Nuclear Power Plant (PNPP') Unit 1 10 Center Road. Perryv Ohio 44081 200280555 (RepairOrg. P.O. No., etc.)
3. Work Performed By: FIRSTENERGY Nuclear ODeratinq Company PNPP Type Code Symbol Stamp NR 10 Center Road. Perry. Ohio 44081 Authorization No. 33 Expiration Date 09/2812011
4. Identification of System: NUCLEAR BOILER PROCESS 1B21
5. (a) Applicable Construction Code: ASME Section III Class 1 1974 Edition NAMEJSECTION/DIVISION/CLASS WINTER 19 75 Addenda Code Case(s) N272, 1644-5, 1728. N413 (b) Construction Code used for repairs, modifications, or replacements: 1974 W 1975 none Edition Addenda Code Case(s)

(c) ASME Code Section XI applicable for Inservice Inspection: 1989 .none none Edition Addenda Code Case(s) (d) Applicable Edition of Section XI Utilized for Repairs, Modification, or Replacements: 1989 _ 19 none Addenda none Code Case(s) (e) Design Responsibilities FIRSTENERGY CORP.

6. Identification of Components Repaired, Modified, or Replacement Components Name of Name of Manufacturer NaL Other Year Repair, ASME Component Manufacturer Serial No. Board ID. Built Replacement, Code I No. I I I or Modification Stamped PIPING PULLMAN 1821 N/A N/A 1985 Replacement YES SYSTEM POWER
7. Description of Work: REPLACED SNUBBERS S/N 97-614263-28 AND 97-614263-29 WITH SNUBBERS S/N 30800103/005 AND 01615123/002. PLANT ID 1821 H446.
8. Test Conducted: Hydrostatic- [ Pneumatic- L] Nominal Operating Pressure- El Other- [I Pressure N/A psi Test Temperature N/A degrees F Code Case(s) N/A 99

NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back) PNPP.No. 9308 Rev. 9111/00 NQ;-1741

9. Remarks:

NO NAMEPLATE/STAMPING PERFORMED DUE TO THE INTERFACE CONTROLS OF PART 3 SECTION 1.8.6 BEING IN EFFECT AND JURISDICTIONAL AUTHORITY CONCURRENCE HAVING BEEN RECEIVED. Note: Attach all applicable Manufacturer's Data Reports. Supplemental sheets such as lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded on the front of this form. CERTIFICATE OF COMPLIANCE I, Michael J Teosick , certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and to the National Board Inspection Coda "NR" rules. National Board Certificate of Authorization No. 33 to use the "NR stamp expires 28 Sept. . 20 11 Date 6 MAY 20.09 Signed FENOC-PNPP OC Tech. (name of repairorganization) (authorizd represent.live) (title) CERTIFICATE OF INSPECTION/INSERVICE INSPECTION I, Thomas G. Laos holding a valid commission issued by The National Board-of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO' and employed by .HSB CT. of Hartford, Conn. have inspected the repair, modification or replacement described in this report on.r 1 '3 20 9. and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code "NR' rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, conceming the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from or connected with this inspection. Date _* -.1- , 20 o__ Signed v,. . Commissions NB 9330 "N" "I""A" Ohio Comm, CTnspectol A (NationalBoard (include endorsements), andjurisdiction, and no.)

REPORT NO. P0059-012 NIS-2/NR-1 OWNER'S.REPORT FOR REPAIRS OR REPLACEMENTS As required by the Provisions of the ASME Code Section Xl PNPP No. 9308 Rev. 9f111/00 NQ-1741

1. Owner FIRSTENERGY CORP. Date 5-6-9 10 Center Road. Perrv. Ohio 44081 Sheet 1 of 1
2. Plant: Perry Nuclear Power Plant (PNPP) Unit 1 10 Center R6ad. Perrv. Ohio 44081 200280565 (RepairOrg. P.O. No., etc.)
3. Wdork Performed By: FIRSTENERGY Nuclear Ooeratin Comoany PNPP Type Code Symbol Stamp NR 10 Center Road, Perry. Ohio 44081 Authorization No. 33 Expiration Date 09/28/2011
4. Identification of System: NUCLEAR BOILER PROCESS 18B21
5. (a) Applicable Construction Code: ASME Section III Class 1 1974 Edition NAME/SECTIONIDIVISION/CLASS WINTER 19 75 Addenda - Code Case(s) N272, 1644-5, 1728. N413 (b) Construction Code used for repairs, modifications, or replacements: 1974 W 1975 none Edition Addenda Code Case(s)

(c) ASME Code Section X1 applicable for Inservice Inspection: 1989 none none Edition Addenda Code Case(s) (d) Applicable Edition of Section XI Utilized for Repairs, Modification, or Replacements: 1989 __ 19 none Addenda none Code Case(s) (e) Design Responsibilities FIRSTEN5RGY CORP.

6. Identification of Components Repaired, Modified, or Replacement Components Name of Name of Manufacturer Nat. Other Year Repair, ASME Component Manufacturer Serial No. Board IQ. Built Replacement, Code No. " or Modification I Stamped PIPING PULLMAN 1B21 N/A N/A 1985 Replacement YES SYSTEM POWER 7 Description of Work: REPLACED SNUBBER S/N 97-614263-26 WITH SNUBBER SIN 30800103/010 ALSO INSTALLED FWD BRACKET ASSY HT# N2037-GIN4312. PLANT ID 1B21H491.
8. Test Conducted: Hydrostatic- El Pneumatic- n Nominal Operating Pressure- LI Other- [I Pressure N/A psi Test Temperature N/A degrees F Code Case(s) N/A 100

NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (BaCk) PNP- No. 9308 Rev. 9/11/00 NOI-1741

9. Remarks:

NO NAMEPLATE/STAMPING PERFORMED DUE TO tHE INTERFACE CONTROLS OF PART 3 SECTION 1.8.6 BEING IN EFFECT AND JURISDICTIONAL AUTHORITY CONCURRENCE HAVING BEEN RECEIVED. Note: Attach all applicable Manufacturer's Data Reports. Supplemental sheets such as lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded on the front of this form. CERTIFICATE OF COMPLIANCE I, Michael J TeDsick certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and to the National Board Inspection Code "NR* rules. National Board Certificate of Authorization No. 33 to use the 'NR stamp expires 2B Sept. 20 11

   .Date 6 MjAY. 20 09       Signed             FENOC-PNPP.                           '                        CC Tech.

(name of repair ornanization) (authofized representative) (title) CERTIFICATE OF INSPECTION/INSERVICE INSPECTION

  'I, Thomas G. Laos                    .               ,holding a valid commission issued by The National-Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of                       OHIO and employed by       HSB CT.                                               of Hartford, Conn.                                 have inspected the repair, modification or replacement described in this report on _.M          FL 20 0'1           and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code "NR' rules.

By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from or connected with this inspection. Date ilt., 20 Cl- Signed -44 rs4 Commissions NB 9330 "N" "I""A" Ohio Comm. i7nspector) (National Board (include endorsements), and jurisdiction, and no.)

REPORT NO. P0059-012

                                                                                                 //?i  ZI -

NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As required by the Provisions of the ASME Code Section XI PNPP No. 93DB Rev. 9/11100 NQ1-1741

1. Owner-. FIRSTENERGY CORP. Date 5-19-9 10 Center Road. Perry. Ohio 44081 Sheet 1 of 2
2. Plant: Perry Nuclear Power Plant (PNPP) Unit 1 10 Center Road. Perryv Ohio 44081 200174644 (Repair Org, P.O. No., etc.)
3. Work Performed By: FIRSTENERGY Nuclear Operating Comoany PNPP Type Code Symbol Stamp NR
                            " 10 Center Road. Perry, Ohio 44081                            Authorization No.              33 Expiration Date 09/28/2011
4. Identification of System: NUCLEAR BOILER PROCESS 1 B21
5. (a) Applicable Construction Code: ASME Section III Class 1 ,1974 Edition NAMEISECTIONIDIVISIONICLASS WINTER 19 75 Addenda Code Case(s) 272, 1644-4, 1728 (b) Construction Code used for repairs, modifications, or replacements: 1974 W 1975 none Edition Addenda Code Case(s)

(c) ASME Code Section XI applicable for Inservice Inspection: 1989 none none Edition Addenda Code Cace(s) (d) Applicable Edition of Section XI Utilized for Repairs, Modification, or Replacements: 19 89 19 none Addenda none Code Case(s) (e) Design Responsibilities FIRSTENERGY CORP.

6. Identification of Components Repaired, Modified, or Replacement Components Name of Name of Manufacturer Nat. Other Year Repair, ASME Component Manufacturer Serial No. Board ID. Built Replacement, Code No. or Modification Stamped PIPING GENERAL 1121 64084 1B21F41E 1985 Replacement YES SYSTEM ELECTRIC 7 Description of Work: REPLACED VALVE S/N 160887 WITH VALVE S/N 160850.

SEE REMARKS.

8. Test Conducted: Hydrostatic- EW Pneumatic- E] Nominal Operating Pressure--Z Other- E]

Pressure 1028 psi Test Temperature 125 degrees F Code Case(s) N/A 101

NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back) PNPP No. 9308 Rev. 9111/00 NQI-1741

9. Remarks: INSTALLED 12 STUDS 1-5/8"-8 HT# 0G84 AND 12 HYDRA NUTS 1-5/8"-8 HT# 590A.

16 STUDS 1-8 (15 HT# 2C05 AND 1 HT#OG81), 16 HYDRA NUTS 1-8 HT# 591A. NO NAMEPLATE/STAMPING PERFORMED DUE TO THE INTERFACE CONTROLS OF PART 3 SECTION 1.5.6 BEING IN EFFECT AND JURISDICTIONAL AUTHORITY CONCURRENCE HAVING BEEN RECEIVED. Note: Attach all applicable Manufacturers Data Reports. Supplemental sheets such as lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded on the front of this form. CERTIFICATE OF COMPLIANCE I, Michael J Teosick , certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and to the National Board Inspection Code 'NR' rules. National Board Certificate of Authorization No. 33 to use the '.NR stamp expires 28 Set. . 20 11 Date 19 MAY 20 09 Signed FENOC-PNPP .-- m DC Tech. (name of repairorganization) (authonzedrepresentative) (title) CERTIFICATE OF INSPECTIONIINSERVICE INSPECTION I, Thomas G. Laps holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HSB CT. of Hartford, Conn. have inspected the repair, modification or replacement described in this report on t 20 T and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from or connected with this inspection. Date 20 Signed c-" pl r Commissions NB 9330 "Nr"I" "A" Ohio Comm.

                      /(inspictoo                                 U                         (National Board (include endorsements),

and jurisdiction,and no.)

REPORT NO. P0059-012

                  ,ýORM NV-i MANUFACTURERS- DATA REPORT FOR SAFETY AND SAFETY REUEF VALVES*

(As Required by die Proviions of the ASME Code, Se-ction [iI, Div. Q 1. Manufactured by (,. OLkkers & Co. N.V. Henqgeto (u)*"tuie eherlands (Nnme and Address of Manufactuere

2. Manufactured for (';cry I IN-a and Addre=s of Purchaser or Owner)

Location o1"Installation North Pe£rr-y'. Oh io 3. (Name and Addrel" .

                --- -            --            G4,71=h/2_5.04.-4                                      29                                                   1976 (CRNI                                               (1rwing No.-                             (NatL Brd. No.)                     (Year Built              .

Valve ... 1 ..... Identifying Nos. ](0*5U ... - ..... ." S(ModeNoj No- Scr.c . (Manufaourer° Serial Na. Type .. s-.afstyjzeLief ._. Safety. Sýfety Relief; Pilot; Po*we Actuated Orifice Sze..4... 4 Nominal Inlet Size ..... Outlet Size ... ... ..... lash inch inch Set Pressure (PSIG) - . -- . ....... Rated Temperature .............. SA. -F Stamped Capacity .b..g.. 3m2 ..... ibsihr @---0 .....  % Overpressure Blowdown WPSIGI ._-.5. '.._ Hydrostatic Test (PSIZ) Inlet 2 ...... ...

  • Outlet ._ .. b
                                                                                                                           ....                              975
7. Pressure Retaining Pieces Serial No. or Material Specification Identification IncL Type or Grade Sody B

Sonnet or Yoke SA*--352 -Lr'N Support Rods Nozzle Disc Spring Washers - . Ad.usting Screw A.FU.Ilzi + OL9 SA.. 1a2.._EL&..._________ Spindle A-JE 0015 .A.._hSb,4r2.Ltyprn 6,3t nord P11 00 Spring

        *Sdlting                              AJZ,       AJR,         Ai&ZA,         AJJ,   ALA~,                   Sk_ 193=U2.LSAL196~-71LSA ..JS4.-2H.

Other Pieces anY, ArU(, A4Ži., AJL_ Linaer. Gov er_." SA. 35LC-U ... 55-4b-7 sin b Venrt pipe SA 35tU5.

          .F L aiges                          4FV     uJ74        +    1U2                                          SA 105              -             -
          .a"x.      ,)uts.i*e       dLa~a.        va~ivt            body:                                            476 nua (16.74                inch) lengrh vaLve                                                                   1645 uusa(64.76                inch)

RECEIVED JAN 11 1979. P.N PP-SOIDC. Supplemental sheets in form of fists, sketches or drawings may be used provided (1) size is 8-1/-2 x 11". (2) information in items 1-2 on this data report is included on each sheet, and (31 each sheet is numbered and number of sheets is recorded at top of this form. (I n6) This form (E00642) may be obtained fr,.rn the Order Dept.. ASME, 34S E. 47 St., New York. N.Y. 10017 102

FOQRM NV-1 (Back) 4 CERTIFICATE OF COMPUANCE We certify that the statements made in this report are correct and that this valve conforms to the rules of construction of the ASME Code for Nuclear Power Plan( Components. Section Ill. Div. 1., 1974. Edition, Addenda sern. 7f6

                           . ....                                                                                                                      lOatel Code Case No.
  • 1 )ate Our ASME symbol expires Certificate I3sr Signed G.

of DLikkers. Authorization J~u~y1 , 1 No. Cu.

                                                                                \
                                                                                          /,.tel~v by       .W.ii.

1 bob WiLlems. to use, the NV CERTIFICATION OF DESIGN Design information on file at General Eleccric and Perry Stress analysis report (Class I only) on File at General Eleccric andPr . .. Design specifications certifed by- . L' Bt. . . .. . . . ...... .. . ..... .. ... . PsSate _gal fo..a ... . Re.No..... 1_ ..... Stress report crtified by' . berr b. Weiss . .. . PE state Cal iforn a/_I noios . . eg. No......_HA1492t1 L-2-5 4-- Signature not required--ist name only. CERTIFICATE OF SHOP INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of .- P.h .. _-... .. . ... end employed by - Kell' eL_. I Q s_. -. of .5 U........

                                  ý!,QY_                have inspected the pump, or valve, described in this Data Report on
 .__ 10J1.           ._            19 _.?, and state that to the best of my knowledge and belief, the Manufacturer has con-stn*cte¢d this pump, or valve, in ,ccordanca with the ASME Code for Nuclear Power Plant Components-9y signing this certificate, neither the Inspector nor his employer makes any warrant. expressed or implied, concerning ia equipment described in this Data Report .Furd:ermore, 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 inspect'ion.

Date f... . . " 7. Signed I. pect 'L'S.PCommissions NB3 4n45b lnpOf (Nati ltd State Prov, and No.)

REPORT NO. P0059-012 116, 21- 7W/.X NIS-2!NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As required by the Provisions of the ASME Code Section XI PNPP No. 930B Rev. 9/11/00 NOt-1741

1. Owner-. FIRSTENERGY CORP. Date 5-19-9 10 Center Rnod; Perry, Ohio 44081 Sheet 1 of 2 2, Plant: Perry Nuclear Power Plant (PNPP) Unit 1 10 Center Road, Perry, Ohio 44081 - 200174646 (RepairOfg. P.O. No., etc.)
3. Work Performed By: FIRSTENERGY Nuclear Operatino Company PNPP Type Code Symbol Stamp NR 10 Center Road. Perry. Ohio 44081 Authorization No. 33 Expiration Date 09/28/2011
4. Identification of System: NUCLEAR BOILER PROCESS 1B21
5. (a) Applicable Construction Code: ASME Section III Class 1 1974 Edition NAME/SECTION/DIVISiON/CLASS WINTER 19 75 Addenda Code Case(s) 272, 1644ý4, 1728 (b) Construction Code used for repairs, modifications, or replacements: 1974 W 1975 none Edition Addenda Code Case(s)

(c) ASME Code Section XI applicable for Inservice Inspection: 1989 none none Edition Addenda Code Case(s) (d) Applicable Edition of Section XI Utilized for Repairs, Modification, or Replacements: 19 89 19 none Addenda none Code Case(s) (e) Design Responsibilities FIRSTENERGY CORP.

6. Identification of Components Repaired, Modified, or Replacement Components Name of Name of Manufacturer Nat. Other Year Repair, ASME Component Manufacturer Component _ Serial No. Board ID. Built Replacement. Code

____ No. _____ or Modification Stamped PIPING GENERAL 1821 64084 1B21F41C 1985 Replacement YES SYSTEM ELECTRIC 7, Description of Work: REPLACED VALVE S/N 160885 WITH VALVE S/N 160866. SEE REMARKS.

8. Test Conducted: Hydrostatic- El Pneumatic- F1 Nominal Operating Pressure- Z Other- RI Pressure 1028 psi Test Temperature 125 degrees F Code Case(s) N/A 103
                                                                                                                              -7 NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back)

PNPP No. 9308 Rev. 9/11/00 NQ1-1741

9. Remarks: INSTALLED 12 STUDS 1-518"-8 HT# K745. 12 HYDRA NUTS 1-5/8-8 HT# 590A, 16 STUDS 1"-8 HT# 2C05.AND 16 HYDRA NUTS 1"-8 HT# 591A.

NO NAMEPLATE/STAMPING PERFORMED DUE TO THE INTERFACE CONTROLS OF PART 3 SECTION 1.8.6 BEING IN EFFECT AND JURISDICTIONAL AUTHORITY CONCURRENCE HAVING BEEN RECEIVED. Note: Attach all applicable Manufacturer's Data Reports. Supplemental sheets such as lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded on the front of this form. CERTIFICATE OF COMPLIANCE I, Michael J Tepsick , certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and to the National Board Inspection Code "NR" rules. National Board Certificate of Authorization No. 33 to use the "NR stamp expires 28 Seot. , 20 11 Date 19 MAY 20 09 Signed FENOC-PNPP , -1" -' OC Tech. (name of repairorganization) (authorizedrepresentative). (title) CERTIFICATE OF INSPECTIONIINSERVICE INSPECTION I, Thomas G, Laps holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HSB CT. of Hartford, Conn. have inspected the repair, modification or replacement described in this report on I 20 0 c9 and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from or connected with this inspection. Date 9a1A0 , 20 0 '? Si gned Commissions NB 9330 "N" 'I""A" Ohid Comm. Cinspect~io) (National Board (include endorsements), andjurisdiction, and no.)

B'EPORT NO. P0059-012

                                                                                                                                                                 '2.
                                                                                                              /,& Z/ - Z/                *l
  • 2 FOCM4 NV-1 N CERTIFICATE HOLDERS' DATA REPORT FOR SAFETY AND'SAFETY RELIEF VALVES.

As Required by the Provisions of the ASME Code, Section Ill, Div. I

i. Menucur-'d b -G. Dikkers & Co. NV. HenFelo (_) The Netherlands IN ne and e o
                                                                         .(rssN cer-tificste Nolar-,       I
2. Manufacturvd for. . General EIectric, San JOse, CahI .. oTrnia (Name and Address of Purchaser or 0-nerl
3. Location of In.r.rlation _PFerry I I North Perry Ohio
4. _Gn 471-6/12S.o rev. 65_ _ 197B
5. V7 rsang Nlo.)et' 8.f 6 6 Built) aY...

S. Vale G471........ Identifying Nos... Type IFMod. No..*sroC"S feyo NeR Re] i ef (fN Certlllca*e Holder's Se-r:l No.1

                     *S* ry     4    qSIiRelief:
                                        ,        Pilot; Power Actuated Orifice Sime                             --       Nominal Inlet Size                                             Outlet     Size     ID inch                                                               inch                                                inch 11 65                                        Terperature            -7.Rated
6. Set Preszsure (PS)G)

Stamped Capacity 905739 ibsihr @. ..-.% Overpressure Blowdown (PSIGI 108.08 st.L Steam 2350 975 2350 Outlet Hydro-retic Test [MSlG) Inlet lAppli*c *le to -olu-. for closed sysxm. onlyl

7. Pressure.Retaining Pieces ,

Serial No. or Material Specification Identification Incl. Type or Grade Body 1I .12.8 sn 1 SA 352 LCB Bonnet or Yoke __14.32.8 sn 1 SA 352 LCB Support Rods Nozzle AJW _01 1 SA 350 LF2 Disc 53-. 04.8 2B SA 351 CF3A Spring Washers "26.30.95-44 45..Cr Mo V 67. Adjusting Screw 'AFU 123 ANE 00* SA 182 F-316 Spindle AJE 0,8 A 564-74 type .30 cornd. H1100 Spring Boating AYE/ANY/AVS/ALRY SA7nTg3-B/S-A 15y-/7S-A- 1947-2H AWZ/AMR/AJM/AfJL/AJJ L e Fk .5 18.8 sn 1 %. s7A .51 LI-3A uover 53.28.d sn 10 Vent. Pipe AKE 059 .... SA iUb

   -F-ages                       AKF 0'-9 -AFV 105.. *"""...                                       ~SA-105 Max. outside diam. valve body                                   481    mmi(18,94)"

Max. outside length valve 1645 m(64.76)" Supplemental sheets in form of lists, sketches or drawings. may be used provided (1) size is 8-1/2" x 11-, (2) information in items 1-2 on this Data Report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at top of this form. (10/771 This form (EO00421 may be obtained from the Order Dept.., ASME. 345 E. 47th St, New York, N.Y. 10017 104

FORM NV-1 (Back) CERTIFICATE OF COMPUANCE We certify that the satements made in this report are correct and that this valv*e conforms to ,he rules of construction of the ASME Code for Nuclear Power Plant Components. Section Ill. Div. I.. CJ9/ Edition. Addenda 7, Code Case No. * -Iae Date c i- C K, e 5 Signed G. Dikkers & Co NV I IN Ce ~~rlf

                                                                     ~ ealeNlr)                by Our    ASME Certificate          of Authorization    No.                                        06                 to use  theby (NV) symkybol expires            1st. July 1980 lDale)

CERTIFICATION OF DESIGN Design information on file at G.npral Flprtrir and_ Perr-v It Stress analysis report (Class 1 only) on file at ._GenEral Fl erti r Andl Perrm I1 Design specifications certified by' Bovd P. Brooks FIEState Cal ifornia flag. No. ,55 tress report certified b Robert L. Weits PEState " Cal iornia/ 1/ I nois Reg. No. M 14921/62-25749 Signature not required-list name only. CER1TIFICATE OF SHOP INSPECTION I. the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of _ hin - r6 "- and employed by. --4rpipr is . of I ohg Grnv. T TT have inspected the pump. or valve, described in this Data Report on 12 March -. 19 75 'and state that to the best of my knowledge and belief, the N Certificate Holder has - .,- constructed this punrp, or valve, in accordande with the ASME Code for Nuclear Power Plant Components. By signing this certificate, neither the lnspector'nor his employer makes any warrant, expressed or implied, concerning the equipment described in this Data Report. Furthermore. neither the Inspector nor his employer shali be liable in any manner for any personal injury or property damage or a loss of any kind arising from-or bonnected with this inspection. Date -a 1. Signed " ... Commissions NB 4805 (

6. e*atrl . . ,4ati'L8., State Pro,. and No.1

REPORT NO. P0059-012 NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As required by the Provisions of the ASME Code Section XI PNPP No. 9308 Rev. 9/11/00 NQI-1741

1. Owner: FIRSTENERGY CORP. Date 5-19-9 10 Center Road. Penr. Ohio 44081 Sheet 1 of 2
2. Plant Perry Nuclear Power Plant (PNPP) Unit 1 10 Center Road. Perry, Ohio 44081 200174647 (Repair Org. P.O. No., etc.)
3. Work Performed By: FIRSTENERGY Nuclear Operating Comoany PNPP Type Code Symbol Stamp NR 10 C~enter Rnerd Perry flhin 44081
                                .  . Ce
                                       .  ... te  ..Road . Per   ......     .....

Authorization No. 33 Expiration Date 09/28/2011

4. Identification of System: NUCLEAR BOILER PROCESS 1 B21
5. (a) Applicable Construction Code: ASME Section IIMClass 1 1974 Edition NAME/SECTION/DIVISION/CLASS WINTER 19 75 Addenda Code Case(s) 272, 1644-4, 1728 (b) Construction Code used for repairs, modifications, or replacements: 1974 W 1975 none Edition Addenda Code Case(s)

(c) ASME Code Section XI applicable for Inservice Inspection: 1989 none none Edition Addenda Code Case(s) (d) Applicable Edition of Section XI Utilized for Repairs, Modification, or Replacements: 19 89 , 19 none Addenda none Case(s) Code (e) Design Responsibilities FIRSTENERGY CORP.

6. Identification of Components Repaired, Modified, or Replacement Components Name of Name of Manufacturer Nat. Other Year Repair, ASME Component Manufacturer Serial No. Board ID. Built.' Replacement, Code No. I or Modification Stamped PIPING GENERAL 1B21 64084 1B21F41G 1985 Replacement YES SYSTEM ELECTRIC " E 7 Description of Work: REPLACED VALVE S/N 160865 WITH VALVE S/N 160852.

SEE REMARKS.

8. Test Conducted: Hydrostatic- E] Pneumatic- D Nominal Operating Pressure- [ Other- El Pressure 1028 psi Test Temperature 125 dearees F Code Case(s) N/A 105
                                                                         .*=..*- *-._.*       ......-.........-............-...................-....-.....
                                                                                                                                                   "-.....'.-.,.-......"........¸
                                                                                                                                                            -     -'.----         y- "'.'*

NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back) PNPP No. £308 Rev. 9I11/00 NO1-1741

9. Remarks: INSTALLED 12 STUDS 1-5/8"-8 HT# K745. 12 HYDRA NUTS 1-5/B"8 HT# 590A, 16 STUDS 1"-8 HT#2C05.AND 16 HYDRA NUTS 1"-8 HT# 5lA NO NAMEPLATE/STAMPING PERFORMED DUE TO THE INTERFACE CONTROLS OF PART 3 SECTION 1.8.6 BEING IN EFFECT AND JURISDICTIONAL AUTHORFIY CONCURRENCE HAVING BEEN RECEIVED.

Note: Attach all applicable Manufacturer's Data Reports. Supplemental sheets such as lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded on the front of this form. CERTIFICATE OF COMPLIANCE I, Michael J Teosick , certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section X1 of the ASME Code and to the National Board Inspection Code "NR' rules. National Board Certificate of Authorization No. 33 to use the "NR stamp expires 28 Sept, 20 11 Date 19 MAY 20 09 Signed FENOC-PNPP QC Tech. (name of repairorganization) (authdrizedrepreseritative) (title) CERTIFICATE OF INSPECTION/INSERVICE INSPECTION I, Thomas G. Laps . ,holding a valid commission issued by The National-Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HSB CT. of Hartford Conn. have inspected the repair, modification or replacement described in this report on M)L).2 20 Oq and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section X1 of the ASME Code and the National Board Inspection Code "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from or connected with this inspection. Date 0,20 CA1 Signed kIit-m sc~a.Lz Commissions NB 9330 "N"*"I' ",A"Ohio Comm. rInspecfor , (National Board finclude endorsements), andjurisdiction,and no.)

REPORT NO. P0059-012

                                                                                                                                                           *                     /S2;I-y'w-                   *i,;-      e_

FORM NV-i MANUFAcTURERS DATA REPORT FOR SAFETY AND SAFETY RELIEF VALVES' 1/4f-- (As Required by the Provisions of the ASME Code, Section III, Div. I)

       .. Manufactured by                        G. U.kkers & Co.                           NV.              liengelo             (0)        The       Necherlands (Niame andýAddirtss of IAMactu-aOrl
2. Manufactured for ?eir-y. r (Name and Addrmex of Purchaser Or Owned
2. Location of Installation .,rh Per*. ry, Qlo io. ..

(Nam -ncl Addrcz-) 4..- . C-471-:-/.125,0.(, 4 . . .7 1978 (CRNi (Orawing No.1 (N.Cl. Brd. Na.) (year Bsuik S. Valve ..... 4T1

  • Identifying Nos. 1M 0.2-... -

(Model No, Series'No.) (Manufactufer" Seeal No.) T saf y.Irel.ief .-- ...-...... Salfey. Safety Fletict; Pilot-; Po "erA.Iuated Orifice Size e2 . Nominal Inlet Size ._ . . . Outlet SiZe . li_

     -. Set Pressure IPSIG)              _...4          5 ....           ....           .........              Rated Temperature                                                                   .....       "F Stamped Capacity .. _--'-9057312 S~t. Steam lbsrhr         @      -. _CL ..             %   CX'erpressure Blowdown                  (PSIG)'        -  9,(,     3   ...  .

Hydrostatic Test (PSIG) Inlet ._2.3......0.---.. . Outlet...f ym onl..

                                                                                                                                              .       ieabta to vas       for ckx"4 -ytor             oýVyj
7. Pressure Retalning Pieces Serial No. or Material Specification Identification kncL Type or Grade Body . etA- 8. 2- ..... ...... ..... -. SA 357ilL~

Bonnet or Yoke - .0L --..- - -.4 ..... Support Rods .... .. .... Nozzle --- A U -.... . .. --S-k=35aLE.__....... Disc..- -5 . -- __. . . . . SA 951 M~FA Spring Washers .2.1./165.3_ s n_ 17. ..49 Cr HoIV 67 Adjusting Screw AV.-iF.04SAELF flab SAL&E1... 18 F.. Spindle ..AE*: G22.. Spring ... &JZ, .A.JIL, AKA ALj, ALR, Bolting . --A.J AMR,- .AJIH, AlL Li"e Oh

        .Liner
               - .          ..       ..     -  .S.&.......&.a.."58;. I Gover                ...                  &1.& .s/a              5                                                         -SAi3             L~                      :.           .-

Venr pipe ....... AFV 0U0 FLanges- -- --AFV.-.-U5fr./AFV 093 tlax. outsid.e diam. valve body: 475 tmu (16~.70 inch) Flax. ourside length valve %164 m (64.72 inch) R E CE IV ED JAN 11 1979 PNPP-SO/DC Supplemental sheets in form of lists, sketches or drawings may be used provided (1I size is 8-11V' x 11-, (2) information ir items 1-2 on this data report is included on each sheet, and (3) each sheet is numbered and number of sheets is .i re*urded at top of this form. (1/751 This form (EO00421 may be oblainetd (tom the Order Dept..ASME 345 E. 47 St.. New York. N.Y. 100 7 106

FORM NV-I (Back) Ill" 7 ' CERTIFICATE OF COMPUANCE . We certify that the statements made in this report are correct and that this valve conforms to the rules of construction of the ASME Code for Nucle-ar Power Plant Components. Section lit. Div. I..1974 . Editiot. Addenda su-nt 7b Code Case No. .....

   )ate      lU-1I-76            Signed       G. Dikkers & C.                . V.       by     W-14. W1I Lerns Our ASME Certificate of* Authorization No.(~~ManutSacrurerl             \.                  I\806          . to    use the             NV (NVJ tlasr July,-

ayrnboeepir , Datel CERTIFICATION OF DESIGN Des ignin orm tion on ile at .... . Gee ra_ l _lect2 =*r c and P rr*y ... . _..~.-. - -.. . . .. . GeertElera General

                                                                       ~ctric Electric and   Perry and. Prr-Stre=s analysis report     (Class 1 only) on file at..

Des;igns pecifations certified by' Boyd P. Brooks PE State . foro1655 R.i __a_.____ Stress report certfied by' Robert L. Weiss PE State_. C.liori s .. Reg. No ......... 114921/62-25749

.t Signature not requied-4ist name only.

CERTIFICATE OF SHOP INSPECTION 1,ffe undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of. .. J11iQ .. .. and employed by r.Zp._ -. ..-nT of - .L.ouroL&._A L. ... . have inspected the pump, or valve, described in this Data Report on

 .,-..~-J1 I                  ., 1.&.     , and state that to the best of my knowledge and belief, the Manufacturer has con-gtructed this pump, or valve, in accordance'with the ASME C*de for Nuclear Power Plant Componen.ts By sýgning this certificate, neither the Inspector nor his employer makes any warrant, expressed or implied., concemrring
 .be equipment described in this Data Repo&r          ."Jthermore, neither the Inspector nor his employer shall be liable in any

.I manner for any personal injury or property damnTage or a loss of any kind arising from or connected with this inspection-Date U-I Signed .. _-( '1...- Commissions ... . .... MB...il 445 .b. ............ llaseoNrt'L Std, State Prov. and NO-)

REPORT NO. P0059-012

                                                                                                     //32/         -

NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As required by the Provisions of the ASIME Code Section X] PNPP No. 9303 Rev. 9/11/00 NQF-1741

1. Owner- FIRSTENERGY CORP. Date 5-19-9 10 Center Road. Perry, Ohio 44081 Sheet 1 of 2
2. Plant Peru Nuclear Power Plant (PNPP) Unit 1 10 Center Roadn Perry Ohio 44081 200174650 (RepairOrg. P.O. No., et6.)
3. Work Performed By: FIRSTENERGY Nuclear Ooeratinq Comoany PNPP Type Code Symbol Stamp NR 10 Center Road, Perry. Ohio 44081 Authorization No. 33 Expiration Date 09/2812011
4. Identification of System: NUCLEAR BOILER PROCESS 1B21
15. (a) Applicable Construction Code: ASME Section III Class 1 1974 Edition NAME/SECTION/DIVISIO N/C LASS WINTER 19 75 Addenda Code Case(s) 272, 1644-4. 1728 (b) Construction Code used for repairs, modifications, or replacements: 1974 W 1975" none Edition Addenda Code Case(s)

(c) ASME Code Section XI applicable for Inservice Inspection: 1989 none none Edition Addenda Code Case(s) (d) Applicable Edition of Section Xl Utilized for Repairs, Modification, or Replacements: 1969 _ 19 none Addenda none Code Case(s) (e) Design Responsibilities FIRSTENERGY CORP.

6. Identification of Components Repaired, Modified, or Replacement Components Name of Name of Manufacturer Nat. Other Year Repair, ASME Component Manufacturer Serial No. Board ID. Built Replacement, Code No. or Modification Stamped PIPING GENERAL B121 T 64084 1B21F51A 1985 Replacement YES SYSTEM-. ELECTRIC _

Description of Work: REPLACED VALVE S/N 160878 WITH VALVE S/N 160853. SEE REMARKS.

8. Test Conducted: Hydrostatic- i] Pneumatic- [I Nominal Operating Pressure- Z Other- nl Pressure 1028 psi Test'Temperature 125 degrees F Code Case(s) N/A 107

NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back) PNPP No.'9308 Rev. 9/11/00 NQI-1741

9. Remarks: INSTALLED 12 STUDS 1-508"-8 HT# K745. 12 HYDRA NUTS 1-5/8"-8 HT# 590A.

1 STUDS 1"-8 HTt 2C05 AND 1 HYDRA N1UTS 1-8 HT* 591 A NO NAMEPLATE/STAMPING PERFORMED DUE TO THE INTERFACE CONTROLS OF PART 3 SECTION 1.8.6 BEING IN EFFECT AND JURISDICTIONAL AUTHORITY CONCURRENCE HAVING BEEN RECEIVED. Note: Attach all applicable Manufacturer's Data Reports. Supplemental sheets such as lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 of this

       - report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded on the front of this form.

CERTIFICATE OF COMPLIANCE I, Michael J Teosick certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and to the National Board Inspection Code "NR' rules. National Board Certificate of Authorization No. 33 to use the "NR stamp expires 28 Sept. 20 11 Date 19 MY, 20 09 Signed FENOC-PNPP - "<' / OC Tech. (name of repairorganization) (authorized representative) (tile) CERTIFICATE OF INSPECTION/INSERVICE INSPECTION I, Thomas G. Laps holding a valid commission issued by The National -Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HSB CT. of Hartford, Conn. have inspected the repair, modification or replacement described in this report on [ 20 L and. state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from or connected with this inspection. oate~e 20 ( Signed _ITi" Caj ,o Commissions NB 9330 'N"'I" "A"Ohio Comm. OLý.A (inspector U_ (National Board (include endorsements), andjurisdiction, and no.)

FREPORT N17. P0059-012 FORM NV-1 MANUFACTURERS' DATA REPORT FOR SAFETY AND"SAFETY RELIEF VALVES* (As Required.by the Provisions of the ASME Code, Section III, Div. 1) Mas..ta,,,Lord by C. Dk.k.ers & Co. N.V. __eqgel (.) The .ie-berl.iads IName and Address of Manufacturer) J. Maul*uctud lot .G une ra I lectric San Jose Calif. INaine and Address of Purchai*r r OwnejI Lucaltun of Installaton tiorNQh rerry, Q io.'er.._._ (Name and Addrecs) 4.

                                                  - - --G"471-.J,125.04,Q.4            ...

ICRN) IDra; sing Ned (Nat'l. Brd. No.) (Year Built) 5 Valve . U471 .... Jdentifying N ls.-.0. .-------. (Model No.. Series No.) fMsnuacturera';'Serial No.) Type .. Fafe:t yy/rv I i*I*f-Safety. Safety Relief; Pildt; Power Actuaied .. . Orifice Size ... inch 4. 84"V Nominal Inlet Size .. ---. inch .......

                                                                                                                                     .-         . Qutlet Size                       L_._
                                                                                                                                                                                      ' inch-         __
7. Set Pressure (PSIG) i1 dQ . Rated Temperature .. .... --

Stanmped Capacity

                          *ShsL 9123 Steam 5'           IbsJh2 W           ý_               % Overpreseura Blowdown (PSIG) ...-                             1     l.--5---

7. Hydrostatic Test (PSIG) Inlet .- -2a-5. .. Ou.t........ O t. -Abl e _e r o Pressure Retaining Pieces Serial No. or Material Specification Identification . {i-ln Type or Grade Body * - .1 0 .4 2_ .a / . 2".......- .. .. Bonnet or Yoke Support Rods Nozzle -SA -J35-L-l-- - A- ---- AEU 025 Disc - 55.52.7 a/n.IA-...... .. . . - Spring Washers 21.1b53.s/n 14 . . 4.5 C-r--Mo..V .67 Adjusting Screw -AFU 054 + 003 Spindle A.&W 0 17 A- 54-74 c-ype-6.3G coed;. R41100 Spring Bolting AUP, AJR, AKA, AJJ, ALR, AUY, SA 193ýB7.fLSA -194-7/SA.ki.94-2i AHR, AJH, .AJ.L........... ... Li e r-

                                          -"     *-5-.13.8        s/a      2              .                                           -S-A -351    Ci--3A--

Cover 62.04.8 s/nli " .. . -BA- 4- GP8M- -. -... VenIt pipe AFW 016 .. ... . SA-- 10 .. . ... F LaLget ' AFV U070 + 0U3"- -7.....A-98-5"-- . ... Max. ourside diam. valve body: 47b nun (18.74 inch) Max. ourside Length valve 1642 itan(b4.65 inch) C5-'7 Supplemental sheets in form of lists, sketches or drawings may be used provided (1) size is 8-1(2' x 11', (2) information in items 1-2 on this data report is included on each sheet, and (3) each sheet is numbered'and number of sheets is recorded at top of this form. Itt761 This form (E00042).may be obtained from the Order Dept., ASME, 345 E. 47 St., New York, N.Y. 10017 108

FORM NV-i1 (Wck. ... CERTIFICATE OF COMPLIANCE We certify thai the stalements made in.this report are correct .and that this .valve conforms-to the rules of construction Of.the ASME Code for Nuclear Power Plant Componentp, Section ItI, Div. 1., .112 Editiqp, Addenda .. UM,1-

                                                                                                                  "etel                  (DOW Code Case No.

Date IU-11-76 Sind C D ikktrs & .~;L IMenufacturer \ - Our ASME Certificate of Authorization No........ ......--- " 1806 tO use the -{,L... toi use the-(NV) symboleaspires IS U CERTIFICATION *QF*PEFGN "" " Design information on file at General ElectrLc and Per. Stress analysis report fCless 1 only) on file at Generzal Elec.ric and Perr__. Design specifications certified by' Boyd P. BrQoks " ' - .. PE State .California - : - _ " No. 13655 Stress report certified by' ." Robert L. Weiss - PE State iNfornia/l tnois Rei.No. -, ____ - Signature not required-list name only. CERTIFICATE OF SHOP INSPECTION I. the undersigned, holding a valid commission issued by the National Board of Boiler atid Pressure Vessel Inspectors and the State or Province of Oh io . and employed by -. , e-.-..T-.1n of ýq-k.O Il. -... have inspected the pump, or valve, described in this Data Report on I -U- L. .9._Jd and ,tate that to the best of my knowledge end belief, the Manufacturer has con-structed this pump, or valve, in accordance with the ASME Code for Nuclear Power Plant Components. By signing this certificate, neither the Inspector nor his employer makes any warrant expressed or implied, concerning the equipmenl described in this Date Report Furthermore, neither the Inspector nor his employer shell 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 I i Signed .......... Commissions .. 44 Ilnepdeni Nett Sta~t tro' aund ml

R7ZORT NO. P0059-012

                                                                                                          /1            -z-1   7 NIS-2fNR-          OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As required by the Provisions of the ASME Code Section XI PNPP No. 930B Rev. 9/11/00                                                                                          NQI-1741
1. Owner: FIRnTENERCGY CORP Date 5-19-9 10 Center Road. Perry, Ohio 44081 Sheet 1 of 2
2. Plant: Perry Nuclear Power Plant (PNPP) Ur it 1 10 Center Road, Perry. Ohio 44081 20 0174645 (i &epairOrg. P.O. No., etc.)
3. Work Performed By: FIRSTENERGY Nuclear Operating Comoanv PNPP Type Code Symbol Stamp NR 10 Center Road, Perry. Ohio 44081 Authorization No. 33 Ex 'piration Date 09/28/2011
4. Identification of System: NUCLEAR BOILER PROCESS 1B21
5. (a) Applicable Construction Code: ASME Section III Class 1 1974 Edition NAME/SECTION/DIVISION/CLASS WINTER 19 75 Addenda Code Case(s) 272. 1644-4, 1728 (b) Construction Code used for repairs, modifications, or replacements: 1974 W 1975 - none Edition Addenda Code Case(s)

(c) ASME Code Section XI applicable for Inseryice Inspection: 1989 none none Edition Addenda Code Case(s) (d) Applicable Edition of Section X1 Utilized for Repairs, Modification, or Replacements: 1989 19 none Addenda none Code Case(s) (e) Design Responsibilities FIRSTENERGY CORP.

6. Identification of Components Repaired, Modified, or Replacement Components
6. Other Year Repair, ASME Name of Name of Manufacturer Nat.

Component Manufacturer Serial No. Board ID. Built Replacement, Code No. orModification Stamped PIPING GENERAL 1B21 64084 1B21F41A 1985 Replacement YES SYSTEM ELECTRIC 7 Description of Work: REPLACED VALVE S/N 160900 WITH VALVE S/N 160884. SEE REMARKS.

8. Test Conducted: Hydrostatic- E Pneumatic. El Nominal Operating Pressuur&- Z Other- EI Pressure 1028 psi Test Temperature 125 degrees F Code Case(s) N/A 109

NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back) PNPP No. 9308 Rev. 9/11/00 NQI-1741

9. Remarks: INSTALLED 12 STUDS 1-5/8"-8 HT# 0G84. 12 HYDRA NUTS 1-5/8"-8 HT# 590A, 16 STUDS 1"-8 HT# 2C05.AND 16 HYDRA NUTS 1"-8 HT# 591A.

NO NAMEPLATE/STAMPING PERFORMED DUE TO THE INTERFACE CONTROLS OF PART 3 SECTION 1.8.6 BEING IN EFFECT AND JURISDICTIONAL AUTHORITY CONCURRENCE HAVING BEEN RECEIVED. Note: Attach all applicable Manufacturer's Data Reports. Supplemental sheets such as lists, sketches, or drawings maybe used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded on the front of this form. CERTIFICATE OF COMPLIANCE I, Michael J TeDsick , certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and to the National Board Inspection Code "NR" rules. National Board Certificate of Authorization No. 33 to use the 'NR stamp expires 28 Seot. . 20 11 Date 19 MAY 20 09 Signed FENOC-PNPP OC Tech. Q (name of repairorganization) (authorizedrepresentative) (title) CERTIFICATE OF INSPECTION/INSERVICE INSPECTION I, Thomas G. Laos holding a valid commission issued by The National Board ofBoiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HSB CT. of Hartford Conn. have inspected the repair; modification or replacement described in this report on l 20 O3 and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code."NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the work described .in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damageqr loss of any kind arising from o&connected with this inspection. I " inspack-*I (National Board (include endorsements), andjurisdiction, and no.)

REPORT NO. P0059-012 113 11 i7-571,rl" _ o7Z 2 Ui` U I

1. A %Corrected report F0R RV-1 W~CERTI~tC.TE HOLUUM' DATA RiEPOUr POM SAFETY AUD aAFETY RELIEF VALVES- R 1~ AD R~jukud by 1tho Prov~tinlo G. Dikkiirs A Co. NV.

of ttin ASMqE Code $action IQ, Div.- I IHenpeo (0) The Netherlands.... 2.mh~fhý o, GndYýEVCLt__us rt1'ifornia I aLe. t.6 r for -w r _; ___~ý- em 4.- G 471-6A1..2. e NL~ F G471 11OB~ t~' ____ - ____ __ 8" (Flanges) ~ _ 10' S&inpd C~tW1 eIih? o*%pmmwjro Bk~ldoP_ým a'`ý rez (P=1) ft4___n-- _____ FL A% niiow Pao. Or Id~k~ah bxI TYPS or136 SA 352, LCB SA 350L F2 kj -- .- .-.

                                                                                                                                                                      -3t 2*      Dim: r                         55.D8.9B5r W

F AdMak coutid dAre. viveAody "77nxn(JB7 5r *351 SA i5 TBKA

                                                                                                                  ~        -      -         .

zj VA outside length valvyý -14 n~. (64. 73) .Ij.

~1 L   *SaPPklinW          MOM          IO~-f ipt; (Off      ligaL Bkof CMe or dravirflp may be used provided (1) OL-a in X.Ia- - W1. (2) informotion In ft~ns 1-2 on~ &AsData Rep~ort Is incitLod an sen                     sh oot, and (3) *Dz shoot is rwimbiard &nd fltmbor of 5hoats is recorded eit too of chit form.

V F 110/7"11 Tks k1~

                                              -in    EMAxZIi nzy be vw.,nofl' ljoin trt Omwai,      0.0.. ASME. 346 E, 47th, St.. No,,, York. N.Y. 10017

[. 110

g7 159 Z2 FORiM HY-1 Ibsaý CERTIFIATE OF COMPIJANCE We conity, that tthe stetmenriint made ,inthi -p, -,& cOrrarX and that t.his vbtl' confo~rms to the ml.as of ~hoif ofthe ASME Cod lo ula Co 1in Comp~onent%. Sbac~on fit, Nu. 1.. 1974 Edition.Addondassm.7 IL Dm &J- 7-05 Sgo G ikkers Co NV y Our A-SME Csrilfcsia of Aulholi.ution ~ ________- 1806 KV Ist. July 1980, CERTH)CATION OF DESfON 0*"nm~wrnstn onfitf DGeneral Electric 4.rd Perry 1-t-1 spares analyass report fCtaua on~y y ýj w General El ectric 4r Perry 1+1 1 seares F

    *Svpnotwrs not re,.,,,rd-4.xt name Only.:

CERXMCATE OF SHOP' IUfS1ECT~oF4 I. rnaragneI.hodldng he 0 .rAlid cornimmejiov ulixed tbythe National btoard of Boiler and Prevaurts Vona) Inspclors ond ~ sZ,,o ~ .t ,.-- 1h and vmsloyad by R~oyal Indeffuity of -- - 2 _ . 7 1~ i d th . pFurp. 0 , valvre.

                                                           . h av e. insen to                                O o r b d Int this Da ta FRepo rt o n
         *-26         Sap.Lepaberj,3id                         State Ehxt to the beet Of my knowlA~dg and belIiaf. the ki Certificate Holder has (Onstitrcld       this punmp. or waive. inaccordance with,the ASME Code for Heicltee Po-oreIlintComponents.

By signing tisb cartsfhcalt neithar the Ir;,,Pecior nor his emPlioyer makes any waesrani cirpreeza&d or impired. cotncernng

             ~

F ol .R10 t~aln?t, rde..odI a~kpgtze, ttnnOam.RýPon Fi.irthermotis, naujittet he tInspector no, hit employer ishall be he.loi in anty ry trip, rry dangor a losc of any kind ane.ng from or cornnected vaththe hitnati-1,on WitO.. r* t-en t4.. seeN.,. n-~ F f. r-.

REPORT NO. PC005-)-0"12 NIS-2JNR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As required by the Provisions of the ASME Code Section XI PNP:P No. 9308 Ray. 9/11/00 NQI-17t1

1. Owner: FIRSTENERGY CORP. Date 5-19-9 10 Center Road. Perrv. Ohio 44081 Sheet 1 of 2
2. Plant Perry Nuclear Power Plant (PNPP) Unit 1 10 Center Road. Perry, Ohio 44081 200174649

(/Repair Org. P.O. No., etc.)

3. Work Performed By: FIRSTENERGY Nuclear Operatino Companv PNPP Type Code Symbol Stamp NR 10 Center Road. Perry. Ohio 44081 Authorization No. 33 Expiration Date 09/28/2011
4. Identification of System: NUCLEAR BOILER PROCESS 1B21
5. (a) Applicable Construction Code: ASME Section III Class 1 1974 Edition NAME/SECTION/DIVISION/CLASS WINTER 19 75 Addenda Code Case(s) 272, 1644-4, 1728 (b) Construction Code used for repairs, modifications, or replacements: 1974 W 1975 none Edition Addenda Code Case(s)

(c) ASME Code Section Xl applicable for Inservice Inspection: 1989 none none Edition Addenda Code Case(s) (d) Applicable Edition of Section X1 Utilized for Repairs, Modification, or Replacements: 19 89 19 none Addenda none Code Case(s) (e) Design Responsibilities FIRSTENERGY CORP.

6. Identification of Components Repaired, Modified, or Replacement Components Name of. Name of Manufacturer Nat. Other Year Repair, - ASME Component Manufacturer Serial No. Board ID. Built Replacement, Code No. *Ior Modification Stamped PIPING GENERAL IB21 64084 1821F47G 1985 Replacement I YES SYSTEM ELECTRIC _

7 Description of Work: REPLACED VALVE S/N 160872 WITH VALVE SIN 160893. SEE REMARKS.

8. Test Conducted: Hydrostatic- [ Pneumatic- 0 Nominal Operating Pressure- JZ Other- D]

Pressure 1028 psi Test Temperature 125 degrees F Code Case(s) N/A ill

NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back) PNPP No. 9308 Rev. 9/11/00 NQ-1741

9. Remarks: INSTALLED 12 STUDS 1-5/8"-8 HT# K745. 12 HYDRA NUTS 1-5/8"-8 HT# 590A.

16 STUDS 1"-8 HT# 2C05.AND 16 HYDRA NUTS 1-8 HT# 591A. NO NAMEPLATE/STAMPING PERFORMED DUE TO THE INTERFACE CONTROLS OF PART 3 SECTION 1.8.6 BEING IN EFFECT AND JURISDICTIONAL AUTHORITY CONCURRENCE HAVING BEEN RECEIVED. Note: Attach all applicable Manufacturer's Data Reports. Supplemental sheets such as lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded on the front of this form. CERTIFICATE OF COMPLIANCE I, Michael J Teosick , certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section Xl of the ASME Code'and to the National Board Inspection Code "NR' rules. National Board Certificate of Authorization No. 33 to use the 'NR stami expires 28 Sebt. 20 11 Date MAY 20 09 Signed FENOC-PNPP . -- ' DC Tech. (name of repair organization) (authnrizedrepresentative) (tbte) CERTIFICATE OF INSPECTION/INSERVICE INSPECTION I, Thomas G. Laos holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HSB CT. of Hartford. Conn. have inspected the repair, modification or replacement described in this report on MP2. 20 9 and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code "NR' rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage r loss of any kind arising from or connected with this inspection. Date , 20 Q'5 Signed = . Commissions NB 9330 "N" "I""A" Ohio Comm.

                                                   ..nspecr*or l                               (National Board finctude endorsements),

and jurisdiction, and no.)

REPORT NO. P0059-012 NV-1 N CERTIFiCATE HOLDERS' DATA REPORT FOR SAFETY AND SAFETY REUEF VALVES-iA

                                  .AsRequired by the Provisions of the ASME Code, Section fit, Div. I                                                                               n-L        QC--H
 '. l'.enufciured by              G. 121
                                           )kl*esrs                , Co             ,.          U n .,                                      ,-

(HNTe and Addrc= oa U Ccrtlr etc -oldcr)

2. Monufacturedf.ar General Electric San _Ju.s!t Qil]ifocrL _
  • meandAdree of Pur&-or or Orwn*DI
2. Lo-ation of ktaitatlion Perry I + j spares North Perry 01hio lNrn and Addreoe
  .         N            "     **c474-6/1l5.0i.03                                     ruv.      6     __l                     t                                            - 1979 NIN)                                        (Dra*ti              No.)                                 (NH 'L Brd. No-i                        .             (Year B6ill)
5. '~e-~iC 71 Identifying Nos. *3 (Modal go.; Series No.). . CMCrtlflate Holder's Serial No.)

I yp e S_ ~ ,*- eI ~. [ Safety. Saey eieflt4 U P0w- Actuated Oric s 4,84 Nominal Inlet Size 8"(PL.;inl;,s) Outlet Siz (I. C. S-t Pre--zure (PSIG) 90 Rated"Temper.tur . 585 -F

     £'~m(ped C*           ty"      973                               bstr                    .3              % Overpressure Slowdown (P.[G) 42.35 Hyd-4_etecTTtg(pS4G)Inlth             2350                                                                      Outlet                                                     97                          -

7, Prwr Reta*ining FMC" ............................. . ...................................... "' (Appticsbt yalves fdir cto-sed zyvatem Onsy

                                                            .Serial                                        .                                  :           '..:'Matorial Specifia ion               '     .

identtfication . . , . . .. . lnc. Type or Grade. Body05,l19.8Y ý.1n 5 SA r-)7 Ir:M . aortor yoke I~~8sr SA 352 ICBt Support Rods No~aAJW~ 113 SA- 350 LF2 _ 60.07.9 S/n .2B SA 351 CIF3A ng Wahers 2'6.30.95 s/n 153 45. Cr"*o l; 67 Ae4,Ueig Screw AS8 08I/ASE8 009. SA 182 F31`6 A 50.4.-74 t'ype.630..cbnd. E11100 sprdaCtl) 010. Bo ~AwIY/ANZ/AVS/ALISIA.PA/ýAI'B/AM1Z SA 193-B7/SA'194-7/SA 194-211 other Pieces____ Liner 63.(14,09 s/n I SA\ 351 CF3A: Cover . 53.198j s/n I SA 351 CF-,."i SA 1105 I SA 105 1.1 nn-es ASA-~ 124IASIA 213 SA I C,5 la.OLMSidc dias;. valve body: 4 78 tc~.2

.4a%. outstider length valve 164B' nfsi8~

' Supplemental sheets in fortn of lists, sketches or drawings may be used provided (1) size is 6-112- x 11"' (2) info nation In items 1-2 onthis Deta Report is included on each sheet, and (3) each sheet is numbered and number of skeets is iecorded.at top of this form. (10r77) This form (E00042l may be obtained from the Order Dept., ASME. 345 E. 47th St., New, York, N.Y. 1001"7 112

N! FORM NV-1 (Back) (~ L l " . ~~CERTIFIC.ATE "OF COMPLIANCE""- We certify that the statements made in this report are correct and that this valve conforms to the rules of construction of the ASME Code for Nuclear Power Plant Components, Section Ill, Div. 1.. 1974 Edition, Addenda ttfLi, ' 76 Cokde Case No. NILA .. .. . owae) Date ( .Signed ikers & Co, N-V. by h ' "

                                                    "(         -erliric te Holder)                          'I {,

Our ASME Certificate Of Authorization No. ""to se the synmbol expires lsE July*.1 980 -... CERTIFICATION OF- DESIGN D*e*gn i.nforniation on flip at General'Electric and Petý-rv I + TT suares Stress analysis report (Class. 1 bnlyl on fle.at Ceneral t1ec'tric and Perr' I + IT srares. "Oeal.gn specificcation,4 certified by' B'oyd P. " " " " " P'EStatc Califo-ia" Reg. No 13655" Stress report certified by' Fobert 1U. Weiss. PE State CaliEornia/Illinbis" Reg. No. MI 4921,/62 :-25749

'Signature not required-list name only.
                                                    .CERTIFICATE           OF SH.OP INSPE.CTIO"N                    ...      ..        ..

L the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors ond the State or Province of Ontario (Canada), and employed by R3 al:l-demn nrv'Co. f f New York *. - have inspected the pui-np, .or valve, described* in

  • this. Data Report on of [__7______.... 19 I---.*'L"arid state that to the best of my knowledge and belief, the N C.rtdficate Holder has constructed this pump, or valve, in accordanc~e.wkth the ASME Code for'Nuclear Power Plant*Components.

By signing this certificate, neither the Inspector nor his employer makes any warranL expressed or implied, concerning . the equipment described this Data Report- Furthermore, neither the' Inspector nor. his emplc.yer shall be liable in any rnanner.lor a rsoal i jur, or 0roperty damage or a loss of any kind arising from or connected with this inspection. Date 1 Signed Comissions -N.B. 6653-fir r. 6

  • I,.

REPORT NO. P0059-012 NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS PNPP No. 9308 Rev, 9/111/Do As required by the Provisions of the ASME Code Section XI NOI-1741 1.. Owner: FIRSTENERGY CORP. Date 5-19-9 10 Center Road. Perry. Ohio 44081 Sheet 1 of 2

2. Plant: Perry Nuclear Power Plant (PNPP) Unit 1 10 Center Road. Perry. Ohio 44081 200174651 (Repair Org P.O. No., nei.)
3. Work Performed By: FIRSTENERGY Nuclear Operating Comoany PNPP Type Code Symbol Stamp NR 10 Center Road. Perry. Ohio 44081 Authorization No. 33 Expiration Date 09/28/2011
4. Identification of System: NUCLEAR BOILER PROCESS 1B21
5. (a) Applicable Construction Code: ASME Section III Class 1 1974 Edition NAME/SECTION/DiVISION/CLASS A/INTER 19 75 Addenda Code Case(s) 272. 1644-4, 1728 (b) Construction Code used for repairs, modifications, or replacements: 1974 W 1975 none Edition Addenda Code Case(s)

(c) ASME Code Section XI applicable for Inservice Inspection: 1989 none none Edition Addenda Code Case(s) (d) Applicable Edition of Section XI Utilized for Repairs, Modification, or Replacements: 1989__ 19 none ' Addenda none Code Case(s) (e) Design Responsibilities FIRSTENERGY CORP.

6. Identification of Components Repaired, Modified, or Replacement'Components.

Name of Name of Manufacturer Nat. Other Year Repair, ASME Component Manufacturer Serial No. Board ID. Built Replacement, Code No. or Modification Stamped PIPING GENERAL 1B21 64084 1B21F51C 1985 Replacement YES SYSTEM ELECTRIC

7. Description of Work: REPLACED VALVE S/N 160880 WITH VALVE S/N 160861.

SEE REMARKS.

8. Test Conducted: Hydrostatic- [I Pneumatic- E Nominal Operating Pressure- [ Other- ]

Pressure 1028 psi Test Temperature 125 degrees F Code Case(s) N/A 113

NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back) PNPP No. 9308 Rev. 9/11/D00 NQ1-1741

9. Remarks: INSTALLED 12 STUDS 1-5/8"-8 HT# K745. 12 HYDRA NUTS 1-5/8"-8 HT# 590A.

16 STUDS 1"-8 HT# 2C05.AND 16 HYDRA NUTS 1"-8 HT# 591A. NO NAMEPLATE/STAMPING PERFORMED DUE TO THE INTERFACE CONTROLS OF PART 3 SECTION 1.8.6 BEING IN EFFECT AND JURISDICTIONAL AUTHORITY CONCURRENCE HAVING BEEN RECEIVED. Note: Attach all applicable Manufacturer's Data Reports. Supplemental sheets such as lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded on the front of this form. CERTIFICATE OF COMPLIANCE I, Michael J Tepsick , certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and to the National Board Inspection Code "NR" rules. National Board Certificate of Authorization No. 33 to use the "NR stamp expires 28 Seot.* 20 11 Date 19 MAY., 20 09 Signed FENOC-PNPP .,'../ .?Z.._J DC Tech. (name of repairorganization) (authorizedrepresentative) (title) CERTIFICATE OF INSPECTION/INSERVICE INSPECTION I, Thomas G. Laps holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HSB CT. of Hartford, Conn. have inspected the repair, modification or replacement described in this report on 1*1. (. 20 Q9 and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code "NR' rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in

 .any manner for any personal injury, property damage or loss of any kind arising from or connected with this inspection..

Date J5ý(apz. 20 Q! Si g (P n ed-t Commissions NB 933b "'N""I""A"Ohio Comm. frispectorT*Q. (National Board (include endorsements), andjurisdiction,andno.)

REPOR.T NO. P0059-O122 FORM NV-1 MAANUFACTURERS' DATA REPORT FOR SAFETY AND SAFETY RELIEF VALVES' (As Requiredby tde Provisions of the ASME Code, Section III, Div. I)

1. Manul,,cti cl uty D ~kk.r.-I,1. Ch,:

CJ). l.V. , , (u) T ith,.h:rLands"

                                                                        +.1            _C
2. Mar it.wiwi i*"

4 ...-... ,. .... -- - h,,°,- D~imwini N. Nu fN-E'L fA (Y-ar Built! IdsNo3 Ninu i.Nres. b.de) No.. S'e. NojI(~ lI(.rr.+S t~ No.) jMod'-f No., S.,,es 1 I-l Nominal Inlet Size 81, Outlet Si-ze j0' Orifice Size .84"l-' inch inch G. Set Pressure IPSIGI -AA... ..Q.. Rated Temperature58 Stamped capacity _ hr lb-W @

                                                                              @     .Q..          Overpressure Blowdown iPSIGI                -)  -6 SX Ste 8 ni Outlet Hydrosstatic Test i(SIG) Inlet                2350                                                     lApplicbie to vaIvCX tor etome2?'....I       ty(
7. Pressure Retaining Pieces Serial No. or Material Specification Identification IncL Type or Grade Body SA 352 -,OB Bonnet or Yoke SA 352 LOB Nozzle SA 350 LF2 Disc SA 351 CF3A Spring Washeis xyfr 45 "Cr Ho V 67 Adlustn'g Screw cJi6 SA 182 P316 Spindle A 564-74 type 630 cond. H11'00 Bolting StA 193-B7-ISA 194-7/SA 194-2H O~thtr Pieems I.in, r SA 351 CF3A o v '... 3 SA 351 CF8M SA 105 V,.n:kii -P 2q-V C>i2 C SA 105 t CA RECEIVED JAN li. 1979 PNPP-SOIDC is B-112' ', 11' (2) information Supplinimital sheets in form of lists, sketches or drawings may be used provided (I) size and number of sheets is in items 1-2 un tIns data report is included on each sheet, and (3) each sheet is numbered reiirded al top of this form.

N.Y. 10017 1/'1t "This formn IE000421 tinji I,), ntittzIijimi hjoii, the Order Dept., ASME, 345 E. 4? St., New York, 114

FORM NV-1 (Back) ' CERTIFICATE OF COMPLIANCE We c:ertlfy Ihul ll' staleflneC ritmade itlhis report ,ate cotect *-d thai cilis v*live con formis to thc rules of curem;tructiun of lth ASME C.txeli NulCued Po,,er Plsdrn Conipcpor! u. Sur,,lln It(.Div. 1.. I Y4 Editiconr. Addenda Sinn. a 76. Coe ,: ,,,*c No* l~c7

                      .>k<:-  ......                                                      v             + -         "* .', <- *"*:./
   ')ate         lI     t7          Signecd         C;. likkcrs        1, Cui.       ,'V.            by     I)                              lal Our ASME           Cunilicata o( Authorization             No.                                           1806              to use     (ie    N1V INvt t&yrnbolexpires            1st JuLy,             [L98(

IO~iel CERTIFICATION OF DESIGN Design informaicon on file at GCtttteral EI ectric antI Sress analy-sis report (Class I only) on file al CL.al .cc'*1C- a d. . Design specificartons certified by' Boyd P. Brooks PE State C:iJ ifor -ia Reg. No. 13655. Stress report certirted by' lkobc-r L. Wej[ss' PE State Ca Lifornia/I I inuins Reg. No. M11492-1162-25-749

'   Signature not requited-list name only.

CERTIFICATE OF SHOP INSPECTION 1, the undersigned, holding a valid commission issued by the National Board of Boiler ahd Pressure Vessel Inspectors 9 aid 1:16 State or Pr vrnce of $C2 Vl fo and employed by bkJ2ipxf 'ij of ()_)U . It

                                             'it            have    inspected the pump or valve, described in this Data Report on N~ .~ .19Cp. and state that to the best of umy knowledge and belief, the Manufacturer has con-
  .tructed t~hs pump, or rvalve, in eccordance with the ASME Code for Nuclear Power Plant Components.

b'y signing rhis certificate, neither the inspector nor his employer makes any warrant, expressed or implied, concerning

   -ceequipment described in.this Data Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or prooersy d-rhge or a loss ofany kind arising from or connected with this inspection.

Date 79tL)O . ,S . Signerd Commissions '-* L- *_f/* itnapectocl~INBC-L tea, StatSPea~~~

REPORT NO. P0059-012 NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS PN?? No. 9308 Rev. 9/S 1/00 As required by the Provisions of the ASME Code Section XI NQ1-1741

1. Owner: FIRSTENERGY CORP. Date 5-19-9 10 Center Road Perry, Ohio 44081 Sheet 1 of 2
2. Plant: Perru Nuclear Power Plant (PNPP) Unit 1 10 Center Road Perry Ohio 44081 200174652 *

(RepairOrg. P.O. No., etc.)

3. Work Performed By: FIRSTENERGY Nuclear ODeratino Company PNPP Type Code Symbol Stamp _RR 10 Center Road, Perry, Ohio 44081 Authorization No. 33 Expiration Date 09/28/2011
4. Identification of System: NUCLEAR BOILER PROCESS 1B21
5. (a) Applicable Construction Code: ASME Section III Class 1 1974 Edition NAMEISECTIOIoDViSION/CLASS WINTER 19 75 Addenda Code Case(s) 272, 1644-4, 1728 (b) Construction Code. used for repairs, modifications, or replacements: 1974 W 1975 none Edition Addenda Code Case(s)

(c) ASME Code Section XI applicable for Inservice Inspection: 1989 none none Edition Addenda Code Case(s) (d) Applicable Edition of Section Xl Utilized for Repairs, Modification, or Replacements: 19 89__ 19 none Addenda none Code Case(s) (e) Design Responsibilities FIRSTENERGY CORP.

6. Identification of Components Repaired, Modified, or Replacement Components Name of Name of Manufacturer Nat. Other Year Repair, ASME Component Manufacturer Serial No. Board ID. Built Replacement, Code No. or Modification Stamped PIPING GENERAL 1121 64084 1B21F51G 1985 Replacement YES SYSTEM ELECTRIC
7. Description of Work: REPLACED VALVE S/N.160899 WITH VALVE SIN 160876.

SEE REMARKS.

8. Test Conducted: Hydrostatic- E] Pneumatic- [] Nominal Operating Pressure- 0 Other- --

Pressure 1028 psi . Test Temperature 125 degrees F Code Case(s) N/A 115

NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back) PNPP No. 9308 Rev. 9/11/00 N01-1741

9. Remarks: INSTALLED 12 STUDS 1-5/8"-8 HT# K745. 12 HYDRA NUTS 1-5/8"-8 HT# 590A, 16 STUDS 1"-8 HT# 2C05.AND 16 HYDRA NUTS 1"-8 HT# 591A.

NO NAMEPLATE/STAMPING PERFORMED DUE TO THE INTERFACE CONTROLS OF PART 3 SECTION 1.8.6 BEING IN EFFECT AND JURISDICTIONAL AUTHORITY CONCURRENCE HAVING BEEN RECEIVED. Note: Attach all applicable Manufacturer's Data Reports. Supplemental sheets such as lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in iteins 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded on the front of this form. CERTIFICATE OF COMPLIANCE I, Michael J Tepsick certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and to the National Board Inspection Code "NR' rules. National Board Certificate of Authorization No. 33 to use the "NR stamp expires 28 Seot. 20 11 Date 19 MAY 20 09 Signed FENOC-PNPP OC Tech. (name of repairorganization) (authorizedrepresentative) (title) CERTIFICATE OF INSPECTION/INSERVICE INSPECTION 1, Thomas G. Laps holding a valid commission issued by Thp National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HSB CT. of Hartford, Conn. have inspected the repair, modification or replacement described in this report on M 20 C12A and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section Xl of the ASME Code and the National Board Inspection Code "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from or connected with this inspection. Date , 20 6 Signed 71 *1x .- Commissions NB 9330 "N" "I' "A" Ohio Comm. rinspecto (Nlational Board (include endorsements), andjurisdiction, andno.)

REPORT NO. P0059-012 J.t-4 NV-I N CERTIFICATE 113,2 HOLDERS' DATA REPORT FOR SAFETY AND SAFETY RELIEF VALVES,

                                                                                                                  -1/20                              T-2_o                2-As Required by the Provisions of the ASME Code, Section Ill, Div. I
  .Manuf.riured       by    .        G. Dikkers & Co.                     NV.      Hengelo (0)         The Netherlands l-*.                     f N cxrliflcoto        O.ý   ..'O   _,
2. Manulsctured for Ge ean " r... ( d Ad -.. ose, Ca iorna (M~mpra;p Adldress oVMuCha~ar or Owvned
3. Location of Inz-tallation Perry I 1 0r erry 1 0o n dress)

A. + G 471-5/125.03r.ee. 6_ 77 1979 ICR NI 7Dra-ing No.) INt'l. Brd. Niu2 87, (Year Cuiltl S. Valve .471.. Identifying Nos. ]b" Type Sa fety/R eI ii eff IModal NO.,So. ie, N .)

                                                                                        ...                     (N  Certifltcte       Holder'% Serial    No.)

Soflty Sa ',Relief: Pilot; Power Actuaed Orifice Size , -- Nominal Inlet Size ..-. Outlet Size -0" - inch inch inch

  . Set Presure PG                         1180                    .....                  Rated Temperature          - .        ....         R                       'F..

Stamped Capacity 917253 lbs/hr @ --. 3- ....  % Overpressure Blowdown (PSIG) 445 Sat. Steam Hydro*t*tic Tes;t (PSIGI Inlet ?3" )0 Outlet 975 jAppJicable 10 -Nlo-e or closed syotern, only)

7. Pressure Retaining Pitces Serial No. or Material Specification Identification incl. Type or Grade Body 15. 15. 8-2 Bonnet or Yoke 16.06.8-2 Support Rods Nozzle. AJW 031 SA 350 LF2 Disc 57.25.8 2B SA 351 CF3A Spring Washers 26-30.95-70 _ 45 Cr Mo0V 67 Adjus*ting Screw AFU 109 AME 007 SA- 182 F .316 Spindle AJE 044 A--I--- 4 type 630 cond. H1100 Spring Bolting . ANY/AYE/AVS/AJK/AWZ/AJJ
                                                                                                       .SA lq3-8R71Sa                "I94-_7Lý_&__            2*.
                                .AJS/APA/AJL                   "

55.31.8-I 1U I'1 CF3A. _* 5.8.04.8-6

    .-Y~ent-     Pipn             AKE 040'                                                          _. SA Ing AFV 127 AKF 045                                   ....

1U in5 Max. outside diam. 'valve body 478 mm. (18,82)" Max* outside length valve 1640 mm .(64,57)"

  • Supplemental sheets in form of lists, sketches or drawings may be used provided (1) size is 8-112- x 11". (2) information in items 1-2 on this Data Report is included on each sheet, and l31 each sheet is numbered and number of sheets is recorded at top of this form.

(10/77) This form (E00042) may be obtained from the Order Dept.. ASME. 345 E.47th St.. New York, N.Y. 10017 116

_7 FORM NV-1 (Back) CERTIFICATE OF COMPLIANCE We certify that the' statements ma de in th-is report are correct and that this valve conforms to the rules of construction of the ASME Code lot Nuclear Power Plant Components. Section Ill. Di": 1... 97' Edition. Addenda 5US1101

                                                                                                                                                        'l.7 (Date)

Code Case Noý. N A . Da te* cq- L -2cR Signed Q. D kkE~rS & Co NV by (N Certificate Hodert 1806 to use the. N NV Our ASME Certificate of Authorization No. INV, symbol expires Ist. July 1980 (DatIe CERTIFICATION OF DESIGN Design information on file at - .pnpre 1 Fl edtri r nr Rer-ry I

                   -I         ,r~~,.......r, ,....                   lt     n     r~

I",.. L l otr i Perrv II ttCres analysis repuort ii-ass uiyi on uon e at "~t 1 ' - - Design specification.s certified by' R.yd P. Brooks PE State- Cal iforri a Reg. No. 13555 . -

-.a.ress report certified by'                                        Robert L. Weiss PE Stata               California/Illingis                                               Reg. No.             M 14921/62-25749 Signatur6 not required-list name only.

CERTIFICATE OF SHOP INSPECTION I. the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectork (. and the State or Province oi Ohio-D PA and employed by K-mper Ins of LIng C io.'e ITI have inspected the pump, or valve, described in this Data Report' on 23 March. 19 *7,- and state that to the best of 'my knowledge and belief, the N Certificate Holder has constructed this pump, or valve, in accordanc&, with the ASME Code for Nuclear Power Plant Components. B, signing this certificate, neither the Inspector nor his employer makes any warrant, expressed or implied, concerning the equipment described in this Data- Report. Furhermore, 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 inspectiol¶. Date - Signed V -" ,...o. Commissions NB 4805'

                       -~o~-~ecta                                                                       INati. Bd.. State Pro..  .rid No.I

(,..

REPORT NO. P0059-012 NIS-2INR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As required by the Provisions of the ASME Code Section XI PNPP No. 9308 Rev. 9111100 N01-1741

1. Owner. FIRSTENERGY CORP. Date 5-19-9 10 Center Road, Perry, Ohio 44081 Sheet 1 of 2
2. Plant Perry Nuclear. Power Plant (PNPP) Unit 1 10 Center Road. Perry, Ohio 44081 200174648 (Repair Org. P.O. No., etc.)
3. Work Performed By. FIRSTENERGY Nuclear Doerating Company PNPP Type Code Symbol Stamp NR 10 Center Road. Perry. Ohio 4.4081 Authorization No. 33 Expiration Date 09/28/2011
4. Identification of System: NUCLEAR BOILER PROCESS 1B21
5. (a) Applicable Construction Code: ASME Section III Class 1 1974 Edition NAMEISECTION/DIVIS ION/CLASS WINTER 19 75 Addenda Code Case(s) 272. 1644-4. 1728 (b) Construction Code used for repairs, modifications, or replacements: 1974 W 1975 none Edition Addenda Code Case(s)

(c) ASME Code Section XI applicable for Inservice Inspection: 1989 none none Edition Addenda Code case(s) (d) Applicable Edition of Section XI Utilized for Repairs, Modification, or Replacements: 19 89__ 19 none Addenda none Code Case(s) (e) Design Responsibilities FIRSTENERGY CORP.

6. Identification of Components Repaired, Modified, or Reoilacement Components Name of Name of Manufacturer Nat Other Year Repair, ASME Component Manufacturer Serial No. Board ID. Built Replacement, Code No. or Moaification Stamped PIPING GENERAL 1B21 64084 1B21F47C 1985 Replacement YES SYSTEM ELECTRIC
7. Description of Work: REPLACED VALVE S/N 160895 WITH VALVE S/N 160854.

SEE REMARKS.

8. Test Conducted: Hydrostatic- Dl Pneumatic- L Nominal Operating Pressure- 0 Other- EI Pressure 1028 psi Test Temperature 125 degrees F Code Case(s) N/A 117

NIS-2INR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back) PNPP No. 9308 Rev. 9!11/00 NQI-1741

9. Remarks: INSTALLED 12 STUDS 1-5/8"-8 HT# K745, 12 HYDRA NUTS 1-5/8"-8 HT# 590A.

16 STUDS 1"-8 HT# 2C05.AND 16 HYDRA NUTS 1"-8 HT# 591A. NO NAMEPLATE/STAMPING PERFORMED DUE TO THE INTERFACE CONTROLS OF PART 3 SECTION 1 8.6 BEING IN EFFECT AND JURISDICTIONAL AUTHORITY CONCURRENCE HAVING BEEN RECEIVED. Note: Attach all applicable Manufacturer's Data Reports. Supplemental sheets such as lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded on the front of this form. CERTIFICATE OF COMPLIANCE I, Michael J Teosick certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and to the National Board Inspection Code "NR' rules. National Board Certificate of Authorization No. 33 to use the "NR stamp xpires 28 Seer. 20 11 Date 19 MAY 20 09 Signed FENOC-PNPP QC Tech. (name of repairorganization) (authiorized representative) (title) CERTIFICATE OF INSPECTION/INSERVICE INSPECTION I, Thomas G. Laps holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors and certificate (? competency issued by/the jurisdiction of OHIO and employed by HSB CT. of Hartford, Conn. have inspected the repair, modification or replacement described in this report on M 20 Oj and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code 'NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concern-ing the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from or connected with this inspection. Date L . 20 DO, Signed g n e d14- - Commissions NB 9330 "N' "I""A" Ohio Comm. (inspectol (*National Board (include endorsements), andjurisdiction,and no.)

REPORT NO. P0059-012 q12/. */-7 '-/2! -t 6

  • vP-FORM NV-1 MANUFACTURERS' DATA REPORT FOR SAFETY AND SAFETY REUEF VALVES' (As Required by the Provisions of the ASME Code. Section I11,Div. I)
1. Manufactured by G. Dikkers & Co. N.V. fiengelo (0) The Nerhe~rLeans (Nan-, and Xddress of iA=.ultaduerl
2. Manufactured for Perry I (Name and-Addre=s of urchasr o, Ownerl
3. Location of Installation .NQ.r"h Perry, Ohj.o (Nae and Addres)
4. ---- ---------- U471-.b/125.04.04 26 197b (cRNI (Drawing No.) (Nf{'t. 8 rd. No.) (Year Pui itl)
5. Valve - -G7.. Identifying N o-s. 160b54 (Model No. Series No.) (Manuftcturerx, Serial No.)

Typa ... s.a-fe rel jef Safety, Salety Relief:tP.ort Po-e Actuated Orifice Size..........4,..8-'.'. Nominal Inlet Size 13" Outlet Size I 0" Inch 1ch ir-h

6. Set Pressure (PSIG) _. 11&0......... Rated Temperature 585 Stamped Capacity 9...
                                                        ..... 27?3                Ibs/ir     @                   % Overpressure        Blowdown (PSIG)               97,9 SaL Steam Hydrostatic Test "(PSIG} Inlet - 2350                                                                     Outlet                                            975 (Applicable to vatv=e f(or closed sysms         r,*y
7. Pressure Retaining Pieces Serial No. or Material Specification Identification' Incl. Type or Grade Body -- 2-f&.8_s/.n I SA 352 LCH

.... BonnMe or Yoke 6------.- 6-. E . s n 3 S u pp o rt R o d s . . - . . .. . . . . Nozzie AR! W302-.-... SA 350 LF2 ... Disc 55-. C 1--&/-n 1A SA 351 CZ.3A Spring Washers 721..&5"L "V'-!. 12 45Cr ho.V.67.- Adjustlng Screw -AE-U-13-/A'FIJ 094 SA .162 -F316.-.. - -

       'Spindle                                  -       -W 0 . ... "                                                        A 564-74 t=ype.630 -cond, Hl1O0 Spring                                   . .         . .........

Bolting -AUP----AJFRJ--AUK, AJJ, ALR, SA 193-,B7/SA 194-7/SA J94-214 Other Pieces --- A9 -,--AJL SA 35 -CF3A..

         -Coy                                       5.5U..s.n_.                                                    *  ... SA 351..c.8, ..
         .V-YenLr p ip_                            ,W0271                             .              ...               .... SA .15..........
        ..FLanges._                                 AFV            19.IAV_ -U               _'.   .                          SA 105..

L'ax. outside diam. valve body:

  • 476. mut (16.74 inch)

Max. outside length valve ib45 mm (64.76 inch) Supplemental sheets in form of. lists, sketches or drawings may be used provided (1) size is 8-1d' 11-, (2) information in items 1-2 on this data report is included on each sheet, and (3) each sheet is numbered and number ot shoot,. is recorded at top of this rorm._ 118

FORM NV-1 (Back) CERTIFICATE OF COMPLIANCE We certify that the .tatements made in this report are correct and that this valve conforms to the rules of construction of the ASME Code for Nuclear Power Plant Components. Section IR,Div. 1.. 1I'74 Edition. Add enda Sum. ' 7.6 Code Case No. ..... lU-Uat L-7d Signetd q, jýýCkrs. & Co, by - W.4. WiLLems Our ASME Certific*t* of Authorization No- IJb to use the fNV i ~~(Date)"7 - CERTIFICATION OF DESIGN-Dezign information on file at G;eneral Elecrric andFry....-- Stress artalysis report (Class 1 only) on file at -.- General Electric and Perr-y__. De:ign specifications certified by' - Byd P.. Brooks este .._ a__ifz-na 13655.. Stre report cerfied by, .... .. _e l . eLri ... PE State CaliiforniaLI*i1 o a .. .. Reo. No.. .. 492 62 I Sign-ature not required-4ist name only. CERTIFICATE OF SHOP INSPECTION' L,the undersigned, holing a valid commisson issued by the Nationral Board of Boiler and Pressure Vessel Inspectors end the State or Province of .... -.Ihi. .-... and employed by - Kemper Tns. of . Lon _..s-ov..a., TI..UL........ have inspected the pump, or valve, described In this Data Report on

      ._Lf-i.[ ..      ..       19. 713and state that'to the best of my knowledge and belief,:the Manufacturer has con-structed this pump, or valve, in accordance with the ASME Code for Nuclear Power Plant Components By 5ignlng this certificate, neither the Inspector nbr his employer makes any warrant. expressed or Implied, concerning
" equip'rnct described in this Data Report Furthermore, neither the Inspector nor his employer shall be liable in any manner for any per.dnal injury or property damage or a loss of any kind arising from or connected with this inspection.

Date L L .. ....... S~ignedComsin-45 Commissions. ....

            .-    "apctoc                                                         I~t      'L State P'ov. and NaJ.

REPORT NO. P0059-012 1132/- ' NIS-2/NR-.1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As required by the Provisions of the ASME Code Section XI PNPP No. 9308 Rev. 9/11/00 NQ0-1741

1. Owner: FIRSTENERGY CORP. Date 6-5-9 10 Center Road, Perry, Ohio 44081 Sheet 1 of 3
2. Plant: Perry Nuclear Power Plant (PNPP1 Unit 1 10 Center Road. Perry. Ohio 44081 200357532 (RepairOrg. P.O. No., etc.)
3. VVork Performed By: FIRSTENERGY Nuclear Operatino Company PNPP Type Code Symbol Stamp NR 10 Center Road. Perry. Ohio 44081 Authorization No. 33 Expiration Date 09128/2011
4. Identification of System: NUCLEAR BOILER 1B21
5. (a) Applicable Construction Code: ASME Section III Class 1 1974 Edition NAMAE/S ECTION/DIVISI ON/C LASS NONE 19 Addenda Code Case(s) 1622 (b) Construction Code used for repairs, modifications, or replacements: 1974 none none Edition Addenda .Coda Case(s)

(c) ASME Code Section Xl applicable for Inservice Inspection: 1989 none none Edition Addenda Code Case(s) (d) Applicable Edition of Section XI Utilized for Repairs, Modification, or Replacements: 19 89 19 none Addenda none Code Case(s) (e) Design Responsibilities FIRSTENERGY CORP. S. Identification of Components Repaired, Modified, or Replacement Components I Name of Name of Manufacturer Nat. Other Year Repair, ASME Component Manufacturer Serial No. Board ID. Built Replacement, Code I No. or Modification Stamped VALVE AT\WOOD & MORRILL 7-560 N/A 1B21 F0028C 1976 Replacement. _ _ _ I YES

7. Description of Worki REBUILT VALVE S/N 7-560 USING NEW POPPET S/N 1.
8. Test Conducted: Hydrostatic- E] Pneumatic- LI Nominal Operating Pressure- M Other- EL Pressure 1030 psi Test Temperature 150 degrees F Code Case(s) N/A 119

NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back) PNPP No. 9308 Rev. 9111100 NQI-1741

9. Remarks:

NO NAMEPLATE/STAMPING PERFORMED DUE TO THE INTERFACE CONTROLS OF PART 3 SECTION 1.8.6 BEING IN EFFECT AND JURISDICTIONAL AUTHORITY CONCURRENCE HAVING BEEN RECEIVED. Note: Attach all applicable Manufacturer's Data Reports. Supplemental sheets such as lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in-, (2) information in items 1 through 6 of this report is included on each sheet, and (3) each .sheet is numbered and the number of sheets is recorded on the front of this form. CERTIFICATE OF COMPLIANCE I, Michael J Teusick certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and to the National Board Inspection Code "NR' rules. National Board Certificate of Authorization No. 33 to use the "NR stamp expires 28 Soot. , 20 1i Date 5 JUNE . 20 09 Signed FENOC-PNPP QC Tech. (name of repairorganization) (auth rized representative) (title) CERTIFICATE OF INSPECTIONIINSERVICE INSPECTION I, Thomas G. Laos holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction 6f OHIO and employed by HSB CT. of Hartford, Conn. have inspected the repair, modification or replacement described in this report onýu-k:_ £20 . and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code 'NR' rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from or connected with this inspection. Date 5 June ,20 09 Signed "k* 5'Lý,&O Commissions NB 9330 "N" "I""A" Ohio Comm. (inspector)"- (NationalBoard (include endorsements), andjurisdiction,and no.)

REPORT NO. P0059-012

                                                         ': :         -                                               / 7_1-       uz _.. it54T 2-o FOR1.;M  NPV-1 MANUFACTURERS' DATA REPORT FOR NUCLEAR PUMPS OR VALVES" As Retuircd by due Provisiors of Lhe ,SSE                        Code fults
1. Mzanua:rured b.Atwood & Morrill CodingSle, Mass 01970 ortr No. 1 .001 (N.m., Addrcss of 5anP'r-trer)
2. Manufactured for. I 7Z)L. -ýC Order No. 205-AF774 (Name and Address)

.3. 0' ,m~r.Brf- -ncy VC'

4. Location of Planrr NoOZrth .Perr*.* 0"hio
5. Pssmp or Valve ldenificarion V;IV,, S Z 9/7" 7-560 26 ;7c Mai bStea - DIa 17J- o n Valve For Service in Main Steam Piping Svstem (Brief des. ri pti.nr of ..r.vie If, whiah cquiprntn w-as designed)

(a) Drawing No.1 '3SE--1 -H Bev Prepaxed by._ bp rt (b) National oad No... &.Dcsin - Condiions I 37r, ( Prrs s -r) Dsi (T emperatnre) OF

7. The macerial, design, constructioh, and wýorkmanship complies with ASME Code Section Ill. Class 1 Edition 1974 Addenda Dare N/JA Case No. 1 2
                        -   -2  : -. Mark No.  -  -, ---
                                                     ..                    Mwlr    l Spec, No,              M    rsfecesrrr                     Rerars (a)      Castings RTA N267{

(b) ForginAs

                                                                         '%*< r- )   t'2_
                                                                                       ---  7.-                    r-   C     I I _____________

Q /hT P - C:A Cover cSA (QT.)- c rvn q alll q/N 7-5r'----- "Srpple-rentalsh*etr in for-m Of list, sketches -at drawlings may be used pro-ided (,) sian is sid" x I1", (2) iformfation In it..s, 1, 2, 5. and Sb no this data report is included on each sheet, and (3) each" sheet is ntnboteed and number of Sheets is recorded at top of this ormn. 120

FOI;\l NP V-1 (back)

                                                                       .lteriat O        Sra=. No.

Marki No. M-f oa-fa ture? perear.is (c) Bolting

                     -    _'-                                                               ; .1,Q               -

4 __'_or Ni__ .. L.(13) l___A540 Gr-B 23 1JS.DVson&SoriS Heat#13 9 (d) Other Parts 33/4 - T\iIID1P- (21 AI Q~ A lrA TI - .1;L

                                                                                                                  ,/~.7r-6Oe
      *°              I~+~r--Qs2mp~ly                                        i~thth-           'ODhE f01- Mmi-tri 31- con-rrix-tion
a~n wQorZcmanbJ-. _ntare not linrluded as fae as design is nn~~~rn~~~A no _ _ _ _ _ _ _ _ _ _ _ _ _
                                                                     *     /             *            ,            ,

Bod-v Poppet

8. Hydrostatic test 2 1 7 145D psi.

CERTIFICATION OF DESIGN Design information on file at *(Pn-r-*. 1 ecl--ri'- Ca San Joe;. Calfornia Stress analysis report on file at ZtwnnA 9, M-r 1 1 (In Tn r , . ,q.I-MI M _ Design specifications certified by.---- 4(anj.i t.-- Ra-m An-i-os- -- (1) Prof. Eng. Staw Ca i fReg. No. 163 Stress analysis report certified by T4mrhtr-f- (C'nk (1) Prof. Eng. State MIa s..S Reg. No.*1 98 1 (1) Signature not required. List name only. We certify that the statements made in this report are correct. J Date 3-24 19-7----- Signed .t ch Tr p y-tor' g Certificate of Authorization No.- -T2i expires M;ij 7 1)77 V .. CERTIFICATE OF SHOP INSPECTION 1, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and/or the State of Province of M.A. S CT It q and employed by 1171+ fC'rA 3S -m rn 1 mr Trf of Earf-f rnr., (0nn have inspected the eqo .pm=.tfest Data f'ns 1 Report on 9 -- 19--7-6------, and state that to the best of my knowledge and belief, the Manufacturer has constructed this equipment in accordance with the applicable *Subsections of ASSME Code, Section III. . By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concern-ing the equipment described in this Data Report. Furthermore, neither the Inspector nor his employer shall be liable in any ma*iner lor any personal injury or property damage or a loss of any kind arising from or connected with this inspection. Date 3-24 197f*

                       .-                                                   Comissions                M-,.             1264                Ohio
                                                                                                                                              --          mmision (o-epeintar)      0   "3                                                           (National Board, State, Provence and No.)

Gerard Cocuzzo 9 Printed in U4.S.A, j6/72) r i (This form (E37) is obtainable from the ASME, 345 E. 47th St., New York, N.Y. 10017

R-EPORT NO. P0059-012 87//- 7. g/4i 3 ~ 0 FOPR. NI-2 CERTIFICATE- HCOLERG` DAr r -t R M;DENT;0AL NUCLEAR PARTSV&AliD A NC S' As Required by t~he Provisionrs 'of the ASME .Code,~in i Not to Excee Oiie Osays Rradqr on Marorfactured a~ndcertified b'! ArrS~ood &, YcorrilC.,b.

5C"o.zt 4.rsYA i9~

2 Manufactured to, Ce t~tar2.C Enere-v l0Certtexr Rad _ýry,

                                                                                                                                                        .hio            41i081 3,    Locarionof   a insTal~atior             Perrv            iiucl             Poae        P!.anr            10 Oenter                Rd..      ock No..1 No- -h-                    err.y _0H 44081 4

4.Type*32L6/ 26:- Rev. 3 SA105 573.7Mt. PS 1 ______ 0

5. ASMdECode, S-tion Il. Dmie'io 1: 1974 .N.o1NA
6. Fabricated in accordanice withr Const. Sper. low~. Z .iijrN V!'i, hAA~ ae ~ /
7. Remarks: Gu~sr. Item 01, A6NrhItem 01, Qnyr. 1 optANPl 2.T669. 2 C 25637) *tDwg. preprar.,ed by AiIIL This .crtif.c nsriait the reqar-e.d :..ratii ASHMI Section 1974 Edktiomý No Adi~en~.ri.

S. NrIrta.Iackrness linj .)....L.7...... Mi. design :hicimraecuiies 6. L/8 a. IDrr&, L.......Langth i A 0.snr4ift & in")i 2- Whstmropvlicobte, Certificate Holders' Data Iloporis are~artachedl to, each' bern t his-repesr: Part or Appurtenance National Parn or A-dpprleanrn(e Ndi~ Serial Number Soard No. S!;rialWtsmb- 6. rdadN o. in Numerical Order i:lih/raOidir FiT ,'1 C6601 S.,N I N/A Q174 _______1_______________ 0,_____________ (41 1S)____________ (30.1** 4 161-(101

          !1131 1(391 0415 44.5:7 (4.3 (117                                                                                                  (44)_

(461 14.71 I 'N 1(251-- 1' _ _ _ _ I ___ l___j. Mt. Design pressure 1375 psi.  !%mp. 586 F.. A at tefrp. af SSupplem ~ntal is innis~ni in ,.'nasion in th0 -'zt: of lits, sketi hs.. ar drawings may be used prWnids LL; sic: is 8.j X 11. 2,,r. leu od in items 2 and 3on -his a-m*s (tporf

o. e r~i 13 (3t '

4h"t inrsebered

                                                       ,le              errz 5:5 -a be, f1s45505 iS reCaldsl -rtern =000 thisnIV      54, (1 ';se    }                                                  ,-hisform             )say' mEr, ti  ft Lrnaied f.   "she C r4,,! rO    t. A I5-1. =2t. a Drfi ,e. B.. 23 03. Fairfield. NJ 0    --D0 -2300.

Rp.rint [7j*9) 45

                                           -                                   .r.5~ir~5bi~t~       -.

121

REPORT NO. P0059-012 1821I- L/12 3 N!S-2!NR-1 OWNER'S RE-PORT R RPAIRSOR R .PLACERAENTS AS required by the Provisions of the ASME Code Section Xl PN PR No. 9308 Rev. 2/11/00 P NDI-1741

1. Owner: ,RSTINRGY COPP. Date 5-24-9 10 Center Road. Perry, Ohio 44081 Sheet 1 of 2
2. Plant. Perry Nuclear Power Plant (PNPP) Unit 1 10 Center Road. Perry. Ohio 44081 200288203 (Repair Org. P. 0. No., etc.)
3. VVork Perormed By: FIPSTENERGY Nuclear Doeratino Comoany PNPP Type Code Symbol Stamp NR 10 Center Road. Perry. Ohio 44081 Authorization No. 33 Expiration Date 09/28/2011
4. Identification of System: NUCLEAR BOILER 1B21
5. -(a) Applicable Construction Code: ASME Section III Class 1 1974 Edition NAMESECTION/DIVISION/CLASS NONE 19 _ Addenda Code Case(s) 1622 (b) Construction Code used for repairs, modifications, or replacements: 1974 none none Edition Addenda Code Case(s)

(c) ASME Code Section XI applicable for Inservice Inspection: 1989 none none Edition Addenda Code Case(s) (d) Applicable Edition of Section Xl Utilized for Repairs, Modification, or Replacements: 1989,__ 19 none Addenda none Code Case(s) (e) Design Responsibilities FIRSTENERGY CORP. 8.. Identification of Components Repaired, Modified, or Replacement Components Name of Name of Manufacturer Nat. Other Year Repair, ASME Component Manufacturer Serial No. Board ID. Built Replacement, Code No. or Modification Stamped VALVE ATWOOD & 2-560 N/A 1B21 1976 Replacement YES MORRILL FO0223

                                                                     +                   4
7. Description of Work: REWORKED VALVE USING 1 COVER STUD 2.25-B HT# OU16 AND 1 COVER NUT 2.25-8 HT# EE69.
8. Test Conducted: Hyduostatic- ED Pneumatic- [] Nominal Operating Pressure- Z Other- E3 PressUre 1011 psi Test Temperature 143 degrees F Code Case(s) N/A 122

NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR RP-L.A.,_NIENTS (Sack) PNPP No. 9305 Rev. 9111/00 "Q1-.

9. Remarks:

NO NAMEPLATE/STAMPING PERFORMED DUE TO THE INTERFACE CONTROLS OF PART 3 SECTION 1.8.6 BEING IN EFFECT AND JURISDICTIONAL AUTHORITY CONCURRENCE HAVING BEEN RECEIVED.. Note: Attach all applicable Manufacturer's Data Reports. Supplemental sheets such as lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded on the front of this form. CERTIFICATE OF COMPLIANCE I, M*ichael J Teosick , certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and to the National Board Inspection Code 'NR" rules. National Board Certificate of Authorization No. 33 to use the "NR stamp expires 28 Sect 20 i'1 Date 24 JUNE 20 09 Signed FENOC-PNPP OC Tech. (name of repairorganization) (authorL rdrepresenta ve) (title) CERTIFICATE OF INSPECTIONIINSERVICE INSPECTION I, Thomas G. Laos holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HSB CT. of Hartford, Conn. have inspected the repair, modification or replacement described in this report on 20 0-1 . and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code "NR' rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, conceming the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from or connected with this inspection. Date ~e~ 2009 Signed Commissions NB 9330 "N""I"A"Ohio Comm. (inspector) (National Board (Include endorsements), and jurisdiction, and no.)

REPORT NO. P0059-012 192-1--YZ 4"W.,{7" 2-6,r.z FOPM NPV\-! MI NUFACTURERSý DATA REPORT FOR NUCLEAR PULMPS OR VALVES* As Required by Lhe Provisions of lao ASNIE Co6c Rholes 1.Manufacturad by M 01 97 OJJOrder No. 360-01 (34are

                                                           -    Address ot .1 utaeturer)
2. M*a*ufccuredfor G7
                          -Prn              EIlectric            Co. .San          Jose,         Caifornia                  OrderNo.       205-AF774 (14-e  -d  Add-.o) 3.Own er-      -- Oc' *!       3_               r--Flr i c-r TI I     mi        J=-*r. -r7           .
4. Location of Plant _i-7or-tb Perrv. Ohio S. Pump or Valve Identificacion *aIve S/N _-ren 26 575: MaiD Steam Isolation Valve Fnr Servzice in_ Main Steam ?iping System (Bri! u.rip.i..eto .er..cefi r ,uhicb"h uipc ont uio ctienod)

(a) Dravw'ing No.. -3S6 - R 3 Prepared by Ro*bert J X-QOx (b) National Board No. N/A

6. Design Conditions " 1 375 psi 586 05

(.Pressur*e) (?Te.--pe rarr.-r )

7. The material, design, construction, and workmanship complies with ASME Code Section IU. Class Edition - 1974 Addenda Date N/A , Case No. 1622 (a) C-srings Mark No, ateial SMac, Nofatrr ]R ak R A9 I f -vc'( pnu1i pr- alrv I q~/N ->--,F "N " 1 7 I" "_

I./ ________________ ___________________ (b) Forgings F ~. J {A350 SPripplt GrT, F- C n Rr S /N 2- 05 Covter SA1O5 (OT) Ca n & Sanl S/N 3-560 cSupplemental sheets L, form of .ioto, sketches or dr-winzs'may be used prodded (1) i..e is S," . 11 ", (2) informatins in items, 1, 2, 5- -nd 5b or this data report is included on each sheet, and (3) each sheet is nuribered and nuobzr of sheets is recorded at top of this form. 123

FUIDI NPV-l (back) M.Iak No. r.~ar=-ialSpas.Na. M..ufa ctrnre (c) Bol3rin Cover Studs~ (-fSi ~ :, 5Afr' ~2 3 -r~ r -rQ I ~ (-m-Q

                               -          Ni     S               PLLa. -                                   IQ,~?

ar~r D\ Cnz~ Em P775j (ti)

                                  *~                          ~5              t~l;A      i     nr           I T1 P      qi-=.l                                         C'0~f

__ _ _ _I_ q n_ _ _ _ _ _ _ _ _ _

                                      *Pl 1
                                             ,1 ~c~
                                            -rr;,j                                  .cs-(          h       Ir-QT-nj-    Mrh         MC'r-A                _3       *.

Body Poppet

8. Hydrosta ic test_ 9 1 7 ' I A. 0___ psi.

CERTIFICATION OF DESIGN Design intfoma*tion on file at G(r-M-c- 1 El Fc-ji-i rc C San -TnP, c* r 1 i forni a Stress a ,alysis report on file at AtVwoor--7 0, Ir . CO T ,"c- . -' -s . MC Design specifications certified by Ranh it Ranian Ghosh (1) prof. Eng. StatClf eg. No.l 537 Stress analysis report certified by.....- C.'., (1) Prof. Eng. State .M- Reg. No.In-9-.9. 1 (I) Signature nor required. List name only.

                                                                                                                                                                                        )

We certihy that tihe statements made in this report are correct. Dat.... r Sign-A7t.w*o_o o.&M

                                                                                     *"(Mana.......

_z,_1I ICL ma. yDBy. Qua ity Control Manage 2 Certificate of Authorization No. NRP 12 expires MaSr 7 1g 77 CERTIFICATE OF SHOP INSPECTION I, the undersigni.d, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and/or'the State of Provrince of Mr ,hlc0t-- and employed byllar- ',r1=3 St- gm "no I 1 r "* I of ji _H r frTrt rl C'r, n n have inspected the equCpment e n ro-Report on / "" , 192..*..* , and state that to the best of mv knowledge and belief, the Manufacturer has constructed this equApment/in accordance with the applicable Subsections of ASME Code, Section III. By signing this certificate, neither the inspector nor his employer makes any warranty, expressed or implied, concern-ing the equipment described in this Data Report. Furthermore, neither the Inspector nor his employer sha.ll be liable in any manner for any personal in)ury or property damage or a loss of ary kind arising from or connected with this inspection. Date - /- 7 --

                                                                                                        -~  ~~~~ý (Ntinl      Bad           ttPrvneadN.

Yr

                                                                                 -    C m isins                    Nai..      S      -,     ttet-Y..             n    N.

Printed in U.S*.A. (6/72) This form (F37) i. obtainable &.o.a the ASfE, 34S E. 47th St., New York, N.Y. 10017

REPORT NO. P0059-012 NIS-2/NR-i OWNER'S REPORT FOR REPAIRS OR REPLACEMAENTS As required by the Provisions of the ASME Code Section XI PNPP No. 9308 Rev. 91 1/00 NQ0-1741

1. Owner: zIRS7ENERGY CORP, Date 5-30-9 10 Center Road. Perrv Ohio 44031I Sheet 1 of 2
2. Plant: Perry Nuclear Power Plant (PNPP) Unit 1 10 Center Road. Perry Ohio 44081 200262683 (RepairOrg. P.O. No., eic.)
3. Vork Performed By: FIRSTENERGY Nuclear Operatino Company PNPP Type Code Symbol Stamp NR 10 Center Road, Perry, Ohio 44081 Authohzation No. 33 Expiration Date 09/28/2011
4. Identification of System: NUCLEAR BOILER 1B21
5. (a) Applicable Construction Code: ASME Section III Claý 1974 Edition NAMEJSECTION/DIVIS WINTER 19 75 Addenda Code Case(s)

(b) Construction Code used for repairs, modifications, or replacements: 1974 VN75 none Edition Addenda Code case(s) (c) ASME Code Section XI applicable for Inservice Inspection: 1989 none none Edition Addenda Code Case(s) (d) Applicable Edition of Section XI Utilized for Repairs, Modification, or Replacements: 1989_.9 __ 19 none Addenda none Code Case(s) (e) Design Responsibilities FIRSTENERGY CORP .

6. Identification of Components Repaired, Modified, or Replacement Components Name of Name of Manufacturer Nat. Other 1 Year Repair, ASME Component Manufacturer Serial No. Board ID. Built Replacement, . Code No. or Modification Stamped VALVE ROCKWELL QC-51 670 IB21 1982 Replacement YES F0032B
7. Description of Work: REMOVED AND REINSTALLED TEST CONNECTION FOR INSPECTION.

USING FILLER METAL HT# 159443, 42379.

8. Test Conducted: Hydrostatic- [D - Pneumatic- [ Nominal Operating Pressure- 0 Other- U Pressure 1030 psi Test Temp'erature 150 degrees F Code Case(s) N-416-3 124

NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back) PNPP lo. 9308 Rev. 9/11/00 NQI-1741

9. Remarks:
  • NO NAMEPLATE/STAMPING PERFORMED DUE TO THE INTERFACE CONTROLS OF PART 3 SECTION 1.8.6 BEING IN EFFECT AND JURISDICTIONAL AUTHORITY CONCURRENCE HAVING BEEN RECEIVED.

Note: Attach all applicable Manufacturer's Data Reports. Supplemental sheets such as lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded on the front of this form. CERI1FICATE OF COMPLIANCE I, Michael J Teosick certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and to the National Board Inspection Code "NR" rules. National Board Certificate of Authorization No. 33 to use the "NR stamp expires 28 Sept., 20 11 Date 30 JUNE 20 09 Signed FENOC-PNPP , // < OC Tech. (name of repairorganization) (authorinadrepresentative) (title) CERTIFICATE OF INSPECTION/INSERVICE INSPECTION I, Thomas G. Laos holding a valid commission issued by The National Board of Boiler and Pressure Vessel Irrspectors and certificate of competency issued by the jurisdiction of --- OHI and employed by HSB CT. of Hartford, Conn. have inspected the repair, modification or replacement described in this report on 6/30/9 20 09 and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code "NR' rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied. concerning the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or oc of any kind arising from or connected with this inspection. Date 30 JUNE, 20 09 Signed ,- ._ -,-- W-ommissions NB 9330 "N" "I""A" Ohio Comm. (inspector) (National Board (include endorsements), andjurisdiction,and no.)

REPORT NO. P0059-012 I2-1 - 1/1-/ */ / 2 -;1/- As Sequrc-6 by th Frcw~isiuns 7 1'1l!~0v 7 Zlt L;t Dn~oaa COp. 2~a1 1900 S. SZILoers ýtS 32L_ýg ,AC 97,2, (Nanrri anroAddress o! N Ce~tificate Noldarl

2. uan.ausl ,or Cleveland Elec. II!. Comjoo-y, ?... .oox 500, C.lev.l*nd, Ohl- 4-410
   ;      .                            [rt'bme end* AS.,ur, o: Pu,ches-* ,0'o...lt=
3. Lo0licsn o Inslallijon Perry 1iuclaeer ?o-oer Flanc, onirs i 2 vorth ?--exr. 0hio IN~ -1 And ,~o--)
4. Pump or V Vl-le .*Nominal Inlal Siz'J *0

_ _ Ouil_ Siz-e _ 2-0 a!)Model No.. (b) N Co*ilfale Holder's (c) Canadian or Type No. l-Cls No.No. -Bcd. N.. guoll

             - 7592(()0CC)                   QC-51                     V/A          D81-24401-1.5                  1                 670             19*81 i21     .INQTY                                                              Rev. A (4)

(5) (7) (SD) S. Controlled closure Check Valve

                          .e**-

1r3*.I33K '..cpo . r.izisCoodhions 4P,=ssuarsl ps1i 42 liarsp=otu...1 ' or Valve Pfewsure Class- __________

7. C.16 Wo.-.;r;!? Pressure 2250 psi a, tOOF.

" BS. P-e--ure Re:aIring Pieces Marl: No. f Material Spot. No. Marxut)actumr (a) Catings f I 4810433 SA 216 Gr. WCC Rocds-lk l .t'i Bi)d*, Ib) Forg-inqa 116447 SA 105 ]C--h"--'-. I.e 1 -son_ _____ _ __er 10502 SA 105 . Le:r-son ECh-ar+/- Dissk 36996 SA 638 Cr. 66032 Charl~eý 5L*,_*I--0 [Gl.et Ci 12637G SA 105

                                            &                                         ]              R 1, ,-- Lazr..u             .Drain -- tgp (42);

116792 J SA 105 VC_-.. l:are,-n Tesr 3'Fi iLg fl) For manuaollyope-tatd v-sin-S only. Suepplemrental streets inr fom ol Uisus.skerirhec or d-arsirrgs may be sodross- e 911 1--SVY 11-. 121intnvrMaiion it, heome 1. 2 and 5 on this DOs Ct*,*ri is included, mu each bhe.eL and Q' S-a=h h', i Am,5;..Lrr: " d nurnbr o:vhiP t=o irst=rdt:6 .. p r!n: lp to-ir.ý=.

                                         'so eons        215571mao'M.~rmin~OOaorr otreCrdar C~s         .52       555-5 -55r), S-s. Na., rtoOkAC!~.5OZ5~

125

-- .-:-~..~-~.-n.v..<----. .~. REPORT NO. P0059-012 NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As required by the Provisions of the ASIviE Code Section XI i PNPP No. 9308 ReV. 9111/00 N01-1741

1. Owner FIRSTFNERGY CORP Date 6-30-9 10 Center Road. Perry. Ohio 44081 Sheet 'I of 2
2. Plant Perry Nuclear Power Plant (PNPP) Unit 1 10 Center Road, Perry, Ohio 44081 200262682 (RepairOrg. P.O. Me., etc.)
3. Work Performed By: FIRSTENERGY Nuclear Ooeratino Comoany PNPP Type Code Symbol Stamp NR 10 Center Road. Perry, Ohio 44081 Authorization No. 33 Expiration Date 09/28/2011
4. Identification of System: NUCLEAR BOILER 1 B21
5. (a) Applicable Constriction Code: ASME Section III Class 1 1974 Edition NAMESECT]ON/oDIVISION/CLASS WINTER 19 75 Addenda Code Case(s) NONE (b) Construction Code used for repairs, modifications, or replace.ments: . 1974 W 75 none Edition Addenda Code Case(s)

(c) ASME Code Section X1 applicable for Inservice Inspection: 1989 none none Edition Addenda Code Case(s) (d) Applicable Edition of Section X1 Utilized for Repairs, Modification, or Replacemrents: 198 __ 19 none Addenda none Code Case(s) (e), Design Responsibilities FIRSTENERGY CORP. 6, Identification of Components Repaired, Modified, or Replacement Components Name of Name of Manufacturer Nat.. Other Year Repair, ASME Component Manufacturer Serial No. Board ID. . Built Replacement, Code No. or Modification Stamped VALVE ROCKWELL DA-26 665 11821 F0032A 1981 Replacement YES

7. Description of Work: REMOVED AND REINSTALLED TEST CONNECTION FOR INSPECTION.

USING FILLER METAL HT# 159443. 42379.

8. Test Conducted: Hydrostatic- 0 Pneumatic- El Nominal Operating Pressure- . Other- E]

Pressure 1030 psi Test Temperature 150 degrees F Code Case(s) N-416-3 126

NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEM'ENTS (Back) PNPP No. 230B Rev. 9111100 N I1-1741

9. Remarks:

NO NAMEPLATE/STAMPING PERFORMED DUE TO THE INTERFACE CONTROLS OF PART 3 SECTION 1.8.6 BEING IN EFFECT AND JURISDICTIONAL AUTHORITY CONCURRENCE HAVING BEEN RECEIVED. Note: Attach all applicable Manufacturer's Data Reports. Supple mental sheets such as lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded on the front of this form. CERTIFICATE OF COMPLIANCE I, Michael J TeDsick , certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and to the National Board Inspection Code 'NR' rules. National Board Certificate of Authorization No. 33 to use the R stamp expires 28 seot. 20 11 Date 30 JUNE 20 09 Signed FENOC-PNPP DC Tech. (name of repair organization) (authbo'zed en (title) CERTIFICATE OF INSPECTION/INSERVICE INSPECTION I, Thomas G. Laps holding a valid commission issued by The National -Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HSB CT. of Hartford, Conn. have inspected the repair, modification or replacement described in this report on 6/30/9 20 09 and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code "NR" rules. By signing.this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or assof any kind arising from or connected with this inspection. Date 30 JUNE 20 09 Signed ikM 4 Commissions NB 9330 "N""I""A"Ohio Comm. (inspector) (National Board (include endorsements), andjurisdition, and no.)

REPORT NO. P0059-012 1r.~--&~c by EoJ7.ýE:17 TtIe-ato Ccr-rp .2190D s. Sander-s St. aeh, C270i [Fizarn and Address of N Cc tifiirae Hol~er)

                                  ~~    vladEiectr-:c                  111.,       cc,-pany,        ?.0. 'Box 500, cleveland, olhi                           Lp.41i.

i ýtn br,d 46dr,,c of Purch -~rr of C'ý-'er) upn

                -Z      a:-.-       -     V= ve                               Noins     Intl'-    sinc           -             Q~        Size      -

Series No. RergJis7trvtion (d) Drrwi.-%a - ) NS'lI. tg) Y'earn or Type W0o.. No. (ee) Claem d. No. Suitt JNQ j TV- . Rev. A 17) (1oi

5. ConTtrolled Closure Cbetkl *Valve, Behat No. 4810453.122 ~ 36-9acccripcwe d~oS3-0.ssfrr~h~i 214401
6. Design Conditrions - 1510 pzi- 420 ':or Valh~e Pressure Closs IV
7. Cold Workin~g Prssr 2250 ps,'-- MF 6, I. Pre-tsri~e R~etaining2 PI5ieze&

Mark No. ManjSpls NCL Msrnztature-r } Remarks (0)cachrros 4~10A53 05-. ?Q (~iWt~al Castm~i- D1..7) ________ (b) Forgrings

                  ý11447                         SA 10                                         lae            . a-e                              oe 20
                              ,10                         5         ..                  < ar-   ~        Sa Ul St eel                          Dis-k 3699.6                         SA 638 Gr.            660T2               Chartes E.           LarsoR                         Gas'ket     Retaine*

1 1 in 12637b S.. 1A0 Charles r. Larscýn D)rain Cap (2)

                  -L.Ib/014~.                   SA     1UL                                 LMarlas E.           Larsou                         Test Fittinra
                                                              -    _____________         4 ______________________                +/- ____________________

(1) For rriarluefy op~raied valves only~. SupplrerernLA) sh'eate in form Qfligele. Fkcichc: or drat-eirnos may be vse~d rqv;dtcd (I) size insS1-x 2.tin .()Inorm-ation R in icnns A. 2 on 5 on 1his Dsla Rep-or ir includr.d an each chtel. ~n~d (3) each.L.Keel ;j numbered arid numhpr of Sh-ýtt5 is r-crcitc! asttop of lhif form. 127

S' ... . -  :- .4 i-- L246 .. 7-k 10 cr B. Capta PiPE Ste Prdut __ 5_5_____06 Gr. B ait P - .1> Daz__________ _ _ae _ I-r _ 7_ _ _ t _ _

2. 3375 Pýi- prý !I'm- ýZ-5.'Q Pýt-CERnRG)ATE OF C(DMN0-'kAE VP tErTifY that the Wtatemenfns rr-ade in tbis reotaecorz-rt i~l rap r'ab. rfrt to the. rules of conslr-crnmo the; ASMIF rpde ftzr Nhuctea- Po~.'zr Min I Cornpor.enTe Secan IlLi-. I- Editionr 17 A~ddeni.a -Wintai7 1'375. Coda Case tia__________
3. eo _____

M1Ccrtilklwe Flatlder

  • Qur ASMZ Certificalc oi Author-iz-alln No, ro. týFarthr aymbol a ~.!res -2 Devign infarmation on rfle 2q k~ Int-augianal Comp, I NC 216,3
 &tress wi.nlys epe ort fCtaea. 1 onjyy e fjt,              I~~Tp~ke                ImAteroa~tiona.                Cctrp. ,    Ral~h             NTC 21693 PE Sizte         PA                       Reg, No.02              -                                                                               5    ;        )

SITEES tra)lysi tcrtifjic by (1) R.. .ppLx) K StIV a v. RcS. W No., OS ~ (1) S;gnvure! nlt ro~uirad, Li~a naMa only. CERTIFICATES OF S&140P IN&-ECT1ON 1,the und~errig-ne. holding a valid cornmiaeon i-satred by the Nationil Board of 15,o;1r and Rrcsvpa, Veteadil tr~aorr ondS the Stbie or F'roe.Ince of North CBarpli-a -snd employed by ESBI & I Co. cS Hartford., CT htt'm inst~erted the pump, or valve-. described in this Dbta Rcepori on 1,19 'R1d and tqe that to the besti of my ko-le-doc t' nd be'lic!. the H Cmrlificw, c Holders hall con-ztr.cto&d this purvp, or v"eh!. ;n 5ccrdzrno~ with Vie AS.M' Cojde. Stejion inl. EPy eipnirrg this certEificale. neither tf~r Insepeetor no~r his emnployer mates any warranty. exa aerscd or irnptie'd. conce~rning the er~uipmenerr dcsecribcd in this Obeia PReport Furthermore. ne-jlhcr the tInspecior nor hits employer chall be Eitble in anry manner fror any pe-r;*enzI injur.y or property darrnagQ or 6 Ice-c of any Urd brietino from o~rco~nnoeed withl this ifltpcrtti~l.

REPORT NO. P0059-012 1B33-130 NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As required by the Provisions of the ASME Code Section XI PNPP No. 9308 Rev. 9/11/00 NOI-1741

1. Owner: FIRSTENERGY CORP. Date 10/03/07 10 Center Road. Perry, Ohio 44081 Sheet 1 of 2
2. Plant: Perry Nuclear Power Plant (PNPP) Unit one 10 Center Road Perrv Ohio 44081 ORDER 200099255 (Repair Org. P.O. No., etc.)
3. Work Performed By: FIRSTENERGY Nuclear Ooeratinq Company PNPP Type Code Symbol Stamp NR 10 Center Road. PerrY. Ohio 44081 Authorization No. 33 Expiration Date 09/28/08
4. Identification of System: 1B33 REACTOR RECIRC. SYSTEM
5. (a) Applicable Construction Code: ASME SECTION III NB C,(&4S i 1971 Edition NAMEJSECTIoN/DIVISION/CLASS i-SUMMER 19 73 Addenda Code Case(s) N/A (b) Construction Code used for repairs, modifications, or replacements: 1974 winter 75 see abov Edition Addenda Code Case(s)

(c) ASME Code Section Xl applicable for Inservice Inspection: 1889 no n/a Edition Addenda Code Case(s) (d) Applicable Edition of Section XI Utilized for Repairs, Modification, or Replacements: 1989,' n/a 19 n/a *Addenda 'n/a Code Case(s) (e) Design Responsibilities First Energy Nuclear Ooerating Company, PNPP

6. Identification of Components Repaired, Modified, or Replacement Components Name of Name of Manufacturer Nat. Other Year Repair, ASME Component I IvManufacturer Serial.No. Board No.

ID. Built Replacement, or Modification Code Stamped PUMP BYRON 741-S-1281 NA 1B33 1978 RPL YES JACKSON C0001A

7. Description of Work: REPLACED SEAL CARTRIDGE ASSEMBLY WITH NEW REBUILT CARRIDGE ASSEMBLY SIN 318455.
8. Test Conducted: Hydrostatic- D] Pneumatic- El Nominal Operating Pressure- 0 Other- f]

Pressure 1000 psi Test Temperature 132 degrees F Code Case(s) 128

NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back) PNPP No. 9308 Rev. 9111/00 NOI-1741

9. Remarks:

NO NAMEPLATE/STAMPING PERFORMED DUE TO THE INTERFACE CONTROLS OF RA-2370 BEING IN EFFECT AND JURISDICTIONAL AUTHORITY CONCURRENCE HAVING BEEN RECEIVED. Note: Attach all applicable Manufacturer's Data Reports. Supplemental sheets such as lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded on the front of this form. CERTIFICATE OF COMPLIANCE I, John W. Messenger , certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section Xl of the ASME Code and to the National Board Inspection Code "NR" rules. National Board Certificate of Authorization No. 33 to use the "NR stamp expire* 9/28_ 20 08 Date '/ 200/ Signed FENOC-PNPP D OE (name of repairorganization) i_.....

                                                                               'athorizedrepreserdtative)            (title)

CERTIFICATE OF INSPECTIONIINSERVICE INSPECTION I, Thomas Laps ,h6lding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HSB CT. of Hartford CT.. have inspected the repair, modification or replacement described in this report on O . -_, 20 0-7 and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from or connected with this inspection. Date \* , 20 ti* Signed 1-;.Atýl1 *l Commissions NB 9330 "N" "I""A"OHIO COMM. (inspector) (NationalBoard (include endorsements). andjurisdiction, and no.)

REPORT. NO. P0059-012 1333- 105 FORM N-2 CERTIFICATE HOLDERS' DATA REPORT -FOR IDENTICAL ?G. 2 of 2 NUCLEAR PARTS AND APPURTENANCES' As Required by the Provisions of the ASME Code, Section lII Not to Exceed One Day's Production Pg. 1 of 2 aafacturedand certified by W/ITP T'T=-alM=IONAL 1rC- PUMP DIV-'LOS ] ANGE LE(S 0?ERAIOIIS 2300 E. V kC AVE., VERNON, CA 90058 f"orne end add-z of NPT CnýW-sat oHIoril arrf,,c-ured for T85 ZrE-ND Et.C3T!IC DIaZtEUltGIý C29 10 CMznR ROAD,I-Wll OaIO 44081 (- an.dd*c; at Pof F-6-6 cztinoj of installationl PlaW 1113IZI r(iMR Pl ZT, t11ftET 1 10 C1EWR IR02W, DOCX !IOSER 1, NORIH PEZft, 0U10 44081 ( anbdod,m-]l

                                                                                            -odrso
  .v      EM02168 REV-         A         SA-182 tRt F316                   75,000 PSI                                ,/A                           1996.

ldrevnr1g I.1ra'L noon.--. 1 ft-1-ato ranshl ICRNI fye-h*au

   .ME Code, Section IJ1,Division 1:                                           SUMMM 1973                                1                          K/A

(,oddonl Wad.- dat.) Wd-1 (Cod4C_. na.

br-;cated in accordance with Const. Spec. (Div. 2 only) H/A Revision ,. /A Date _ /A I-.)

comirks: E7/' JOB MO: 95--,E-254:1 ATURE: N--7500 SEAL. CAPM A 4SSMEMtY. L DESl+ M e l, L, CBf*IXCt= O zANDEMIIOB INI ACOMNCZ W= 19813 EDITIO SMMt 1984 A "DM6A. sin. thickness (in.) 2-625 Min. design'thickness fin.) 2-15 Dia. ID (ft & in.-) . .. 500 Length overall (ft & in.)l 3.105, hen applicable, Certficate Holders' Data Reports are attached for each item of this report: 0 tsign pressure 1650 psi Temp. 5F. Hydro. test pressure 2065prsau PSI / 600 LIN at temp. F app(rcablni .mental information in the lore of fists. sketches. or draawings may be used provided 01l size is BY) x 11. (21 information in items 2 and 3 an this Data Report led on each sheet. (3) each sheet is nurmbered and the number of sheets is recorded at the top of this lorm This form (EO0040) may be obtained from The Order Oept.. ASME. 22 Law Drive. Box 2300, Fairfield. NJ 07007-2300. Reprint (7/911 129

                                        .-- -7. -- -- -'   - -           -      -       -.

I -ý'- : I . ... ,-. - - FORM N-2 (Back - Pg. 2 of 2 ) Certificate Holder's Serial Nos. 318455 through iK/A CERTIFICATION OF DESIGN Design specifications certified by K/A 'P.E. State K/A Reg. no. IK/A C.esign report' certified by - RIA P.E. State /WA Reg. no. W/A CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and that thisheese X.-7500 SEIL fl* CE AS-';EKY conforms to the rules of construction of the ASME Code, Section ItI, Division 1. NPT Certificate of Authorization No. H--_31 Expires L 199 Date t&A~4n k Name ERI I~UHM tte't C-riffem L Hotdod IS-_ rdol4r Signed A4. . in omdo CERTIFICATE OF INSPECTION 1, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the-State or Province of

       - OIOr                   -and employed by         AMCX2I(U          EIUIIML 1ISIIRAH= CO~, FACflRY Nlfl1JAL EINGMUING .ASSOCIATICOI{

of wtRmZ*I, LUSS. have impected tiese items described in this Data Report on *S//12-1 ( , and state that to the beet of my knowledge and belief, the Certificate Holder has fabricated these parts or appurtenances in accordance with the ASME Code, Section

.14 Division 1. Each part listed has been authorized for stamping on the date shown above.

By signIn thlis certificate, neither.-the inspector nor his employer makes any warranty, expressed or implied, concerning the equipment described in this Data Report. Furthermore, naitherthe-inspector nor his employer shall be liable in any manner for any personal injury or property damage or loss of any kind arising from or connected with this ispec*. , ______ e tAodiqdo~d Eo~iooOofl Commi ainsC / 7 11,1tt Bd. floo. endo 4 '/ C

                                                                                                                                                                  ) -oIod -ot or p-. ate -01
                                                                                           ,*÷ *
               -  c r.t,     4' 70 -
           'a'      t~-/

REPORT NO. P0059-012 NI S-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As required by the Provisions of the ASME Code Section XI PNPP No. 9308 Rev. 9/I 1/00 NQI-1741 L. Owner: FIRSTENERGY CORP. Date 4-25-9 10 Center Road. Perry, Ohio 44081 Sheet 1 of 2

2. Plant . Perry Nuclear Power Plant (PNPP) Unit 1 10 Conter Rnad. Perrv Ohio 44081 200284501 (RepairOrg. P.O. No., etc.)
3. Work Performed By: FIRSTENERGY Nuclear Ooeratino Company PNPP Type Code Symbol Stamp NP 10 Center Road. Perry. Ohio 44081 Authorization No 33 I - - ___

Expiration Date 09/28/2011

4. Identification of System: REACTOR RECIRCULATION 1B33
5. (a) Applicable Construction Code: ASME Section III Class 1 .1974 Edition NAME/SECTION/DIVISION/CLASS WINTER 19 75 Addenda Code Case(s) 272. 1728. 1644-4 (b) Construction Code used for repairs, modifications, or replacements: 1974 W 1975 none Edition Addenda Code Case(s)

(c) ASME Code Section XI applicable for Inservice Inspection: 1989 none none Edition Addenda Code Case(s) (d) Applicable Edition of Section XI Utilized for Repairs, Modification, or Replacements: 19 89__ 19 none Addenda none Code Case(s) (e) Design Responsibilities FIRSTENERGY CORP.

6. Identification of Components Repaired, Modified, or Replacement Components Name of Name of Manufacturer Nat. Other Year Repair, ASME Component Manufacturer Serial No. Board ID. Built Replacement, Code No. or Modification Stamped PIPING GE 1B33 64076 N/A 1985 Replacement YES SYSTEM 7 Description of Work: REPLACED SNUBBER S/N 022 WITH SNUBBER S/N 060.

PLANT ID 1B33 G7066A.

8. Test Conducted: Hydrostatic-j Pneumatic- [] Nominal Operating Pressure- E] Other- E]

Pressure N/A psi Test Temperature N/A degrees F Code Case(s) N/A 130

NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back) PNPP No. 9308 Rev. 9/11/00 NkI741

9. Remarks:

NO NAMEPLATE/STAMPING PERFORMED DUE TO THE INTERFACE CONTROLS OF PART 3 SECTION 1.8.6 BEING IN EFFECT AND JURISDICTIONAL AUTHORITY CONCURRENCE HAVING BEEN RECEIVED. Note: Attach all applicable Manufacturer's Data Reports. Supplemental sheets such as lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded on the front of this form. CERTIFICATE OF COMPLIANCE I, Michael J Teosick , certify that to the best of my knowledge and belief the statements made in this"report are correct and the repair, modification or replacement of the items described above conforms to Section X1 of the ASME Code and to the National Board Inspection Code "NR" rules. National Board Certificate of Authorization No. 33 to use the "NR stamp expires 28 Sept. 20 11 Date 25 April . 20 09 Signed FENOC-PNPP QC Tech. (name of repair organization) (authorized representative) (title) CERTIFICATE OF INSPECTION/INSERVICE INSPECTION 1, Thomas G. Laos holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HSB CT. of Hartford, Conn. have inspected the repair, modification or replacement described in this report on Aftr iŽ* 20 OC and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section Xl of the ASME Code and the National Board Inspection Code "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, conceming the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damag r loss of any kind arising from or connected with this inspection. Date ~20~9..41Sgne Commissions NB 9330 "N" "I""A Ohio Comm. (inspector) *(National Board and (include endorsements), jurisdiction, and no.)

REPORT NO. P0059-012 131

Ooýi REPORT NO. P0059-012

                                                                                                                   /,?3 3    -      13 2 NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As required by the Provisions of the ASME Code Section XI PNPP No. 9305 Rev. 9/111/00                                                                                                 NQI-1741
1. Owner: FIRSTENERGY CORP. Date 4-25-9 10 Center Road. Perry, Ohio 44081 Sheet 1 of 2
2. Plant. Perry Nuclear Power Plant (PNPP) Unit 1 10 Center Road. Perry, Ohio 44081 200284502 (RepairOrg. P.O. No., etl.)
3. Work Performed By: FIRST.NERGY Nuclear Operating Company PNPP Type Code Symbol Stamp NR in Center Roeri Perry. Chin 44n81 Autbojrizati.onjNlo.. 33 .... r--

I *----.-..-.-.-.- Expiration Date 09/28/2011

4. Identification of System: REACTOR RECIRCULATION 1B33
5. (a) Applicable Construction Code: ASME Section III Class 1 1974 Edition NAME/SECTION/DIVISION/CLASS WINTER 19 75 Addenda Code Case(s) 272, 1728. 1644-4 (b) Construction Code used for repairs, modifications, or replacements: 1974 W 1975 none Edition Addenda Code Case(s)

(c ) ASME Code Section XI applicable for Inservice Inspection: 1989 none none Edition Addenda Code Case(s) (d) Applicable Edition of Section XI Utilized for Repairs, Modification, or Replacements: 1989 . 19 none Addenda none Code Case(s) (e) Design Responsibilities -FIRSTENERGY CORP.

6. Identification of Components Repaired, Modified, or Replacement Components Name of Name of Manufacturer Nat. Other Year .1 Repair, ASME I 1 I Component Manufacturer Serial No. Board ID. Built Replacement, Code INo. or Modification Stamped.

PIPING GE 1B33 64076 N/A 1985 Replacement YES SYSTEM

7. Description of Work: REPLACED SNUBBER SIN 006 WITH SNUBBER S/N 059.

PLANT ID IB33G7070A.

8. Test Conducted: Hydrostatic- El Pneumatic- El Nominal Operating Pressure- F] Other- U Pressure NIA psi Test Temperature N/A degrees F Code Case(s) N/A 132

NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back) PNP No. 9308 Rev. 9/11/00 NQI-1741

9. Remarks:

NO NAMEPLATE/STAMPING PERFORMED DUE TO THE INTERFACE CONTROLS OF PART 3 SECTION 1.8.6 BEING IN EFFECT AND JURISDICTIinNAI A[JTHnRITY CONCJI RRFNCF HAVING RFFN RF=CFIVFD -ýi -1______________ I-Note: Attach all applicable Manufacturer's Data Reports. Supplemental sheets such as lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 of this

      /      report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded on the front of this form.

CERTIFICATE OF COMPLIANCE I, Michael J Teosick , certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and to the National Board Inspection Code "NR" rules. National Board Certificate of Authorization No. 33 to use the "NR stamp expires 28 Sept. , 20 11 Date 25 Auril 20 09 Signed FENOC-PNPP Q.C Tech. (name of repairorganization) (a6thorizedrepresentative) (title) CERTIFICATE OF INSPECTION/INSERVICE INSPECTION I, Thomas G. Laps ,holding a valid commission issued by The National Board of Boiler and Preswure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HSB CT. of Hartford, Conn. have inspected the repair, modification or replacement described in this report on l 20 91_ and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from or connected with this inspection. Date 20 Signed *, ~ "4 (insetr - Commissions NB 9330 "N" "I""A" Ohio Comm. (inspecto) kA (National Board (include endorsements), andjurisdiction, and no.)

REPORT NO. P0059-012 &ld -7191-1 133

REPORT NO. P0059-012

                                                                                                 .'1
                                                                                                   / 33.-/13'3 NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As required by the Provisions of the ASME Code Section XI PNPP No. 9308 Rev. 9/1,1100                                                                                          NQI-1741
1. Owner FIRSTENERGY CORP. Date 6-3-9 10 Center Road. Perry. Ohio 44081 Sheet i of 2
2. Plant: Perry Nuclear Power Plant (PNPP) Unit 1 10 Center Road. Perry. Ohio 44081 200005700
                                                                                              '(Repair Org. P.O. No., etc.)
3. Work Performed By: FIRSTENERGY Nuclear Doeratino Comoany PNPP Type Code Symbol Stamp NR 10 Center Road. Perry, Ohio 44081 Authorization No. 33 Expiration Date 09/28/2011
4. Identification of System: REACTOR RECIRCULATION 1 B33
5. (a) Applicable Construction Code: ASME Section III Class 1 1974 Edition NAMEISECTION/DIVISION/CLASS NONE 19 __ Addenda Code Case(s) 1567. 1516-1. 1637 (b) Construction Code used for repairs, modifications, or replacements: 1974 none none Edition Addenda Code Casels)

(c) ASME Code Section XI applicable for Inservice Inspection: 1989 none none Edition Addenda Code Cesels) (d) Applicable Edition of Section X1 Utilized for Repairs, Modification, or Replacements: 19 89 19 none Addenda none Code Case(s) (e) Desigp Responsibilities FIRSTENERGY CORP.

6. Identification of Components. Repaired, Modified,. or Replacement Components Name'of Name of Manufacturer Net 1 Other YIear Built Repair, Replacement, ASME Code Component Manufacturer Serial No. Board ID.

10No. I I or Modification Stamped VALVE ANCHOR E-602_D-2-3 N/A 133 ment DARLING F0067B

7. Description of Work: REBUILT VALVE USING 3 NEW BODY TO BONNET STUDS AND NUTS.

1.75"-8 STUDS HT # 47024 AND 1.7F"-8 HH NUTS HT # R608.

8. Test Conducted: Hydrostatic- ED Pneumatic-, Nominal Operating Pressure- 0 Other- E]

Pressure 1025 psi Test Temperature 123 degrees F Code Case(s)- N/A 134

NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back) PNPP No. 9308 Rev. 9/11/00 NW1-1741

9. Remarks:

NO NAMEPLATEJSTAMPING PERFORMED DUE TO THE INTERFACE CONTROLS OF PART 3 SECTION 1.8.6 BEING IN EFFECT AND JURISDICTIONAL AUTHORITY CONCURRENCE HAVING BEEN RECEIVED. Note: Attach all applicable Manufacturer's Data Reports. Supplemental sheets such as lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x I1 in., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded on the front of this form. CERTIFICATE OF COMPLIANCE 1, Michael J Teosick certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and to the National Board Inspection Code "NR' rules. National Board Certificate of Authorization No. 33 to use the "NR stamp aeXires 28 Seot. 20 11 Oat3 JUNE 20 09 Signed FENOC-PNPP DC Tech. (name of repair organization) (authorzed representative) (title) CERTIFICATE OF INSPECTIOWINSERVICE INSPECTION I, Thomas G. Laos holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors and certificate orcompetency issued by the jurisdiction of OHIO and employed by HSB CT. of Hartford, Conn. have inspected the repair, modification or replacement described in this report on 5 JUNE 20 09 and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code 'NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, conceming the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from or connected with this inspection. Date 20 20* Signed " 4, Commissions NB 9330 "N" "I""*A" Ohio Comm. (inspector) t (National Board rinclude endorsements), andjur*sdiction, and no.)

REPORT NO. P0059-012 "REVISED C0P..

                                                                                                                                     /I333 -/33 FORM SPY-! MANUFACTURERS' DATA REPORT FOR NUCLEAR. PUMPS OR YALYES
                                            ,-.s Requimd 6y the Prcýisiors of                       the A4-2E Code Rules Anchor/Darl ing Valve Company L Yo.znu=vurtd          ,b     701 First St.. Williamrsoort. P3.                                            17701                    o~d=- Nc.         E-6020 General Electric Company
2. fo~zr~d cr 175 Curtner Ave.. San Jose. Calif. 95125 .Order No. 2O5-AGA42 4

C1 o=o ood Ad~rooo) C*.n. ueend lIectric IuIuminating UTomanv 4- Locaionof poo_ North Perry, Ohio Pump r V1o 1i co.... E-6020-2-3 2 4 x20x24" Recirc. Gate Valve (Sd(Oori fp' o.*;=m of* oorioom fo*r o*hioi o il~mooiL woo droicoodfJ D--,=g N. "94-13862 Rev, F Prepa--d by Anchor/Darling Valve Co. (b) N rioal Bo*-d No- _._. .. .. S. Design Condiio, s 1650 psi 575 _ °F

7. lbe ooocrio, dosoio ponsrwcoroc, ý.od work=mship compD', = wic4 A.SME Code Sicdon II. Cloos Edicioo 1974 ddeeda Addnd D.ce D.-- N/A ceo 1567, 1516-1, 1637 (C) C-xci*p
                               -  M~,-k No.                         -i    Motoriol Sp~. No.           [                f~oooro~         I              Rooo~

Body Ht. F701, !S.04 N2118 SA351-CFBM D Ouaker *-lo " Bonnet Ht. F6700, S/N N188 SA351-CF8M I Quaker Allov __ i 1 Discs Ht. F6919, S/N N2251 SA351-CF3A QIuaker Alloy _ Ht. F691'9, S/N aý1.27 _______ _________I_________ (b) Foroings ______________________ ___________I _____________ _______________ _______________________________________________________________________ I _____________________________________________________________________________________________I ______________________________________ 135

FOlPEd iqpV-l (back) Mark Na. S'-r No. I ?AeoW1 t- I?--I (z) Body/BonnE t Stud I S-A10 1 P,7 1 D~:c r Bodv/Bonnet Nut __________ Vi tr-r _____________Ing. Nt 8067384 _______ ________ _____ ____ (d) Other Pncrcs L. 4 2*K* Drain Pioe. HT.#0D973 CaDDoraaZon Drain_ _ _ SA4/9-3lb l1il)eaheny Ludlun, ILteel e- Bypass Pipe, HT.#1B616 SA479-316L . llegheny Ludlum $teel Corporation II I Vent Pipe, T.#00973 SA479-316 4llegheny Ludlum ýteel Corporation _ __ _ _ _ _ _ _ I I1 _ _ _ _ _ _ _ _ _ _ _ _ _ _ I _ _ _ _ _ _ _ _ B. HyMS-Ci test3638 Di CERTIFICATION OF DESIGN Design irmo. file .,lGFn5 I -Erlttric [n 1 7S rr+n.- bvy. Sat . r. 5-stress

  • analysis .. or file a Anchor/Darling Valve Co Wi1li arn nrft Pp 177n1i Design specifications ccrtifid c .. "Has s anal i Ta fa rrodi (1)Pro'. E*-. State CA I J f R:g. N*o, St...ss ... ysis rorr cr.r.fied by Gener ico M. Simeon (1) Prof.--a.scae .C. Pa . o.;?,4. 4f-E (I) Signatmre nor renoired. List name only.

We certify chat the statrements caadt in thi.s report orc courrec. D ace

  • 19 I 6o si--d Anchor/Darl i ng Valve Cosry , *(:

R. L. Houseknecht Czrrific-re of Authorizz-ion No. N779 ==ppirc 3-4-77 CERTIFICATE OF SHOP INSPECTION 1, the undersigned, holding a ralid commission issued by the Nztirmzl Bord of Boier and Pressure Vessel Inspectors and/Uchc State of ZXY_*Y Pennsylvania and employed b CuTforeCial Union intzranr= f0. 0_ Boston, Mass. have inspected the equipm=t described in chis Data Report onL-/8-7Sb MA q 197( .o sod strarr Ehat to the best of my knoowledge and belief, the Marrufecrurr ha. onstrUTed tlis equipment in acccardace with rthe applicable Subsections of ASME Cede. Sccrion.il. By si'ning this certificate, neither the lnspeztor not his employer makes any warranry, c=presscd or implied, concern-ing the equipment* described i*n his Daca KR.m Furtcherore, uaeih= the Inspector.not his employer shall be Li'ble in aoy

    .manner for any personal injury or property canuago or a loss of soy kind ariising from or connccted %tith thais inspection.

Dare 97C, K r.....,..:...Pennsylvania WC972 (Naro.UoI B-de, St-t, Prei-e -od No.) Russel 1m - PlrL.dt: L-nU.S.A, (7/71) Pt n /This form (E.37) ia abtr.nable from the ASftE:, 345 Z. 4 tth St., New York, N.Y. lOOt7

REPORT NO. P0059-012

                                                                                                    !B33-134 NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As required by the Provisions of the ASME Code Section XI PNPP No. 9308 Rev. 9/11100                                                                                          NDI-1741
1. Owner: FIRSTENERGY CORP. Date 6/22/09 10 Center Road. Perrv, Ohio 44081 Sheet 1 of 1
2. Plant: Perry Ntuclear Power Plant (PNPP) Unit one 10 Center Road, Perry, Ohio 44081 ORDER 200299722 (Repair Org. P.O. No., etc.)
3. Work Performed By: FIRSTENERGY Nuclear ODeratino Comoanv PNPP Type Code Symbol Stamp NR 10 Center Roadn Perry Ohio 44081 Authorization No. 33 Expiration Date 09/28/2011_
4. Identification of System: 1B33 REACTOR RECIRC. SYSTEM
5. (a) Applicable Construction Code: ASME SECTION III NB ce4gsc / ,1971 1 Edition
                                            . NAMEISECTION/DIVISION/CLASS     T-. "-,I-Z/Dii SUMMER           19 73       Addenda       Code Case(s) N-272. .N-242, N-413, 1644-56, 1728 (b) Construction Code used for repairs, modifications; or replacements:       1974             winter 75       see abov Edition      Addenda        Code Case(s)

(c) ASME Code Section XI applicable for Inservice Inspection: 1889 no n/a Edition Addenda Code Case(s) (d) Applicable Edition of Section XI Utilized for Repairs, Modification, or Replacements:, 19 89, n/a 19 n/a Addenda n/a Code Case(t) (e) Design Responsibilities First Enerqy Nuclear Operating Comoany PNPP

6. Identification of Components Repaired, Modified, or Replacement Components Name of . Name of Manufacturer Nat. Other Year Repair, ASME -

Component Manufacturer Serial No. Board ID. Built Replacement, Code No. or Modification Stamped PIPING PULLMAN 1B33 119 NA 1985 REPLACEMENT YES SYSTEM POWER

7. Description of Work: REPLACED 11 NEW 1-1/8-8 SUTDS HT. CODE "2G77', AND 31 NEW 1-1/8 NUTS (23-HT CODE 'Z149". AND 8-HT CODE "TRS') DURING CHEM DECON OF REACTOR RECIRCULATION B-33 SYSTEM.
8. Test Conducted: Hydrostatic- E] -Pneumatic- E] Nominal Operating Pressure- Z Other- E0 Pressure 1025 psi Test Temperature 123 degrees F Code Case(s) N/A 136

NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back) PNPP No. 930 .Rev. 9111/00 N01-1741

9. Remarks:

NO NAMEPLATE/STAMPING PERFORMED DUE TO THE INTERFACE CONTROLS OF RA-2370 BEING IN EFFECT AND JURISDICTIONAL AUTHORITY CONCURRENCE HAVING BEEN RECEIVED. Note: Attach all applicable Manufacturer's Data Reports. Supplemental sheets such as lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is reoorded on the front of this form. CERTIFICATE OF COMPLIANCE I, John W. Messenoer . certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification or replacement'of the items described above conforms to Section XI of the ASME Code and to the National Board Inspection Code "NR" rules: National Board Certificate of Authorization No. 33 to use the "NR.stamp expires 9/28 . 2011 Date 6123/ 20 09 Signed FENOC-PNPP . QE (name of repair organization) -authorized representative) (title) CERTIFICATE OF INSPECTION/INSERVICE INSPECTION I, Thomas' Laos -holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors' and certificate of competency issued by the jurisdiction of OHIO and employed by HST CT. OF HARTFORD CONN. have inspected the repair, modification or replacement described in this report on.3,,19 24-ý 20 69 and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the wvork described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from or connected with this inspection. Date A. a, 20 _. Signed- Commissions NB 9330 "N "I' "A" OHIO COMM. lenspector" (3 (NationalBoard (include endorsements), andjurisdiction, and no.)

REPORT NO. P0059-012 iB33-135 NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As requi red by the Provisions of the ASME Code Section X! PNPP No. 9308 Rev. 9/11/00 NQ1-17A1

1. Owner: FIRSTENERGY CORP. Date 6/24/09 10 Center Road. Perry, Ohio 4-4081 Sheet 1 of 2
2. Plant: Perry Nuclear Power Plant (PNPP) Unit one 10 Center Road. Perrvy Ohio 44081 ORDER 200282000 R/O A-2 (Repair Org. P.O. No., etc.)
3. Work Performed By: FIRSTENERGY Nuclear Doerating Comoany PNPP Type Code Symbol Stamp NR 10 Center Road. Perry, Ohio 44081 Authorization No. 33 Expiration Date 09/28/2011_
4. Identification of System: 1833 REACTOR RECIRC. SYSTEM
5. (a) Applicable Construction Code: ASME SECTION III NB CL,.' / .1971 Edition NAME/SECTION/DIVISION/CLASS L. 4-9 19 73 Addenda Code Case(s) N/AA SUMMER (b) Construction Code used for repairs, modifications, or replacements: 1974 winter 75 see abov Edition Addenda Code Case(s)

(c) ASME Code Section XI applicable for Inservice Inspection: 1889 no n/a Edition Addenda Code Case(s) (d) Applicable Edition of Section X1 Utilized for Repairs, Modification, or Replacements: 1989, n/a 19 n/a Addenda n/a Code Case(s) (e) Design Responsibilities First Energy Nuclear Operating Comoany PNPP

6. Identificabon of Components Repaired, Modified, or Replacement Components Name of Name of Manufacturer Nat. Other Year Repair, ASME Component Manufactureri Serial No. Board ID. Built Replacement, Code No. or Modification Stamped PUMP Byron Jackson 741-S-1280 N/A 1833 REPLACEMENT YES CO01B i+
7. Description of Work: REPLACED SEAL CARTRIDGE ASSEMBLY SIN 313456 WITH NEW ASSEMBLY SIN S/N 318454
8. Test Conducted: Hydrostatic- [3 Pneumatic- E] Nominal Operating Pressure- Other- [D Pressure 975 psi Test Temperature 160 degrees F Code Case(s) N/A 137

NIS-2[NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back) PNPP Ncs. 9308 Rev. 9/11/00 N01-1741 9- Remarks: NO NAMEPLATE/STAMPING PERFORMED DUE TO THE INTERFACE CONTROLS OF RA-2370 BEING IN EFFECT AND JURISDICTIONAL AUTHORITY CONCURRENCE HAVING BEEN RECEIVED. Note: Attach all applicable Manufacturer's Data Reports. Supplemental sheets such as lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded on the front of this form. CERTIFICATE OF COMPLIANCE I, John W. Messenoer , certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and to the National Board Inspection Code "NR" rules. National Board Certificate of Authorization No. 33 to use the "NR stamp expires 9/28 . 2011_ Date 6/231 20 09 Signed FENOC-PNPP ./ DE OE.L2.,n-4.. (name of repairorganization)( ,uhorized refpresentative) (title) CERTIFICATE OF INSPECTION/INSERVICE INSPECTION I, Thomas Laos holding a valid commission issued by The National Board of Boiler and certificate of competency issued by the jurisdiction of QHI0 Pressure Vessqf Inspectors and and employed by HST CT. OF HARTFORD CONN. have inspected the repair, modification or replacement described in this report on 3,jt__7, 20D(- and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code "NR' rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damag, or loss of any kind arising from or connected with this inspection. Date .__A , 20 O Signed n e d-/- Commissions NB 9330 "N" "I""A" OHIO COMM. (inspeci~or)l. (National Board (include endorsements), and juf*isdiCtion, and nlo.)

REPORT NO. P0059-012 FORM N-2 CERTIFICATE HOLDERS' DATA REPORT FOR IDENTICAL NUCLEAR PARTS AND" APPURTENANCES' rm~Ž\,>LT 7L2 As Required by the Provisior.s of the ASME Code, Section [It Not to Exceed O-ne Day's Production

         -.. reatsur-d end ce-rt ified b~y3-2'                                   DI         V---OU7Z                ry~S230~t~~A~,~HZIJ_                             --nsxt     Ci.9Ck amaeor TEEP          i0.iOEE~T                U
                                                                    =XCiCLNt20iL              O                OA              -OTO£5S       4 2.L--<-etion of bnstlaltie t~ZE           R~~R~?iFL7                          1     -.0                      M-       PP mni3Ea    1,             P1f2J2 , 0C)=,       ý0444 EQWD21GS             -Z4        &&.-192 CGt.7316                75,f=0 tSItA                                                          19 6CH,   Cods, 1:

saOOIa (nddWnd. ZEZ.57 Corno

2. er'tae
                       -i to-az          with Caest. Spec. (0) v. 2 only)             '-               Revisidn-           PTYR           . Date                Kf-k
7. 42. 33N: RDt d4I~~2:1-7500 L524 SET1 C&MMIDG -ASsLT-DEý>-GSý F'WfCA0F WLMa~ M MAauwaq TK va 193 EDJTB04C Sum 1954 AM0E2A..

S. =t -doAhzznssýin G.I2 Min. design thicizness rn-) 2.202 Dia. ID (ft & l't. V 7-00'Uegth overal ft& in.) 0' 3-105' S te pPcabIle, Cam-eflcate Ho$lders' Data Reports are artachad for eac~hitem of tsts repo=c

  • ign. pressure 1.50 pet. Temp. 575 'F. Hydra. test pressure 205" Io~e 1 60, I PSIsv*n*pptr_.ablo) at temp. *F Supplcm*ntal infomation in tte form of its, lketcht.h ,or drawings may bý t.sd prlvded '(I) sire is BY. x I I. (2) information in items 2 and 3 on thKs Dat, Fport

.ilrdr-d on ,ach (3) ea-h sheet e; numbered and the number of sheets is recorded at the top of this fom.. Che-t. 455)8} ThWs form (EO0040) may be obtained from the Order Dept., ASMhf_. 22 Law Dnrie, Boo 2300. Fair) eld, NJ'07007-2300-Reprint (7/31) 138

FORMN-21 (Back- Pg. 2of 2 C.eitiffizate Holder's S--rial NHa. thro.gh CZERTIICA.*-'O, OF DESIGN rf---~ sti3nrs Cerifed by N-/-A " _ _ P.F State V A. Reg. non. 0.--- i:3 cart! frsd by_ . Kil. P.E. s-ate N/A Reg- no. N-,/A CERTIFICATE OF COMPLIANCE We cer-fy that the, statements made in this report are co-rrect and that this ,hcee- -- 7503 S.L CSKDGE .SS ." c*.icomina'Lo the rules of =rtstruction of the ASME Code, Section It, Divisýon 1. fIPT C-ea*t-icate of A ',iZation No. E-x31 JlEpires!Or j - NPr C-r C*aif~ F I-kJ4* . -L,. " 4 CE-RTIFICATE OF INSPECTION the t dgn.d, hoklirig a valid commission issued by the N'tional Board of Boiler and Pressure Vessel Inrspectors and the State or. Provin-e of FCOM& CA and employed by "UG9NNI -Pl flE-I;LXNE OD- IrTRY IEtTIJL DrtI mm7 AssEC ha"e krep-cted these Items de-scibe-d in this Data Rep'r oD?'/ and sastat h bCst of Wyko*wledge arnd belief, the Certificate Holder has fabricated these parts or appurtenances in accordance with the ASMAE Code, Sectio 54 Division 1. Each part Ested has been authorized for stamping on the data shown above.' e-Y - T ths certific , neither the l nor his employer makes any warranty, e-prsse-d or Implied, concernmi3 the equipm-nt desrTbed

                                                       -spector
-t         D&tt Report Fu             o,          thrt       pector, nor h= employer *h*all be liable in any manner for any personal InJury or pMperty dama9ge or I:os- Of csiy t~d: arisin-g frosmor conneccted v.ith this inapectiors.
                   ~e        SD       E!  t
                                              ~                                                            Commissionsa        I-1F
                                                         .- Aglo-ed       I4ror~                                             NLS. el  n      eeo    e         p-. -,~d-a.

REPORT NO. P0059-012

                                                                                                            /CI/           -037 NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As required by the Provisions of the ASME Code Section XI PNPP No. 9308 Rev- 9/11100                                                                                         N01-1741
1. Owner FIRSTENERGY CORP. Date 5-22-9 10 Center Road. Perry. Ohio 44081 Sheet 1 of 2
2. Plant: Perry Nuclear Power Plant (PNPP) Unit 1 10 Center Road. Perry. Ohio 44081 200297167 & 200358886 (RepairOrg. P.O. No., etc.)
3. Work Performed By: FIRSTENERGY Nuclear ODeratinq Company PNPP Type Code Symbol Stamp NR 10 Center Road, Perry, Ohio 44081 Authorization No. 33 Expiration Date 09/28/2011
4. Identification of System: STANDBY LIQUID CONTROL 1C41
5. (a) Applicable Construction Code: ASME Section Ill Class 2 1974 Editio n NAME/S ECTIONIDIVISIONICLASS WINTER 19 75 Addenda Code Case(s) N272. N240. N242, N413. 1644-5, 1644-8 (b) Construction Code used for repairs, modifications, or replacements: 1974 W 1975 none Edition Addenda Code Case(s)

(c) ASME Code Section XI applicable for Inservice Inspection: 1989 none none Edition Addenda Code Case(s) (d) Applicable Edition-of Section X1 Utilized for Repairs, Modification, or Replacements: 19 89_____ 19 none Addenda none Code Case(s) (e) Design Responsibilities FIRSTENERGY CORP.

6. Identification of Components Repaired, Modified, or Replacement Components Name of Name of Manufacturer Nat. Other Year Repair, ASME Component Manufacturer Serial No. Board ID. Built Replacement, Code No. or Modification Stamped PIPING PULLMAN 1C41 108 1C.41F29A 1985 Replacement YES SYSTEM POWER
7. Description of Work: REPLACED VALVE S/N B WITH VALVE S/N 2.

5FF RFMARKS RPE REMARKS

8. Test Conducted: Hydrostatic- E] Pneumatic- El Nominal Operating Pressure- N Other- E]

Pressure 1250 psi Test Temperature 90 degrees F Code Case(s) N-416-3 139

NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back) PNPP No. 9308 Rev. 9/11/00 NQI-1741

9. Remarks: REPLACED PIPING USING 1.5" FLANGE HT# BXU. AND 1.5" SCH 40 PIPE HT# 466565.

ADJUSTED HANGER 1.C41-H0!8 BY REMOVING FW-3 AND CUTTING THE 2X2 TUBE STEEL AND REWELDING FW-3. USED WELDING ROD ER316L HT# CT5953 &'DT5953 AND ER70S-2 HT# 065905 & CP780B NO NAMEPLATE/STAMPING PERFORMED DUE TO THE INTERFACE CONTROLS OF PART 3 SECTION 1.8.6 BEING IN EFFECT AND JURISDICTIONAL AUTHORITY CONCURRENCE HAVING BEEN RECEIVED. Note: Attach all applicable Manufacturer's Data Reports. Supplemental sheets such as lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded on the front of this form. CERTIFICATE OF COMPLIANCE I, Michael J Teosick , certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and to the National Board Inspection Code "NR' rules. National Board Certificate of Authorization No. 33 to use the "NR stamp expires 28 Sept. 20 11 Date 22 20 09 Si ned FENOC-PNPP oC Tech. (name of repairorganization) (authoriiedreprese tative) (title) CERTIFICATE OF INSPECTIDN(INSERVICE INSPECTION I, Thomas G. Laos holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HSB CT. of Hartford, Conn. have inspected the repair, modification or replacement described in this report on M 20 C0` and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code "NR' rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from or connected with this inspection. Date d 7 , -20 Signed Z in t Commissions NB 9330 "N" "I""A Ohio Comm. (inspect4 " (National Board (include endorsements), and jurisdictiono and no.)

REPORT NO. P0059-012

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REPORT NO. P0059-012 NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As required by the Provisions of the ASME Code Section X1 PNPP No. 9308 Rev- 9/11/00 NOI-1741

1. Owner: FIRSTENERGY CORP. Date 4-30-9 10 Center Road, Perry, Ohio 44081 Sheet 1 of 2
2. Plant: Perry Nuclear Power Plant (PNPP) Unit 1 10 Center Road. Perry, Ohio 44081 200261645 (RepairOrg. P.O. No., etc.)
3. Work Performed By: FIRSTENERGY Nuclear Operating Company PNPP Type Code Symbol Stamp NR In flent~r Rnrvtr Prrr-v ~hin 440R1 Authorization No. 33 In.. ...... Roa.. Perry Ohi Expiration Date 09/28/2011
4. Identification of System: RESIDUAL HEAT REMOVAL 1E12
5. (a) Applicable Construction Code: ASME Section III Class 2 1974 Edition NAM E/SECTION/DIVISION/CLASS WINTER 19 75 Addenda Code Case(s) N272, 1644-5 (b) Construction Code used for repairs, modifications, or replacements: 1974 W 1975 none Edition Addenda Code Case(s)

(c) ASME Code Section XI applicable for Inservice Inspection: 1989 none none Edition Addenda Code Case(s) (d) Applicable Edition of Section X1 Utilized for Repairs, Modification, or Replacements: 1989.__ 19 none Addenda none Code Case(s) (e) Design Responsibilities FIJSTENERGY CORP.

6. Identification of Components Repaired, Modified, or Replacement Components Name of Name of Manufacturer Nat. Other Year Repair, ASME Component Manufacturer Serial No. Board ID. Built Replacement, Code No. or Modification . Stamped PIPING PULLMAN 1E12 83 N/A 1984 Replacement YES SYSTEM POWER
7. Description of Work: REPLACED VALVE S/N 1-52969-B WITH VALVE S/N 1-51906-A.

PLANT ID 1E12FOO63C.

8. Test Conducted: Hydrostatic- E] Pneumatic- D] Nominal Operating Pressure- [] Other- LI Pressure 165 psi Test Temperature N.O.T degrees F Code Case(s) N/A 141

NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back) PNPP No. 9308 Rev. 9111/00 NQI-1741

9. Remarks:

NO NAMEPLATE/STAMPING PERFORMED DUE TO THE INTERFACE CONTROIS OF PART 3 SFCTION 1.8.6 BEING IN EFFECT AND JURISDICTIONAL AUTHORITY CONCURRENCE HAVING BEEN RECEIVED. Note: Attach all applicable Manufacturer's Data Reports. Supplemental sheets such as lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded on the front of this form. CERTIFICATE OF COMPLIANCE I, Michael J Tepsick , certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and to the National Board Inspection Code "NR* rules. National Board Certificate of Authorization No. 33 to use the "NR stamp expires 28 Sept. , 20 11 Date 30 April , 20 099 Signed FENOC-PNPP . 4/ ' ./ O Tech. QC (name of repairorganization) fauthori'ed representative) (title) CERTIFICATE OF INSPECTION/INSERVICE INSPECTION I, Thomas G. Laps ,holding a valid c6mmission issued by The National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HSB CT. of Hartford, Conn. have inspected the repair, modification or replacement described in this report on 30 April . 20 09 and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from or connected with this inspection. Date 30 Apri, 20 09 Signed ,cz A Commissions NB 9330 'N" "I""A" Ohio Comm. finspector)'~l (National Board (include endorsements), and jurisdiction, and no.)

REPORT NO. P0059-012

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REPORT NO. P0059-012 NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As required by the Provisions of the ASME Code Section XI PNPP No. 9308 Rev. 9/11/00 NQI-1741

1. Owner: FIRSTENERGY CORP. Date 4-30-9 10 Center Road, Perry. Ohio 44081 Sheet 1 of 1
2. Plant: Perry Nuclear Power Plant (PNPP) Unit 1 10 Center Road. Perry. Ohio 44081 200365780 (RepairOrg. P.O. No., etc.)
3. Work Performed By: FIRSTENERGY Nuclear Operating Company PNPP Type Code Symbol Stamp NR 10 Center Road, Perry, Ohio 44081 Authorization No. 33 Expiration Date 09/28/2011
4. Identification of System: RESIDUAL HEAT REMOVAL 1E12
5. (a) Applicable Construction Code: ASME Section III Class 2 ,1974 Edition NAM E/SECTION/DIVISION/CLASS WINTER 19 75 Addenda Code Case(s) N272, N242, N413 (b) Construction Code used for repairs, modifications, or replacements: 1974 W 1975 none Edition Addenda Code Case(s)

(c) ASME Code Section XI applicable for Inservice Inspection: 1989 none hone Edition Addenda Code Case(s) (d) Applicable Edition of Section XI Utilized for Repairs, Modification, or Replacements: 198 __ 19 none Addenda none Code Case(s) (e) Design Responsibilities FIRSTENERGY CORP.

6. Identification of Components Repaired, Modified, or Replacement Components Name of Name of Manufacturer Nat. Other Year Repair, ASME Component Manufacturer Serial No. Board ID. Built Replacement, Code No. or Modification Stamped PIPING PULLMAN 1E12 NA N/A 1985 Replacement YES SYSTEM POWER 7 Description of Work: MODIFIED SUPPORT PER ECP 09-246 BY MOVING TUBE STEEL TO A NEW.

ELEVATION AND REWELDING USING E7018 WELD ROD HT# 159443. PLANT ID 1E12HO588.

8. Test Conducted: Hydrostatic- [] Pneumatic- D Nominal Operating Pressure- El Other- El Pressure N/A psi Test Temperature N/A degrees F Code Case(s) N/A 143

NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back) PNPP No. 9308 Rev. 9/11/00 NQI-1741

9. Remarks:

NO NAMEPLATE/STAMPING PERFORMED DUE TO THE INTERFACE CONTROLS OF PART 3 SECTION 1.8.6 BEING IN EFFECT AND JURISDICTIONAL AUTHORITY CONCURRENCE HAVING BEEN RECEIVED. Note: Attach all applicable Manufacturer's Data Reports. Supplemental. sheets such as lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded on the front of this form. CERTIFICATE OF COMPLIANCE I, Michael J Tepsick certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and to the National Board Inspection Code "NR" rules. National Board Certificate of Authorization No. 33 to use the "NR stamp expires 28 Sept. , 20 11 Date 30 April , 20 09 Signed FENOC-PNPP O-'-'.OC Tech. (name of repairorganization) (authoatzedrepresentative) (title) CERTIFICATE OF INSPECTION/INSERVICE INSPECTION I, Thomas G. Laps ,holding a valid commisgion issued by The National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HSB CT. of Hartford, Conn. have inspected the repair, modification or replacement described in this report on 30 April . 20 09 and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from or connected with this inspection. Date 30 Aoril ,20 09 Signed ~Commissions NB 9330 "NW"1"'A" Ohio Comm. (inspecfor I(National Board (include endorsements), and jurisdiction,and no.)

REPORT NO. P0059-012 NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As required by the Provisions of the ASME Code Section XI PNPP No. 9308 Rev. 9/11/00 N01-1741

1. Owner FIRSTENERGY CORP. Date 5-4-9 10 Center Road, Perry, Ohio 44081 Sheet 1 of 2
2. Plant Perry Nuclear Power Plant (PNPP) Unit 1 10 Center Road, Perry, Ohio 44081 200261986 (RepairOrg. P.O. No., etc.)
3. Work Performed By: FIRSTENERGY Nuclear Operating Comoanv PNPP Type Code Symbol Stamp NR 10 Center Road. Perry. Ohio 44081 Authorization No. 33 Expiration Date 09/28/2011
4. Identification of System: RESIDUAL HEAT REMOVAL 1E12
5. (a) Applicable Construction Code: ASME Section III Class 2 1974 Edition NAME/SECTIoN!DIVIs)ONICLAsS WINTER 19 75 Addenda Code Case(s) N272, 1644-5 (b) Construction Code used for repairs, modifications, or replacements: 1974 W 1975 none Edition Addenda Code Case(s)

(c) ASME Code Section XI applicable for.Inservice Inspection: 1989 none none Edition

  • Addenda Code Case(s)

(d) Applicable Edition of Section XI Utilized for Repairs, Modification, or Replacements: 19 89.., 19 none Addenda none Code Case(s) (e) Design Responsibilities FIRSTENERGY CORP.

6. Identification of Components Repaired, Modified, or Replacement Components Name of Name of Manufacturer Nat. f Other Year Repair, ASME Component Manufacturer Serial No. Board ID. Built Replacement, Code No. or Modification Stamped PIPING PULLMAN 1E12 83 NIA 1984 Replacement YES SYSTEM POWER

__________ ~_____ __________I

7. Description of Work: REPLACED VALVE S/N 2-52969-B WITH VALVE SIN 2-51001-A.

____ 1 I _____ PLANT ID 1E12FOO63B. 8.. Test Conducted:. Hydrostatic- LI Pneumatic- El Nominal Operating Pressure- Z Other- E] Pressure 315 psi Test Temperature N.O.T degrees F . Code Case(s) N/A 144

NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back) PNPP No. 930B Rev. 9111100 . NQI-1741

9. Remarks:

NO NAMEPLATFISTAMPING PERFORMED DUE TO THE INTERFACE CONTROLS OF PART 3 SECTION 1.8-6 BEING IN EFFECT AND JURISDICTIONAL AUTHORITY CONCURRENCE HAVING BEEN RECEIVED. Note: Attach all applicable Manufacturer's Data Reports. Supplemental sheets such as lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded on the front of this form. CERTIFICATE OF COMPLIANCE I, Michael J Teosick _, certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section X1 of the ASME Code and to the National Board Inspection Code "NR' rules. National Board Certificate of Authorization No. 33 to use the 'NR stamp expires 28 Sept. . 20 11 Date 4 MAY 20 09 Signed FENOC-PNPP QC Tech. (name of repairorganization) (authozrzed representave) (title) CERTIFICATE OF INSPECTIONIINSERVICE INSPECTION I, Thomas G. Laos holding a valid commission issued by The National Board of Boiler and. Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction, of OHIO and employed by HSB CT. of Hartford Conn. have inspected the repair, modification or replacement described in this report on 30 April . 20 09 and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code "NR rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or I s of any kind arising from or connected with this inspection. Date -,1 20 09 Signed - . ,P--ommissions CM NB 9330"N" 'N ""A" Ohio Comm. finspectoI- (NationalBoard (include endorsements), andjurisdiction,and no.)

R-EPOR-T NO. P0059-012 OR VALVES* DATA REPORT FOR NUCLEAR PUMPS F0O N NP-V-1 CERTIFICATE HOLDERS brythe Proviionis of the ASME Code, Section MI Divsion I As Required

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REPORT NO. P0059-012

                                                                                                 / Fý/2 - 3,!*272 NIS-2!NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As required by the Provisions of the ASME Code Section XI PNPP No. 9308 Roy. 9/11100                                                                                         NQI-1741
1. Owner. FIRSTENERGY CORP. Date 5-4-9 10 Center Road. Perrv, Ohio 44081 Sheet 1 of 2
2. Plant Perry Nuclear Power Plant (PNP40 Unit 1 10 Center Road. Perry, Ohio 44081 200262065 (RepairOrg. P.O. No., etc.)
3. Work Performed By: FIRSTENERGY Nuclear Doerating Comaany PNPP Type Code Symbol Stamp NR 10 Center Road Perrv. Ohio 44081 Authorization No. 33 Expiration Date 09/28/2011
4. Identification of System: RESIDUAL HEAT REMOVAL 1E12
5. (a) Applicable Construction Code: ASME Section III Class 2 1974 Edition NAME/SECTION/DIVISION/CLASS WINTER 19 75 Addenda Code Case(s) N272. 1644-5 (b) Construction Code used for repairs, modifications, or replacements: 1974 W 1975 none Edition Addenda Code Case(s)
  *(c) ASME Code Section XI applicable for Inservice Inspection:                1989             none            none Edition      Addenda        Code Case(s)

(d) Applicable Edition of Section XI Utilized for Repairs, Modification, or Replacements: 1989., 19 none Addenda none Code Case(s) (e) Design Responsibilities FIRSTENERGY CORP-R

6. Identification of Compon~ents Repaired, Modified, or Replacement Components Name of Name of Manufacturer Nat. Other Year Repair, ASME Component Manufacturer Serial No. Board ID. Built Replacement, Code No. I or Modification Stamped PIPING PULLMAN 1E12 83 N/A 1984 Replacement YES SYSTEM POWER
7. Description of Work: REPLACED VALVE S/N 1-52183-A WITH VALVE SIN 3-50079-A.

PLANT ID 1EE12FOO63A.

8. Test Conducted: Hydrostatic- E] Pneumatic- E] Nominal Operating Pressure Other- E:

Pressure 176 psi

  • Test Temperature N.O.T degrees F Code Case(s) NIA 146

NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back) PNPP No. 9308 Rev. 9/11/00 NQI-1741

9. Remarks:

NO NAMEPLATE/STAMPING PERFORMED DUE TO THE INTERFACE CONTROLS OF PART 3 SECTION 1.8.6 BEING IN EFFECT AND JURISDICTIONAL AUTHORITY CONCURRENCE HAVING BEEN RECEIVED. Note: Attach all applicable Manufacturer's Data Reports. Supplemental sheets such as lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded 0 n the front of this form. CERTIFICATE OF COMPLIANCE 1, Michael J Teosick , certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and to the National Board Inspection Code "NR' rules. National Board Certificate of Authorization No. 33 to use the "NR stamp expires 28 Sept. . 20 11 Date 4 MAY 20 09 Signed FENOC-PNPP , ' DC Tech. (name of repair organization) (authoiizedrepresentative) (title) CERTIFICATE OF INSPECTION/INSERVICE INSPECTION I, Thomas G. Laps . holding a valid commission issued by-The.NationalBoard of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHI) and employed by HSB CT. of Hartford Conn. have inspected the repair, modification or replacement described in this report on 30 ADril 20 09 and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from or connected with this inspection. Date 20 09 Signed & Commissions NB 9330 N""I"'A"Ohio Comm. (inspect'r)to (National Board Cinclude endorsements), andjurisdiction,and no.)

REPORT NO. 20059-012 FORM WPV-1 CERTIFICATE HOLDERS DATA REPORT FOR NUCLEAR PUMPS OR VALVES* As Req uirad by the Provisions of the ASME Code, Section III, Division I P . I of 2

1. Marrufa twed and certified by". Arwood &Mt.4o.ca In-9 C~nal,St_ salna MA 01970 (nanleandaid;-~ of N Certilicate Nelder) 2- Manufacturedl or_ Fr-n Einvoy Corvnoio I CenterRd, P.0 Soat9 ND.l* Perry OH 4-4081 (marann andaddrý 0I.Purchasar) 0
3. Loc~ion orinstalltaion Pr-naN-cI.,r eerPb1. 10CenteraRoad OockN., I.-N..In'hP,-nOH 4A051 (nameandaodres)

A. PModJl No,. series No,. or Type Onal ptatn Cherl- Vataner-9507 - Rev. 01 CR0 NA W S. ASIE Code, Secfilon HI,Draneon 1: IS74 Wiaio197S - N/A lCO-nCa.- nj G.POoenp or Vale V21'. No..n-nl inlef size 8 O'tlel size

7. M~aterial Body SAZI5-Va'C3 Bonnet NA OntOi SA't07-Q.ABI.A Bolting N.A Ce Cai . Body B~onnet HleeBoard .Serialt  ;' Senial 50001 No. No. No. No. No.

3-5DO3n9A -7 NIA HT. 00O78 N/A HT. -CBB-40 __________________________ SIN: M162 _______ / :15& 6 7 a..a So~tzppal Woton~ation in Innorrtfr5=seOtOs or drroaonae y ben pnneAeJed I) ~e~ 81M x ¶ (2)ml. nAen hnaa erein Data Rep= is hclaed on ac %fietof(3) e~ht1sem isnnnbseredartS11 nao. of is~ et o i thetvp o: t5ý I lis loran(20007) e-aybeobtoenedInxethneOrerDept ASSA 7t2~ ~L:a Dti.,ox~ =00, Farlii NJ G7=7Z=.X SC-I 147

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a. Cold -or T0. NYdro.=otc te0 tf2 psi. OIst dilererdial 1,,t prm "s psi 11 Rcrný-A-C PiýRetzi, m
                                               . .                 E.RTIFICATlON OFD           IGN                                                          I pefi--apoctan certiheg by    Hivyn1 R Rerptt                              PF.- Stoto R.A.~ Reg-no. 249L reprti~r by                 NJF                           -                    ýE SZOt N?             Reg. no. NIA ID:                                             one~

C-SM7SFICATE OF COb¶FUANCE We oýtdy tr.ai thm slzteonts redc n this repan ore oo:red oandthot PSp or vý)e cenform to the ru to=for Muctkor ot C-o ASMSCode, S ecttr Ill. Diiooo 1. N Ceft=ttof Au0 ý Nio N~Fr Noose It eo~ 14t . . ... toseooo reIO~r~o M.

                            -~        -CE~TIF0CATE                                  OF ImSFE(

conmnrdon boredb eNOx teo BLOoof w this cnV Data RqxiRIt tt Cho te.~ ofJ my Iroledgpo mi~dbe~e( fte Ceotfltoe Hdokirhas modrtutted diii ftes Data oo -Ftrnrwoerw the frmpor pmols ereplopebibS be L0lbte0 anoymannerm for ny pmvonal irpoy orppe~retY l-oeot ry Icdwtvg Ibnor aO mConnected reMthrt M tp~~

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REPORT NO. P0059-012 IE12-308 pg I of 2 NIS-2/NR-1 OWNER'S REPORT FOR REPAiRS OR REPLACEMENTS As required by the Provisions of the ASME Code Section XI PNPP No. 9308 Rev. 9/11/00 NOI-1741

1. Owner: FIRSTENERGY CORP. Date 6/8/2009 10 Center Road. Perry. Ohio 44081 Sheet 1 of 2
2. Plant: Perry Nuclear Power Plant (PNPP) Unit 1 10 Center Road. Perry, Ohio 44081 order 200261987 (RepairOrg. P.O. No., etc.)
3. Work Performed By: FIRSTENERGY Nuclear Operating Comoany PNPP Type Code Symbol Stamp NR 10 Center Road. Perrv. Ohio 44081 Authorization No. 33 Expiration Date 2/28/2011
4. -Identification of System: 1El12 Residual Heat Removal
5. (a) Applicable Construction Code: ASME SECTION III CLASS 1 ,1974 Edition NAME/SECTION/DIVISION/CLASS WINTER 19 75 Addenda Code Case(s) 1644-5. 1728. N-224, N-242. N-272. N-275. N-282.

N-416-1. N-413

 -  (b) Construction Code used for repairs, modifications, or replacements:       1974            W75             N/A Edition       Addenda       Code Case(s)

(c) ASME Code Section Xl applicable for Inservice Inspection: 1989 NONE N/A Edition Addenda Code Case(s) (d) Applicable Edition of Section X1 Utilized for Repairs, Modification, or Replacements: 19 ý N/A 19 N/A Addenda N/A Code Case(s) (e) Design Responsibilities First Energy Coro

6. Identification of Components Repaired, Modified, or Replacement Components Name of Name of Manufacturer Nat. [ Other Year Repair,. ASME Component Manufacturer Serial No. Board ID. Built Replacement, Code No. " . or Modification Stamped Piping Pullman Power 1E12 83 N/A 1985 replacement yes System
7. Description of Work Replaced 6S diameter check valve with new check valve S/N 3-52969-A.
8. Test Conducted: Hydrostatic- El Pneumatic- El Nominal Operating Pressure- Z Other- [

Pressure 161 - psi Test Temperature AMB degrees F Code Case(s) N/A 148

NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back) PNPP No. 9308 Rev. 911110G NQk-1741

9. Remarks: NA NO NAMEPLATE/STAMPING PERFORMED DUE TO THE INTERFACE CONTROLS OF RA-2370 BEING IN EFFECT AND JURISDICTIONAL AUTHORITY CONCURRENCE HAVING BEEN RECEIVED.

Note: Attach all applicable Manufacturer's Data Reports. Supplemental sheets such as lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x II in., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded on the front of this form. CERTIFICATE OF COMPLIANCE I, JOHN W. MESSENGER, certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification'or replacement of the items described above conforms to Section XI of the ASME Code and to the National Board Inspection Code "NR" rules. National Board Certificate of Authorization No. 33 to use the "NR stamp expires 28 Sept. 20 2011 Date 6/8/2009 Signed FENOC-PNPP 6I QC (name of repa'"r anization) (a uthontzed representative) (title) CERTIFICATE OF INSPECTION/INSERVICE INSPECTION I, Thomas G Laps holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HSB CT. of Hartford, Conn. have inspected the repair, modification or replacement described in this report on J r__..- 20 O and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section X1 of the ASME Code and the National Board Inspection Code "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, conceming the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from or connected with this inspection. Oate D,1) Ol Signed t Commissions NB 9330 "N""'l""A" Ohio Comm. t-(spector) I (NationalBoard (include endorsements), and jurisdiction,-andno.)

REPORT NO. P0059-012

                                                                                                              /                            2oF2_

FORM NPV-1 CERTIFICATE HOLDERS DATA REPORT FOR NUCLEAR PUMPS OR VALVES* As Required by the Provisions of the ASME Code, Section III, Division 1 " Pg. 1 of 2

1. Manufactured and certified by: Weir Valves and Controls USA Inc., 285 Canal St-, Salem, MA 01970 (name and address of N Certiicate Holder)
2. Manufactured for First Enerov Corporation, 10 Center Rd., P.O. Box 97, North Perry, OH 44081 (name and address of Purchaser)
3. Location of installtaion Perry Nuclear.Power Plant, 10 Center Road, Dock No. 1. North Perry OH 4-4081 (name and address)
4. Model No., Series No., or Type Dual Plate Check Valve Drawing 11949.01 Rev. 04 CRN N/A S. ASME Code, Section III, Division 1: 1974 Winter 1975 2 NI"A ldiion) naddenda date) lcal) lcoe. c.- e.)

6, Pump or Valve Valve Nominal inlet size 6 Outlet size 6 (in.) (in.)

7. Material: Body SA216-WCB Bonnet N/A Disk SA487-CA6NM Bolting N/A (a) (b) (c) (d) (e)

CerL Nat'l Body Bonnet Disk Holder's Board Serial Serial Serial Serial No. No. No. No. 3-52969--A NIA HT. (/87643 N/A HT. #:87506 RT#: 75244 RT#: 75221 & 757222

  • Supplemental information in form 6f lists, sketches, or drawings may be used provided (1) size5 'Ax 11, (2) inforrmatfori in items 1 through 4 on this Dais Report is included on each sheet, (3) each sheet is numbered and the number of sheets Is recorded at the top of this form (12J88) This form (E00037) may be obtained from the Order DepL, ASME. 22 Law Drive, Box 2300, Fairfield, NJ 07007-2300.

149

FORM NPV-I (Back - Pg. 2 of 2) Certificate Holder' s Serial No. 3-529S9-A

8. Design conditions 740 psi 100 °F orvalve pressure class 300 (1)

(pressure) (temperature)

9. Cold working pressure 740 psi at 1DD°F
10. Hydrostatic test. 1125 psi. Disk differential test pressure B25 psi
11. Remarks: Pin Retainers SA 479-410 HT#: 504420 TR# 151D CERTIFICATION OF DESIGN Design specification cerfified by Hiram R. RepperI P.E. State PA. Reg. no. 24928-E

(.hen appliablel Design report cerlitied by N/A P.E. State N/A Reg. no. NIA (.h.n appfiabl.) CERTIFICATE OF COMPUANCE We certify that the statements made in this report are correct and that pump or valve conforms to the rules for construction of the ASME Code, Section lit, Division 1. N Certific*te nf AutIhriza*fion Non -N-2f6 . , 6-13-07 Date44~~ Name WEIR VALVES & CONTROLS USA INC. ISrtoigedrpeaA IN Cergticale H-older) CERTIFICATE OF INSPECTION

1. the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Massachusetns ano employed by HSBCT of HartfordCT" have inspected the pump, or valve, described in this Data Report on / -'0.- and stale that to the best of my knowledge and belief, the Certiftcate Holder has constructed this pump, or valve; in accordance with he ASME Code, Section IlII,Division 1.

By signing this Certificete, neither the inspector nor his employer makes any warranty, expressed or implied, concerning the equipment described In this Data Report. Furthermore. neither the inspector nor his employer shall be liabte in any manner for any personal injury or property darnag or oss oaany kind art from or connpad with Ibis inspection. Date // f Signed A.?,- Commission_ _ ___ (AuthOfrZed Irs.pe-i) (MNail.Bd.(ied. endoersemernts and stateor prey.and rro.) (1) For manually operated valves only.

REPORT NO. P0059-012 NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As required by the Provisions of the ASME Code Section X1 PNPP No, 9308 Rev. 9/11/00 NOI-17Z1

1. Owner: FIRSTENERGY CORP. Date 8-!6-9 10 Center Road. Perry. Ohio 44081 Sheet . of 3
2. Plant. Perry Nuclear Power Plant (PNPP) Unit 1 10 Center Road. Perry Ohio 44081 200367342 (Repair Org. P.O. No.. etc.)
3. Work Performed By: FIRSTENERGY Nuclear Operatina Company PNPP Type Code Symbol Stamp NR 10 Center Road. Perry. Ohio 44081 Authorization No. 33 Expiration Date 09/28/2011
4. Identification of System: RESIDUAL HEAT REMOVAL 1E12
5. (a) Applicable Construction Code: ASME Section III Class 2 .1977 Edition NAME/SECTIONIDIVISION/CLASS SUMMER 19 77 Addenda Code Case(s) NONE (b) Construction Code used for repairs, modifications, or replacements: 1974 W 75 none Edition Addenda Code case(s)

(c) ASME Code Section XI applicable for Inservice Inspection: 1989 none none Edition Addenda Code Case(s) (d) Applicable Edition of Section XI Utilized for Repairs, Modification, or Replacements: 1989,__ 19 none Addenda none Code Case(s) (e) Design Responsibilities. FIRSTENERGY CORP.

6. Identification of Components Repaired, Modified, or Replacement Components Name of Name of Manufacturer 1 Nat, Other Year Repair, ASME Component Manufacturer Serial No. Board ID. Built Replacement, Code No. or Modification Stamped VALVE DRESSER H110AAS N/A 1E12 1981 Replacement YES F0084B Description of Work: REBUILT VALVE SIN H1 10AAS USING SPRING.AND DISC FROM VALVE S/N H109AAS.

B. Test Conducted: Hydrostatic- LI Pneumatic- LI Nominal Operating Pressure- E] Other- F] Pressure N/A psi Test Temperature N/A degrees F Code Case(s) N/A 150

NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back) PNPP No. 9308 Rev. 9111/00 NQI-1741

9. Remarks:

NO NAMEPLATE/STAMPING PERFORMED DUE TO THE INTERFACE CONTROLS OF PART 3 SECTION 1.8.6 BEING IN EFFECT AND JURISDICTIONAL AUTHORITY CONCURRENCE HAVING BEEN RECEIVED. Note' Attach all applicable Manufacturer's Data Reports. Supplemental sheets such as lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded on the front of this form. CERTIFICATE OF COMPLIANCE I, Michael J Tepsick , certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and to the National Board Inspection Code "NR' rules. National Board Certificate of Authorization No. 33 to use the "NR stamp expires 28 Sept.. 20 11 Date 16 JUNE 20 09 Signed FENOC-PNPP _____-_ __-___ DC Tech. (name of repair organization) (authod.(ed representative) (title) CERTIFICATE OF INSPECTIONIINSERVICE INSPECTION I, Thomas G. Laos holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdictibn of OHIO and employed by HSB CT. . of Hartford Conn. have inspected the repair, modification or replacement described in this report onJuA.E . 20 W and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the work described inthis report Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage o Ioss of any kind arising from or connected with this inspection. Date - a-, 20 09 Signed il. . I-- Commissions NB. 9330 "N"'"I "A" Ohio Comm. (inspe'orM', (National Board (include endorsements), andjurisdiction, and no.)

REPORT NO. P0059-012 W~\ c~A~cMa Q~x{ '-[W") IN J.,~ Fo5uA HpV-I .Nuct-i-T-r ci', T -y; (iS RV.QuiAJEiijY 1 PJV I RiANUFACTURED BY INDUS~rR;MLVAIVE 1-A 2.EJ.RUFACTIJRED FOR Clevel an d- .R."r6c tin- ~x30 lvlad014 -ialol ~1 "4~lýO.-AHO ,PADE;Ss t.. F-URC14ASE-RRONR

                                                                                                                                    *1 3.LoDCUTIOI1      OF INSYALLAT-14           ýPpry NclPrP:n                               ala     dHHeryO                 . 031    1 V

(z) MODEL .4. (b) X CERUlFJA-TE ()CCO t SERIES *NO. H1u]I.utAS -T I,- PIA-v OR T TFE sER1lO (1) 5580W ~... (2) .9O .¶. 3~.4fflfM () 5380DW fil1M-5t1\If:7 (5)

                                                                        ý. ...E

( 7) .. 5 L6.3:........ B-,CEO ESOA E~~iiII. IYICESSOREi S .. ........ CA)BSTINGS H14 SAIO0il,-~r 5o K7 S-A-lo 7 i11t L (I) FOR U-NNO.kLLY

           ýSVFFR B- I/r5X4-11 CSr-ES. AUD (,iEluI4 OPERATEDVALVES ONLY 4 MEAI-Wt IMEETS MI-FfORK Jl m~)N OF L S ISON IOff vsI~HSfux T-151

1067 o& o ME-W.Mm.PC- = ýIaiýý:: W-1ý.iM= m l

REPORT NO. P0059-012

              ~ck~c~                                             c~oq-~                                                                  KfI9& )621 1b7 Fou~HVINCF1~~.1~

(.AS.;RE.OOY Io FRý I -3K 1.9ANUF.ACTURED BY HONUSTRJAL YVAIN&; 2.9AHOFkCTUREO FOR Clevea and --Elik- u-a~t~n-fiex50 'Tv n 3.LOCATION OF IRSTALU1ION ,n PryNQPO ~oLne 2 d-oPry 0 (20 MODEL14O. (b) R-CERTA-IE I.Y1 EO'E -A R IN-. SERIZS NO. NOODfSlolweSiwa4oN(d-Dkj :6r)('i OR( tOE EOA ~ o (-~Ls~s ON i (I) (2) 558.W ;qhfrAS-.. . ., (3)

      .(4)                                     ---
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  • Tr "L¸*-*i .*Lt-*ZL- i.

(5) 0 ...... -.

     .tD
     -7. CODU-'W iThD_                                                 4 q..

74-.H FA I. -.-. ____ I (D) FDRGAAGS K84 SA-I15 5___ K7 _______ _ "__ (I) FOR 9AIWkAL.LYOPERATED VALVES DoAT.

           ýSUPPLOAEUEiRg*L  ERE-ETSEDN-fMRXOF I             B-1iZ" X I'l      0)         WNidRWII JON L             SIIEE--.-AWD fr CH                     IS4~

S 152

~~?;f~ ~1c9\A ,qloaW REPORT NO. P0059-012 1E12-3]0 I[S-Z/NR-l OWNERIS REPORT FOR REPAIRS OR REPLACEMENTS As required by the Pro\visions of the ASME Code Section XI PNFP 1'o. 93-0 Rev. 9n, 11o0 NDI-1741

1. Owner FIRSTENERGY CORZP. Date 5125/2009 10 Carnt-er Rcnad, hin 44031 0av Sheet I of 2
2. Plant PCrren Nuclear Poerr Plan', (PNPP8 Unit 1 10 C~enter Road. Perrv, Ohio 44 08 1 Order 200199140 (RepairOrc F 0. No., etc.)
3. W\/ork Performed By: FIRSTENERGY Nuclear Ooeratino C0m.oanv PNPP Type Code Symbol Stamp NR 10 Center Road. Peran Ohio 44 081 Authorization No. 33 Expiration Date 9/28/2011
4. Identification of System: 1E 12 Residual Heat Removal
5. (a) Applicable Construction Code: ASME SECTION III CLASS 1 ý1974 Edition NAMEISECTION/OIVISIONYCLA5S WINTER 19 75 Addenda Code Case(s) 1644-5, 1728. N-224, N-242, N-272, N-275, N-282.

N416-1, N-413 (b) Construction Code used for repairs, modifications, or replacements: 1974 W75 N/A s) Edition Addenda Code Cese(s (c) ASME Code Section XI applicable for Inservice Inspection: 1989 NONE N/A Edition Addenda Code Case(s (d) Applicable Edition of Section XI Utilized.for Repairs, Modification, or Replacements: 19.89

  • N/A 19 N/A Addenda N/A Code Cases).

(e) Design Responsibilities First Enerqv Cor*

6. Identification of Components Repaired, Modified, or Replacement Components Name of Name of Manufacturer Nat Other " Year Repair, ASME Component Manufacturer Serial No. Board )D. Built Replacement, Code
                                                           .. No.                               or Modification     Stamped Piping         Pullman Power        1E12                  83       N/A        1985         Replacement           yes System
7. Description of Work: Modified piping system for cross tie in of 1E12J1 P1 las part of ADHR modification per ECP 04-0270-01 using the following ASME parts: 8' of 8" SA-312 304 Sch. 40.pipe HL Tr.# 930168, 1- 12"x 8" Reducing Tee HL Tr.# MCWZ-2, 1- 8" 150# Gate Valve S/N BE499, and 1- 8" S/40S Pipe Elbow HI Tr.# MJRG-1 using weld rod HL # P2765, DM7832, 8882.
8. Test Conducted: Hydrostatic- LI Pneumatic- D Nominal Operating Pressure- Z Other- [:]

Pressure NOP psi Test Temperature 95 degrees F Code Case(s) .WA //- '116-Zý:

                                                                                                       ý.        'W-ler?

153

NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back) PNPP No. S308 Rev. 9111100 NQ1- 1741

9. Remarks: NA NO NAMEPLATEJSTAMPING PERFORMED DUE TO THE INTERFACE CONTROLS OF RA-2370 R~INC lxi ~F~mT M'Jfl Ii lRP~,nlr~TIr1NAt AxA ITI-W)PITY mwr~ IPRFWC~F WA\fit~1r R~W RFCF~IVPO BEING IN EFFECT AND JUR)SDIQTIQI\1AL/ýUTHQRITY CONCURRENCE HAVING BEEN RECEIVED Note: Attach all applicable Manufacturer's Data Reports. Supplemental sheets such as lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x II in., (2) information in items I through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded on the front of this form.

CERTIFICATE OF COMPLIANCE 1, JOHN W. MESSENGER, certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and to the National Board Inspection Code "NR" rules. National Board Certificate of Authorization No. 33 to use the "NR stamp expires 28 Sept. 2D 2011 Date 6/25/2009. Signed FENOC-PNPP

  • oc (name of rpair organ-ep.in) (authorized rep7esentative) (tilse)

CERTIFICATE OF INSPECTIONIINSERVICE INSPECTION I, Thomas G Laos holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HSB CT. of Hartford Conn. have inspected the repair, modification or replacement described in this report on l._ Z- 20 Oct' - and state that to the best of my knowledge and belief, this repair, modification or replacement has bean completed in accordance with Section XI of the ASME Code and the National Board Inspection Code "NR' rules. By signing this certificate, neither the undersigned nor.my employer makes any warranty, expressed or implied, concerning the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from or connected with this inspection. Date 20 0Cf Signed 7tC11 . rnL o'MMiSSionS NB 9330 "N~""I""A"Ohio Comm. (inspector) (National Board (include endorsements), q . and jurisdiction, and no.)

                                                                                                                                                    / ,/Z-
1. MonutacLured and cerxified by Flowsexve Corporatolon 1900 South Saunders, St. PRaeich, NC 27603 I-nsa rd iddt.oaof N C.Nritoin Ho.1dfl
2. Manufactured for RFIMEnergy Corpormton PC Box 6100 )ohnstown, PA 15907-6100 (hom. .nd .dd'ena of Parch., cii
3. Location of Installation Perry Nuclear Power Plant 10 Center Road Perry, OH 41081 (n-m. .nd odds....
4. Model No., Series No., or Type 150 Drawing 06-10607-10 _aRev. 0 CRN N/A
5. ASME Code, Section III, Division 1: 1974 Winter 1975 3 N/A dt/f0oln) mndonds ddnld . (dso) ICodaCosenm.)
5. Pump or valve Valve Nominal Inlet size outlet site B

{If,.) fIn.I

7. Material:

(al valve Body SA51, 20 Bonnet SA351, CFO Disk SA351 CIf8 Bolting 2A L... (b) pump Casing Cover Bolting H (n) f-n Ibt N~t'l IcI Bonnet/Co ncr Ult Cort. andy/C..1ng Holdr,'. Board Caerial SeriEl Na. No. No. Na. Nn. BE4!99 N/A OIAR--4 DZUL-1 3XXY-l 0 to 01 to 0 H-

2 FORM V'PV-1 (&ack Pg. 2 t t f 2 Cer-ificate Holder's Serial No. __________ S. Daign conritintý Ior r5D valve pressure cless

2. Cold wor~ng pressure 7_piat 30DF Ia. Hydrcszatit l-est _ _- psi. DisL differential test pr*ssurE psi
11. Remarl:ks: Sals Or6dr 40587 !--rn 10 Boitino is as follows-: Studs. SA 193-57. FITTrne Code ZE33 Nut. SA909-2H. HFat Trai- Code OWG2 CERTIFICATION OF DESICN W. Fensburg P.E. State DH Reg. no. .9_____9 Desipn Speification certified by Design Report acrdtfied by RE. State Reg. no. __

CERTIFICATE OF C::Drt&_AANCE We certify that the statements made in this report are corr*ct and that this pump or valve conforms to the rules for construclion of the ASME Code, Section Ill, Division 1. -09 N Certificate of Authorization No. Expires l.1ir9 Date Date Name

                                            ~Flowsave Coirporedoc n                                    Signed S.It*                                     Curtfn:s. Hl#ordrl                                               IIs~all  d reptrneereri CERTIFICATE- OF INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the Srste or Province of        NIC             and employed by                                                            HS$ CT "
                          .    . of     IHartidrdt, C                                        have inspected the pump, or valve, described in this Data Report on 311I*                            and state that to the best of my knowledge and belief, the Certificate Holder has constructed this pump, or valve, in acordance with the ASME Code, Section I11, Division 1.

By cigning this certificate neither the inspector nor his employer makes any warranty, e--pressed or imolied, cconcerning the component dascribed in this Data Report Furthermore, niether 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 connicted with this Inspection. Dat . Signed .Commissions __ ~~ ~ ~ (,eaesre ~ - t~cal lN.n. ad. 0 -ed--)a o-e -e awwe c-d n.l

REPORT NO. P0059-012 E1B2-311

            *S-2INR-! O          NE~R'S REPORT FOR REPAIRS OR REPILACEMIENTS As required by the Provisions of the ASME Code Section X)

PNPP No. 9308 Rev. 9/111/00 NOI-1741

1. Owner: FIRSTENERGY CORP. Date 7-2-9 10 Center Road, Perry, Ohio 44081 Sheet 1 of 6
2. Plant: Perry Nuclear Power Plant (PNPP') Unit one 10 Center Road. Perry, Ohio 44081 ORDER 200199137 (Repair Org. P.O. No., etc.)
3. Work Performed By: FIRSTENERGY Nuclear ODeratino Company PNPP Type Code Symbol Stamp NLR 10 Center Road. Perry, Ohio 44081 Authorization No, 33 Expiration Date 09-28-2011
4. Identification of System: IE12 RESIDUAL HEAT REMOVAL
5. (a) Applicable Construction Code: ASME SECTION III Class 2 .1974 Edition NAME/SECTION/DIVISION/CLASS
         'WINTER          19 75     Addenda       Code Case(s) N-242.N-224,N-272,N-413.1644-5,1728,N275, N282 (b) Construction Code used for repairs, modifications, or replacements:     1974              winter. 75 Edition       Addenda        Code Case(s)

(c) ASME Code Section X1 applicable for Inservice Inspection: 1989 no n/a Edition Addenda Code Case(s) (d) Applicable Edition of Section Xl Utilized for Repairs, Modification, or Replacements: 1989_, n/a 19 n/a Addenda n/a Code Case(s) (e) Design Responsibilities First Energy Nuclear Operatinq Company PNPP

6. Identification of Components Repaired, Modified, or Replacement Components Name of Name of Manufacturer Nat. Other Year Repair, ASME Component Manufacturer Serial No. Board ID. Built Replacement, Code
  ....                                                         No.                             or Modification      Stamped Piping         Pullman Power           1E12                 83    1E12      1985         Replacement.            Yes
   . ystem S
7. Description of Work: See remarks section
8. Test Conducted: Hydrostatic- E] Pneumatic- LI Nominal Operating Pressure. x . Other- LI Pressure 145 psi Test Temperature 61 degrees.F Code Case(s) N-416-3 155

NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back) PNPP No. 9308 Rev. 9/11/00 NQ1-1741

9. Remarks: Modifications made for the ADHR system per requirements of ECP 04-0270 -01 using the following ASME pars: 10' PIPE HT# A20028 & B66952. 10' GATE VALVE S/N BE555 & BE469, SWAY STRUTS S/N 200D-126. 2006-128, 2006-138 2006-140, 2006-143, 4X4X1/4 STEEL TUBE HT# L2379, YW'PLATE HT #8103343, 11/4" PLATE HT t 6103685, SNUBBER S/N

-D4616493/072, 10' 90 DEG. ELB HT # S307AA. & N232E, TEE 18"X10"X18" HT# 2B3E1D3W4, TEE 16"X10"X16" HT4 2E3E1A3F4, '/ PLATE HT t US551/1A, LOAD STUD PSA 10 HT #CMN, JAM NUT PSA 10 HT 3 SSL. NO NAMEPLATE/STAMPING PERFORMED DUE TO THE INTERFACE CONTROLS OF R.A-2370 BEING IN EFFECT AND JURISDICTIONAL AUTHORITY CONCURRENCE HAVING BEEN RECEIVED. Note: Attach all applicable Manufacturer's Data Reports. Supplemental sheets such as lists, sketches, or drawings may be used, provided (i) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 of this report is included on each sheet, and (3) 6ach sheet is numbered and the number of sheets is recorded on the front of this form. CERTIFICATE OF COMPLIANCE I, Michael J Teosick certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and to the National Board Inspection Code 'NR" rules. National Board Certificate of Authorization No. 33 to use the "NR stamp expires 9-2B 20 11__ Date 2 July 20 09 Signed FENOC-PNPP OE (name of repairorganization) (authorized representative) (title) CERTIFICATE OF INSPECTION/INSERVICE INSPECTION I, Thomas Laos holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and.employed by HSB CT.. of Hartford , Conn. have inspected the repair, modification or replacement described in this report on 2 July 1 20 09 and state that to, the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concemirig the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damager loss of any kind arising from or connected with this inspection. Date 2 July , 20 09 Signed -- Commissions NB 9330 "N" "I" "A" OHIO COMM.

                                                   -n'spetor)'                              (National Board (include endorsements),

and jurisdiction, and no.)

REPORT NO. P0059-012 FORM NPV-1 CERTIFICATE HOLDERS' DATA REPORT FOR NUCLEAR PUMPS OR VALVES* As Required by the Provisions of the ASME Code, Section III, DMvision I 2 Pt ml1of

1. Manutfa--tured and certifiel by Flowserve Corpora*ion, 1900 South Saunders St. Palei*h. NC 27603 L.-.. d dd- a' N Ca.dl HalO,,)
2. Manufactured for R Energ, Corporation PC)Box 6100Dohnst-own, PA 15907-6100
3. Loceaton of installamion Perry Nuclear PowDer Plant 10 Center Road Perry, I---

OH 44081

                                                                                                     -nd ddl-~)
4. Model No., Series No., or Type 300 Drawing 06-40697-02 Rev. ECN N/A S. ASME Code, Section III.Division 1: 19?4 f-arian)

WMntr 1975 l00ddsnOd0,al 2 fslaat N/A {ted, C~ia, no

6. Pump or valve V'alve Nominal inlet size 10 Outlet site 10
7. Materieal (a) valve Body SA716-WcB Bonnet SA2!6-WCB Disk SAZ16-WCB Bolting SA193-B (b) pump Casing Cover Boiling -

Iof fef jd) Sndy/Ca;iog Holdar's Serial Se*rialNa. No. No. No. No. B*S5 N/A 5Y~'-2 - Suppl-mental infrmsfion in th farm o~frti.sl,,lc¢= or dlrawirigs ma be =aed provilaed {111all is 0I/2 x 11,(23 information in itaems I through 4 on this Data Report asIncluded on each chant, M eac sheet is numbered and the number of eheeLe ; recorded at Ihe top of (ic foem. 156

FORM NV-1 (Back - Pg. 2 of 2 Certfitce Holder's Serial No. BES

8. Design conditions SO 212 " or valve pressure ele 302
9. Cold working pressure 720 psi ar IODF
10. Hydroslatio test 1125 pcI. Disk differerrtial test preucur- p2i
11. Remarks:. Sas Order 4057 Item 0D5 Bolting IS as fbllows' Studs, SA 153-R7, Ht Traco Code ZB75 Nuts. SA194-2H, HeatTrace CodQe 7Z3 CERTIFICATION OF DESIGN W. Finsbjrg RE. State OK Reg. no, 49729 Design Speclflcation certified by Design Report certified by RE. State Reg. no.

CERTIFICATE OF COMPLIANCE We certify that the tatemrnents made in this report are cor-ect r-d that this pump or valve conforms to the rules for construction of the ASME Code, Sec¢ton 1l1, Division 1. N Certificate of Aýthoriztin"No.n -2 Expires 126-Date Name -HowseraveCorporation Signed Wjce~ee,. Hebdi I-.aho~d Ipo .... WW CERTIFICATE OF XrflSPECTN I, the undersi g n&d, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of 'NC and employed by HSB C-of Hartford, CT - have inspected *he pump, or valve, described in this Data Report on 5-! ,and sate dethato the best of my knowlvdge end belief, the Certificate Holder has constructed this pump, or valve, in accordanco with the ASME Code. Section Il1, Division 1. By signing this certiflicte nelithart*e Inspector nor his amployer- makea any warranty, expreksed or Implied, concerning the component descrIbod in thist Data Report Furthermore, neither the inspector nor his employer shall be liable in arty manner for any personal injury or property damago or a loss of any kind arising from or connected with thibs Inpeotion. Date a'---~~---- indms SindCommlssions 'V ir.a.te..,oerela ~ re.see~

                                                                                                                                                      ,.S

REPORT NO. P0059-012 FORM NPV-1 CERTIFICATE HOLDERSr DATA REPORT FOR NUCLEAR PUMPS OR VALVES* As Required by the Provisions of the ASME Code, Section IIL,Division 1 Pr 2 1 f I. Pa

1. Manufactured and certified by Flows.rve Lorooration, 1900 South Saunders St Raleioh. NC 27603 I1--, and add,- at N Cd(er,-, H.W oldor
2. Manufactured for First Energy Corporation PO Box 6100 )ohnstown, PA 15907-6100 1--m -rd 6ddt-* f Put'h-')
3. Location of installation Perry Nudear Power Plant 10 Center Road Perry-, OH 44081 too,,,, ond o,,dr,,,2 A. Model No., Series No., or Type 300 Drawing 0&-406B7-02 Rev. E CRN N/A S. ASME Code, Section 1i1,Division 1: 1974 Winter 1975S 2 N/A ldee.onr laddonda done) 1c.1,) dCo. no.)
6. Pump or valve Valve Nominal inlet size 10 Outlet size 10 fIn.) ts
7. Material:

(a) valve Body SA216-WCB Bonnet SA216.WC3 Disk SA216-WCB Bolting 953 (b) pump Casing - Cover - Bolting (a) (b) Nor') Ic) (d)

                                                                                                                                                -   DIsh Board                              Serial Serial No.                          No.                                 No.                                     No.                        No.

1E469 N/A BYGT-1 CCN'N-10 BXKW-2 SSupplrameral Informnalion iýnS form oflIit., kIatch==. or ol&;.ois may be used provided (1) ore ia ll/ a 17, (2) Inlormaotin in Items I hrough 4 On this Dt Rapotn o instdud on eacdhshhee M31eacdshoal is numbered and the number of sheots is reiordad at tle top oa this fomn. 157

FORM NPV-1 (Bark - Pg. 2 of 2 Certificate Holder's Serial No. _ _ _ 3, Design conditions 200 psi 'Fi=8or valve pressure cleas 30D [pftZOJt=l icmnpcrflwol 9, Cold worizng pressure 720 psi at ioo-F 1 0. Hydrrosttic test 125 psi. Disk difl6rantial test preUsura 750 psi

11. Remark. Sa.l*s Ordm' 40687 Item 003 BoDno Is:as follows' Studs, SA 193-B7, ;iNtTrace Code Z876 Nts.$A94-2A Heart ce Code Z3 CERT3FICA1TON OF DESIGN Design Specificalion certified by W. Fi5-m*rg P.E. State OH Reg. no. ____-___

Design Report certified by P.E. State - Reg. no. __ CERTIFICATE OF COMPIJANCE We certify that the statements made in this report are correct end that this pump or valve conforms to the rules for construction of the ASME Code, Section Ill, Division 1. N Certificate of Authorization No. KI*5-2 Expires 11-2 9 Date Name -Fowls-=ve Corpr'*ralto Signed CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commilss*ion issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of NC and employed by HSB CT

  .......                  _of        Hartford, CT"                                       have inspected the pump. or valve, described in this Data Report on
            /'[     c* *"   .          , and state that to the best of my knowledge and belief, the Cerrificate Holder has constructed this pump, or valve, In accordance with the ASME Code, Section III, Division 1.

By signing this certificate neither the inspector not his employer makes any warranty, expressed or implied, concerning the component described in thi. Data Report. Furthermnore, neither the inspecetr nor his employer shafl be liable in any manner for any personal infury or property damage or a loss of any kind arising from or connected with this inspection. Date. 1-3( Signed Commissions 3

REPORT NO. P0059-012 FORM NF-1 CERTIFICATE HOLDERS' DATA REPORT FOR COMPONEN)T SUPPORTS' As Required by the Provisions of the ASME Code, Section I11,Division 1 Pg. 1 of 2

1. Manufactured by Anvil International. Inc. - 180 Frenchtown Rd. No.Kingsloarn, RI 02852 name endadreod 0o NPTCe*rn*ine Holwer)
2. 14anufactured for. First Energy, Perry Nuclear Power Plant, 1.0 Center Road, North Perry,. OH 44081 tram. and address e otpdrlanert
3. Location of instlation First Energy, Perry Nuclear Power Plant, 1t Center Road, North Perry, OH 44081 1nameand.. ore..
4. Type: C.S.S. ORS 211 REV.3 2006 (dnaletb.) fOeiD-n Olprn o Land CapeJrryDae Street) (ye-r b.111
5. ASME Code, Section Itt, Division 1; 1974 Winter 1975 1 N-2,19-13 leeliieni (addenca da-) I6-1 tCodeCand e t
6. Identifcation (a) (b) (c.) td) (e)

Component Material Canadian Applicable Suppon Specificalion Registrallonr Drawings With Board

                      .D. NO.                            No.                          No.                        Last Rev. & Date                   No.

(1) 2008- 126 Note 1 N/A CH-1 077/f 12/31J98 N/A (2) 20068- 127 Note 1 N/A CH-1077/I 12131/98 N/A (3) 2006- 128 Note 1 NIA CH-1077/1 12,31/98 N/A (4) 2006- 129 Note 1 NA N/A 2008- 130 Note 1 N/A CH-1077/1 12131/98 N/A (5) 2006- 131 Note 1 N/A - CH-1 077/I 12.31/98 NIA (S) 2006- 132 Note 1 N/A CH-1077/A 12/31/98 NIA (7) 2008- 133 .Note 1 N/A ." CH-1077/1 12131/98 - N/A (81 (9) 2006- 134 Note 1 N/A CH-1077/I 12131/98 N/A (10: 2008- 135 Note 1 N/A CH-1i077/) 12/31/98 N/A

7. Remar ks:

Note 1: SA35, SA105 GR.e, SA553 GR.A. SA193 GR.B7. SA215 GR.WCB. SA307 GR.A P0#: 45194933 SO#: 41-74740

   'Supplemental inlormatlon in the form of lis., sketches, or drawings may be used provided (1) stze Is      t 112z 11. (2) information in items I through 4 on this Deta Report is Included on each sheeL. and P) each sheet is numbered and the number of sheets is recorded at the top of histtorn.

t*lTah) torm 1E00075)rmay be ooained InrontheOrder DepL. ASME, 22 Law Orive, Bao2300, Fairlield. NJ 07001-2300. fT 158

FORM NF-1 (Back - Pg. 2 of 2 Component Suppon I.D. Nos. 2005-126 throuch 2006-135 CERTIFICATE OF DESIGN Design Specification certified by H. R. Sonderegger P.E. State R.1 Reg. no 3537 Design Report certified by Frank J. Birch P.E. State R.I. Reg. no .4149 CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and that these component supporns conform to the rules for construction of the ASME Code, Section III, Division 1. NPT Certificate of Authorization No. N-2802 Expires 9129/2007 Date "-/.__-______ _Name Anvil International, Inc. Signed-_ _._ __- Dat 72-

                   /76,            Nme         (NPFT Certificate Holder)U CERTIFICATE OF INSPECTION I. the undersIgned, holding a valid commission issued by the National Board or Boiler and Pressure VeaseJ Inspectors and the State or Province oif                         Rhode Island                          and employed by                     H.S.B. C.T.

of / Hartford, C.T. have inspected the component supports described in this Data Report on 75,7't and state that to the best of m"yknowledge and belief, the Certificate Holder has constructed these omponent supports in accordance with the ASME Code, Section III, Division 1. 8ys.igning this certificate, neither the inspector nor his employer makes any warranty, expressed or implied, concerning (he component supports described in this Data ReporL Furthermore. n-ither the inspector nor his employer shall be lable in any manner for any personal injury or property darnag~e or a loss of any kind arising from or connected with this inspeclion. Date S Agne thor Commissions X Al, 2. 46 a? (Authorized Inspection) (Nall. ad. (iied. endorsements) and stale or proc.andno.)

REPORT NO. P0059-012 FORM NF-1 CERTIFICATE HOLDERS' DATA REPORT FOR COMPONENT SUPPORTS' As Required by the Provisions of the ASME Code, Section II1,DIvision Pg. 1 of 2 I Manufactured by Anvit Internationat.Inc. - 160 Frenchlown Rd. No.Kingslown, RI 02B52 tnam. -0d -~c,- .,$10 ConPTa Ho16.r)

2. Manufactured for First Energy, Perry Nuclear Power Plant, 10 Center Road, North Perry, OH 4-4081 1n-- and addrdl- orP.t.hoeet
3. Location of installation First Energy, Perry Nuclear Power Plant, 10 Center Road, North Perry. OH 44081 jn-ne ndrodwz-st
4. Typeý C.S.S. DRS 2t 1 REV.3 2006 ld.s.i.e) (Dsign Rrodn or Load capaciy Dale Shoall lyeatbuill)

S. ASME Code. Section Ill. Division 1: 1974 Winter 1975 1 N-249-13 tedilian) tadd-nd. dl.t tolost lCoda Cao- mo4

6. Identification (a) (b) (C.) (d) (a)

Component M,.aloeal Canadian Applicable National support Speedfcatlon Registration Drawings Wilh Bo-ard I.D,No. No. No. Last Reo. & Oale No. 2006- 136 Note 1 NIA CH-1077A 12/31/9B N/A (1) (2) 2005- 137 Note 1 N/A CH-1077/l 12/31/98 N/A (3) Z005- 138 Note 1 NIA CH-1077)) 12/31/98 NIA (4) 2006- 139 Note I N/A CH--1077/A 12/31/98 N/A (5) 2006- 140 Note 1 N/A CH-1077A 12/31/98 N/A (8) 2006- 141 Note 1 , N/A CH-i-10T7/, 12.31/98 N/A (7) 2006- 142 Note 1 N/A CH-1077At 12/31/99 N)A (9) (9) (ID

7. Rrma,rtce:

Note 1: SA35, SA106 GR., SA553 GR.A. SA193 GR.B7, SA216 GR.WCB, SA307 GR.A PO#. 45194933 SOi( 40-74740

   'Suppternenlai intolnatiers in the form ot lisls, sketches, or drawings may be used provided (1) sIze is 8 I/Z x it, (2) informaion in items I through 4 on this Data Report it included on each sheet, and (3) each shet'ics numbered and the number of sheets is recorded at thetop of this ftrm.

(12/18) This torte (EOD075) may be obtained from theOrder DepL. ASMF.. 22 Law Drive.Boo 230D,Fairfield. NJ 07007-2300. 159

FORM NF-1 (Back - Pg. 2 of 2 ) Cormponent Support I.D. Nos. 2D00.135 through 2006-142 CERTIFICATE OF DESIGN Design SpeCification certified by H,.R_ Sondereoget P.E. StatE RJý Reg. no 3537 SDesion Report certified by Frank J. Birch P.E. Star÷ R. 1. Reg. no 4149 CERTIFICATE OF COMPLIANCE We certify thai the statements made in this report are correci and that these component supports conform to the rules tor construction of the ASME Code. Section I11, Division 1, NPT Certificate of Authorization No. N-2802 Expires 9/29/2007 Oate 7 2 - Name Anvil International. Inc. Signed .. _ _.. _______.___ (NPT Certificate Holder) U9 CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission Issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Rhode Island and employed by H.S.B. C.T. of / / Hartford, C.T. have inspected the component supports described in this Data Report on 27i. t-/d_. and state that to the best of my knowledge and belief, the Certificate Holder has constructed these component supports In accordance with the ASME Code, Section 111,Division 1, By signing this certificate, neither the inspector nor his employer, makes any warranty, e~cgressed or implied, concerning the component supports described in this Data Report. Furthermore, neither the inspector nor his employer shall be liable In any manner for any ersona Injury or propeity damage or a loss of any kind arising from or connected with this inspection. Date ýn Signed ns Commissions 5, 2 Bd* e dAr (Authorized Inspection) (Nalt. Bd.fincl. endorsements) and stale or prey. andeno)

REPORT NO. P0059-012 FORM NF-1 CERTIFICATE HOLDERS' DATA REPORT FOR COMPONENT SUPPORTS' As Required by the Provisions of the ASME Code, Section 111,Division ! Pg. 1 of 2

1. Manufactured by Anvil Inlernational, Inc. - 160 Frenchlown Rd. NoKingstown, RI 02852 mamaand dd-.eoS HiloetI
2. Manufactured for First Energy. Perry Nuclear Power Ptant( 10 Center Road. Norlh Perry, OH 44091 (nameand d.esS ... at Pur,-,aert
3. Location of installation First Energy. Perry Nuclear Power Plant. 10 Center Road. North Perry. OH 44081 salme and sanrass)
4. Type: C.S.S. DRS 210 REV.5 2006 te6-aej) trleiqe enpan wALa Capay DOa- 5he - lya., ba11t)
5. ASME Code, Section Ill. Divýision 1: 1974 Winler 1975 1 N-249-13 tadoi.nt asddendda-1t taJaaat tC cusa at
6. Identirtration lat .(b) (c.) (d) (e)

Comnpon-n1 Mateulal Canadian Applicabte Naliotna Registration Board Support Spedfication Drawtings With I.D. No. No. No. Last pee. & Odte (1) 2006- 143 Note 1 NIA 210-10000/C 11/16/04 N/A (2) 2005- 144 Note I N/A 210-10000/C 11116104 N/A (3) 2006- 145 Note 1 NIA 210- 0000/C 11/16/04 NIA 2005- 146 Note 1 N/A 210-10000/C 11116104 N/A (4) (6) (7) (9) .k. : . (9)

7. Remarrks: .

Note 1: SA35, SAOS GR.B. SA553 GR.A PC#: 45194933 SO4- 41-74740 "eupptementat intormatton in the lorm ot lists, sketches, or drawings may be used provided (1) size is 8 112x 11. (2) Information in iters I through 4 on this Dalt9P,epor is included on each $heel. and (3) each shee is numbered and the number at sheets is recorded at the top of (his torm. (t 2188) This form (E00075) may be obtained from the Order Oept.. ASMdE.22 Law Drive. Box Z300. Fairfield. NJ 07007-2300. 160

FORM NF-1 (Back - Pg. 2 of 2 ) Component Support LD. No&. 2005-143 through 2005-145 CERTIFICATE OF DESIGN Design Specification certified by H. R. Sonderegger P.E. State RI. Reg. no 3537 Design Report certified by Frank .1. Birch PE. StaEt RI. Reqg no 4149 CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and that these component supports conform to the rules fot construction of the ASME Code, Section I1I, Division 1. NPT Certificate of Authorization No. N-2802 Expires 9129/2D07 Date ~(NPT DAnvil IneTationa(, Inc. Certificate Holder) SignederLceHdr CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission Issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Rhode Island and employed by H.S.B. C.T. of I Hartford, C.T. have Inspected the component supports described in this Data Report on 7./12-,'/*A*ý, , and state that to the best of my knowledge and belief, the Certificate Holder has constructed these component supports in accordance with the ASME Code, Section III, Division 1. By signing this certiicate, neither the inspector nor his employer makes any warranty, expressed or implied, concerning the component supports described In this Data Report Furthermore, neither the inspector nor his employer shall be liable in any manner for any ieona ijury or property damage or a loss of any kind arising from or connected with this Inspection. D ate Signed Commissions 5 (, Z/ ra IuorsdInspectisel (mant.Bd. (vioLtendorsemnents) andstateor Pro* andrno.)

REPORT NO. P0059-012

                  ,        o-oi'*t
                             ..                                                       T, PE104                                        1 NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As required by the Provisions of the ASME Code Section Xl                                 NQI-1741 PNPP No. 93D8 Rbv. 9/111100
1. Owner .FIRSTENERGY CORP. Date 3-21-08 10 Center Road. Perry, Ohio 44081 Sheet 1 of .,___
2. Plant: Perry Nuclear Power Plant (PNPP) Unit one 10 Center Road, Perry, Ohio 44081 ORDER 200298919 (RepairOrg. P.O. No., etc.)
3. Work Performed By: FIRSTENERGY Nuclear Operating Company PNPP Type Code Symbol Stamp NR 10 Center Road. Perry, Ohio 44081 Authorization No. 33 Expiration Date 09-28-2008
4. Identification of System: 1E21 Low Pressure Core Spray
5. (a) Applicable Construction Code- ASME SECTION III Class 2 1974 Edition
                -    -NAME/SECTIONIOMVSION/CLASS tm WINTER,-::<v_.:i219. 75 "*," Addenda       '..Code Case(s) N-242 N-224, N-272 N-413 N-247 1644-51728
i.( bJ*..Construction .Co.-de used for rea~er7. m'di~fic}ti'_ns, .cr replacements!:.-{ 1974 **¢.!i ~*winter 75-1: see abov",:

1 1l

I PNPP No. 9308 Rev. 9/11/00 NOI-1741

9. Remarks:_

N/A NO NAMEPLATE/STAMPING PERFORMED DUE TO THE INTERFACE CONTROLS OF RA-2370 BEING IN EFFECT AND JURISDICTIONAL AUTHORITY CONCURRENCE HAVING BEEN RECEIVED. Note' Attach all applicable Manufacturer's Data Reports. Supplemental sheets such as lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded on

              .t of this formr.,c 2 the' front                                                   :   .

REPORT NO. P0059-012

                                                                                                              /1 Z    2           oql NIS-2INR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As required by the Provisions of the ASME Code Section XI PNPP No. 9308 Rev. 9/11/00                                                                                              NOt-1741
1. Owner: FIRSTENERGY CORP. Date 6-18-9 10 Center Road. Perry, Ohio 44081 Sheet 1 of 2
2. Plant: Perry Nuclear Power Plant (PNPP) Unit 1 10 Center Roadi Perrv Ohio 44081 200218275 (RepairOrg. P.O. No., etc.)
3. Work Performed By: FIRSTENERGY Nuclear Operating Company PNPP Type Code Symbol Stamp NR 10 Center Road. Perry. Ohio 44081 Authorization No. 33 Expiration Date 0912812011
4. Identification of System: RESIDUAL HEAT REMOVAL 1E12
5. (a) Applicable Construction Code: ASME Section III Class 2 ,1974 Edition NAME/SECTION/DIVISION/CLASS WINTER 19 75 Addenda Code Case(s) *N-242, N-224, N-272. N-413 1R44-S 172R 16 4-. . 28..

(b) Construction Code used for repairs, modifications, or replacements: 1974 W 75 Edition Addenda Cpde Case(s) (c) ASME Code Section XI applicable for Inservice Inspection: 1989 none none Edition Addenda Code Case(s) (d) Applicable Edition of Section X1 Utilized for Repairs, Modification, or Replacements: 1989 __._ 19 none Addenda none Code Case(s) (e) Design Responsibilities FIRSTENERGY CORP.

6. Identification of Components Repaired, Modified, or Replacement Components
    . Name of          Name of            Manufacturer       Nat.      Other    Year                Repair,              ASME Component          Manufacturer         Serial No.       Board       ID.      Built         Replacement,              Code No.                             or Modification         Stamped P1PING         PULUvIAN                  1E21              N/A    1E21FO18  1985          Replacement             YES SYSTEM         POWER Description of Work: REPLACED VALVE SIN 1 WITH VALVE SIN 2.
8. Test Conducted: Hydrostatic- E] Pneumatic- E] Nominal Operating Pressure- Z Other- H Pressure 424 psi Test Temperature 77 degrees F Code Case(s) N/A 162

NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back) PNPP No. 9308 Rev. 9/11/00 NQI-1741

9. Remarks:

NO NAMEPLATE/STAMPING PERFORMED DUE TO THE INTERFACE CONTROLS OF PART 3 SECTION 1.8.6 BEING IN EFFECT AND JURISDICTIONAL AUTHORITY CONCURRENCE HAVING BEEN RECEIVED. Note: Attach all applicable Manufacturer's Data Reports. Supplemental sheets such as lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 of this report is included on each-sheet, and (3) each sheet is numbered and the number of sheets is recorded on the front of this form. CERTIFICATE OF COMPLIANCE I, Michael J Tepsick , certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and to the National Board Inspection Code "NR* rules. National Board Certificate of Authorization No. 33 to use the "NR stamp expires 28 Sept. , 20 11 1 Date 18SJUNE 20 09 Signed FENOC-PNPP-,,... DC Tech. (name of repairorganization) (authorizedrepresentative) (title) CERTIFICATE OF INSPECTION/INSERVICE INSPECTION I, Thomas G. Laos - holding a valid commission issued by The -National -Board of Boiler and Pressu-e Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HSB CT. of Hartford, Conn. have inspected the repair; modification or replacement described in this report ona 2,d, 20 qa_ and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code 'NR' rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from or connected with this inspection. Date & A4 20 09 Signed J4 Commissions NB 9330 "N'"" "A"Ohio Comm. (InSp~ctot) *(National Board (include endorsements), andjurisdiction.and no.)

REPORT NO. 20059-012 FOCFI1M !sx-I N CERTfl=CA!,7 HOLrOvFS' DATA RE?OIRT FOR SAFFFY Aiv'D SA.FzTYý  ;ý6ULEEVA,*LV=S' As Ri.c-rur-E-d by the Frovis~cfns of the AS'ME Coee. Sec---on 111.Diy.I

1. 7--sare, Rock 966 -*. 3ý-,a2bo-'-

Loo~io 7-4 - -=*.z:=IeN' 2-o~fur for Cie+/-oo crLelx1in Co. CvahD hio iftrro znd A06,,z- of P-01-1~ or OVCl-or

3. O1 ~s NuOOt:Oar P o-er= r a~i5jr~ PIantr .?aýrt , Ohio S. nia - 758-007A ldL-ntifying Nos. 2
    -yp      --           Reiel          Valve 5o~.svtay Roiij.t FuR.; ?a-~       ...fzte*

Griica S~-si 00 Nominal iniet Size 1 1/2 o____ S __________ irncr ir i,: a n~aeI~O ~255 File'a Tzmp-rzrsre 5 10 Starn~>::d Ca-pe-ýr Ibsihr I_______ @p Ovarcreszure 31--d-v~ iPSIG) 8/0

7. rnci - 0rl ai- for arcofad za ten- rO tot vsfmst45- Oyl Serial No. a-Mcareria spesification Idenratiirziic Incl. Type a. Grade i, I c AS1A2 S.i-05 2--1 a,riYoko 30039f -1 Su.pport Poads ____

Nartle 300832 ASi*E SA 479-316L 0l,, 20202.5.--1 S6ESA 564 . 630. S.S 1-? Spring Wa&ems.~r __ 2ut-irr6n Store ____ Spinc(I6 Spring - -- Orirar Pace

                - lanse           202096 5-v~r           Vi-9U1      -a 1 1/'

Screw.Sock Fd 102609 AZI[E 5 619 3-Ai

           ?7't/8-6 J~lrhr 7R
  • Water Capacity: 267 GPM at I10% set press.
  • Surpplemnteral sh"nrs in form or1 frmt sketchres or drsswrrrrg may be ased provirded (1) oa-. ;s &ir 1,-. 12) mfrmr.;.n in iterms 1-2 on tis, QOnz Rrport is included on each siheet. and (31 each sheet se norrrhnbend and num~rber o-i sh'e-tt i re~ctifdd 3) too of this form.

D. W. GROW

                                                                                                                                                         .. 63
,0 (10177) Thit f orn (E5020521 rn-rayS cbmrerrem hrnrn- ihe Grder Dem.. ABME. 145 E, Z7,i S. rYnk .y. I~i 163

Mý REPORT NO. P0059-012 1E21-042 NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As required by the Provisions of the ASME Code Section XI PNPP No. 9308 Rev. 9111/00 NQI-1741

1. Owner: FIRSTENERGY CORP. ___ Date 6/23-09 10 Center Road. Perry, Ohio 44081 Sheet 1 of 2
2. Plant: Perry Nuclear Power Plant (PNPP) Unit one 1D Center Road. Perry. Ohio 44081 ORDER 200257510 (Repair Org. P.O. No., etc.)
3. Work Performed By: FIRSTENERGY Nuclear Ooeratino Comoany PNPP Type Code Symbol Stamp NR 10 Center Road, Perry, Ohio 44081 Authorization No. 33 Expiration Date 09-28-2011
4. Identification of System: 1E21 Low Pressure Core Spray 5; (a) Applicable Construction Code: ASME SECTION I1[Class 2 1974 Edition NAM EJSECTION/DIVISION/CLASS WINTER 19 75 Addenda Code Case(s). N-242,N-224,N-272.N-413.1644-5.1728 (b) Construction Code used for repairs, modifications, or replacements: 1974 winter 75 see abov Edition Addenda Code Case(s)

(c) ASME Code Section XI applicable for Inservice Inspection: 1889 no n/a Edition Addenda Code Case(s) (d) Applicable Edition of Section XI Utilized for Repairs, Modification, or Replacements: 1989 n/a 19 n/a Addenda n/a Code Case(s) (e) Design Responsibilities First Energy Nuclear Operating Company PNPP

6. Identification of Components Repaired, Modified, or Replacement Components Name of Name of Manufacturer Nat. Other Year Repair, ASME Component Manufacturer Serial No. Board ID. Built Replacement, Code
                                        '                       No.                           or Modification       Stamped Piping         Pullman Power        1E21                   85       1E21      1985        RPL                     Yes System
7. Description 6f Work: REPLACED WATER LEG PUMP S/N 021-1 WITH NEW WATER LEG PUMP S/N 1A021.
8. Test Conducted: Hydrostatic- D Pneumatic- E] Nominal Operating Pressure- X Other- El Pressure 46 psi Test Temperature 77 degrees F Code Case(s) N/A 164

NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back) PNPP No. 9308 Rev. 9/111/00 NQI-1741

9. Remarks:-

N/A NO NAMEPLATEJSTAMPING PERFORMED DUE TO THE INTERFACE CONTROLS OF RA-2370 BEING IN EFFECT AND JURISDICTIONAL AUTHORITY CONCIJRRFNr.F HAVING BEEN RECEIVED Note: Attach all applicable Manufacturer's Data Reports. Supplemental sheets such as lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded on the front of this form. CERTIFICATE OF COMPLIANCE I, John W. Messenaer , certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and to the National Board Inspection Code "NR' rules. National Board Certificate of Authorization No. 33 to use the "NR stamp expires 3-28 20 08 Date 6/23 20 09 Signed FENOC-PNPP QE (name of repairorganization) Rod repress.tive) (title) CERTIFICATE OF INSPECTION/INSERVICE INSPECTION 1, Thomas Laos holding a valid commission issued by The National Board of Boiler and Pressure Vessel inspectors and certificate of competency issued bythe jurisdiction of OHIO and employed by HSB CT.. of Hartford , Conn. have inspected the repair, modification or replacement described in this report on )2000.. and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section Xl of the ASME Code and the National Board Inspection Code "NR' rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from or connected with this inspection. Date ..*(o20 oc... Signed Z1~M~.~c2cCommissions NB 9330 "N""I""A' OHIO COMM. Ons'pector)*'/ *(National andBoard (Include endorsements). jurisdiction. and no.)

REPORT NO. P0059-012 165

~B~N ~Th ,-/log IN

                  *t FI*
  • REPORT NO. P0059-012 "1E21-043 NIS-21NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As required by the Provisions of the ASME Code Section XI PNPP No. 9308 Rev. 9/11/00 NQI-1741
1. Owner FIRSTENERGY CORP. Date 7-1-9 10 Center Road. Perry, Ohio 44081 Sheet 1 of 6
2. Plant: Perry Nuclear Power Plant (PNPP) Unit one 10 Center Road. Perry. Ohio 44081 ORDER 200199135 (RepairOrg. P.O. No., etc.)
3. Work Performed By: FIRSTENERGY Nuclear Operating Company PNPP Type Code Symbol Stamp NR 10 Center Road, Perry, Ohio 44081 Authorization No. 33 Expiration Date 09-28-2011
4. Identification of System: 1E21 Low Pressure Core Spray
5. (a) Applicable Construction.Code: ASME SECTION III Class 2 1974 Edition NAMEJSECTION/DIVISION/CLASS WINTER 19 75 Addenda Code Case(s) N-242,N-224,N-272.N-413,1644-5,72*

(b) Construction Code used for repairs, modifications, or replacements: 1974 . , winter 75 _ Edition Addenda Code Case(s) (c) ASME Code Section XI applicable for Inservice Inspection: 1989 no n/a Edition Addenda Code Case(s) (d) Applicable Edition of Section XI Utilized for Repairs, Modification, or Replacements: 19 89, n/a 19 n/a Addenda n/a

                                                     *Code Case(s)

(e) Design Responsibilities First Energy Ndclear Operating Company PNPP

6. Identification of Components Repaired, Modified, or Replacement Components Name of
  • Name of Manufacturer Nat Other Year I Repair, ASME Component Manufacturer Serial No. Board ID, Built Replacement, Code No. or Modification Stamped Piping Pullman Power 1E21 85 1E21 1985 Replacement Yes System
7. Description of Work: See remarks section
8. Test Conducted: Hydrostatic- W Pneumatic- D Nominal Operating Pressure x Other- []

Pressure 321 psi Test Temperature 76 degrees F Code Case(s) N-416-3' 166

NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back) PNPP No. 9308 Rev. 9/I 1DO0 NQI-1741

9. Remarks: Modifications made for the ADHR system per requirements of ECP 04-0270 -01 using the following ASME parts: (12')-l0 "dia. Sch. 40 SA106 pipe Ht# B66952, (12')-10 "dia. Sch. 40 SA106 pipe Ht.# A20028, (2)-

150 # 10" gate valves S/N BE467, BA780, (2)-300# 10" Sch. 40 gate valves S/N BE465, BA773, (1)- pipe weldolet 24`xl 0" Ht # 4036ANF,(2) 24" dia. 150 psi Flanges Ht # 207K740, and (1) Sway Strut SZ-2 S/N 2006-116 & 117, 1" plate Ht# U8493/2E, tee Ht# S609, 24" pipe Ht# B67599, 40 studs 1`-8 Ht# 2J200 and 80 nuts 1"-8 Ht#1 0280, using weld rod HT # CP7808, 065735,789X.,065767,42379,065905,159443. NO NAMEPLATEISTAMPING PERFORMED DUE TO THE INTERFACE CONTROLS OF RA-2370 BEING IN EFFECT AND JURISDICTIONAL AUTHORITY CONCURRENCE HAVING BEEN RECEIVED. Note: Attach all applicable Manufacturer's Data Reports. Supplemental sheets such as lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded on the front of this form. CERTIFICATE OF COMPLIANCE I, Michael J Tensick , certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and to the National Board Inspection Code "NR" rules. National Board Certificate of Authorization No. 33 to use the "NR stamp expires 9-28 20 11_ Date 1 July .20 09 Signed FENOC-PNPP . OE (name of repairorganization) (authorized representative) (title) CERTIFICATE OF INSPECTION/INSERVICE INSPECTION Ij Thomas Laps holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO - and employed by HSB CT.. of Hartford , Conn. have inspected the repair, modification or replacement described in this report on 1 July . 20 09 and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code "NR* rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from or connected with this inspection. Date 1 July , 20 09 Signed. l-* .,*&.. Commissions NB 9330 "N" "'" "A" OHIO COMM. (inspector)l (National Bard (include endorsements), andjurisdiction,and no.)

REPORT NO. P0059-012 PORhM N,PV-1 CERTIFRCATE HOLDERS' DATA REPORT FOR NUCLEAR PUMPS OR VALVES' As Required by the Proyisions of the AS;ME Code, Section [it, Division I  ? Pg. 1 of

1. Manufactured and catified by Fow-perve CopDratdi, 1900 SaLdf Saunders St Raleigh, NC 27603 In~aOn-d adtdl.. o. N Cattfa-.t H.o161) 2 Manufactured for Flr* Energy Corporstion PC)Box 6100 3ohnstown, PA 15907-6100 In-r ,d-rdaa of Pa.arl-1
3. Loserion of installation Perr-y Nudear Power PMant 10 Center Road Perry, OH 44091 samerand a=dtonl
4. Model No.. Series No., or Type 300 Drawing 06&40687-02 Rev. E CRN N/A
5. ASME Code, Section III,Division 1: 1-074 Winter 1975 V 2
  • N/A Iodldon) addond, data) Ietaa=l ICoda C.a. -o)1 E. Pump or valve Valve Nominal inlet size 10 Outlet size 10 fn.n.)
7. Material:

(a) valve Body *A216-WCB Bonnet SA216-WCB Disk SAQ16-WCB Bolting SAI3-BZ [b) pump Casing Cover Bolting _ (b) idl lal Coi. Not'l Bonnoercover Dish Hodoer's Board Sorial Serial Sori No. No. No. Na. Na. BE465 N/A BYGR-1 BYCC-2 BXKtA'-5 6--> 9 Supplamental infornation in the forn of liseg.c(letchea. or drawisga -ay be used provided (1) hieois 8'12X 11, 121information In borne through 4 on this Data Report a inlauded on "dh canL, 13Of iah bhmtit numbered and the number of sheets It recorded 31 Mrstop of thit form. 167

i'-Nk Pg. 2 of 2 FORM MPV-1 (Back - Certificate Holder's Serial No. BF-E5 S. Design conditions So 12 F or valve pre21ure class 300 {prnc*rel Itemprn usitrl

9. Cold vaorting pressure 720 psi at 100'F
10. Hydrostatic tes 12. psi. Disk fferential test pressure 750 psi
11. Remarks: Sale Ordý 40687 Item 004 Boltin is ?s followg Studf. SA 193-57. Ht Trace Code Z776 Nuts. SA19+4-2H. Heat Trace Code MI CERTIFICATION OF DESIGN De-sign Specification certified by W. *'tsburg P.C State DH Reg. no. 49729 Design Report certified by PRE. State Reg. no.

CERTIFICATE OF COMIPLIANCE We certify that the statements made in this report are correct and that this pump or valve conforms to the rules for construction of the ASME Code, Section IlII,Division 1. N Certificate of Authortration No. N-WS62 Expires 11 Datea rO . Name lowserve CorporaoDrt Signed CERTIFICATE OF INSPECTION 1, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of NC and employed by HSB CT of HaHford, CT have inspected the pump, or valve, described in this Data Report on

             -3/ - C'                     .and state that to the best of my knowledge and belief, the Certificate Holder has constructed this pump, or valve, in accordance wsith the ASME Code, Section III, Division 1.

By signing this certificate neither the Inspector nor his employer makep any warranty, expressed or implied, concerning the component described In this Date Report. Furthermore, neither the inspector nor his employer shall be liable in any mannerfor any persoenal injury or property damage or a loss of any kind arising from or connected whh this Inspection. Datea / Signed Na~ LkwhsareIr.d psvtor)r Commissionsi___________._____.______....). ad.rindt... d--1e.)e INari -nd i..a pr.es.6 anda. 3

RE~PORT NO. P0059-012

                                                                                                                                                       / -0j.3t 1    3 0 e --

FORM NPV-1 CERTIFICATE HOLDERS' DATA REPORT FOR NUCLEAR PUMPS OR VALVES' As Required by the Provisions of the ASME Code. Section 1., Division 1 2 Pa, 1 of __

1. Manufastured and certified by Flo*-a-,se CorpoDrtion, 19D0 South Saunde-s St Raleinh, NC 27603 I-m. -nd eddr- .1 N C ienfl,,. H.lodnr)
2. lMoanutrctured for Fir't En*qy Co.'poraleon P0 Bo* 100 JohnsLoWn, PA 1i5907-6100 1-n.. ed odd,.., .1 P'l,. n-l
3. Loca-iDn'ofinstallotion Parry Nudear Power Plant 10 Center Road Perry, OH 440B13 Ino.. end edd....)
4. Model No., Series No., or Type 3DD Drawing 06-40697-02 Rev. D CRN I_ A S. ASME Code, Section III,Division 1: 197,4 VirWntr 1975 2 N/A I~dioH) todde=d. dn-) lcCon cod. Coo. no.l
6. Pump or valve Valve Nominal inlet size 10 Outlet size 10
7. Material:

(a) valve Body SA216-WCB Bonnat 5A216-WCi Disk SBAln716-WCB goti (b) pump Casing Cover B-6ng d _ (a) I-) (d)1 lo. C.'L: Body/Ca63n N at. Soard 1 g B.-neC.evor Holder', Sa6. S.6.1l S-6.1raNo. No. No. No. No, BA773 N/A BWGK-1 BWF-K-1 BWSK- 1 ' Supplemental Information In the Iornm of liste. sketche-- or drawjngr may be used provided I1) =o= iseWt'.lx 11. (2) Information In Iteme 1 Ihrough 4 on this Doin Report is included on easl, hecot, (3) each sheet is numbered and the number of sheets s r=ord at the top of this forn. 1.68

t 2 FORMI NPV-1 (Back - Pg. 2 of - ) BA273 No. Certificate Holder's Serial S. Design conditions psi 3_ _ 'F or valve pressure class 300 lpEszutal ltee p~rrtu,*t

9. Cold wvoring pressure 720 psi at 100F 1!2.5 750 pci 1D. Hydro.satic tc-st psi. Disk differential test pressure
1. Remarks: Sal*s* order 40687 It-n 002 Boltino is;as foflows. Studs. SA 193-B7. HtI Trace Code Z876 NutS, &SI94-2H.,Heat Tromr Code M_.1 CERTIFICATION OF DESIGN Design Specification cerrified by W. Flernsburg RE. State OH Reg. no. 49729 Design Report certified by R.E. State - Reg. no.

CERTIFICATE OF COMPLUANCE We certify that the statements made in this report are correct and that this pump or valve conforms to the rulcs for construction of the ASME Code, Section ill, Division I. N Certificate of Authorization No. N-1S62 Expires Date Name - ~Flowo'erve Corpo-tion Sge CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of NC and employed by HSB CT of Hartford, CT -have inspected the pump, or valve, described in this Data Report on

        /i       o?'                 .,and state that to the best of my knowledge and belief, the Certificate Holder has constructed this pump, or valve, in accordance with the ASME Code, Section Ill. Division 1.

By signing this certificate neither the inspector nor his employer makes any warranty, expressed or implied. concerning the component described in this Date Report. Furthermort, 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 Intspactio Dote 7 Signed AC Nud16' 7 c.ommissilons k.5cn/rZ t~ceodN-1-1 lr,.ctcrl INlr.NB. eal

                                                                                                                     -.                  stir Ortea. eed no.1
                                                                                                                                    -n.sa~ntlad
                                                                                                                                                   -3

REPORT NO. P0059-012 FORM NPV-1 CERTIFiCATE HOLDERS' DATA REPORT FOR NUCLEAR PUMPS OR VALVES' As Required by the Proyisions of the ASME Code, Section III. Divsion 1 2 PF1. 1i of

a. I of 2
       '. Manufactured and certified by Rowserve Corporation, 1900 South Saunders St Raleioh, NC 27603 In-oe cod add-c- o1 W Urtfi-    H.drrl
2. Manufacturod for Frs Enery Cor-atdon P0 Box 5100 Johnsown, PA 15907-6100 tn... and b~dd-e.of Parch..)
3. Location of installation PerTy Nudear Power Plant 10 Center Road Perry, OH 44081 teem- .nd add-Arot
4. Model No., Series No.. or Type 150 Drawing D6-40687-08 Rev,. C CRN N/A
5. ASME Code. Section III, Division 1: 1974 Winter 1975 2 N/A ladjooni loddrndc doici {si-=o) ICede C-o no.1 B. Pump or valve Valve Nominal inlet size 10 Outlet size 10 tln.l lin.)
7. Material:

(a) valve Body -. 21-&k WtB Bonnet StA2"!-WC3 Disk A2l&16-WCB Bolting 5&183-57 fb) pump Casing Cover 'Bolting 1sf (b) I0 Id) Ilo Cn.M Not'l Body.Cadng BonnaLCover Dis Holder%; Board Serial Serial Serial No. No. No." No, No.

               -E247                                N/A                                  BYFS-I                                BYGP-1                     BXZW-1 I->____                                 ____                                   ____                                      ____                          ____
    ' SupplernSnlnB Infonrn1lton III Boo form of ri-&,     alotdshes.or drawIngi; may be uvad providod (1l slzt is 811z 11, 1Z.)Infornmation in ILrnre   through 4 on this Data R-pars Is tnlauda-d on a*a- sheetI, M3 eadch shoet is numbarad and tho nurnber of sheets Is recorded at the top of thi-.form.

169

FORM NPV-1 (Rack - Pa. 2 of 2_____ Ca.,tificate Holder's Serial No. BE467

8. Design Conditions 100 psi 212 'F or valve pressure cless 15D tprersir) fttePer..r
2. Cold working pressure 2775 psi at 1ID0F
10. Hydrostatic test 42S psi. Disk differential test pressure 30D psi 1*. Remarks: Sales Order 40587 Item 009 Bolting is as follow5: Studs, SA IL93-B7. Ht Trace Code Z&43 Nut. SA194-2H. Hee Trec Co*de ZE34 (OTY. 11) & 5B4 (OTY- 1)

CERTIFICATION .OF DESIGN W. F_.nsburg P.E. Stat OH Reg. na. 49729 Design Specification certified by Desigri Report certified by PE. State - Reg. no. __ CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and that this pump or valve conforms to the rules for construction of the ASME Code, Section III, Division 1. N Certificate of Authorization No. N-4562 Expires Date Name FIDAP-rve Corixstebofl Signed Z E

                                  -           .              -~INCer55seia IHeidar)                                             iaciha.dra     arl CERTIFiCATE OF INSPECTiON I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspecltors and the State or'Province NC             and employed by                                                       HSB CT of of     Hartf*rd, CT                                        have inspected the pump, or valve, described in this Date Report on OR                    , and state that to the best of my knowledge and belief, the Certificate Holder has Constructed this pump, or valve, in accordance with the ASME Code, Section 11, Division 1.

By signing this certificate neither the inpspector nor his employer makes any warranty. expressed or implied, concerning the component described in this Dait' ReporL 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 yith this inzpaottie Date Signed JCommitssons

                                .. (~e ria~d           A      eor           MSe                                'sort 5i: 11-1, a-d--)ne  andie   aV er-. -ed sat
                                                                                                                                                                    .3

REPORT NO. P0059-012 FORM NPV-I CERTIFICATE HOLDERS' DATA REPORT FOD NUCLEAR PUMviPS OR VALVES-" As Required by the Prov'isions of the ASME Code, Seution Ill, Division 1 2 Pg. 1 of__

1. Manufactured and certified by Rowerve Corpor-bton, 1900 South Saunders St Raleigh, NC Z7603 In- -, d d.'e.o of N C.rtihoou NHo10.
2. Manufactured ior Frs Energy Corporation PC)Box 6100 3ohnltown, PA 15907-6100 ooro. 00d odrooo of Puroho=orl
3. Lonation of insrailation Perry l'udear Power Plant 10 Center Road Perry, OH 44081 (n.meo mnd 6d6-coal
4. Wodel No., Series No., or Type ISO Drawing 50-'407;-O8 Rev. CC_ _ N/A
5. ASME Cotle, Section III, Division 1: _974- Winter i7"5 2 N/A todbol (di,~dol Wofoon d.%I 1.6 Co... ...
6. Pump or'valve Valve Nominal inlet size 10 Ouloet size 1_ _

ih',.}(In.)

7. Mamerial:

(al valve BpdCAsing WCB Bonnet SASIL-WCE Disk Sý 216-WCB Bolting SAIS.2-117 (b) pump Casing Cover - Bolting lb) i0 Id) tol Nat'l Disk Board sori.l Sorial No. No. No. No. No. BA7SO N/A a>XMB-i . BMWB1

ý Supple-mental irtflfrrN8Vlo In the fon-m of fists, s-ketcher, or draw',nD mny be used provided (1) size is 02/x 11, (2) information in items I th'rough 4 on thi Data Report is includod on each sheet, (3) saeh shoot is numbered and the number of cheets Is recorded at the lop of this loont.

170

FORM NPV-1 (Back - Pg. 2 2o Bk7BB _ _ _ _ No. _ _ Certificate Holder's Serial

8. Design conditions 00 p. 212 or valve pressure class ___

psi Irnepur 'F,,] caase-

9. Cold worling pressure 2.75 psi at 100*F 8.25 3D0
10. Hydrostatic tcst psi. Disk differential test pressure pzi
11. Remarks: S.O.406B7 ITEM B aJ_ TfLJG_ SAS FP1 I OINS' STI IDS SAieS7 - Hc 7R43- NUrTS, SA*,-?H Ht-f.-f73B I ~ CERTI3FICAT]ION OF DESIGN Design Spezi.fic~tion certified by W. RLEMNBUPtG P.E. State OH Reg. no. 49729 Design Report ochtified by _ N/A R.E. State N/ Reg. no. NI CERTIFICATE OF COMPLIANCE We certify that the -statements made in this report are correct and that this pump or valve conforms to the rules for construction of the
   .SME Code, Sec'ion Ill, Division 1.

H Certificate of Authorication No. N-IS62 Expires 11-26-09 Date 0"7 Name Flowserve- . Corporation IN Ce55sicr. Holdarl Sigted . ..... . rsrsnrre. CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Ves~sel Inspectors and the State or Province of NC and employed by ,HSB CT hartford, Ha CT have inspecmd the pump, or valve, described in this Date Report on 11/?.. t/'i 7. and state that to the best of my knowledge and belief, the Certificate Holder has constructed this pump, or valve, in accordance with the ASME Code, Section III, Division 1. By signing this cortificate neither the inspector nor his employer makes any warranty, expressed or implied, concerning the component described in this Data Report Furthermore, neither the inspector nor his employer shall be liable in any manner for any personal injury or property damage or a losm of any kind arising from or corenected with this inspecti .on. Date W' ~~~Signe~d ,ý 1-, Iarrw1 N l/VAarsrlrnd C*Z ommissions AIC.- -4 ZeIV rr4.r.ad. nfe,-d asnl n e Mlo reede~

                                                                                                                                                      ,      6-

REPORT NO. P0059-012 je&-%q3 &

  • FORM NF-1 CERTIFICATE HOLDERS' DATA REPORT FOR COMPONEKT SUPPORTS' As Required by the Provisions of the ASME Code, Section III, Division I Pg. 1 of 2
1. Manufactured by Anvil International, Inc. - 160 Frenchlewn Rd. NoKinrgstown, RI 52552 lonre DfnOasdess 0 NPTCeFllel Molderl
2. Manufactured for First Energy, Perry Nuclear Power Plant. 10 Center Road. North Perry, OH 44051 Inme end arlddo, of Purcha-er) 3- Location of installation First Energy, Perry Nuclear Power Plant, 10 Center Road, North Parry. OH 44051
4. Type: C.S.S. DRS 211 REV.3 2005 luesnlbet 1001aesignRepoeLead CaparjilyData Sheel) )r'd b.11[)
5. ASME Code. Section tIl, Division 1: 1974 r/inler 1975 1 N-249-13 cadeint) (loddndo dole.) tCt0- (ced. C-se t
6. Identificatien (a) (b) (c.) (d) le)

ComponenT Malerial Canadian Applicable National Srrncific,toe Support Registration Drawing5 wih Scald Lo, No. Last Rev. & Dole No. (1) 2006- 116 Note 1 N/A CH-T1077/t 12/31/98 NIA (2) 2006- 117 Note 1 N/A CH-1077/1 12131198 NIA (3) 2006- 115 Note I N/A CH-1077,1 12/31/95 N/A (4) 2006- 119 Note I NIA CH-1077/1 12/31/19 N/A (5) 2005- 120 Note I N/A CH-1077I1 12.31/9B NIA (6) 2005- 121 Note 1 N/A -.

  • CH-1077A1 12131/98 NIA CT) 2005- 122 Note I N/A CH-107711 12/31/98 NIA (5) 2005- 123 Note I N/A CH-1077/1 12/31/98 N/A (9)
                  '2005- 124                           Note 1                             N/A                    CH-1077/1 12/31/98                  N/A 2005- 125                           Note 1                             N/A                    CH-107711 12/31198                  N/A 7   Rerea    tro*

Note 1: SA36, SAI05 GRB, SA553 GR., SA193 GR.87, SA215GR.WCB, SA307 GR.A PON: 45194933 SO: 41-74740

    *Supplemental Inlormatoon In thre trm oa -lists, shelrhes, or drawings may be used provided It) size is a 112 a 11. (2)1inlorrnatli   In Items ) through 4 on this Data Report is included on each sheet, and (3) each sheet Is numbered and the numberatol amels Is recolded at the top of Itis term.

(1r21/5 This lomo (E100075) may be obtained from the Order DepL, ASME, 22 Law DOfi.. Box 2300. Fairfield. NJ 07D07-2300. 171

FORM NF-i (eack - Pg. 2 of 2 Component Support I.D. Nos. 2006-116 through 2006-125 CERTIFICATE OF DESIGN Design Specification certified by H. R. Sonderegger P.E. Stalt R.I. Reg. no 3537 Design Report certifled by FrankJ. Birch P.E. Slate R.I. Rag. no 4149 CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and that these component supports conlorm to the rules for construction of 'the ASME Code, Section III, Division 1. NPT Certificate of Authorization No. N-2802 Expires 9/2912007 712- a Name Anvil International, Inc. Signed - .... r Date (NPT CertScate Holder) J CERTIFICATE OF INSPECTION 1, the undersigned, holding a valid commission Issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province or Rhode Island and employed by H.S.B. C.T. of Hartford, C.T. have inspected the component supports described in this Date Report on , and stale that to the best of my knowledge and belief, the Certlifcale Holder has constructed these component supports In accordance with the ASME Code, Section III, Oivtslon 1. Br sign!ng this certliicate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the componernt supports described In this Data Report. Furthermore, neither Ihe 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 wilh this Inspection. 0.

REPORT NO. P0059-012 z 2- - 0 7 ý' NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As required by the Provisions of the ASME Code Section XI PNPP No. 9308 Rev. 9/111/00 N1O-1741

1. Owner: FIRSTENERGY CORP. Date 6-5-9 10 Center Road. Perry. Ohio 44081 Sheet 1 of 2
2. Plant Perry Nuclear Power Plant (PNPP) Unit 1 10 Center Road. Perry Ohio 44081 2002790O2 (Repair Org. P.O. No., etc.)
3. Work Performed By: FIRSTENERGY Nuclear Operating Comoany PNPP Type Code Symbol Stamp NR 10 Center Road. Perry, Ohio 44081 Authorization No. 33 Expiration Date 09/28/2011
4. Identification of System: HIGH PRESSURE CORE SPRAY 1E22
5. (a) Applicable Construction Code: ASME Section III Class 2 .19 74 Edition NAMEISECTION/IDVISION/CLASS WINTER 19 75 Addenda Code Case(s) N-224-1, N242. N272, N275.

(b) Construction Code used for repairs, modifications, or replacements: 1974 W 75 ' none Edition Addenda Code Case(s) (c) ASME Code Section XI applicable for Inservice Inspection: 1989 none none Edition Addenda Code Case(s) (d) Applicable Edition of Section XI Utilized for Repairs, Modification, or Replacements: 19 89 , 19 none Addenda none Code Case(s)

   .(e) Design Responsibilities FIRSTENERGY CORP.
6. Identification of Components Repaired, Modified, or Replacement Components Name of Name of Manufacturer NaL Other Year Repair, ASME Component Manufacturer Serial No. Board ID. Built Replacement, Code No. or Modification Stamped PIPING PULLMAN 1E22 86 1E22 1985 Replacement YES SYSTEM POWER FD035
7. Description of Work: REPLACED VALVE S/N 5 WITH VALVE S/N 3.
8. Test Conducted: Hydrostatic- E] Pneumatic- E] Nominal Operating Pressure- Z Other- n]

Pressure 543 psi Test Temperature N.O.T. degrees F Code Case(s) N/A 172

NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back) PNPP No. 9308 Rev. 9/11/00 NQI-1741

9. Remarks:

NO NAMEPLATE/STAMPING PERFORMED DUE TO THE INTERFACE CONTROLS OF PART 3 SECTION 1.8.6 BEING IN EFFECT AND JURISDICTIONAL AUTHORITY CONCURRENCE HAVING BEEN RECEIVED. Note: Attach all applicable Manufacturer's Data Reports. Supplemental sheets such as lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in.,(2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded on the front of this form. CERTIFICATE OF COMPLIANCE I, Michael J Tepsick , certify thatto the best of my knowledge and belief the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and to the National Board Inspection Code "NR' rules. National Board Certificate of Authorization No. 33 to use the "NR stamp expires 28 Sept. 20 11 Date 5 JUNE 20 09 Signed FENOC-PNPP .*"-K2 DC Tech. O/"'f (name of repairorganization) (authori.ed representabtve) (title) CERTIFICATE OF INSPECTION/INSERVICE INSPECTION I, Thomas G. Laos * ,holding a validcommission issued by The National Board df Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HSB CT. of Hartford, Conn. have inspected the repair, modification or replacement described in this report onSUL.a 20 ga- and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code "NR* rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or Doss of any kind arising from or connected with this inspection. Date 5 June , 20 09 Signed -"rE , eI Commissions NB 9330 "N" "I""A" Ohio Comm. (inspector) (National Board (include endorsements), andjurisdiction,end no.)

REPORT NO. P0059-012

           '7ý65\ WOB \06e_                                                 ýON
                         ;~oINv1 AUCS-I.Ast~db~
                                          *     - " *  .. ..        i¸ f~) 1. Manu4acrursd try           T A.R GE         iR-0 K*

ManZacrucre-d lor ~ ~ I4L 7~EfO~

      -. Locsrion af rInsclIzziofl      Pe!               k!
                                                          ............                          ~'t2lL~.       A-FI
c. ________ 6B. 1.2 :51OQ
                           --               V6,dhN.

Scl Pras--Urq (.PS G) D6 Stamenpd c.-pqdsV -. Hydrs~stzsth Tesi (PSIGft~loit 4Z J.,Sj.

7. Pressre- Rp-taining Fieces .

soo~- . . ITd .-.

                                                                                                                                      .~

________________________ ~T7RI. S c ie ~ r, S o.............................. ~ Bolin Ali .......... SIM..

      *Supooemenrat sheests in form of lists. sIke~c.es or drawings may pats ý_                          pSvd-04i 5~ sW             x in items 1-2 on -zhis daa report is 'inriuded On eah sheet. and jM s5a                               ee s        bý      od~

re--,rded at -top of this form.

                                        -his forT. !EaX0O7)          MaY be Cbtained from toIe 0-ai-E         .       345 E- 47 St-    yTi.7.P.tOt 173

~Th\G~Y\%_cDQ~4 ~W\~ ~M\L~\ 4i~9\a7 We cardy rf.at -he sumtmerns mania in :nis rs-ort a .. Os ant mba'lhisi 'aive~cr~ 1 t~J ~ f S~ _f Nt2 ASME Co~de 'or NucF!a Po-mP o~oomentsz:S (IL.b'i..~ ~dr'~______ cn~Ie C.Žss No. . -- .

           ~   __________s;oned                     Th n.et RoD.               CC- 'o                                               '.

Our A7SME Carzifýt3 of Auti~onzzio-r No. 39t ~Je.W~ syre-nbofexpires__I C-taiin Inforn1iiof ant fils at arqtRc tr~ anafysis rleport .(Clano In~f~e'. . I S-. *~n~-~-..'n-.crrrSa nc'~.g.!i~ ~444~ g~~ Jso o

  • ofiz __________. ~ b.;5 ri epr on .

apr1,, oco'o~t .inig.

                                                                                                    ..~s
                                                                                                     .eto Sioned                                        '-/".                          C   M~tsnon.       .          __._._._._.__._._._._.
                                                                                                                                                                   -y

REPORT NO. P0059-012 IE51-147 NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As required by the Provisions of the ASME Code Section XI PNPP No. 9308 Rev. 9/11/00 NQ1-1741

1. Owner: FIRSTENERGY CORP. Date 06/12/09 10 Center Road. Perry. Ohio 44081 Sheet 1 of 2
2. Plant: Perry Nuclear Power Plant (PNPP) Unit one 10 Center Road. Perry Ohio 44081 ORDER 200275849 R/O (RepairOrg. P.O. No., etc.)
3. Work Performed By: FIRSTENERGY Nuclear Operating Company PNPP Type Code Symbol Stamp NR 10 Center Road. Perry. Ohio 44081 Authorization No. 33 Expiration Date 09-26-2011
4. Identification of System: 1E51 RX ISOLATION COOLING SYSTEM
5. (a) Applicable Construction Code: ASME SECTION IIICLASS NB cOr-s, .1974 Edition NAME/SECTION/DIVISION/CLASS 7&-,.
                                                                                    .]2jOPi WINTER            19 75       Addenda      Code Case(s) N/A (b) Construction Code used for repairs, modifications. or replacements:       1974            winter 75       NA Edition      Addenda        Code Case(s)

(c) ASME Code Section XI applicable for Inservice Inspection: 1889 NA NA Edition Addenda Code Case(s) (d) Applicable Edition of Section XI Utilized for Repairs, Modification, or Replacements: 19 89 n/a 19 n/a Addenda n/a Code Case(s) (e) Design Responsibilities First Energy Nuclear Operating Company PNPP

6. Identification of Components Repaired, Modified, or Replacement Components Name of Name of Manufacturer ther tNat. Year Repair, ASME Component Manufacturer Serial No. I Board ID. Built Replacement, Code No. or Modification Stamped VALVE ROCKWELL RA-53 824 1E51`F06S 1982 REPLACEMENT YES 7, Description of Work: Installed new disk SIN H4460-10. Also replaced (2) 1-3/8-8 studs Ht #D145 and (4) 1-3/8-8 hex nuts Ht# TBX.
8. Test Conducted: Hydrostatic- F] Pneumatic- El Nominal Operating Pressure- Z Other- Ej Pressure 1030_ psi Test Temperature 150 degrees F Code Case(s) N/A 174

NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back) PNPP No. 9306 Rev. 9/11/00 NOI-1741

9. Remarks: N/A NO NAMEPLATE/STAIM PING PERFORMED DUE TO THE INTERFACE CONTROLS OF RA-2370 BEING IN EFFECT AND JURISDICTIONAL AUTHORITY CONCURRENCE HAVING BEEN RECEIVED.

Note: Attach all applicable Manufacturer's Data Reports. Supplemental sheets such as lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded on the front of this form. CERTIFICATE OF COMPLIANCE I. John W. Messenoer , certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and to the National Board Inspection Code "NR' rules. National Board Certificate of Authorization No. 33 to use the "NR stamp expir9-26 20 11 Date _ _ 20 Signed FENDC-PNPP .DQE (name of repairorganization) authorized representative) (title) CERTIFICATE OF INSPECTION/INSERVICE INSPECTION I, Thomas Laps ,holding a valid. commission issued by The National Board of Boiler arid Pressure Vessel Inspectors ar certificate of competency issued by the jurisdiction of OHIO and employed by HSBJ.&ýI CT. of HARTFORD have inspected the repair, modification or replacement described in this report on,ýms,- G7, 20 O" and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerningthe work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any'manner for any personal injury, property damage or loss of any kind arising from or connected with this inspection. Date m. 20 q Signed ji o ommissions NB 9330 "N""I""A" OHIO COMM. (inspgcto"11 (National Board (include endorsements), andiurisdiction,and no.)

REPORT NO. P0059-012 FORM N-2 CERTIFICATE HOLDERS' DATA REPORT FOR IDENTICAL NUCLEAR PARTS AND APPURTENANCES* As Required by the Provisions of the ASME Code, Section I(( Not to Exceed One Day's Production pg. 1 of 2 Flowserve Corporation 19D00 S Saunders St Paleiah, NC

     -' Manufactured and certified by S:-name                             and addre-s a' NPT Certificate Hold-r)
2. hManufactured for First Energy Corp/Accounts Payable/P.O. Box 6100 Johnstown, PA 15907-6100 Iname -nd addrees of purcha-trl Perry Main Warehouse/Perry Nuclear Power Plant/ 10 Center Road, Perry OH 44081
3. Location of installation lIn- Sod addres)

D82-24401-17 P/F SAlDS N/A N/A 2009

4. Type Idraains is) (ma..(. spC.. ns. lnrlie strengttl ICRN) year built)
5. ASIME Code, Section I1[,Division 1: ___________

1974 Winter, 1975 1 N/A

                                                                  ?Zdzideet N/A addenda da-)                                bloCs)

N/A fled, CoeC r. N/A N Revision N/A Date N/A

6. Fabricated in accordance with Cont. Spec. (Div. 2 only)
7. Remarks: DISC FOR DISC PLSTON ASSY FOR Special Int Class 6.3 Testable Piston Check Va)ve S.0. 78312 B. Nom. thickness (in.) N/A Min. design thickness (in.) Per #4 Dia. ID (it & in.) N/A Length overall (ft & in.) N/A
9. When applicable, Certificate Holders' Data Reports are attached for each item of this report:

Part or Appurtenance IBoard INationa.1 No. Part or Appurtenan-e National Board No- { Sorial Number in Namerica) Order Serial Number in Numerical Order 144460-10 N/A (27) (28) (29) (30) (31) (32) - (33) (34) .... (35)' ' " (13) (36) (37) .. (38) (39) (40) (121)___________ (42)- (23) (43).. . (44) 1241) ___________ (45) ... . (25) ___________ (46)- (47)- (48) (49) (50) _ _ _ _ _ _ I - I

10. Design pressure psi. Temp. * "F. Hydro; test pressure
  • Ilwh-n Ppri-blt) at temp. °F Supplemental information in the farm of lists, sketches, or drawing; may be used provided (1) size is 8112x 11, (2) information in items 2 and 3 cn this Data Report is included on each sheet, (3) each sheet is numbered and the number of shee-ts is recorded at the top of this fare.

(IIItS) 175

FORM N-2 (Batk - Pg. 2 of 2 ~ H4C1 / H .46O-10 N/A Certificate Holder's Serial Nos. through CERTIFICATION OF DESIGN Design soecifloations certified by N/A P.E. State N/A Reg. no. N/A wh-n opplie-sblo Design report* certified by N/A P.E. State N/A Reg. no. N/A CERTIFICATE OF COMPLIANCE Parts We certify that the statements made in this report are corrmt and that this (these) conforms to the rules of construction of the ASMS Code, Section III, Division 1. H-1563" !26 ---- NPT Certificate of Authorization No. Expires Dat I 1 _7Name Flow __rve Corporation Signed DateT Hams Signed ',-.--) CERTIFICATE OF INSPECTION I, the undersigned, h6lding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of NC and employed by HSR CT of Hartford CT have inspected these items described in this Data Report on 3/ 0q/o* , and state that to the best of my knowledge and belief, the Certificate Holder has fabricated these parts or appurtenances in accordance with the ASME Code, Section ]Il, Division 1. Each part listed has been authorized for stamping on the date shown above. By signing this certificate, neithertlte inspector nor his employer makes any warranty, expressed or implied, concerning the equipment described in this Data Report- Furthermore, neither the inspector nor his employer shall be liable in any manner for any personal injury or property damage or loss of any kind arising from or connected with this inspection. Date I Signed_ __in____d__ _. C ommissions ____________ r_"__n. Sine Ioýte 1N't d lni

                                                                                                                ýeoýsdNoie      edrcsneslendsmie or pros, and no.)

REPORT NO. P0059-012

                                                                                                     -E51-148 NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As required by the Provisions of the ASME Code Section XI PNPP No. 9308 Rev. W1f1/00                                                                                        NQI-1741
1. Owner: FIRSTENERGY CORP. Date 06/17/09 10 Ce'nt-er Road Pprrv~ Ohio 44081 SheetI . of 1
2. Plant: Perry Nuclear Power Plant (PNPP) Unit one 10 Center Road, Perry, Ohio 44081 ORDER 200280623 R/O (Repair Org. P.O. No., etc.)
3. Work Performed By: FIRSTENERGY Nuclear Operating Company PNPP Type Code Symbol Stamp NR 10 Center Road. Perry. Ohio 44081 Authorization No. 33 Expiration Date 09-26-2011
4. Identification of System: 1E51 RX ISOLATION COOLING SYSTEM
5. (a) Applicable Construction Code: ASME SECTION III CLASS NB CL4-<: / .1974 Edition NAME/SECTION/DIVISION/CLASS "L i17z..J WINTER 19 75 Addenda Code Case(s) N/A (b) Construction Code used for repairs, modifications, or replacements: 1974 winter 75 NA Edition Addenda Code Case(s)

(c) ASME Code Section XI applicable for Inservice Inspection: 1889 NA NA Edition Addenda Code Case(s) (d) Applicable Edition of Section XI Utilized for Repairs, Modification, or Replacements: _1Z 19 89 n/a 19 n/a Addenda n/a Code Case(s) (e) Design Responsibilities First Enrergy Nuclear Operating Company PNPP

6. Identification of Components Repaired, Modified, or Replacement Components Name of Name of Manufacturer Nat. Other Year 1 Repair, ASME Component Manufacturer Serial No. Board ID. BuiltI Replacement, Code No. or Modification Stamped PIPING PULLMAN 1E51 84 1E51 1985 REPLACEMENT YES SYSTEM POWER H0072
7. Description of Work: Replaced snubber SIN 97-614263-32 with new snubber SIN 30800103/009 using new bracket assembly SIN N2038.
8. Test Conducted: Hydrostatic- E1 Pneumatic- E] Nominal Operating Pressure- L] Other- fl Pressure N/A psi Test Temperature N/A degrees F Code Case(s) N/A 176

NIS-2JNR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back) ?NPP No. 9308 Rev. 9/11/00 NQI-1741

9. Remarks: N/A NO NAMEPLATE/STAMPING PERFORMED DUE TO THE INTERFACE CONTROLS OF RA-2370 BEING IN EFFECT AND JURISDICTIONAL AUTHORITY CONCURRENCE HAVING BEEN RECEIVED Note: Attach all applicable Manufacturers Data Reports. Supplemental sheets such as lists, sketches, or, drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded on the front of this form.

CERTIFICATE OF COMPLIANCE I, John W. Messenger , certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and to the National Board Inspection Code "NR" rules. National Board Certificate of Authorization No. 33 to use the "NR stamp expires 9-26 20 11 Date 6/17 . 20 09Signed - FENOC-PNPF' ,'QL r- QE (name of repairorganization) authorizedrepresent tive) (title) CERTIFICATE OF INSPECTION/INSERVICE INSPECTION I, Thomas Laps ,holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by R *-L C-7, of HARTFORD, CiT have inspected the repair, modification or replacement described in this report on&dL-4Z 320 O', and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code 'NR' rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from or connected with this inspection. Date 20 (5( Signed "-hIri-%-,t,* +/- Commissions NB 9330 "N""I""A" OHIO COMM. (inspector) i.j (NationalBoard (include endorsements), andjurisdiction,and no.)

REPORT NO. P0059-012 I!E51-149 NIS-2INR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As required by the Provisions of the ASME Code Section XI PNPP No. 9308 Rev. 9/11/09 NOI-1741

1. Owner. FIRSTENERGY CORP. Date 05/17/09 10 Center Road. Perry, Ohio 44081 Sheet 1 of 2
2. Plant: Perry Nuclear Power Plant (PNPP) Unit one 10 Center Road. Perrv Ohio 44081 ORDER 200073626 R/O A-2 (Repair Org. P 0. No., etc.)
3. W\ork Performed By: FIRSTENERGY Nuclear Operating Comoanv PNPP Type Code Symbol Stamp N.RA 10 Center Road. Perry. Ohio 44081 Authorization No. 33 Expiration Date 09-28-2011
4. Identification of System: 1E51 RX ISOLATION COOLING SYSTEM
5. (a) Applicable Construction Code: ASME SECTION III CLASS NC CL-ý* 2 .. .19 74 Edition NAME/SECTION/DIVISION/CLASS Ti&U-Lý'J2./bl WINTER 19 75 Addenda Code Case(s) N/A (b) Construction Code used for repairs, modifications, or replacements: 1974 winter 75 NA Edition Addenda Code Case(s)

(c) ASME Code Section X1 applicable for Inservice Inspection: 1889 NA NA Edition Addenda Code Case(s) (d) Applicable Edition of Section XI Utilized for Repairs, Modification, or Replacements: 1989 n/a 19 n/a Addenda n/a Code qase(s) (e) Design Responsibilities First Energy Nuclear-Operating Company PNPP

6. Identification of Components Repaired, Modified, or Replacement Components Name of Name of Manufacturer Nat. Other Year Repair, ASME Component Manufacturer Serial No. Board ID. Built Replacement, Code No.

N . . or Modifibation Stamped PIPING PULLMAN 1E51 84 N/A 1985 REPLACEMENT YES SYSTEM POWER

7. Description of Work: Replaced 1-1/2 'CHECK VALVE WITH NEW CHECK VALVE SIN 051030 -6 @ 1E51-F0061 USING NEW 1-1/2 C.S PIPE SIN 2M33358, 2"X2"X3/8 C.S.ANGLE SIN JC7699, AND WELD ROD HEAT NQ'S CP7808, 065905.
8. Test Cofnducted: Hydrostatic- E) Pneumatic- D1 Nominal Operating Pressure- X Other- E]

Pressure 67.7 psi Test Temperature 70 degrees F

  • Code Case(s) N418-2 177

NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back) PNPP No. 9308 Rev. 9/11/D0 NOI-1741

9. Remarks: NI/A NO NAMEPLATE/STAMPING PERFORMED DUE TO THE INTERFACE CONTROLS OF RA-2370 BEING IN EFFECT AND JURISDICTIONAL AUTHORITY CONCURRENCE HAVING BEEN RECEIVED.

Note: Attach all applicable Manufacturer's Data Reports. Supplemental sheets such as lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded on the front of this form. CERTIFICATE OF COMPLIANCE I, John W. Messenger , certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and to the National Board Inspection Code "NR" rules. National Board Certificate of Authorization No. 33 I-e the "NR stamp expire 9 20 11 Date 6/18 20 09 Signed FENOC-PNPP DOE (name of repairorganization)I (authorizedrepresentative) (title) CERTIFICATE OF INSPECTION/INSERVICE INSPECTION I, Thomas.Laps ,holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by .'rs2i C."C. of HARTFORD have inspected the repair, modification or replacement described in this report on 2 20

  • and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code 'NR" rules.

By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage r loss of any kind arising from or connected with this inspection. Date U ,120 0ý Signed7!Lfý 4k,,*- Commissions NB 9330 "N" "I"A" OHIO COMM.

                                                   -("in'spect7"\*                          (NationalBoard (include endorsements),

and jurisdiction,andno.)

REPORT NO. P0059-012

                                         -~     ~~       # j'                          .      DATA PACKRC -0 .                         051D30 FORM'YPV- I CERTIFICATE HOLD ERS                                 DATAk REORT. FOR -NtCLE-AR POv-                                  OR VALVE S 2.AeReqcrired by the Provisions of the AS                                                  Code, Section IY1, C                                     Division 1 Pg. 1 of.           2
1. 'Anuactured'anid-certifi.ed by VE~rblq DqC. -2125 W4ARD.AV'-,M0NTRfiAL.QUf33C C?.NAOA H4M)2'S
2. Maiu~factw'red for A&ReA 11- 3 315 -A OLD "POREST RD.. ,,LYNCHBURG, V2- , DSAk, .2 450 1
3. LouaLtiion of iaatallation FIRST S12,kRGY CORP. StE1P.f ?Lkiq7 STOE'EOOM, 110 C11tTE Rd. NOprs' PtE, 6H 40 4t 81
     ..4~odel N4o.Sac                 4. or. Type:        PISTON CHE-CK Drawirn5g                                      ~1PT...~                      N01409
                                                                                                                                                            /A
   .5. I5153     Code`,   §eortioxx  KIt,     Dlivision      1            1.974                  W1975                         2____               N/_____

(cebbon) (Wft14a date) (cbss) (Cod Cast Tno.)

  *5Plinsp or valve               .VALVZ           kotoinal inlet aize                     1 M.           Outlet si~ze           I  5
7. Mdaterial: Body SA-IDin COVER S-A-105 . DiSC NOPEM-'02. Bolting S-k-193,GR 37 S-k-1-94,C-P.2H (a) (b) (c) (d)

Body Disk Cart. Nat'l COv-R Bolder ' s Board Serial Serial Se.ria Nao. Mo. No. No. No.- 05103-I LA . /: NNTl f/C:. Me5PIW . /C: 210r,

         .051030-2                           N/AM    .               /C:        3....l                  f/C:     MtPKtJ3                S/C:      '21J 051"030-3                          N/A                   H/C:          AMI5_I-NI              f/C:     MPPK-U3                a/C:      21JL
         ý051030-4                          N/A                   "aH/C:       ii0r.l          . .       l/C.: bPKv3                    H/C:      23-a 05.1030-5                         N/A    .               H/C:'       .XMMiRl                 a/C:      HMPKU3                 H/C:      2ZJ 051030-6                          N4/A                   H/C: '         NR._N1               H/C: , NOPKO3                    H/C:      21J
                   .51`030-7                N/A          .          /C:          4K-5I1                H/C: .MMPK(-3                    H/C:      21, Suncisctal infoa-,ntian         ofEsts, infLoon     skhtobcs,ordonwingsmnay be assd provided     (J)siza is 8 112-                 inhmitttI fthbuab4 x 1, (2)intformnnion                  onthisDataReport isintludcd on casbrt,-(3) intin sheto   zonbcred aid Oh cen~bc nfnhnnts I's                               inrondrdtd at thetopofthis    fon=
           *This ir (E=37) maybeobt~ioO fromthtnCider       Dept.ASM?.      22 LAW DR.VF,Box 2300. Fird *NJ             0.3.           .            FRA....?

PAG 3 ýF-178

FOPM NPV-1 (Back - Pg--2. ___________-__ Cert~ilc2ýte aolders Seri l NO. 051030

8. Design Ooaditiouns 500 psi 358 -F or. valve presseure class '600 (l)
9. Cold wo*r~:_g pressure .1640 psi at lbo*F 10.: Eydrostatic test .- 2175 psi. Disk differ'e-atial test -r-esure f "50
                                                                                                                                                              .si-II.' Remar-s:               KPEIALS.oFIET ASE SECTION II                                 MDIT1OI*: 1995                  ADDE=DA:       1996
          "*  .             *.-*>*~~1ý z::- "y-/q
                                              -i ~~~~;
                                                  '.:~
  • r* * .z z/ I:

A .. , CERTIFICATZ OF DESIGN Design Specification certified by R.D.- STAD!EL. P.E.. State OHIO Reg. no. 6201027244 Design report certified by S. ISBITSKY . P.E. State QDE Reg. no. .22115 I j CEPTIricKTI 0F COME'LIANCE We certify that the s6atements made iLn this report are torrect and that this pump or valve conforms to'the*i-+/-les for construction of the ASME Code, Section 1I, -Division 1. N Certificate of.Autborization No. N-2797-1 .Excpires APR 20,2007 Dte *Nae 2 V2LAia INC. Signed

                                                        ... N Ccrtflcom*                          -ode                             Ircpr
                                                                                                                                        *-=kz-)

CEPTI:IciATC 6ý I'smscrzoli I, thfd underiigned, hold-ing a valid commission issued by the National Board of Boiler and Pr--essure Vessel Inspectors and the State or Provin6e of OUEBEC Q and employed by REGGR DU BATI*ENT f. QUEBEC have inspected the. pump, or valve, described in this pata Report oo Ov~'c'2) 't, O2." and sthge.that to the lest of my knowledge and belief, the Certificite Holder hhas nintructed this 'pump, or val've, in accordaic& with the ASNE Code, Sectio- I1I, Division'1 . " . ."- . .." By signimg this certificate,. h ,eithr h.6r:7pioyer h.s .. ma k's.-..'y. warranty, e,~pressed 9rm;ipli~eu concer~ning theucomonent deýai~din -this Da-ta. Report.- Furtjhernore,* neither the insýpector .nor s. emaloyar shall. be liable in- any'manner for any' personal or. property d aýgý.J.-PA.ACHINEM or. a.L 16 ' . o y k' d arising from or cohnected with this inspection. QC Iý"I Dat-. " . .' ""s .gned Com issins "EBEC (AutDeozn Inspmlr ( Naft Bd, ajUNM -W-,V. (1) For mah' ally operated valves only. 0 SUP

REPORT NO. P0059-012 IE51-!50 NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As required by the Provisions of the ASME Code Section XI PNPP No. 9308 Rev. 9111100 NQI-1741

1. Owner: FIRSTENERGY CORP Date 06/24/09 10 Center R;ad1 Perrv OhinA-40R1 Sheet 1 of 1
2. Plant: Perry Nuclear Power Plant (PN4PP1 Unit one 10 Center Road. Perry, Ohio 44081 ORDER 200328428 RJO (Repair Org. P.O. No., etc.)

3.

3. W\iork Performed By: FIRSTENERGY Nuclear Operating Company PNPP Type Code Symbol Stamp NR 10 Center Road, Perry, Ohio 44081 Authorization No. 33 Expiration Date 09§-2--2011 4.
4. Identification of System: 1E51 RX ISOLATION COOLING SYSTEM
5. (a) Applicable Construction Code: ASME SECTION III CLASS NB czi-s ' .1974 Edition NAME/SECTION/DIVISION/CLASS -, L "/-i WINTER 19 75 Addenda Code Case(s) N/A (b) Construction Code used for repairs, modifications, or replacements: 1974 winter 75 NA Edition Addenda Code Case(s)

(c) ASIME Code Section XI applicable for Inservice Inspection: 1889 . NA NA Edition Addenda Code Case(s) (d) Applicable Edition of Section XI Utilized for Repairs, Modification, or Replacements: 1989., n/a 19 n/a Addenda n/a Code Case(s) (e) Design Responsibilities First Energy Nuclear Operating Company PNPP

6. Identification of Components Repaired, Modified, or Replacement Components Name of Name of Manufacturer Nat. 1 Other Year Repair, Replacement, ASME Code Component Manufacturer Serial No. Board ID. Built No. or Modification Stamped PIPING PULLMAN 1E51 84 1E51 1985 REPLACEMENT YES SYSTEM POWER H2074
7. Description of Work: Replaced snubber S/N 29948 with new PSA 1/4 snubber S/N 34879.
8. Test Conducted: Hydrostatic- IZ Pneumatic- Fh Nominal Operating Pressure- [] Other- LI Pressure N/A psi Test Temperature N/A degrees F Code Case(s) N/A 179

NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back) PNPP No. 9308 Rev. 9/11/00 NQI-1741

9. Remarks: N/A NO NAMEPLATE/STAMPING PERFORMED DUE TO THE INTERFACE CONTROLS OF RA-2370 BEING IN EFFECT AND JURISDICTIONAL AUTHORITY CONCURRENCE HAVING BEEN RECEIVED.

Note: Attach all applicable Manufacturer's Data Reports. Supplemental sheets such as lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded on the front of this form. CERTIFICATE OF COMPLIANCE. I, John W. Messenger , certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Sectibn XI of the ASME Code and to the National Board Inspection Code "NR' rules. National Board Certificate of Authorization No. 33 to use the "NR stamp expires 946 20 11 Date 6/24 2009 Signed FENOC-PNPP ______ QE name of repairorganization) - u horized representaive (ttie) CERTIFICATE OF INSPECTION/INSERVICE INSPECTION 1, Thomas Laps holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HSB CT. of HARTFORD CONN. have inspected the repair, modification or replacement described in this report on 1A .Zb20.L._ and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damag eloss of any kind arising from or connected with this inspection. Date . 20 C Signed "t"- r,-..-. Commissions NB 9330 "N" "I"."A' OHIO COMM.

                                                    ..nspecta*ý'  *                          (National Board (include endorsements),

and jurisdiction, and no.)

REPORT NO. P0059-012 Ar_,ý_l - / 5,1 NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As required by the Provisions of the ASME Code Section XI PNPP No. 9305 Roy. 9(11/00 NOI- 1 741

1. Owner: FIRSTENERGY CORP. Date 6-29-9 10 Center Road. Perry. Ohio 44081 Sheet 1 of 1
2. Plant: Perry Nuclear Power Plant (PNPP) Unit 1 10 Center Road. Perry. Ohio 44081 200263398 (Repair Org. P.O. No., etc.)
3. Work Performed By: FIRSTENERGY Nuclear Oparatino Comoany PNPP Type Code Symbol Stamp NR 10 Center Road. Perry, Ohio 44081 Authorization No. 33 Expiration Date 09/28/2011
4. Identification of System: REACTOR CORE ISOLATION COOLING 1E51
5. (a) Applicable Construction Code: ASME Section III Class 1 .1974 . Edition NAME/S ECTION/DIV1S IO N/CLA SS WINTER 19 75 Addenda Code Case(s) *.N413. N275, N242, N241, N224, 1728, 1644-5 (b) Construction Code used for repairs, modifications, or replaciements: 1974 W 75
                                                                                    .Edition      Addenda Code Case(s)

(c) ASME Code Section X1 applicable for Inservice Inspection: 1989 none none Edition Addenda Code Case(s) (d) Applicable Edition of Section XI Utilized for Repairs, Modification, or Replacements: 19 89__ 19 none Addenda none Code.Case(s) (e) Design Responsibilities FIRSTENERGY CORP.

6. Identification of Components Repaired, Modified, or Replacement-Components Name of Name of Manufacturer Nat Other Year Repair, ASME Component Manufacturer Serial No. Board ID. Built Replacement, Code No. or Modification Stamped PIPING PULLMAN IE51 84 1E51 1985 Replacement YES SYSTEM POWER
7. Description of Work: INSTALLED HEAD SPRAY PIPING USING .3 STUDS 1 3/8-8 HT# D145 AND 8 NUTS 1 3/8-8 HT# TBX FOR FLANGE 1. USED 1 NUT 13/8-8 HT# TBX FOR FLANGE 2. SEE REMARKS.
8. Test Conducted: Hydrostatic-.[] Pneumatic- El Nominal Operating Pressure- [ Other- fl Pressure 1036 psi Test Temperature 143 degrees F Code Case(s) N/A 180

NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back) PNPP No. 9308 Rev. 9/11 /DO N01-1741_

9. Remarks: USED 1 NUT 1 1/8-8 HT# TRS FOR FLANGE 3. USED 1 STUD 7/8-9 HT. X492 AND 2 NUTS 7/8-9 HT# 2A73 FOR FLANGE 4.

NO NAMEPLATE/STAMPING PERFORMED DUE TO THE INTERFACE CONTROLS OF PART 3 SECTION 1.8.6 BEING IN EFFECT AND JURISDICTIONAL AUTHORITY CONCURRENCE HAVING BEEN RECEIVED. Note: -Attach all applicable Manufacturer's Data Reports. Supplemental sheets such as lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded on the front of this form. CERTIFICATE OF COMPLIANCE 1, Michael J Tepsick certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and to the National Board Inspection Code 'NR" rules. National Board Certificate of Authorization No. 33 to use the "NR stamp expi es 28 Sept.. 20 11 Date 29 JUNE. 20 09 Signed FENOC-PNPP QC Tech. (name of repair organization) (authori;ed representative) (title) CERTIFICATE OF INSPECTIONIINSERVICE INSPECTION I. Thomas G. Laos holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HSB CT. of Hartford, Conn. have inspected the repair, modification or replacement described in this report on 2 -q 20 Oq and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code 'NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or losof any kind arising from or connected with this inspection. Date 20 09 Signed AI. ommissions NB 9330 "N"""A" Ohio Comm. (inspected (NationalBoard finclude endorsements), and jurisdiction,and no.)

REPORT NO. P0059-012 1033-172 NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As required by the Provisions of the ASME Code Section X1 PNP No. 9308 Rov. 9/11/00 NOI-1741 1 Owner. FIRSTENERGY CORP Date 6/16/09 110 Center Road, Perry, Ohio 44081 Sheet 1__ of 3

2. Plant Perry Nuclear Power Plant (PNPP) Unit one 10 Center Road, Perry, Ohio 44081 order 200360835 R/O (RepairOrg. P.O. No., etc.)
3. Work Pearormed By: FIRSTENERGY Nuclear Operating Company PNPP Type Code Symbol Stamp NR 10 Center Road Perrv Ohio 44081 Authorization No. 33 Expiration Date 9/26/2011
4. Identification of System: 1G33 Reactor Water Cleanup
5. (a) Applicable Construction Code: ASME Sectionll NNC cJqS. .1974 Edition NAME/SECTION/DIVISIONICLASS ":*C_.£ -1 qrc'_

Winter 19 75 Addenda Code Case(s) N/A .'-7 6,( (b) Construction Code used for repairs, modifications, or replacements: 1974 W75 N/A Edition Addenda Code Case(s) (c) ASME Code Section XI applicable for Inservice Inspection: 1989 NONE N/A Edition Addenda Code Case(s) (d) Applicable Edition of Section XI Utilized for Repairs, Modification, or Replacements: 1989, NA 19 NA Addenda N/A Code Casels) (e) Design Responsibilities FENOC (PNPP)C

6. Identification of Components Repaired, Modified, or Replacement Components Name of Name of Manufacturer Nat. Other Year Repair, ASME Component Manufacturer Serial No. Board ID. Built Replacement, Code No. I I or Modification Stamped VALVE BORG WARNER 51308 NIA 1G33F040 1979 REPLACEMENT YES
r. Description of Work: Replaced 6W-1500# gate using new gate SIN 321454.
8. Test Conducted: Hydrostatic- El Pneumatic- El Nominal Operating Pressure- Z] Other- E)

Pressure 1266 psi Test Temperature 150 degrees F Code Case(s) 181

NIS-2fNR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back) PNPP No. 9308 Rev. 9/11/00 NQ0-1741

9. Remarks: N/A Note: Attach all applicable Manufacturer's Data Reports. Supplemental sheets such as lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 of this

( report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded the front of this form. CERTIFICATE OF COMPLIANCE 1, JOHN W. MESSENGER, certify that to the best of my knowledge and belief the statements made in this report are I correct and the repair, modification or replacement of the items described above conforms to Section X1 of the ASME Code and to the National Board Inspection Code "NR" rules. National Board Certificate of Authorization No. 33 to use the "NR stamp expires 9-26 20 11 _ Date 6/19_ 20 09 Signed FENOC-PNPP ')**-L O3.--*-4* DE (name of repairorganization) L.- (authorized representative) (title) CERTIFICATE OF INSPECTION/INSERVICE INSPECTION I, T* 'N' . L Mr'_ holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by WS"5 -.-. of ,A...c- ) , s1, have inspected the repair, modification or replacement described in this report on_" 2q20 t and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code "NR' rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage omrloss of any kind arising from or connected with this inspection. Date G._ s, 20 (* Signed L-. Commissions tma, y CV'

                                                  *inspacto-'
  • iNational Boarti (include endorsements),

andjurisdiction, andno.)

REPORT NO. P0059-012 7ý0-sýý llýýM60-10e a'(wv- e!(raý \ -iIAa ýeq 182

~k. ~ ~ ,I Ioqý oq REPORT NO. P0059-012 FORM N-2 CERTIFICATE HOLDERS' DATA REPORT FOR MDEN'TICAL NUCLEAR PARTS AND APPURTENANCES* As Re-quired by the Provisionsof the ASME Code, Secrion IlI Nat t-CE.eead One Day's Production Pg. I of  :: Map--- ... -.- ".. . ..ra/Eri gmmvglrý-c.L rfle mpD Ply. ins A~mkI Dý-x 'EO 2am~~ WeRR y~zms X-~~5 CA~90058 PMotttrf Re,!'tTll'-a~<FO PLRI 10 CE" ROAD-, mm 1,2- PE~y ma0 --

        .Czz on z* Type       2000105,      REVA                   P-S5- S4.05                      70,000 PSI                                N!11                      1956
6. ASM Code, Semion III, Division 1: 1.74 3 17.5 2 il.-
6. Fabricated in accordance with Conev. Sp.- lDiv. 2 only). W'X' Bevision HIA Datn I-4.
7. eRte&v - R/11? 305 IM. SSS PARP..SlE. G s41..r.rma77 ED.-, S197 ADD_ 4U- - O.GY
a. Norn. Thicknesse(in.)b Cetilest-'r/1 Hnido Min. a evss fir .) W4,-

i , iq.' i fPrt or Appurenance ntz.nl .

               .321.116A.S                                           NI.A (15)

(TS)

        *m. .

5 . .. I.zz MP.. (20,j" II\ý 10.. Deslgn pracsure 300 psl. Temp. " rRF, Hydro. xe;.orcssura_ ._______ as temp. -F "So~lpleceel Ifl~ietnlttleel In 6.tame rm o assl. aletshes.md*hInoh.mni, vbe.enr--drtod 8)1(5-=iena1t.5,15t 11. nn glrnlilneb i!erent :lesdtal De*n

s. Rli=eO1 (inedede-h h-, (3) 31 .a.eh ch.., I-nvqem0aendelrd*t a numh -1411rcIeesle.rcrd"et-)he.r agli-It "

IpJ55l Thhi I MEop,40104 r,'vbtobelO r

  • em t-- th OvDm.bDý,.. Amg. 7,4 ,.. Di,, 8ec zsu.', ýIle.ild, ttJ 0.100.5-300.

183

FOPM N-2 (Back P-cP.2 of3.2 Ce,riflare NaIdert 3vriaI No.. 321,54 NI W CERTFlICATiO'4 OF DESIGN N/ -F x~.WA We.n.RA CERDJCAr¶E W: COMPLIANCE

w. aa yItalt thttoawmnu malde in this rnporataam=lyactaad rhar~tfirr acnli-.a to the rul at cfa-,,-tana at thel ASME Cod,. Saadon lit, Diviion I.

14,-T C.-tf -t. t. . .... CERFIP)ASST -OF II4SFSCOOn IfA, poks1d holding a ___ oy7 .....

                                                       .....                         Hatop)                             -y~   -          -     .

a) F~tl~a5 1MS~- -ha's iaafptclcfl adatb afa, 7 laao it a M,oMflon U. Eatlpdrtllaadk'a -- n; dar.' 4d19a0F~LPSf 10dt nbfo aa~otJna~ah

                 .,,O)V.               n4.pdettr-nert I--*Mýýt                                                            ai!oop    1 a~~~

a.~t~30~. hitaa otdlpr tjb canahi, aaS ldfba, .,aa-a*npSa Lty poaaa," lapyt~fflia~lgfroo. o~ Roatawjhizlpalt. __________________Camndaaian m A1s/-§,C1-R:Pv

REPORT NO. P0059-012 1G33-173 NFS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As required by the Provisions of the ASM1E Code Section XI PNPP No. 9308 Rev. 9/11/0D NQI-1741

1. Owner: FIRSTENERGY CORP. Date 6/19/09 10 Center Road, Perry, Ohio 44081 Sheet 1 of 3
2. Plant: PerrtNuclear Pwerr Plant (PNPP1 Unit one 10 Center Road, Perry, Ohio 44081 Order 200360838 R/O (RepairOrg. P.O. No., etc.)
3. Work Performed By: FIRSTENERGY Nuclear ODeratino Comoany PNPP Type Code Symbol Stamp NR 10 Center Road. Perry. Ohio 44081 Authorization No. 33 Expiration Date 9/26/2011
4. Identification of System: 1G33 Reactor Water Cleanup
5. (a) Applicable Construction Code: ASME SectionlllI-B- it/C.- CL.4s. .2 .1974 Edition NAMEISECTION/DIVISIOlN/CLASS - L "

Winter 19 75 Addenda Code Case(s) N/A (b) Construction Code used for repairs, modifications, or replacements: 1974 W75 N/A Edition Addenda Code Case(s) (c) ASME Code Section XI applicable for Inservice Inspection: 1989 NONE N/A Edition Addenda Code Case(s) (d) Applicable Edition of Section XI Utilized for Repairs, Modification, or Replacements: 1989 , NA 19 NA Addenda N/A

                                                       -Code Case(s)

(e) Design ResponsibilitieS FENOC (PNPP)

6. Identification of Components Repaired, Modified, or Replacement Components Name of Name of Manufacturer Nat. Other Year 1 Repair, ASME Component Manufacturer Serial No. Board ID. BuiltI Replacement, Code I I No. or Modification Stamped VALVE BORG WARNER 50671 N/A 1G33F039 1979 REPLACEMENT YES

___ _ __ _ _ _ _ _ _ [ _ _ _ _ _

7. Description of Work: Replaced 6"-1500# gate using new gate S/N 318061.- 2 6,/2.
8. Test Conducted: Hydrostatic- [] Pneumatic- E3 Nominal Operating Pressure- 0 Other- LI Pressure 1269 psi Test Temperature 150_ degrees F Code Case(s) 184

NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back) PNPP No. 9308 Rev. 9/11100 NOI-1741

9. Remarks: N/A Note: Attach all applicable Manufacturers Data Reports. Supplemental sheetssuch as lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded on the front of this form.

CERTIFICATE OF COMPLIANCE I. JOHN W. MESSENGER, certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and to the National Board Inspection Code "NR' rules. National Board Certificate of Authorization No. 33 to use the "NR stamp expires 9-26 20 11 Date 6/19_ 20 09_ Signed FENOC-PNPP DE (name of rmpair organization) 'a-faflfriz~d representative) (title) CERTIFICATE OF INSPECTION/INSERVICE INSPECTION 1, -T'*( S6 Cy,-' , -A holding a valid commission issued by,The National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by A5'? CT71.-- of " P-/. .. ("-. have inspected the repair, modification or replacement described in this report on ZT 20 ' and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section Xl of the ASME Code and the National Board Inspection Code "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from or connected with this inspection. Date __, 2009 Signedd Commissions AA 1A"i Oý CA.

                                            '     (inspectoTr                               (NationalBdard (include endorsements),

and jurisdiction, and no.)

REPORT NO. P0059-012 cS(y cxr~aý\ ~J~ ~~O\QLa\&6w QCýCXA 185

-~ ~c~Ž~e ~if'~N~x\ ,Iýgo

  • REPORT NO. P0059-012 1~

~MoA\ c~C iA\8{~ 186

SAMT bJa'&1,19&)o9 PREPORT NO. P0059-012

                                                                                                        ~-                  00~5 NIS-2INR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As required by the Provisions of the ASME Code Section XI PNPP No. 9308 Rev. 9/11/00                                                                                              1NOI-1741
1. Owner: PIRSTENERGY CORP Date 4-21-09 I0 Center Road. Perry. Ohio 44081 Sheet 1 of 1
2. Plant: Perrv Nuclear Power Plant (PNPP) Unit 1 10 Center Road, Perry, Ohio 44081 200281931 (RepairOrg. P.O. No., etc.)
3. Work Performed By: FIRSTENERGY Nuclear Operating Company PNPP Type Code Symbol Stamp NR 10 Center Road. Perry. Ohio 44081 Authorization No. 33

-I. - .,. - -.- "-.-.---. I Expiration D~ate 09/2/l201 1

4. Identification of System: LOCAL PANELS AND RACKS
5. (a) Applicable Construction Code: ASME Section III Class NC f;*s L. . .1974 Edition NAME/SECTION/DIVISION/CLASS 7t "7-)j(*-

WINTER 19 75 Addenda Code Case(s) N249,N71-11 .N71-9, N71-6, N225. N272. N413 1728 (b) Construction Code used for repairs, modifications, or replacements: 1974 W 1975 none Edition Addenda Code Case(s) (C) ASME Code Section XI applicable for Inservice Inspection: 1989 none none Edition Addenda Code Case(s) (d) Applicable Edition of Section XI Utilized for Repairs, Modification, or Replacements: 1989,__ 19 none Addenda none Code Case(s) (e) De'sign Responsibilities FIRSTENERGY CORP. ...

6. Identification of Components Repaired, Modified, or Replacement Components Name of Name of Manufacturer Nat Other Year Repair, ASME Component Manufacturer Serial No. Board ID. Built Replacement, Code No. or Modification Stamped PIPING JOHNSON 1B21 N/A N/A 1985 Replacement YES SYSTEM CONTROLS
r. Description of Work: REPLACED SNUBBER SIN 34264 WITH SNUBBER S/N 28138.

PLANT ID 1H22-H2761.

8. Test Conducted: Hydrostatic- Z Pneumatic- E] Nominal Operating Pressure- E] Other- Li Pressure N/A psi Test Temperature N/A degrees F Code Case(s) N/A 187

NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back) PNPP No. 9305 Rev. 9/11/00 NQI-1741

9. Remarks:

NO NAMEPLATE/STAMPING PERFORMED DUE TO THE INTERFACE CONTROLS OF PART 3 SECTION 1.8.6 BEING IN EFFECT AND JURISDICTIONAL AUTHORITY.CONCURRENCE HAVING BEEN RECEIVED. Note: Attach all applicable Manufacturer's Data Reports. Supplemental sheets such as lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded on the front of this form. CERTIFICATE OF COMPLIANCE 1, Michael J TeDsick certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section Xl of the ASME Code and to the National Board Inspection Code "NR" rules. National Board Certificate of Authorization No. 33 to use the "NR stamp expires 28 Sept. , 20 11 Date 21APRIL 20 09 Signed FENOC-PNPP J" Q." ..- QC Tech. (name of repairorganization) (authorizedrepreientativef ft/ite) CERTIFICATE OF INSPECTION/INSERVICE INSPECTION I, Thomas G. Laos holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HSB CT. of Hartford, Conn. have inspected the repair, modification or replacement described in this report on AkŽc42a,20 C9 and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance With Section XI of the ASME Code and the National Board Inspection Code "NR* rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from or connected with this inspection. Date .1. 20 0L.. Signed tVP-d2J ý Commissions -NB 9330 "N" "I""A"Ohio Comm. (National Board (include endorsements), and jurisdiction, and no.)

REPORT NO. P0059-012 NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As required by the Provisions of the ASME Code Section XI PNPP No. 9308 Rev. 9111/00 NQI-1741

1. Owner: FIRSTENERGY CORP. Date 3-24-2009 10 Center Road, Perry, Ohio 44081 Sheet 1 of 1
2. Plant: Perry Nuclear Power Plant (PNPP) Unit 1 10 Center Road. Perry. Ohio 44081 200276695 (RepairOrn. P.O. No., etc.)
3. Work Performed By: FIRSTENERGY Nuclear Doeratinq Comoany PNPP Type Code Symbol Stamp NR 10 Center Road. Perry. Ohio 44081 Authorization No. 33 Expiration Date 09/28/2011
4. Identification of System: 1M17 CONTAINMENT VACUUM RELIEF
5. (a) Applicable Construction Code: ASME Section III Class Z" 1974 Edition NAME/SECTION/DiViSIoI/ClLASS WINTER 19 75' Addenda Code Case(s) N272, 1644-5 (b) Construction Code used for repairs, modifications, or replacements: 1974 W 1975 none Edition Addenda Code Case(s)

(c) ASME Code Section XI applicable for Inservice Inspection: 1989 none none Edition Addenda Code Casels) (d) Applicable Edition of Section X1 Utilized for Repairs, Modification, or Replacements: 1989__,_ 19 none Addenda none Code Case(s) (e) Design Responsibilities FIRSTENERGY CORP.

6. Identification of Components Repaired, Modified, or Replacement Components Name of Name of Manufacturer Nat. Other Year[ Repair, ASME Component Manufacturer Serial No. Board ID. - BuiltI Replacement, 'Code No. or Modification Stamped PIPING PULLMAN 1M17 N/A N/A 1985 Replacement YES SYSTEM POWER
7. Description of Work: REPLACED SNUBBER SIN 29534 AND 25957 WITH SNUBBERS S/N 42992 AND SIN 42991. PLANT ID 1M17HO002 AND 1M17H0003.

S/N 42991. PLANT ID 1M17HOO02 AND 1M17HQQ03.

8. Test Conducted: Hydrostatic- Z Pneumatic- El Nominal Operating Pressure- Fl Other- [

Pressure N/A psi Test Temperature N/A degrees F Code Case(s) N/A 188

NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back) PNPP No. 9308 Rev. 91111D0 NQI-1741

9. Remarks:

NO NAMEPLATE/STAMPING PERFORMED DUE TO THE INTERFACE CONTROLS OF PART 3 SECTION 1.8.6 BEING IN EFFECT AND JURISDICTIONAL AUTHORITY CONCURRENCE HAVING BEEN RECEIVED. Note: Attach all applicable Manufacturer's Data Reports. Supplemental sheets such as lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded on the front of this form. CERTIFICATE OF COMPLIANCE I, Michael J Tepsick certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and to the National Board Inspection Code "NR" rules. National Board Certificate of Authorization No. 33 to use the "NR stamp ex ires 28 Seot. . 20 11 Date 25 March 20 09 Signed FENOC-PNPP . -. OC Q Tech. (name of repair organization) (authorized representative) (title) CERTIFICATE OF INSPECTIONIINSERVICE INSPECTION I, Thomas G. Laps ,holdinb avalid commission issued by The National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HSB CT. of Hartford, Conn. have inspected the repair, modification or replacement described in this report on M/RA*__* 20 DR and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or I ss of any kind arising from or connected with this inspection. Date 3_. ., 20 1L. Signed " '-. - Commissions NB 9330 "N" "I" "A" Ohio Comm. (inspector) k (NationalBoard (include endorsements), andjurisdiction, andno.)

REPORT NO. P0059-012

                                                                                                     / co6' NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As required by the Provisions of the ASME Code Section XI PNPP No. 9308 Rev. 9111 /00                                                                                         NQI-1741 1 Owner:                        FIRSTENERGY CORP.                                          Date     3-24-2009 10 Center Road, Perry, Ohio 44081                                 Sheet 1           of     1
2. Plant: Perry Nuclear Power Plant (PNPP) Unit 1 10 Center Road. Perry. Ohio 44081 200276692 (Repair Org. P.O. No., etc.)
3. Work Performed By: FIRSTENERGY Nuclear Operating Company PNPP Type Code Symbol Stamp NR 10 Center Road. Perry. Ohio 44081 Authorization No. 33 Expiration Date 09/28/2011
4. Identification of System: 1M17 CONTAINMENT VACUUM RELIEF
5. (a) Applicable Construction Code: ASME Section III Class/,7. 1974 Edition NAME/S ECTION/DIVISION/CLASS WINTER 19 75 Addenda Code Case(s) N272, 1644-5 (b) Consiruction Code used for repairs, modifications, or replacements: 1974 W 1975 none Edition Addenda Code Case(s)

(c) ASME Code Section XI applicable for Inservice Inspection: 1989 none none Edition Addenda Code Case(s) (d) Applicable Edition of Section Xl Utilized for Repairs, Modification, or Replacements: 19 89___ 19 none Addenda none Code Case(s) (e) Design Responsibilities FIRSTENERGY CORP.

6. Identification of Components Repaired, Modified, or Replacement Components Name of Name of Manufacturer Nat. Other Year Repair, ASME Component Manufacturer Serial No. Board ID. Built Replacement, Code No. or Modification Stamped PIPING PULLMAN 1M17 N/A N/A 1985 Replacement YES SYSTEM POWER
7. Description of Work: REPLACED SNUBBER S/N 29538 AND 26001 WITH SNUBBERS S/N 42989 AND S/N 42990. PLANT ID 1M17H0005 AND 1M17HO006.
8. Test Conducted: Hydrostatic- f] Pneumatic- ED 'Nominal Operating Pressure- F1 Other- D Pressure N/A psi Test Temperature N/A degrees F Code Case(s) N/A 189

NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back) PNPP No. 9305 Rev. 9/11/00 NQI-1741

9. Remarks:

NO NAMEPLATE/STAMPING PERFORMED DUE TO THE INTERFACE CONTROLS OF PART 3 SECTION 1.8.6 BEING IN EFFECT AND JURISDICTIONAL AUTHORITY CONCURRENCE HAVING BEEN RECEIVED. Note: 'Attach all applicable Manufacturer's Data Reports. Supplemental sheets such as lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded on the front of this form. CERTIFICATE OF COMPLIANCE I, Michael J Tepsick , certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and to the National Board Inspection Code "NR' rules. National Board Certificate of Authorization No. 33 to use the "NR stamp expires 28 ser., 20 11 Date 25 March. 20 09 Signed FENOC-PNPP /-'%-.Y/ " OC Tech. (name of repairorganization) (authorizedrepresentative) (title) CERTIFICATE OF INSPECTION/INSERVICE INSPECTION I, Thomas G..Laps ,holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HSB CT. of Hartford, Conn. have inspected the repair. modification or replacement described in this report on QMAA2L" 20 o.. and state that to the best of my knowledge and belief, this repair, modification or ieplacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from or connected with this inspection. Date 2 20 Sgnd Commissions NB 9330 "N""I"A"Ohio Comm. (inspector)I (National Board (include endorsements), andjurisdiction,and no.)

REPORT NO. P0059-012 NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As required by the Provisions of the ASME Code Section XI PNPP No. 9308 Rev. 9/11/00 NOI-1741

1. Owner FIRSTENERGY CORP Date 4-13-9 10 Center Road, Perry, Ohio 44081 Sheet 1 of 1
2. Plant: Perry Nuclear Power Plant (PNPPh4 Unit 1 10 Center Road, Perry, Ohio 44081 200276693 (RepairOrg. P.O. No., etc.)
3. Work Performed By: FIRSTENERGY Nuclear Operating Company PNPP Type Code Symbol Stamp NR 10 Center Road. Perry, Ohio 44081 Authorization No. 33 Expiration Date 09/28/2011
4. Identification of System: 1M1 7 CONTAINMENT VACUUM RELIEF
5. (a) Applicable Construction Code: ASME Section III Class 2 Edition
                                                                                              ,1974 NAME/SECTION/DIVISION/CLASS WINTER             19 75      Addenda      Code Case(s) N272, 1644-5 (b) Construction Code used for repairs, modifications, or replacements: 1974                 W 1975          none Edition      Addenda        Code Case(s)

(c) ASME Code Section XI applicable for Inservice Inspection: 1989 none none Edition Addenda Code Case(s) (d) Applicable Edition of Section XI Utilized for Repairs, Modification, or Replacements: 19 89__ 19 none Addenda none Code Case(s) (e) Design Responsibilities FIRSTENERGY CORP.

6. Identification of Components Repaired, Modified, or Replacement Components Name of Name of Manufacturer Nat. Other Year Repair, ASME Component Manufacturer Serial No. Board ID. Built Replacement, Code No. or Modification Stamped PIPING PULLMAN 1M17 N/A N/A 1985 Replacement YES SYSTEM POWER 7 Description of Work: REPLACED SNUBBER SIN 29506 AND 29601WITH SNUBBERS S/N 42987 AND SIN 42988. PLANT ID 1M17H0008 AND 1M17H0009.
8. Test Conducted: Hydrostatic- E] Pneumatic- EI Nominal Operating Pressure- EI Other- LI Pressure N/A psi Test Temperature N/A degrees F Code Case(s) N/A 190

NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back) PNPP No. 9308 Rev. 9/11/00 NOI-1741

9. Remarks:

NO NAMEPLATE/STAMPING PERFORMED DUE TO THE INTERFACE CONTROLS OF PART 3 SECTION 1.8.6 BEING IN EFFECT AND JURISDICTIONAL AUTHORITY CONCURRENCE HAVING BEEN RECEIVED. RECEIVED. 1.8.6 BEING IN EFFECT AND JURISDICTIONAL AUTHORITY CONCURRENCE HAVING BEEN Note: Attach all applicable Manufacturer's Data Reports. Supplemental sheets such as lists, sketches, or drawings may be used, provided (1) size is B 1/2 in. x 11 in., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded on the front of this form. CERTIFICATE OF COMPLIANCE I, Michael J Tepsick . certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and to the National Board Inspection Code "NR" rules. National Board Certificate of Authorization No. 33 to use the "NR stamp expires 28 Sept. , 20 11 Date 13 April , 20 O9 Signed FENOC-PNPP OC Tech. (name of repairorganization) (authorizedrepresentative) (title) CERTIFICATE OF INSPECTION/INSERVICE INSPECTION L'Thomas G. Laps ,holding a valid commission issued.by The National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HSB CT. of Hartford, Conn. have inspected the repair, modification or replacement described in this report on Mr- JI, 20 Oct and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising. from or connected with this inspection. Date 4 Ile, 20 QA. Signed -fVg/ Commissions -NB 9330 "N""I' A" Ohio Comm. (inspecbfI4 - (NationalBoard (include endorsements), andjurisdiction,and no.)

REPORT NO. P0059-012 NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As required by the Provisions of the ASME Code Section XI PNPP No. 9308 Rev. 9/11/00 NQI-1741

1. Owner: FIRSTENERGY CORP. Date 4-25-9 10 Center Road. Perry. Ohio 44081 Sheet 1 of 1
2. Plant: Perry Nuclear Power Plant (PNPP) Unit 1 10 Center Road. Perry. Ohio 44081 200276694 (Repair Org. P.O. No., etc.)
3. Work Performed By: FIRSTENERGY Nuclear Operating Company PNPP Type Code Symbol Stamp NR 10 Center Road. Perry. Ohio 44081 Authorization No. 33 .

-1* I-Expiration Date 09/28/201 1

4. Identification of System: 1 M17 CONTAINMENT VACUUM RELIEF
5. (a) Applicable Construction Code: ASME Section III Class 2 1974 Edition NAME/SECTION/DIVISION/CLASS WINTER 19 75 Addenda Code Case(s) N272, 1644-5 (b) Construction Code used for repairs, modifications, or replacements: 1974 W 1975 none Edition Addenda Code Case(s)

(c) ASME Code Section Xl applicable for lnservice Inspection: 1989 none none Edition Addenda Code Case(s) (d) Applicable Edition of Section Xl Utilized for Repairs, Modification, or Replacements: 1989 __ 19 none Addenda none Code Case(s) (e) Design Responsibilities FIRSTENERGY CORP. "

6. Identification of Components Repaired, Modified, or Replacement Components Name of Name of Manufacturer Nat. Other Year Repair, ASME Component Manufacturer Serial No. Board ID. Built Replacement, Code No. or Modification Stamped PIPING PULLMAN 1M17 N/A N/A 1985 Replacement YES SYSTEM POWER
7. Description of Work: REPLACED SNUBBER S/N 29255 AND 29256 WITH SNUBBERS SIN 43324 AND SIN 43327. PLANT ID 1M17HOOl AND 1M17H0012.
8. Test Conducted: Hydrostatic- El Pneumatic- [I Nominal Operating Pressure- E] Other- E]

Pressure N/A psi Test Temperature N/A degrees F Code Case(s) N/A 191

NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back) PNPP No. 9308 Rev. 9/11100 NQI-1741

9. Remarks:

NO NAMEPLATE/STAMPING PERFORMED DUE TO THE INTERFACE CONTROLS OF PART 3 SECTION 1 R~R~ IN FFFFCT AND Jll~lSnlC~TICM'JAl Al ITHflRITY CflNCI 1RRl~NCl~ HAVINC~ P~N RFCRVI~D 1 8 6 BEING IN EFFECT AND JURISDICTjQNAL AUTHORITY CONCURRENCE HAVING BEEN RECEIVED I. .1 Note: Attach all applicable Manufacturer's Data Reports. Supplemental sheets such as lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 of this report Is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded on the front of this form. CERTIFICATE OF COMPLIANCE 1, Michael J Tepsick certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and to the National Board Inspection Code "NR" rules. National Board Certificate of Authorization No. 33 to use the "NR stamp expires 28 Sept. , 20 11 Date 25 April 20 09 Signed FENOC-PNPP OC Tech. (name of repairorganization) (authorj/edieprpsentative) (titde) CERTIFICATE OF INSPECTION/INSERVICE INSPECTION I, Thomas C. Laos ,holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HSB CT. of Hartford, Conn. have inspected the repair, modification or replacement described in this report on R 20 0 - and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code 'NR* rules. By signing this certificate, neither the 'undersigned nor my employer makes any warranty, expressed or implied, concerning the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from or connected with this inspection. Date 20 0A_ Signed "-,,o4 Z Commissions NB 9330 "N 1" "A" Ohio Comm. (inspector'- (National Board(include endorsements), andjurisdiction, and no.)

REPORT NO. P0059-012

                                                                                                                          /0-/-~

NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As required by the Provisions of the ASME Code Section XI PNPP No. 9308 Rev. 911/100 NOI-1741

1. Owner: FIRSTENERGY CORP. Date 10/4/07 10 Center Road. Perry. Ohio 44081 Sheet 1 of 1
2. Plant: Perry Nuclear Power Plant (PNPP) .Unit 1 10 Center Road. Perrv. Ohio 44081 200153518 (RepairOrg. P.O. No., etc.)
3. Work Performed By: FIRSTENERGY Nuclear Ooeratino Comoany PNPP Type Code Symbol Stamp NR 10 Center Road. Perry, Ohio 44081 Authorization No. 33 Expiration Date 9/28/08
4. Identification of System: CUMBUSTIBLE GAS CONTROL 1 M51
5. (a) Applicable Construction Code: ASME SECTION III CLASS 2 1974 Edition NAME/SECTION/DIVISION/CLASS Winter 19 75 Addenda Code Case(s) NONE (b) Construction Code used for repairs, modifications, or replacements: 1974 W75 N/A Edition Addenda Code Case(s)

(c) ASME Code Section XI applicable for Inservice Inspection: 1989 NONE N/A Edition Addenda Code Case(s) (d) Applicable Edition of Section XI Utilized for Repairs, Modification, or Replacements: 19 89 19 N/A Addenda N/A Code Case(s) (e) Design Responsibilities First Energy Corp

6. Identification of Components Repaired, Modified, or Replacement Components Name of Name of Manufacturer Nat. Other Year Repair, ASME Component Manufacturer Serial No. Board ID. Built Replacement, Code No. or Modification Stamped VALVE BORG WARNER 53874 N/A 1M51F10b 1980 REPLACEMENT YES
7. Description of Work: INSTALLED 36 BONNET/BODY 5/8 - 11 HH NUTS 21 HT# 506C AND 15 HT#P762 8: Test Conducted: Hydrostatic- E] Pneumatic- [] Nominal Operating Pressure- [I Other- E]

Pressure N/A psi Test Temperature N/A degrees F - Code Case(s) N/A 192

NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back) PNPP No. 9308 Rev. 9/11/00 NOI-1741

9. Remarks:

NO NAMEPLATE/STAMPING PERFORMED DUE TO THE INTERFACE CONTROLS OF RA-2370 BEING IN EFFECT AND JURISDICTIONAL AUTHORITY CONCURRENCE HAVING BEEN RECEIVED. Note: Attach all applicable Manufacturer's Data Reports. Supplemental sheets such as lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded on the front of this form. CERTIFICATE OF COMPLIANCE 1, Michael J Tepsick certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and to the National Board Inspection Code "NR' rules. National Board Certificate of Authorization No. 33 to use the "NR stamp expires 28 Sept. , 20 08 Date 4 OCT. 20 07 Signed FENOC-PNPP . I*O*Z'/ OC Tech. (name of repairorganization) (authorized representative) (title) CERTIFICATE OF INSPECTION/INSERVICE INSPECTION I, Thomas G Laps ,holding a valid commnission issued by The National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HSB CT. of Hartford, Conn. have inspectedthe repair, modification or-replacemenl described in this report on DCX, (N . 20 ý3 and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code 'NR* rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from or connected with this inspection. Date I 20 c:7 Signed Commissions NB 9330 "N" "I""A" Ohio Comm. (inspector) . (National Board (include endorsements), andjurisdiction,and no.)

REPORT NO. P0059-012 NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As required by the Provisions of the ASME Code Section XI PNPP No. 9308 Rev. 9/11100 NOI-1741

1. Owner: FIRSTENERGY CORP. Date 10/4/07 10 Center Road, Perry, Ohio 44081 Sheet 1 of 1
2. Plant: Perry Nuclear Power Plant (PNPP) Unit 1 10 Center Road, Perry, Ohio 44081 200153517 (RepairOrg. P.O. No., etc.)
3. Work Performed By: FIRSTENERGY Nuclear Operating Company PNPP Type Code Symbol Stamp NR.

10 Center Road, Perry. Ohio 44081 Authorization No. . 33 Expiration Date 9/28/08

4. Identification of System: COMBUS'tIBLE GAS CONTROL 1M51
5. (a) Applicable Construction Code: ASME SECTION III CL 1974 Edition NAME/SECTION/DIVIS I Winter 19 75 .Addenda Code Case(s)

(b) Construction Code used for repairs, modifications, or replacements: 1974 W75 N/A Edition Addenda Code Case(s) (c) ASME Code Section XI applicable for Inservice Inspection: 1989 NONE N/A Edition Addenda Code Case(s) (d) Applicable Edition of Section XI Ubilized for Repairs, Modification, or Replacements: 19 89 19 N/A Addenda N/A Code Case(s) (e) Design Responsibilities First Energy Corp

6. Identification of Components Repaired, Modified, or Replacement Components Name of Name of Manufacturer Nat. Other Year Repair, ASME Component Manufacturer Serial No. Board ID. Built Replacement, Code No. or Modification Stamped VALVE BORG WARNER 53873 N/A 1M51F10a 1980 REPLACEMENT YES
7. Description of Work: INSTALLED 36 BONNET/BODY 5/8 - 11 HH NUTS HT# 506C.
8. Test Conducted:' Hydrostatic- LI Pneumatic- E- Nominal Operating Pressure- LI Other- EI Pressure N/A psi Test Temperature N/A degrees F Code Case(s) N/A 193

NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back) PNPP No. 9308 Rev. 9/11/00 NQI-1741

9. Remarks:

NO NAMEPLATE/STAMPING PERFORMED DUE TO THE INTERFACE CONTROLS OF RA-2370 BEING IN EFFECT AND JURISDICTIONAL AUTHORITY CONCURRENCE HAVING. BEEN RECEIVED. Note: Attach all applicable Manufacturer's Data Reports. Supplemental sheets such as lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded on the front of this form. CERTIFICATE OF COMPLIANCE I, Michael J TeDsick , certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and to the National Board Inspection Code "NR* rules. National Board Certificate of Authorization No. 33 to use the 'NR stamp expires 28 Sept. 20 08 Date 4 OCT. 20 07 Signed FENOC-PNPP .AO 1 f) -- '-< DC Tech. (name of repairorganization) (authorized representative) (title) CERTIFICATE OF INSPECTION/INSERVICE INSPECTION I, Thomas G Laps holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HSB CT. of Hartford Conn. have inspected the repair, modification or replacement described in this report on P 20 OCT and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied. concerning. the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from or connected with this inspection. Date V 20 Signed Commissions NB 9330 "N" "I""A"Ohio Comm.

                                                  *(inspector) '-. X.JP
                                                                        "(National                      Board rinclude endorsements),

and jurisdiction,and no.)

REPORT NO. P0059-012 1- -o( 7 NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As required by the Provisions of the ASME Code Section Xl PNPP No. 9308 Rev. 9/11/00 N10-I" 741I 41

1. Owner FIRSTENERGY CORP. Date 4-27-9 10 Center Road, Perry, Ohio 44081 Sheet 1 of I
2. Plant: Perry Nuclear Power Plant (PNPP) Unit 1 10 Center Road, Perry, Ohio 44081 200284468 (RepairOrg. P.O. No:, etc.)
3. Work Performed By: F.IRSTENERGY Nuclear Operating Company PNPP Type Code Symbol Stamp NR 10 Center Road, Perry, Ohio 44081 Authorization No. 33 Expiration Date 09128/2011
4. Identification of System: MAIN, REHEAT, EXTRACTION, AND MISC. DRAINS 1N22
5. (a) Applicable Construction Code: ASME Section III Class 2 1974 Edition NAME/SECTION/DIVISION/CLASS' WINTER 19 75 Addenda Code Case(s) N272, 1644-5 (b) Construction Code used for repairs, modifications, or replacements: 1974 W 1975 none Edition Addenda Code Case(s)

(c) ASME Code Section XI applicable for Inservice Inspection: 1989 none none Edition Addenda Code Case(s) (d) Applicable Edition of Section XI Utilized for Repairs, Modification, or Replacements: 19 89_____ 19 none Addenda none Code Case(s) (e) Design Responsibilities FIRSTENERGY CORP.

6. Identification of Components Repaired, Modifi'ed, or Replacement Components Name of Name of Manufacturer Nat Other Year Repair, ASME Component Manufacturer Serial No. Board ID. Built Replacement, Code No. or Modification Stamped PIPING PULLMAN 1M17 N/A N/A 1985 Replacement YES SYSTEM POWER 7 Description of Work: REPLACED SNUBBER S/N 15988 WITH SNUBBER S/N 18237.

PLANT ID 1N22H0089.

8. Test Conducted: Hydrostatic- Li Pneumatic- E] Nominal Operating Pressure- Li Other- Li Pressure N/A psi Test Temperature N/A degrees F Code Case(s) N/A 194

NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back) PNPP No. 9308 Rev. 9111/00 NOI-1741

9. Remarks:

NO NAMEPLATE/STAMPING PERFORMED DUE TO THE INTERFACE CONTROLS OF PART 3 SECTION 1.8.6 BEING IN EFFECT AND JURISDICTIONAL AUTHORITY CONCURRENCE HAVING BEEN RECEIVED. Note: Attach all applicable Manufacturer's Data Reports. Supplemental sheets such as lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded on the front of this form. CERTIFICATE OF COMPLIANCE I, Michael J Tepsick , certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and to the National Board Inspection Code "NR' rules. National Board Certificate of Authorization No. 33 to use the "NR stamp expires 28 Sept. , 20 11 Date 27 April , 20 09 Signed FENOC-PNPP .,;;4,.. - 1**- OC Tech. (name of repairorganization) (authdrizedrepresehtative) (title) CERTIFICATE OF INSPECTION/INSERVICE INSPECTION I, Thomas G. Laos ,holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO

 .and employed by       HSB CT.                                                of Hartford, Conn.                              have inspected the repair, modification or replacement described in this report on                Z.i 20 ,1.       and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code "NR* rules.

By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from or connected with this inspection. Date 20 Signed Commissions NB 9330 "N""l' 'A"Ohio Comm. (inspector) "(National Board (include endorsements), andjurisdiction,and no.)

REPORT NO. P0059-012

                                                                                                     /A)J2- 2       -~ 0     "'

NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS PNPP No. 9308 Rev. 9/11 /00 As required by the Provisions of the ASME Code Section XI NQI- 1741

1. Owner: FIRSTENERGY CORP. Date 4-27-9 10 Center Road. Perry, Ohio 44081 Sheet I of 1
2. Plant: Perry Nuclear Power Plant (PNPP) Unit 1 10 Center Road. Perry. Ohio 44081 200284471 (RepairOrg. P.O. No., etc.)
3. Work Performed By: FIRSTENERGY Nuclear Operating Comoany PNPP Type Code Symbol Stamp N[R 10 Center Road, Perry, Ohio 44081 -Authorization No. 33 I

Expiration Date 09/28/2011

4. Identification of System: MAIN, REHEAT, EXTRACTION, AND MISC. DRAINS 1N22
5. (a) Applicable Construction Code: ASME Section III Class 1 ,1974 Edition NAME/SECTION/DIVISION/CLASS WINTER 19 75 Addenda Code Case(s) N272, 1644-5 (b) Construction Code used for repairs, modifications, or replacements: 1974 W 1975 none Edition " Addenda Code Case(s)

(c ) ASME Code Section XI applicable for Inservice Inspection: 1989 none none Edition Addenda Code Case(s) (d) Applicable Edition of Section XI Utilized for Repairs, Modification, or Replacements: 1989,_ 19 none Addenda none Code CaseL(s) (e) Design Responsibilities FIRSTENERGY COFR1.

6. Identification of Components Repaired, Modified, or Replacement Components Name of Name of Manufkcturer NaL Other Year Repair, ASME Component Manufacturer Serial No. Board ID. Built Replacement, Code No. or Modification Stamped PIPING PULLMAN 1N22 N/A N/A 1985 Replacement YES SYSTEM POWER 7..Description of Work: REPLACED SNUBBER S/N 22908 WITH SNUBBER S/N 24405.

PLANT ID 1N22H0148.

8. Test Conducted: Hydrostatic- ] Pneumatic- [] Nominal Operating Pressure- E] Other- []

Pressure N/A psi Test Temperature N/A degrees F Code Case(s) N/A 195

NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back) PNPP No. 9308 Rev. 9/11100 NQI-1741

9. Remarks:

NO NAMEPLATEJSTAMPING PERFORMED DUE TO THE INTERFACE CONTROLS OF PART 3 SECTION 1.8.6 BEING IN EFFECT AND JURISDICTIONAL AUTHORITY CONCURRENCE HAVING BEEN RECEIVED. Note: Attach all applicable Manufacturer's Data Reports. Supplemental sheets such as lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number-of sheets is recorded on the front of this form. CERTIFICATE OF COMPLIANCE I, Michael J lepsick , certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and to the National Board Inspection Code 'NR" rules. National Board Certificate of Authorization No. 33 to use the "NR stamp e pires 28 Sept. 20 11 Date 27 April , 20 09 Signed FENOC-PNPP , /,4" DC Tech. (name of repairorganization) (authorizedrepresentative) (tile) CERTIFICATE OF INSPECTIONIINSERVICE INSPECTION I, Thomas b. Laps ,holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HSB CT. of Hartford, Conn. have inspected the repair, modification or replacement described in this report on 4 20 0i and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or oss of any kind arising from or connected with this inspection. Date . 20 L Signed IVA4 . Commissions NB 9330 "N""I" "A Ohio Comm. (inspector I (National Board rinclude endorsements), andjursdiction,and no.)

REPORT NO. P0059-012 NIS-2JNR-1 OWNER'S REPORT. FOR REPAIRS OR REPLACEMENTS As required by the Provisions of the ASME Code Section XI PNPP No. 9308 Rev. 9/11/00 NQI-1741

1. Owner FIRSTENERGY CORP. Date 5-26-9 10 Center Road, Perry. Ohio 44DB 1 Sheet 1 of 1
2. Plant: Perrv Nuclear Power Plant (PNPP) Unit 1 10 Center Road, Perry, Ohio 44081 200194807 (RepairOrg. P.O. No., etc.)
3. Work Performed By: FIRSTENERGY Nuclear Operating Company PNPP Type Code Symbol Stamp NR 10 Center Road. Perry Ohio 44081 Authorization No. 33 Expiration Date 09/28/2011
4. Identification of System: FEEDWATER 1 N27
5. (a) Applicable Construction Code: ASME Section III Class 2 .1974 Edition NAME/SECTION/DIVISION/CLASS WINTER 19 75 Addenda Code Case(s) N272, 1644-5. N413, N242, N282 (b) Construction Code used for repairs, modifications, or replacements: 1974 W 1975 none Edition Addenda Code Case(s)

(c) ASME Code Section XI applicable for Inservice Inspection: 1989 none none Edition Addenda Code Case(s) (d) Applicable Edition of Section XI Utilized for Repairs, Modification, or Replacements: 19 89__ 19 none Addenda none Code Case(s) (e) Design Responsibilities FIRSTENERGY CORP.

6. Identification of Components Repaired, Modified, or Replacement Components Name of . Name of Manufacturer Nat. Other Year Repair, ASME Component Manufacturer Serial No. Board ID. Built Replacement, Code No. or Modification Stamped PIPING PULLMAN 1N27 89 1N27F828 1985 Replacement YES SYSTEM POWER
                                        *1'                                                                    ______
7. Description of Work: ADD SMALL BORE VENT ISOLATION VALVE AND ASSOCIATED TUBING AND SUPPORTS PER ECP-04-0091 SEE REMARKS SECTION FOR PARTS USED (GREATER THEN 1"I
8. Test Conducted: Hydrostatic- El Pneumatic- [I Nominal Operating Pressure- Ll Other- LI Pressure 46 psi. Test Temperature 78 degrees F . Code Case(s) N-416-3 196

NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back) PNPP No. 9308 Rev. 9/11/00 NQI-1741

9. Remarks: USED THE FOLLOWING PARTS: 1.5" ELBOW HT# 76996, 1.5" TEE HT# 77464, 1.5" PIPE SCH 160 HT# 292064, 1.5" COUPLING HT# 9618, 1.5" X .75" REDUCER HT# 0957, FOUR 1.5" U-BOLTS HT# 269041502193, 2.5"X2.5"X .1875" ANGLE HT# 59972, 2"X2"X.1875"ANGLE HT# JG5237 & JG3525.

USED THE FOLLOWING WELD ROD HT# 159443 065905, CP78D8, CT7339. DM7772, AND P1819. NO NAMEPLATE/STAMPING PERFORMED DUE TO THE INTERFACE CONTROLS OF PART 3 SECTION 1.8.6 BEING IN. EFFECT AND JURISDICTIONAL AUTHORITY CONCURRENCE HAVING BEEN RECEIVED. Note: Attach all applicable Manufacturer's Data Reports. Supplemental sheets such as lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items I through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded on the front of this form. CERTIFICATE OF COMPLIANCE I, Michael J Tepsick certify that to the best of my kn6wledge and belief the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and to the National Board Inspection Code "NR' rules. National Board Certificate of Authorization No. 33 to use the "NR stamp expires 28 Sept. , 20 11 Date 26 MAY 20 09 Signed FENOC-PNPP DC Tech. (name of repairorganization) (au orized representative) "

  • tie)

CERTIFICATE OF INSPECTION/INSERVICE INSPECTION I, Thomas G. Laps holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HSB CT. of Hartford, Conn. have inspected the repair, modification or replacement described in this report onA.Lii.E_. 20 2S and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code "NR' rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage o Aoss of any kind arising from or connected with this inspection. Date 20 Signed . 41 Commissions NB 9330 "N"T'"A" Ohio Comm. (inspecfoor) - I (NationalBoard (include endorsements), andjurisdiction, andno.)

REPORT NO. P0059-012

                                                                                                       /, ,2 7 -

N1S-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As required by the Provisions of the ASME Code Section X1 PNPP No. 9308 Rev. 9/11/DO NOI-1741 I Dwnr"~ FlR£TPNFRrY m*RP Date 6-19-9 10 Center Road. Perry, Ohio 44081 'Sheet 1 of 1

2. Plant: Perry Nuclear Power Plant (PNPP) Unit 1 10 Center Road. Perrv. Ohio 44081 200264675 (RepairOrg. P.O. No., etc.)
3. Work Performed By: FIRSTENERGY Nuclear Operating Company PNPP Type Code Symbol Stamp NR 10 Center Road. Perry. Ohio 44081 Authorization No. 33 Expiration Date 09/28/2011
4. Identification of System: FEEDWATER 1N27
5. (a) Applicable Const-uction Code: ASME Section III Class 1 ,1974 Edition NAME/SECTION/DIVISION/CLASS WINTER 19 75 Addenda Code Case(s) N272, 1644-5, N413, N242, N282 (b) Construction Code used for repairs, modifications, or replacements: 1974 W 1975 Edition Addenda Code Case(s)

(c) ASME Code Section XI applicable for Inservice Inspection: 1989 none none Edition Addenda Code Case(s) (d) Applicable Edition of Section XI Utilized for Repairs, Modification, or Replacements: 19 89 __ 19 none Addenda none Code Case(s) (e) Design.Responsibilities FIRSTENERGY CORP.

6. Identification of Components Repaired, Modified, or Replacement Components Name of Component Name of Manufacturer Manufacturer Serial No.

Nat. Board Other 1D. rI Year Built Repair, Replacement, ASME Code No. or Modification Stamped PIPING PULLMAN 1N27 89 1N27 1985 Replacement YES SYSTEM POWER F559A _ __ _ __.__ I _

7. Description of Work: REMOVED VALVE TEST FITTING FOR INTERNAL INSPECTION AND INSTALLED NEW FITTING HT# 14512. USED FILLER METAL HT # 159443.
8. Test Conducted: Hydrostatic- El Pneumatic- El Nominal Operating Pressure- 0 Other- [I Pressure 1041 psi Test Temperature 143 degrees F Code Case(s) N-416-3 197

NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back) PNPP No. 9308 Rev. 9/11/00 NQI-1741

9. Remarks:

NO NAMEPLATE/STAMPING PERFORMED DUE TO THE INTERFACE CONTROLS OF PART 3 SECTION 1.8.6 BEING IN EFFECT AND JURISDICTIONAL AUTHORITY CONCURRENCE HAVING BEEN RECEIVED. Note: Attach all applicable Manufacturer's Data Reports. Supplemental sheets such as lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded on the front of this form. CERTIFICATE OF COMPLIANCE I, Michael J Tepsick , certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and to the National Board Inspection Code "NR" rules. National Board Certificate of Authorization No. 33 to use the "NR stamp expires 28 Sept. 20 11 Date 19June 20 09 Signed FENOC-PNPP OC Tech. (name of repair organization) *(authelfzed representative) (title) CERTIFICATE OF INSPECTIONIINSERVICE INSPECTION I, Thomas G. Laps holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors and certificate gf competency issued by the jurisdiction of' OHIO and employed by HSB CT. of Hartford, Conn. have inspected the repair, modification or replacement described in this report onlýAIE 20 -Q!.. and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from or connected with this inspection. Date _ 20 _j. Signed' I Commissions NB 9330 "N""I""A Ohio Comm.

                                                   .(inspectorY   .,                          (National Board (include endorsements),

andjurisdiction, and no.)

REPORT NO. P0059-012

                                                                                                      /Pil- 0/f NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As required by the Provisions of the ASME Code Section XI PNPP No. 9308 Rev. 9/11/00                                                                                          N01-1741
1. Owner: FIRSTFNPR('Y CORP Date 4-27-9 10 Center Road. Perry. Ohio 44081 Sheet 1 of 1
2. Plant: Perry Nuclear Power Plant (PNPP) Unit 1 10 Center Road. Perry, Ohio 44081 200323587 (Repair Org. P.O. No., etc.)
3. Work Performed By: FIRSTENERGY Nuclear Operating Company PNPP Type Code Symbol Stamp NR 10 Center Road. PerrY. Ohio 44081 Authorization No. 33

-I Expiration Date 09/28/2011

4. Identification of System: CONDENSATE TRANSFER AND STORAGE 1P11
5. (a) Applicable Construction Code: ASME Section III Cla, 1974 Edition NAMEISECTIONIDIVIS WINTER 19 75 - Addenda Code Case(s)

(b) Construction Code used for repairs, modifications, or replacements: 1974 W 1975 none Edition Addenda Code Case(s) (c) ASME Code Section XI applicable for Inservice Inspection: 1989 none none Edition Addenda Code Case(s) (d) Applicable Edition of Section Xl Utilized for Repairs, Modification, or Replacements: 198,__9 19 none Addenda none Code Case(s) (e) Design Responsibilities FIRSTENERGY CORP.

6. Identification of Comp6nents Repaired, Modified, or Replacement Components Name of Name of Manufacturer Nat. Other Year Repair, ASME Component Manufacturer Serial No. Board ID. Built Replacement, Code No. or Modification Stamped PIPING PULLMAN 1-P11-37 N/A N/A 1983 Replacement YES SYSTEM POWER
7. Description of Work: INSTALLED 12 NEW STUDS 7/8"-9 HT# 55051 AND 24 HH NUTS 7/8"-9 HT# 2C27.

PI ANT Ifl 1P11-~Fr){30. PLANT lD 1P! 1-FOO60

8. Test Conducted: Hydrostatic- E] Pneumatic- F1 Nominal Operating Pressure- E] Other- LI Pressure N/A psi Test Temperature N/A degrees F Code Case(s) N/A 198
  • NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back)

PNPP No. 9308 Rev. 9/1100 " NQI-1741

9. Remarks:

NO NAMEPLATE/STAMPING PERFORMED DUE TO THE INTERFACE CONTROLS OF PART 3 SECTION 1.8.6 BEING IN EFFECT AND JURISDICTIONAL AUTHORITY CONCURRENCE HAVING BEEN RECEIVED. Note: Attach all applicable Manufacturer's Data Reports. Supplemental sheets such as lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 of this report is included on each sheet, and .(3) each sheet is numbered and the number of sheets is recorded on the front of this form. CERTIFICATE OF COMPLIANCE I, Michael J Teosick , certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and to the National Board Inspection Code 'NR" rules. National Board Certificate of Authorization No. 33 to use the "NR stamp expires 28 Sept. , 20 11 Date 27 April , 20 09 Signed FENOC-PNPP / /C Tech. (name of repairorganization) (autdrizedreapresentative) (title) CERTIFICATE OF INSPECTION/INSERVICE INSPECTION

 .1,Thomas G. Laps                                  ,holding a valid commission issued-by The National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of                        OHIO and employed by        HSB CT.                                               of Hartford, Conn.                                have inspected the-repair, modification or replacement described in this report on         A           20 09        and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code "NR" rules.

By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the work described in this reporL Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage ,loss of any kind arising from or connected with this inspection. Date 20 0 *L Signed t Commissions NB 9330 "N" "I""A"Ohio Comm. rinspectbr?( (National Board (include endorsements), anojurisodction, ano no.J}}