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Submittal of Eleventh Inservice Inspection Summary Report
	ML072250365
Person / Time
Site:	Perry
Issue date:	08/07/2007
From:	Allen B S; FirstEnergy Nuclear Operating Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	FOIA/PA-2010-0209, PY-CEI/NRR-3050L
	Download: ML072250365 (328)
	v • d • e

{{#Wiki_filter:FENOC Perry Nuclear Power Station* 10 Center Road FirstEnergy Nuclear Operating Company Perry, Ohio 44081 Barry S. Allen 440-280-5382 Vice President Fax: 440-280-8029 August 7, 2007 PY-CEI/NRR-3050L ATTN: Document Control Desk United States Nuclear Regulatory Commission Washington, D.C. 20555 Perry Nuclear Power Plant Docket Number 50-440 License Number NPF-58

Subject:

Perry Nuclear Power Plant Eleventh Inservice Inspection Summary Report Ladies and Gentlemen: 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 Eleventh Inservice Inspection Summary Report (Form NIS-1)is enclosed. This report documents the inservice examination activities conducted from return to commercial operation from the tenth refueling outage until completion of the eleventh refueling outage.There are no regulatory commitments contained in this letter or its enclosure. If there are any questions or if additional information is required, please contact Mr. Thomas A. Lentz, Manager -FENOC Fleet Licensing, at (330) 761-6071.Sincerely,

Enclosure:

FirstEnergy Nuclear Operating Company Perry Nuclear Power Plant Eleventh Inservice Inspection Summary Report cc: NRC Region III Administrator NRC Resident Inspector NRR Project Manager Authorized Nuclear Inservice Inspector Ohio Department of Commerce, Boiler Inspection Section Enclosure PY-CEI/NRR-3050L FirstEnergy Nuclear Operating Company Perry Nuclear Power Plant Eleventh 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 Generation Corp. & Ohio Edison Co., 76 South Main Street, Akron, OH 44308 (Name and Address of Owner)Perry Nuclear Power Plant, 10 Center Road, Perry, OH 44081 2. Plant (Name and Address of Plant)3. Plant Unit 1 4. Owner Certificate of Authorization (if required) N//5. Conmmercial Service Date 11/18/87 6. National Board Number for Unit N/A 7. Components Inspected (only the systems with Class 1 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 11B13 64077 Nuclear Boiler System GE/A& ES I B21 1 B21 64084 Nuclear Boiler System Pullman Power Products I B21 I B21 109 Reactor Recirculation System GE/A&ES I B33 I B33 64076 Reactor Recirculation System Pullman Power Products I B33 I B33 I119 CRD Hydraulic Control System Pullman Power Products 101 lCI 1 92 Standby Liquid Control System Pullman Power Products I C41 I C41 108 Containment Atmosphere Monitoring Johnson Controls I D23-0064-F I D23 008 Residual Heat Removal System Engineers & Fabricators Company ME12 1El2 1621 Residual Heat Removal System Pullman Power Products IE12 I E12 83 Containment Spray System Pullman Power Products I E 15 IE 15 105 Low Pressure Core Spray System Pullman Power Products 1 E21 1 E21 85 High Pressure Core Spray System Pullman Power Products I E22 I E22 86 Leak Detection System Johnson Controls I E31-0068-F I E31 15 MSIV Leakage Control System Pullman Power Products I E32 I E32 104 Reactor Core Isolation Cooling System Pullman Power Products I E51 I E51 84 Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (I) size is 8/2 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 fornt.This Form (E00029) may be obtained from the Order Dept., 22 Law Drive, Box 2300, Fairfield, NJ 07007-2300 FORMI NIS-1 (Back)8. Examination Dates 5/7/05 to 9. Inspection Period Identification: Third Pc 10. Inspection Interval Identification: Second 5/13/07 eriod 11. Applicable Edition of Section XI 1989 Addenda None 12. Date/Revision of Inspection Plan: Rev 11, PNPP Inservice Examination Program Plan, dated 2/22/07 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 P0059-0011" 14. Abstract of Results of Examinations and Tests.See attached summary report P0059-0011

15. Abstract of Corrective Measures.See attached summary report P0059-0011

- Report is 180 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 I'/ p " Signed FENGENCO&OE By 4b Owner CERTIFICATE OF INSERVICE 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 Ohio and employed by Hartford Steam Boiler of Hartford, CT have inspected the components described in this Owner's Report during the period 5/7/05 to 5/13/07 , 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 Xl.By 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. Ise___ors__ _ Commissions NB9330 "N"," B ", & "A", Ohio Commission Inspector's Signat1Jfe National Board, State, Province, and Endorsements Date 10-7, Page 2 of 2 1. Owner FirstEnergy Nuclear Generation Corp. & Ohio Edison Co., 76 South Main Street, Akron, OH 44308 (Name and Address of Owner)Perry Nuclear Power Plant, 10 Center Road, Perry, OH 44081 2. Plant (Name and Address of Plant)3. Plant Unit 1 4. Owner Certificate of Authorization (if required) N/A 5. Conmmercial 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 I E61 I E61 120 Fuel Transfer System General Electric I F42 I F42 64079 Reactor Water Cleanup System GE/A&ES 1G33 1 G33 64075 Reactor Water Cleanup System Pullmnan Power Products 1G33 1 G33 100 Fuel Pool Cleaning System Pullman Power Products I G41 I G41 95 Suppression Pool Drain and Cleanup System Pullnan Power Products IG42 IG42 96 Suppression Pool Makeup System Johnson Controls I G43-0065-F 1 G43 019 Containment Vessel Purge System Pullnan Power Products I M 14 1 M 14 113 Drywell Vacuum Relief System Pullnan Power Products IM1 6 1 M 16 115 Containment Vacuum Relief System Pullnan Power Products I M1 7 I M 17 87 Combustible Gas Control System Pullnan Power Products I M51 I M51 106 Main Steam System Pullnan Power Products IN II I NII Ill Main, Reheat, and Miscellaneous Drains Pullnan Power Products IN22 IN22 112 Feedwater System Pullman Power Products 1N27 1N27 89 Condenser Transfer and Storage System Pullnan Power Products IPI I IPII 102 Mixed Bed Demineralizer Water Sys. Pullnan Power Products 1 P22 I P22 73 Nuclear Closed Cooling System Pullnan Power Products I P43 I P43 101 Containment Chilled Water System Pullnan Power Products I PSO I P50 103 Service Air System Fisher Controls 6393471 1 P51 6170 Instrument Air System Pullnan Power Products I P52 1 P52 74 Post Accident Sampling System Johnson Controls I P87 1 P87 034 Containment System Newport News NNI-OS-02 IT23 N/A REPORT NO. P0059-0011 INSERVICE INSPECTION

SUMMARY

REPORT FOR PERRY NUCLEAR POWER PLANT (PNPP)UNIT #1 LOCATED AT: 10 Center Road Perry, Ohio 44081 OWNER: FirstEnergy Nuclear Generation Corp. & Ohio Edison Co.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: COMMERCIAL OPERATION DATE: INSPECTION INTERVAL: INSPECTION PERIOD: REFUELING OUTAGE: DOCUMENT COMPLETED: 50-440 NPF-58 1305 November 18, 1987 November 18, 1998 -May 17, 2009 Third (Nov 18, 2005 -May 17, 2009)RFO11 July 17, 2007 1 REPORT NO. P0059-0011 ABSTRACT Perry Nuclear Power Plant (PNPP) Unit #1 was shutdown for approximately eight weeks to refuel the reactor vessel [Refueling Outage ll(RFOII)] and perform plant maintenance commencing April 2, 2007. 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 American Society of Mechanical Engineers (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 1 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 11.Automated and manual ultrasonic examinations were performed on the lower course, and one upper course, reactor pressure vessel dissimilar metal nozzle to safe-end welds (previously Category B-F, now Risk Informed R-A) .These included one of the two Recirculation outlet (Nl) nozzles, the 10 recirculation inlet (N2) nozzles, the two Jet Pump Instrumentation (N9) nozzles, and Feedwater nozzle N4E. These examinations met the new ASME Section XI, Appendix VIII, Supplement 10 requirements. No relevant indications were found in the lower course welds and pre-existing flaws in the upper course N4E weld were found to be unchanged. 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 Inservice Inspection (ISI), which is documented in Relief Request IR-049.In-vessel examinations consisted of the required Code visual examinations along with augmented visual examinations of numerous vessel interior components. The augmented visual examinations were primarily conducted in accordance with the Boiling Water Reactor Vessel and Internals Project (BWRVIP) inspection guidelines. Follow-up examinations of the minor jet pump wedge wear that was found on jet pump 15 in RFO10, and which was evaluated as acceptable for operation through RFOII, were performed and the wear was found to be unchanged (documented in Condition Reports (CRs) 05-02242 and 07-18578). Follow-up examinations were also performed on the vessel interior crud deposits found during RFO9. The crud deposits were found to be essentially unchanged (documented in CRs 03-01995 & 05-01928). Finally, follow-up examinations were performed on the SHSAM bolts for the anti-rotation pin wear found in RFO9 and the wear was found to be acceptable for another cycle of operation (documented in CRs 03-02831, 05-01794 and 07-18329). Other than described above, there were no reportable indications. RFOll was the first refueling outage of the third Inspection Period within Perry's second 10-Year Inservice Inspection Interval. With the completion of the Cycle 11 and RFOII examinations, approximately 55% 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, and all required corrective actions and/or evaluations were completed. 2 REPORT NO. P0059-0011 CONTENTS PAGE

1.0 INTRODUCTION

4 2.0 REFUELING OUTAGE DURATION 4-------------------------------------4 3.0 CODE REQUIREMENTS 4---------------------------------------------4

4.0 INSPECTION

4 5.0 CERTIFICATIONS

47------------------------------------------4

5.1 Personnel

4-----------------------------------------------4

5.2 Equipment

and Materials 6---------------------------------6 Thermometers 6--------------------------------------------6 Magnetic Particle Equipment 6-----------------------------6 Magnetic Particle Materials 6-----------------------------6 Dye Penetrant Materials 6---------------------------------6 Ultrasonic Flaw Detectors 7-------------------------------7 Ultrasonic Couplants 7------------------------------------7 Transducers 7---------------------------------------------7

6.0 CALIBRATION

STANDARDS 9-----------------------------------------9

7.0 PROCEDURES

AND INSPECTION PLANS 9--------------------------------9

8.0 RELIEF

REQUESTS 0-----------------------------------------------10

9.0 SCHEDULE

CHANGES ---------------------------------------------- 13 10.0 EXAMINATION

SUMMARY

RESULTS ----------------------------------- 13 11.0 NIS-2/NR-l

14 APPENDICES A. CYCLE 11 & RFOll EXAMINATIONS RESULTS

SUMMARY

17-------------" Cycle 11 & RFOll Scheduled Inservice Examinations

18* Cycle 11 & RFOll Preservice Examinations

45 B. CYCLE 11 & RFOll NIS-2/NR-l FORMS ------------------------- 48 LAST PAGE ---------------------------------------------------------- 180 3 REPORT NO. P0059-0011

1.0 INTRODUCTION

The information provided herein is supplied to document compliance with ASME Boiler and Pressure Vessel (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 RFO0 through the completion of RFOll.Included in this report are the following:

Personnel and Equipment Listings* Examination Results Summaries* NIS-2/NR-l Reports* Other Pertinent Information

2.0 REFUELING

OUTAGE DURATION The Perry Nuclear Power Plant, Unit #1, was shutdown for RFOll from April 2, 2007 to May 13, 2007. The plant returned to commercial operation on May 13, 2007, at 04:31. 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-416-2, N-457, N-460, N-461-1, N-491-2, N-498-1, N-509, N-522, N-524, N-526, N-546, N-552, N-566-2, N-568, N-578 as applied in PNPP's Risk-Informed Class 1 Piping program, N-586, N-599, N-601, N-613-1, N-623, N-624, N-647, N-648-1, N-652, N-663, N-664, and N-695.4.0 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 11 operations and RFOll.Certification records for personnel and equipment are kept on site and are available for review.5.1 Personnel Nondestructive Examination (NDE) personnel were qualified and certified to perform specific nondestructive examinations in accordance with PNPP or approved vendor procedures as verified by PNPP personnel and the Authorized Nuclear Inservice Inspector. 4 REPORT NO. P0059-0011 The following is a listing of personnel responsible for the performance of the NDE activities related to ISI during Cycle 11 operations and RFOII: ISI NDE PERSONNEL Name UT PT MT VT Anderson, Edward NA NA NA III++Andrie, Bryan NA NA NA II+Balcom, Allen NA NA NA II++Blood, Eric NA NA NA I+Boyd, Rodney NA NA NA II++Boyette, Nathan NA NA NA II++Brees, Michael NA NA NA IT+Buck, George III** III III III Catron, Earnest III** II II NA Clare, John NA NA NA II+Cox, Stephen IT** NA NA II Crane, Martin II** NA NA NA Drazich, Rodney NA NA NA III++Dummer, Brad ITI*' NA NA NA Fish, Kevin II** NA NA NA Gauthier, Clint !I** NA NA NA Gaskins, Vernard NA NA NA II Gilliard, John III** NA NA NA Ginder, Todd II*_ NA HA IT Green, Jack NA NA NA 11.+.Green, Jerry NA NA NA III++Guillote, Jonathan II** NA NA NA Hancock, David II** NA NA II Holmes, George NA NA NA II++Henry, Douglas NA NA NA III++Horn, John NA NA NA II++Hurlburt, Vivus NA NA NA II++Jenniges, Michael NA NA NA Ii Joffe, Christopher NA NA NA II++Johns, Shelvie NA NA NA IT+Jopko, Steve NA NA NA II Kee, Jon NA NA NA II++Kirkendall, Dennis NA NA NA II++Lesnjak, Damijan NA II II NA Lynch, Norbon NA NA NA II+Matthys, Russell NA NA NA II Martinez, William NA NA NA I++McClure, Matthew NA NA NA II+Messenger, John NA NA NA IIi Montgomery, Joseph IIj* NA NA NA Munson, Dewey III** III III NA Musgrove, Floyd NA NA NA II+4+Owens, Johnny NA NA NA Ii+Patterson, John NA NA NA II+Pelton, Corey NA NA NA II++Phelps, Antwonette NA NA NA II+Rachal, Andre II** NA NA NA Richardt, Joseph NA NA NA 114 Schroeder, Daniel NA NA NA II++Shearer, Levi NA NA NA II Sipple, Bruce NA NA NA 1i+.+Snyder, Steve II** II II II Steinbauer, Troy NA NA NA II**Tepsick, Michael NA I NA NA III 5 REPORT NO. P0059-0011 ISI NDE PERSONNEL CONT.Name UT PT MT VT Thomas, Dave NA NA NA III++Todd, Eugene NA NA NA 1I+VanHecke, Charles II*ý NA NA NA Walters, Donald III** NA NA NA Warren, Jason NA NA NA II+Wolf, Ronald NA NA NA II+Williams, Larry NA NA NA II+Winney, Ryan NA NA NA II++Wirtz, Charles NA II II III+ -Limited to VT-2 only++ -Limited to in-vessel VT-+++ -Limited to VT-3 only** -PDI qualified personnel 1 and VT-3 examinations only for manual and/or automated UT 5.2 Equipment and Materials The equipment and materials used during the performance of the nondestructive 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 11 operations and RFOll: THE RMOMETERS Manufacturer Model No. PNPP M&TE No.OMEGA 450 Digital L70Q0463J OMEGA 450 Digital L80Z0103E OMEGA 450 Digital L80Z0103F OMEGA 450 Digital L80Z0103K OMEGA 450 Digital L80Z0103P OMEGA 450 Digital L80Z0103R MAGNETIC PARTICLE EQUIPMENT Manufacturer Model No. PNPP M&TE No.Parker B-300 AC Yoke PAR-ACMT-049 Parker B-300 AC Yoke PAR-ACMT-058 MAGNETIC PARTICLE MATERIALS Manufacturer Type Batch No.Magnaflux 8A Red Powder 94B029 DYE PENETRANT MATERIALS Cleaner Penetrant Developer SKC-S OOK03K SKL-SPI 05A06K SKD-S2 06C05K 6 REPORT NO. P0059-0011 ULTRASONIC FLAW DETECTORS Manufacturer Model Serial No.Stavely SONIC-136P 136-786J Panametrics Epoch 4 031536006 Panametrics Epoch 4 031539806 Panametrics Epoch 4 031540506 Panametrics Epoch 4 031573111 Panametrics Epoch 4 031573311 Panametrics Epoch 4 031574712 Krautkramer USK-7 31459-2830 General Electric* GERIS-2000 System #3 Zetec+ MICROTOMO 166931 Used for RPV Nozzle to Shell Weld and Nozzle Inner Radii exams.+ Used for Nozzle to Safe-End dissimilar metal weld exams.ULTRASONIC COUPLANTS Manufacturer Type Batch No.Sonotech Ultragel II 95325 Sonotech Ultragel II 98325 Sonotech Ultragel II 99125 TRANSDUCERS USED FOR MANUAL EXAMS Manuf. Type Freq. Angle Size Ser No.KBA Comp-G 2.25 MHz 450 .25" Dia. 1003PBN KBA Gamma 5.0 MHz 00 .25" Dia. 003VOC KBA Comp-G 2.25 MHz 45°&70' .5" Dia. OODTX6*KBA Comp-G 5.0 MHz 450 .25" Dia. OOXB3P KBA Comp-G 5.0 MHz 45°&70' .25" Dia. OOXKHL KBA Comp-G 2.25 MHz 450 .375" Dia. 01ODY4 KBA Comp-G 2.25 MHz 45°&60' .375" Dia. 01ODY6 KBA Comp-G 2.25 MHz 450 .375" Dia. 010HWI KBA Comp-G 2.25 MHz 450 .5" Dia. 010HXP KBA Comp-G 2.25 MHz 450,700 .25" Dia. 01190H KBA Comp-G 5.0 MHz 450 .25" Dia. 0148D0 KBA Comp-G 5.0 MHz 45' .375" Dia. 01C7C9 KBA Comp-G 5.0 MHz 450 .5" Dia. 01CWDY KBA Comp-G 2.25 MHz 450 .375" Dia. 01CX29 KBA Comp-G 2.25 MHz 450 .5" Dia. 01CYT4 KBA Comp-G 2.25 MHz 250 .5" Dia. 01D65R KBA MSEB4E 4.0 MHz 00 4 x 10 mm 06438 KBA MSWQC 2.25 MHz 45°&70' .25" Dia. 24711*KBA Gamma 2.25 MHz 00 1.0" Dia. G14209SP KBA Gamma 5.0 MHz 00 .25" Dia. J29329 Panametrics A111S 10.0 MHz 00 .5" Dia. 212161*Panametrics A111S 10.0 MHz 00 .5" Dia. 268287* Denotes Perry transducers; all others supplied by GE 7 REPORT NO. P0059-0011 GERIS(Auto) & MANUAL RPV EXAM TRANSDUCERS Manuf. Type Freq. Angle Size Ser No.KBA SWS 1.0 MHz 70° .5" x 1" 010HX0*KBA SWS 1.0 MHz 700 .5" x i" O0OHX.2*KBA SWS 1.0 MHz 70- .5" x i" 010HX4*KBA SWS 1.0 MHz 450 .5" x I" 010HX6*KBA SWS 1.0 MHz 600 .5" x 1" 100HX91 KBA SWS 1.0 MHz 450 .5" x i" 011784*KBA SWS 1.0 MHz 45" .5" x i" 011785*RTD L 2-St 2.0 MHz 60'L (30x25)mm 04-12 RTD T 1-St 1.0 MHz 680 (32x16)mm 04-22 RTD T 1-St 1.0 MHz 680 (32x16)mm 04-23 RTD T 1-St 1.0 MHz 450 (32x22)mm 05-1484 RTD T 1-St 1.0 MHz 45' (32x22)mm 05-1485 trTD L 2,25 2.25 MHz 00 1" Dia. 05-1517 RTD T 1-St 1.0 MHz 450 (32x22)mm 05-164 RTD T 1-St 1.0 MHz 650 (32%17)mmm 05-168 RTD T 1-St 1.0 MHz 650 (32x17)nu 05-169 RTD TRL 2-St 2.0 MHz 70'L 2(12x25)mm 05-170 RTD T 1-St 1.0 MHz 450 (32x22) nm 06-273 RTD T 1-St 1.0 MHz 450 (32x22)mm 06-275 RTD TRL 2-St 2.0 MHz :70 0 L 2(12x25) mm 06-495 RTD TRL 2-St 2.0 MHz 70'L 2(12x25)mm 97-676 SIGMA SDC3 3.0 MHz 60'L 2(1.1"x.62"2 22BC-03007÷ SIGMA SDC3 3.0 MHz 60'L 2 (1 .l"x. 62") 22BC-03008* Harrisonic Spectrum 10.0 MHz 0° .5" Dia. 8158 Harrisonic Spectrum 10.0 MHz 00 .5" Dia. 8270** Denotes used for manual exams; all other used for GERIS System.SMART(Auto) & MANUAL SAFE-END WELD TRANSDUCERS Manuf. Type Freq. Angle Size Ser No.MKBA Comp-G 2.25 MHz 450 .25" Dia. DOXHOD RTD TRL2-Aust 2.0 MHz 60'L 2(10x18)mm 00-343 RTD TRL2-Aust 2.0 MHz 45'L 2(7xl0)mm 03-177*RTD TRL2-Aust 2.0 MHz 60'L 2(7xl0)mm 03-178*RTD TRL1-Aust 1.0 MHz 45 0 L 2(15x25)mm 03-682 RTD TRLI-Aust 1.0 MHz 60'L 2(15x25)mm 03-683 RTD TRL2-Aust 2.0 MHz 70'L 2(10xl8)mm 04-307 RTD TRL1-Aust 1.0 MHz 60'L 2(10xl8)mm 04-317 RTD TRL2-Aust 2.0 MHz 45'L 2(15x25)mm 04-318 RTD TRL2-Aust 2.0 MHz 60°L 2(15x25)mm 04-323 RTD TRL1.5-Aust 1.5 MHz 38 0 L 2(10xl8)mm 05-1350'RTD L 2,25 2.25 MHz 0o 1" Dia. 05-1517 RTD TRL1-Aust 1.0 MHz 45"L 2(10xl8)mm 05-159 8 REPORT NO. P0059-0011 SMART(Auto) & MANUAL SAFE-END WELD TRANSDUCERS CONT.I Ser No.I El1 (24x17)mm 06-505 11 Eli (24xi[7)mm 98-154 mm 98-166 I.7)mm 198-154 HM 1 98-166 for SMART System.6.0 CALIBRATION STANDARDS Ultrasonic calibration standards used for ISI related work activities during Cycle 11 operations and RFOII are as listed below: 7.0 CALIBRATION STANDARD IDENTIFICATION NUMBERS PY-4-XXI-SS PY-12-100-CS PY-26-XX2-CS PY-STUD-RR-3-CS PY-6-80-CS PY-16-100-CS PY-123-1-RPV PY-SE-BI-I PY-6-120-CS PY-18-40-CS PY-124-1-RPV PY-SE-BI-4 PY-6-XXI-CS-F PY-18-STD-CS PY-128-1-RPV PY-SE-BI-5 PY-8-100-CS PY-20-40-CS PY-NUT-RPV-1-A PY-VALVE-XXI-CS PY-12-40-CS PY-24-40-CS PY-STUD-l-RPV-A PY-VALVE-XX2-CS PY-12-80-CS PY-24-STD-CS PY-STUD-MS-2.25-CS-I CAL-STEP-151 PROCEDURES AND INSPECTION PLANS The examination procedures and inspection plans used during Cycle 11 operations and RFOll were as follows: Number I Rev Title Perry NDE Procedures: NQI-0941 11 Liquid Penetrant Examination NQI-0942 9 Magnetic Particle Examination NQI-0944 9 Ultrasonic Examination (General Procedure) NQI-1042 12 Visual Examination Inspection Plans used with NQI-0944: NDE-002 6 Ultrasonic Instrument Linearity Verification Manual Ultrasonic Examination of Ferritic Piping Welds NDE-012 4 Straight Beam Ultrasonic Examination of Bolts and Studs Procedure for Ultrasonic Examination of NDE-018 9 Stainless Steel (Austenitic) Piping Welds for Intergranular Stress Corrosion Cracking Ultrasonic Examination of Flued Head Penetration Attachment Welds Ultrasonic Examination of Reactor Pressure Vessel (RPV) Nut Threads and Flange Threads Manual Ultrasonic Examination of Valve Body NDE-030 2 Wed Welds Ultrasonic Examination of Piping Base Metal ,adjacent to Socket Welds 9 REPORT NO. P0059-0011 PROCEDURES AND INSPECTION PLANS CONT.Number Rev Title General Electric NDE Procedures: GE-PDI-UT-10 Rev. PDI Generic Procedure for The Ultrasonic 2 Examination of Dissimilar Metal Welds Ver. Procedure for Automated Ultrasonic GE-UT-209 Examination of Dissimilar Metal Welds, and Nozzle to Safe-End Welds Procedure for Manual Examination of Reactor GE-UT-300 V0 Vessel assembly Welds in Accordance with PDI With PDQS Ver. Procedure for Manual Ultrasonic Planar Flaw 8 Sizing in Vessel Materials With PDQS Procedure for Manual Ultrasonic Planar Flaw GE-UT-309 V0 Sizing of Nozzle Inner Radius and Bore Regions With PDQS Procedure for Manual Ultrasonic Examination of GE-UT-311 Vr Nozzle Inner Radius, Bore and Selected Nozzle to Vessel Regions With PDQS Procedure for The Examination of Reactor Ver. Pressure Vessel Nozzle Inner Radius and Nozzle 5 To Vessel Welds With The GERIS 2000 OD IN Accordance With Appendix VIII Ver. Procedure for Invessel Visual Inspection (IVVI 8 of BWR 6 RPV Internals 8.0 RELIEF REQUESTS Due to geometric, metallurgical, and physical limitations, some of the items scheduled for examination during RFOIl 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 that have been submitted to and approved by the Nuclear Regulatory Commission (NRC) for PNPP's second 10-year Inspection Interval: RR NO/REV SYSTEM TYPE RELIEF CATEG ITEM NO IR-001 R-2 Reactor Pressure Vessel Partial Exams B-A B1.21 B1.22 B1.40 B-D B3.90 B3.100 B4.11 10 REPORT NO. P0059-0011 RELIEF REQUESTS CONTINUED RR NO/REV SYSTEM TYPE RELIEF CATEG ITEM NO IR-007 R-1 Residual Heat Removal, Partial Exams B-K-i Bl0.10 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-0 B14.10 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-l 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-1 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-1 Main Steam Alternative B-K-l BI0.10 Exams IR-026 R-1 Main Steam, Feedwater Alternative C-C C3.20 Exams IR-027 R-1 Standby & HPCS Diesel, Alternative D-B D2.20 Fuel Oil Exams IR-029 R-1 Reactor Recirculation Alternate Weld B-J B9.11 Selection IR-030 R-1 Reactor Pressure Vessel Alternate Exam B-A BI.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 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 11 REPORT NO. P0059-0011 RELIEF REQUESTS CONTINUED RR NO/REV SYSTEM TYPE RELIEF CATEG ITEM NO 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-0 Reactor Water Cleanup Alternate B-M-I B12.30 Categorization IR-044 R-0 Reactor Vessel Use of Code B-G-1 B6.10 Case N-627 IR-045 R-0 Reactor Vessel Use of Code B-A B1.30 Case N-623 BI.40 IR-046 R-0 Reactor Vessel Alternate B-A B1.10 Length Sizing BI.20 Criteria IR-048 R-0 N/A Alternate UT N/A N/A Annual Training Requirements IR-049 R-0 Class I 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 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 D1.10 Valve Discharge Piping Hydrostatic Test Notes: 1. Relief Requests IR-016, IR-017, IR-022, and PT-003 were withdrawn in the 1't Inspection Interval; IR-004, IR-005, IR-006, IR-008, IR-010, IR-011, IR-014, IR-020, IR-028, IR-031, PT-002, PT-004 and PT-005 were withdrawn in the 2nd Inspection Interval; IR-002, IR-033, IR-050, IR-051 and IR-052 were superseded by the NRC 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 11 and RFO1I 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.12 REPORT NO. P0059-0011

9.0 SCHEDULE

CHANGES Scheduling changes were made during RFOll to facilitate the examinations, or to account for unforeseen physical or schedule interferences, or radiological conditions. These changes differ from the schedule in Revision 11 of PNPP's Inservice Examination Program (ISEP).The changes, which will be incorporated in the next revision to the ISEP, are as follows: MARK NO. DESCRIPTION AND REASON FOR CHANGE IBI3-38/03-FW Under Order 200173592, Control Rod Drive 38/03 housing to flange weld was scheduled for a penetrant (PT) examination. However, it was found that there were permanent braided lines lying across the weld. CRD flange weld IB13-54/15-FW was substituted in its place as it had no obstructions. Document Change Request Notification 600379351 was generated for revision of the ISEP to reflect the substitution. IE12-H0675 Under Order 200173635, variable spring support IE12-H0675 was scheduled for a VT-3 examination. Previous history and the ISI database did not indicate that scaffolding was necessary for this support as it's pipe attachment is located just above the Drywell 630 platform. However, it was found that the majority of the support assembly is below the 630 platform grating and could not be examined without scaffolding. As such, variable sprinq support 1E12-H0661, which was not scheduled and which did not require any scaffolding, was substituted in its place. Document Chanqe Request Notification 600379351 was generated for revision of the ISEP to reflect the substitution. 10.0 EXAMINATION SUMM4ARY RESULTS RFOll was the fifth refueling outage of Perry's second 10-Year Inservice Inspection Interval and it was the first of two outages in the third inspection period. With the completion of the Cycle 11 and RFOl1 examinations, approximately 50% of the examinations scheduled for the third period are complete. The remaining third period examinations will be completed by the end of RFC12.Cycle 11 and RFOlI 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. Appendix "A" is a computer-generated summary of the Cycle 11 and RFOll examination results. Component identifications (Mark Nos.)and order of appearance may differ slightly from that listed in Revision 11 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.13 REPORT NO. P0059-0011 11.0 NIS-2/NR-I 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-1 Forms.The following is a listing of NIS-2/NR-1 forms applicable to this report (Class 1 and 2 only) which have been completed since PTIPP's last summary report: NR-I/NIS-2 FORMS SYS/NO. MPL NO. DESCRIPTION/COMMENTS CLASS PAGE Reactor Pressure Vessel (IB13) Cycle 11 & RFOII Reports: 1B13-052 1B13-D0008 Replaced 14 CRDMs and 8 capscrews each 1 49 at locations 22/27, 46/27, 50/19, 42/15, 34/47, 42/51, 50/23, 46/15, 42/27, 46/43, 54/23, 42/39, 10/35, 50/31; and also replaced 8 capscrews each on existing CRD0s located at 42/31, 50/27, 14/19, and 26/35.Main Steam (IB21) System Cycle 11 & RFO11 Reports: 1B21-366 1B21-G7091 Replaced E-Systems hydraulic snubber 1 80 with like snubber 1B21-367 IB21-F0032A Removed and replaced 1-3/4" inch welded 1 81 IB21-F0032B test connections for inspection 1B21-368 1H22-H2744 Replaced Lisega hydraulic snubber with 1 84_like snubber IB21-369 1B21-E0445 Replaced Lisega hydraulic snubber with 1 85 like snubber 1B21-370 1B21-H0449 Replaced Lisega hydraulic snubber with 1 86 like snubber 1B21-371 1B21-H0450 Replaced Lisega hydraulic snubber with 1 87 like snubber IB21-372 1B21-H0471 Replaced Lisega hydraulic snubber with 1 88 like snubber 1B21-373 1B21-F041D Replaced SRV with like SRV 1 89 1B21-374 IB21-F047H Replaced SRV with like SRV 1 91 1B21-375 IB21-F047F Replaced SRV with like SRV 1 93 1B21-376 1B21-F047B Replaced SRV with like SRV 1 95 1B21-377 1B21-F047D Replaced SRV with like SRV 1 97 1B21-378 1B21-F051B Replaced SRV with like SRV 1 99 1B21-379 1B21-F041F Replaced SRV with like SRV 1 101 1B21-380 1B21-F051D Replaced SRV with like SRV 1 103 1B21-381 1B21-F041B Replaced SRV with like SRV 1 105 1B21-382 IB21-FO41K Replaced SRV with like SRV 1 107 1B21-383 IB21-F028C Replaced MSIV poppet with new poppet 1 109 Reactor Recirculation (1B33) System Cycle 11 & RFOll Reports: 1B33-127 IB33-G7064B Replaced E-Systems hydraulic snubber 1 112 with like snubber 1B33-128 1B33-G7066B Replaced E-Systems hydraulic snubber 1 114 with like snubber 1B33-129 1B33-G7065B Replaced E-Systems hydraulic snubber 1 116 with like snubber_ _ _ I I__ _ I_ _ _ _ _ _ _ _ _ _ I _14 REPORT NO. P0059-0011 NR-1/NIS-2 FORMS CONTINUED SYS/NO. MPL NO. DESCRIPTION/COMMENTS CLASS PAGE Standby Liquid Control (0&IC41) System Cycle 11 & RFO1I Reports: 1C41-036 IC41-D0003 Replaced heater flange with like flange 2 118 1C41-037 IC41-F0004B Replaced primer/trigger assembly of 1 119 explosive SQUIB valve IC41-038 IC41-F0029B Replaced Ix2" relief valve with like 2 123 valve Residual Heat Removal (1E12) System Cycle 11 & RFOll Reports: IE12-293 IE12-C0003 Replaced waterleg pump rotating element 2 125 of the pump with like element (casing unchanged) 1E12-294 IE12-H0066 Installed a new load stud 2 127 1E12-295 IE12-H5002 Replaced PSA mechanical snubber with 2 128 like snubber IE12-296 1H22-H0209 Replaced PSA mechanical snubber with 2 129 like snubber IE12-297 1E12-F063C Replaced 8" check valve with like valve 2 131 IE12-298 IE12-F086 Replaced 6" check valve with like valve 2 133 IE12-299 IE12-F063A Replaced 8" check valve with like valve 2 135 IE12-300 IE12-F063B Replaced 8" check valve with like valve 2 137 IE12-301 IE12-F041A Installed new disc in 12" testable check 2 139 valve 1E12-302 IE12 Replaced 6" piping and tee downstream of 1 141 1E12-F018B due to FAC IE12-303 1E12-F055B Replaced 4x6 relief valve with like 2 142 valve Low Pressure Core Spray (IE21) System Cycle 11 & RFOII Reports: 1E21-039 1E21-C0002 Replaced waterleg pump rotating element 2 144 of the pump with like element (casing unchanged) High Pressure Core Spray (IE22) System Cycle 11 & RFOll Reports: 1E22-062 IE22-C0003 Replaced stuffing box and seal gland of 2 146 Waterleg pump 1E22-063 IE22-C0003 Replaced waterleg pump with like pump 2 148 1E22-068 IE22-C0003 Replaced waterleg pump rotating element 2 150 of the pump with like element (casing unchanged) IE22-069 1E22-F0541B Replaced 2-way air start valve with like 2 152 valve IE22-070 1E22-F0541A Replaced 2-way air start valve with like 2 153 valve 1E22-072 1E22-F0034 Replaced 2" globe valve with like valve 2 154 Reactor Core Isolation Cooling (IE51) System Cycle 11 & RFOll Reports: 1E51-139 1E51-F0011 Replaced 6" Duo check valve with like 2 156 valve IE51-140 IE51-D0002 Replaced rupture disc with like disc 2 158 1E51-141 1E51-H0073 Replaced Lisega hydraulic snubber with 1 159 like snubber 1E51-142 IE51-H0074 Replaced Lisega hydraulic snubber with 1 160 like snubber 1E51-143 IE51-H2078 Replaced Lisega hydraulic snubber with 2 161 like snubber 1E51-144 IE51-F066 Replaced 6" check valve disc retainer 1 162 assembly 15 REPORT NO. P0059-0011 NR-I/NIS-2 FORMS CONTINUED SYS/NO. MPL NO. DESCRIPTION/COMMENTS CLASS PAGE Reactor Core Isolation Cooling (IE51) System Cycle 11 & RFOl1 Reports Cont.: 1E51-145 IE51-DO001 1 Replaced rupture disc with like disc 2 164 1E51-146 lE51-C0003 JReplaced waterleg pump with like pump 2 165 Combustible Gas Control (1M51) System Cycle 11 & RFO11 Reports: 1M51-028 1M51-F0010B Replaced nuts on globe valve bonnet 2 166 Main, Reheat, Extraction, and Misc. Drains (IN22) System Cycle 11 & RFOll Reports: IN22-065 1B21-F0016 Replaced gate in 3" globe valve 1 167 IN22-066 1B21-F0019 Replaced gate in 3" globe valve 1 169 Feedwater (IN27) System Cycle 11 & RFOl1 Reports: IN27-047 1N27-F0559B Removed and reinstalled 1-3/4" test 1 171 connection from 20" check valve 1N27-048 1N27-F0559A Removed and reinstalled 1-3/4" test 1 173 connection from 20" check valve Condensate Transfer and Storage (IP1I) System Cycle 11 and RFOII Reports: IPlI-009 lPll-F0060 Replaced 12" globe valve with like valve 2 174 1Pll-010 lPll-F0545 Installed new wafer disc in 12" check 2 176 valve Nuclear Closed Cooling (1P43) System Cycle 11 & RFOlI Reports: 1P43-018 1P43-F0355 Rebuilt 10" butterfly valve using new 2 177 cap screws, studs, and shaft/disc assembly Fire Protection (1P54) System Cycle 11 & RFO11 Reports: 1P54-009 I1P54-F1098 Replaced check valve with like valve 2 179 Copies of the NIS-2/NR-I forms are contained in Appendix "B" and the corresponding starting page numbers are provided in the above table.16 REPORT NO. P0059-011 APPENDIX A"CYCLE 11 & RFO11 EXAMINATION RESULTS

SUMMARY

" INSERVICE INSPECTION

SUMMARY

REPORT FOR PERRY NUCLEAR POWER PLANT (PNPP)UNIT 1 17 REPORT NO. P0059-011 First Energy Nuclear Operating Company Perry Nuclear Power Plant ISI Summary Report No. P0059-0011 Second Interval, Third Period, First Outage (RFO11)Cycle 11 and RFO11 Inservice Examinations Prepared by: Reviewed by: V, ISe En inee -Date: Authorized Nuclear Inservice nspelcy Friday, July 13, 2007 Page 1 of 54 18 ID of Component Examined Description of Component Size -Sched. -ISI Dwg. No.ASME Category ASME Item No.Exam Method Exam Report No. Status Remarks 1613-0001 RPV VENT & HEAD SPRAY TEE, FLANGE TO TEE 6" 305-631-108 11B13-0001 RPV VENT & HEAD SPRAY TEE, FLANGE TO TEE 6" 305-631-108 1B13-22/03-FW CRD HOUSING TO FLANGE WELD 6" N/A 305-006-110 1B13-22159-HW CRD HOUSING TO HOUSING WELD 6" N/A 305-006-110 1B13-38/59-HW CRD HOUSING TO HOUSING WELD 6" N/A 305-006-110 1B13-54/15-FW CRD HOUSING TO FLANGE WELD 6" N/A 305-006-110 1B13-AG TOP HEAD TO TOP HEAD FLANGE N/A N/A 305-006-103 1B13-AG TOP HEAD TO TOP HEAD FLANGE N/A N/A 305-006-103 1B13-DG BOTTOM CENTER PLATE TO SIDE PLATE, 270 AZ SIDE N/A N/A 305-006-104 1B13-DH BOTTOM CENTER PLATE TO SIDE PLATE, 90 AZ SIDE N/A N/A 305-006-104 R-A R2.11 R-A R2.11 B-0 B14.10 UT 0944-07-E193 UT 0944-07-E192 PT 0941-07A-007 GEO Root geometry and counterbore seen 360" intermittently. NRI Zero degree exam performed as weld was being examined for the first time.SAT 85% coverage (IR-009). No indications. B-0 B14.10 B-0 B14.10 PT 0941-07A-005 PT 0941-07A-004 SAT None.SAT None.B-0 814.10 PT 0941-07A-006 SAT 85% coverage (IR-009). No indications. B-A B1.40 MT 0942-07A-015 SAT None.B-A B1.40 B-A B1.22 B-A B1.22 UT 1Q800-07-002 UT 1Q800-07-005 UT 10800-07-004 NRI 83.7% coverage and no indications (IR-001).SAT 29% coverage and no relevant indications (IR-001).SAT 29% coverage and no relevant indications (IR-001).Friday, July 13, 2007 Page 2 of 54 Friday, July 13, 2007 Page 2 of 54 REPORT NO. P0059-011 ID of Component Examined Description of Component Size- Sched. -ISI Dwg. No.ASME Category ASME Item No.Exam Method Exam Report No. Status Remarks 1B13-DM TOP HEAD MERIDIONAL WELD @ 195 AZ N/A N/A 305-006-103 1B13-DR TOP HEAD MERIDIONAL WELD @ 15 AZ N/A N/A 305-006-103 1B13-F4-N RPV CLOSURE HEAD NUT 5" N/A 305-006-112 1B13-F4-S RPV CLOSURE HEAD STUD 5" N/A 305-006-112 1B13-F4-S RPV CLOSURE HEAD STUD 5" N/A 305-006-112 1B13-F4-T RPV SHELL, THREADS IN FLANGE AREA 5" N/A 305-006-112 1B13-F4-W RPV CLOSURE HEAD WASHER 5" N/A 305-006-112 1B13-F5-N RPV CLOSURE HEAD NUT 5" N/A 305-006-112 1613-F5-S RPV CLOSURE HEAD STUD 5" N/A 305-006-112 1B13-F5-S RPV CLOSURE HEAD STUD 5" N/A 305-006-112 B-A B1.22 B-A B1.22 B-G-1 B6.10 UT 10800-07-001 UT 10800-07-003 VT-1 1042-07-048 SAT None.SAT None.SAT None.B-G-1 B6.20 B-G-1 66.20 B-G-1 66.40 UT 0944-07-E019 UT 0944-07-E020 UT 0944-07-E067 NRI Zone 1 Exam.NRI Zone 2 Exam.NRI Achieved approximately 92% coverage.B-G-1 B6.50 B-G-1 B6.10 VT-1 1042-07-038 VT-1 1042-07-049 SAT None.SAT None.B-G-1 B6.20 B-G-1 B6.20 UT 0944-07-E021 UT 0944-07-E022 NRI Zone 1 Exam.NRI Zone 2 Exam.Friday, July 13, 2007 Page 3 of 54 19 ID of Component Examined Description of Component Size- Sched. -ISl Dwg. No.ASME Category ASME Item No.Exam Method Exam Report No. Status Remarks 181 3-F5-T RPV SHELL, THREADS IN FLANGE AREA 5" N/A 305-006-112 1B13-F5-W RPV CLOSURE HEAD WASHER 5" N/A 305-006-112 1B13-F6-N RPV CLOSURE HEAD NUT 5" N/A 305-006-112 1B13-F6-S RPV CLOSURE HEAD STUD 5" N/A 305-006-112 1B13-F6-S RPV CLOSURE HEAD STUD 5" N/A 305-006-112 1B13-F6-T RPV SHELL, THREADS IN FLANGE AREA 5" N/A 305-006-112 1B13-F6-W RPV CLOSURE HEAD WASHER 5" N/A 305-006-112 1B13-F7-N RPV CLOSURE HEAD NUT 5" N/A 305-006-112 1B13-F7-S RPV CLOSURE HEAD STUD 5" N/A 305-006-112 1B13-F7-S RPV CLOSURE HEAD STUD 5" N/A 305-006-112 B-G-1 B6.40 UT 0944-07-E068 NRI Achieved approximately 92% coverage.B-G-1 B6.50 B-G-1 B6.10 VT-1 1042-07-039 VT-1 1042-07-050 SAT None.SAT None.B-G-1 B6.20 B-G-1 B6.20 B-G-1 B6.40 UT 0944-07-E023 UT 0944-07-E024 UT 0944-07-E069 NRI Zone 1 Exam.NRI Zone 2 Exam.NRI Achieved approximately 92% coverage.B-G-1 B6.50 B-G-1 B6.10 VT-1 1042-07-040 VT-I 1042-07-051 SAT None.SAT None.B-G-1 B6.20 B-G-1 B6.20 UT 0944-07-E026 UT 0944-07-E025 NRI Zone 2 Exam.NRI Zone 1 Exam.Friday, July 13, 2007 Page 4 of 54 REPORT NO. P0059-011 ID of Component Examined Description of Component Size -Sched. -ISI Dwg. No.ASME Category ASME Item No.Exam Method Exam Report No. Status Remarks 1B13-F7-T RPV SHELL, THREADS IN FLANGE AREA 5" N/A 305-006-112 1B13-F7-W RPV CLOSURE HEAD WASHER 5" N/A 305-006-112 1B13-F8-N RPV CLOSURE HEAD NUT 5" N/A 305-006-112 1B13-F8-S RPV CLOSURE HEAD STUD 5" N/A 305-006-112 1B13-F8-S RPV CLOSURE HEAD STUD 5" N/A 305-006-112 1B13-F8-T RPV SHELL, THREADS IN FLANGE AREA 5" N/A 305-006-112 1B13-F8-W RPV CLOSURE HEAD WASHER 5" N/A 305-006-112 1B13-F9-N RPV CLOSURE HEAD NUT 5" N/A 305-006-112 1B13-F9-S RPV CLOSURE HEAD STUD 5" N/A 305-006-112 1B13-F9-S RPV CLOSURE HEAD STUD 5" N/A 305-006-112 B-G-1 B6.40 UT 0944-07-E070 NRI Achieved approximately 92% coverage.B-G-1 B6.50 B-G-1 B6.10 VT-1 1042-07-041 VT-1 1042-07-052 SAT None.SAT None.B-G-1 B6.20 8-G-1 86.20 B-G-1 86.40 UT 0944-07-E027 UT 0944-07-E028 UT 0944-07-E071 NRI Zone 1 Exam.NRI Zone 2 Exam.NRI Achieved approximately 92% coverage.B-G-1 B6.50 B-G-1 B6.10 VT-i 1042-07-042 VT-1 1042-07-053 SAT None.SAT None.B-G-1 86.20 B-G-1 B6.20 UT 0944-07-E030 UT 0944-07-E029 NRI Zone 2 Exam.NRI Zone 1 Exam.Friday, July 13, 2007 Page 5 of 54 20 ID of Component Examined Description of Component Size- Sched.- ISI Dwg. No.ASME Category ASME Item No.Exam Method Exam Report No. Status Remarks 1B13-F9-T RPV SHELL, THREADS IN FLANGE AREA 5" N/A 305-006-112 1813-F9-W RPV CLOSURE HEAD WASHER 5" N/A 305-006-112 1B13-G1-N RPV CLOSURE HEAD NUT 5" N/A 305-006-112 1813-G1-S RPV CLOSURE HEAD STUD 5" N/A 305-006-112 1B13-G1-S RPV CLOSURE HEAD STUD 5" N/A 305-006-112 1B13-GI-T RPV SHELL, THREADS IN FLANGE AREA 5" N/A 305-006-112 1B13-G1-W RPV CLOSURE HEAD WASHER 5" N/A 305-006-112 1B13-G2-N RPV CLOSURE HEAD NUT 5" N/A 305-006-112 1B13-G2-S RPV CLOSURE HEAD STUD 5" N/A 305-006-112 1B13-G2-S RPV CLOSURE HEAD STUD 5" N/A 305-006-112 B-G-1 B6.40 UT 0944-07-E072 NRI Achieved approximately 92% coverage.B-G-1 B6.50 B-G-1 B6.10 VT-1 1042-07-043 VT-1 1042-07-072 SAT None.SAT None.B-G-1 86.20 B-G-1 86.20 B-G-1 B6.40 UT 0944-07-E031 UT 0944-07-E032 UT 0944-07-E073 NRI Zone 1 Exam.NRI Zone 2 Exam.NRI Achieved approximately 92% coverage.B-G-1 B6.50 B-G-1 B6.10 VT-I 1042-07-058 VT-1 1042-07-073 SAT None.SAT None.B-G-1 B6.20 B-G-1 B6.20 UT 0944-07-E034 UT 0944-07-E033 NRI Zone 2 Exam.NRI Zone 1 Exam.Friday, July 13, 2007 Page 6 of 54 REPORT NO. P0059-011 ID of Component Examined Description of Component Size- Sched. -IS[ Dwg. No.ASME Category ASME Item No.Exam Method Exam Report No. Status Remarks 1B13-G2-T RPV SHELL, THREADS IN FLANGE AREA 5" N/A 305-006-112 1B13-G2-W RPV CLOSURE HEAD WASHER 5" N/A 305-006-112 1B13-G3-N RPV CLOSURE HEAD NUT 5" N/A 305-006-112 1B13-G3-S RPV CLOSURE HEAD STUD 5" N/A 305-006-112 1B13-G3-S RPV CLOSURE HEAD STUD 5" N/A 305-006-112 1B13-G3-T RPV SHELL, THREADS IN FLANGE AREA 5" N/A 305-006-112 1B13-G3-W RPV CLOSURE HEAD WASHER 5" N/A 305-006-112 1B13-G4-N RPV CLOSURE HEAD NUT 5" N/A 305-006-112 1B13-G4-S RPV CLOSURE HEAD STUD 5" N/A 305-006-112 1B13-G4-S RPV CLOSURE HEAD STUD 5" N/A 305-006-112 B-G-1 B6.40 UT 0944-07-E074 NRI Achieved approximately 92% coverage.B-G-1 B6.50 B-G-1 B6.10 VT-1 1042-07-059 VT-1 1042-07-074 SAT None.SAT None.B-G-1 86.20 B-G-1 B6.20 B-G-1 B6.40 UT 0944-07-E035 UT 0944-07-E036 UT 0944-07-E075 NRI Zone 1 Exam.NRI Zone 2 Exam.NRI Achieved approximately 92% coverage.B-G-1 66.50 8-G-1 B6.10 VT-1 1042-07-060 VT-1 1042-07-075 SAT None.SAT None.B-G-1 86.20 B-G-1 86.20 UT 0944-07-E037 UT 0944-07-E038 NRI Zone 1 Exam.NRI Zone 2 Exam.Friday, July 13, 2007 Page 7 of 54 21 ID of Component Examined Description of Component Size -Sched.- ISI Dwg. No.ASME Category ASME Exam Item No. Method Exam Report No. Status Remarks 1B13-G4-T RPV SHELL, THREADS IN FLANGE AREA 5" N/A 305-006-112 1B13-G4-W RPV CLOSURE HEAD WASHER 5" N/A 305-006-112 1B13-G5-N RPV CLOSURE HEAD NUT 5" N/A 305-006-112 1B313-G5-S RPV CLOSURE HEAD STUD 5" N/A 305-006-112 1B13-G5-S RPV CLOSURE HEAD STUD 5" N/A 305-006-112 1B13-G5-T RPV SHELL, THREADS IN FLANGE AREA 5" N/A 305-006-112 1B13-G5-W RPV CLOSURE HEAD WASHER 5" N/A 305-006-112 1B13-G6-N RPV CLOSURE HEAD NUT 5" N/A 305-006-112 1B313-G6-S RPV CLOSURE HEAD STUD 5" N/A 305-006-112 1B13-G6-S RPV CLOSURE HEAD STUD 5" N/A 305-006-112 B-G-1 86.40 UT 0944-07-E076 NRI Achieved approximately 92% coverage.8-G-1 86.50 B-G-1 86.10 VT-1 1042-07-061 VT-1 1042-07-076 Sat None.Sat None.B-G-1 B6.20 B-G-1 B6.20 B-G-1 B6.40 UT 0944-07-E040 UT 0944-07-E039 UT 0944-07-E077 NRI Zone 2 Exam.NRI Zone 1 Exam.NRI Achieved approximately 92% coverage.B-G-1 B6.50 B-G-1 86.10 VT-1 1042-07-062 VT-1 1042-07-077 SAT None.SAT None.8-G-1 B6.20 B-G-1 B6.20 UT 0944-07-E041 UT 0944-07-E042 NRI Zone 1 Exam.NRI Zone 2 Exam.Friday, July 13, 2007 Page 8 of 54 Friday, July 13, 2007 Page 8 of 54 REPORT NO. P0059-011 ID of Component Examined Description of Component Size- Sched. -ISI Dwg. No.ASME Category ASME Item No.Exam Method Exam Report No. Status Remarks 1B 13-G6-T RPV SHELL, THREADS IN FLANGE AREA 5" N/A 305-006-112 1813-G6-W RPV CLOSURE HEAD WASHER 5" N/A 305-006-112 1B13-G7-N RPV CLOSURE HEAD NUT 5" N/A 305-006-112 1B13-G7-S RPV CLOSURE HEAD STUD 5" N/A 305-006-112 1813-G7-S RPV CLOSURE HEAD STUD 5" N/A 305-006-112 1B13-G7-T RPV SHELL, THREADS IN FLANGE AREA 5" N/A 305-006-112 1B13-G7-W RPV CLOSURE HEAD WASHER 5" N/A 305-006-112 1B13-G8-N RPV CLOSURE HEAD NUT 5" N/A 305-006-112 1B13-GB-S RPV CLOSURE HEAD STUD 5" N/A 305-006-112 1813-G8-S RPV CLOSURE HEAD STUD 5" N/A 305-006-112 B-G-1 B6.40 UT 0944-07-E078 NRI Achieved approximately 92% coverage.B-G-1 B6.50 B-G-1 B6.10 VT-1 1042-07-063 VT-1 1042-07-078 SAT None.SAT None.B-G-1 B6.20 B-G-1 B6.20 B-G-1 B6.40 UT 0944-07-E044 UT 0944-07-E043 UT 0944-07-E079 NRI Zone 2 Exam.NRI Zone 1 Exam.NRI Achieved approximately 92% coverage.B-G-1 B6.50 B-G-1 B6.10 VT-1 1042-07-064 VT-1 1042-07-079 SAT None.SAT None.,-G-1 B6.20 B-G-1 B6.20 UT 0944-07-E045 UT 0944-07-E046 NRI Zone I Exam.NRI Zone 2 Exam.Friday, July 13, 2007 Page 9 of 54 22 ID of Component Examined Description of Component Size -Sched. -ISl Dwg. No.ASME Category ASME ftem No.Exam Method Exam Report No. Status Remarks 1B13-G8-T RPV SHELL, THREADS IN FLANGE AREA 5" N/A 305-006-112 1B13-G8-W RPV CLOSURE HEAD WASHER 5" N/A 305-006-112 1813-G9-N RPV CLOSURE HEAD NUT 5" N/A 305-006-112 1813-G9-S RPV CLOSURE HEAD STUD 5" N/A 305-006-112 1 B13-G9-S RPV CLOSURE HEAD STUD 5" N/A 305-006-112 1813-G9-T RPV SHELL, THREADS IN FLANGE AREA 5" N/A 305-006-112 1 B13-G9-W RPV CLOSURE HEAD WASHER 5" N/A 305-006-112 1B13-H1-N RPV CLOSURE HEAD NUT 5" N/A 305-006-112 1813-Hi-S RPV CLOSURE HEAD STUD 5" N/A 305-006-112 1813-H1-S RPV CLOSURE HEAD STUD 5" N/A 305-006-112 B-G-1 B6.40 UT 0944-07-E080 NRI Achieved approximately 92% coverage.B-G-1 86.50 B-G-1 B6.10 VT-1 1042-07-065 VT-1 1042-07-080 SAT None.SAT None.B-G-1 B6.20 8-G-1 86.20 B-G-1 B6.40 UT 0944-07-E047 UT" 0944-07-E048 UT 0944-07-E081 NRI Zone 1 Exam.NRI Zone 2 Exam.NRI Achieved approximately 92% coverage.B-G-1 B6.50 B-G-1 B6.10 VT-i 1042-07-066 VT-i 1042-07-081 Sat None.Sat None.B-G-1 B6.20 B-G-1 B6.20 UT 0944-07-EO50 UT 0944-07-E049 NRI Zone 2 Exam.NRI Zone 1 Exam.Friday, July 13, 2007 Page 10 of 54 Friday, July 13, 2007 Page 10 of 54 REPORT NO. P0059-011 ID of Component Examined Description of Component Size- Sched. -ISI Dwg. No.ASME Category ASME Item No.Exam Method Exam Report No. Status Remarks 1B13-H1-T RPV SHELL, THREADS IN FLANGE AREA 5" N/A 305-006-112 1B13-H1-W RPV CLOSURE HEAD WASHER 5" N/A 305-006-112 1B13-H2-N RPV CLOSURE HEAD NUT 5" N/A 305-006-112 1113-H12-S RPV CLOSURE HEAD STUD 5" N/A 305-006-112 1B13-H2-S RPV CLOSURE HEAD STUD 5" N/A 305-006-112 1B13-H2-T RPV SHELL, THREADS IN FLANGE AREA 5" N/A 305-006-112 1B13-H2-W RPV CLOSURE HEAD WASHER 5" N/A 305-006-112 1813-H3-N RPV CLOSURE HEAD NUT 5" N/A 305-006-112 1113-H3-S RPV CLOSURE HEAD STUD 5" N/A 305-006-112 1B13-H3-S RPV CLOSURE HEAD STUD 5" N/A 305-006-112 B-G-1 86.40 UT 0944-07-E082 NRI Achieved approximately 92% coverage.B-G-1 B6.50 B-G-1 B6.10 VT-i1 1042-07-067 VT-1 1042-07-082 Sat None.Sat None.B-G-1 B6.20 B-G-1 B6.20 B-G-1 B6.40 UT 0944-07-E052 UT 0944-07-E051 UT 0944-07-E083 NRI Zone 2 Exam.NRI Zone 1 Exam.NRI Achieved approximately 92% coverage.B-G-1 86.50 8-G-1 86.10 VT-1 1042-07-068 VT-1 1042-07-083 SAT None.SAT None.8-G-1 86.20 B-G-1 86.20 UT 0944-07-E054 UT 0944-07-E053 NRI Zone 2 Exam.NRI Zone 1 Exam.Friday, July 13, 2007 Page 11 of 54 23 ID of Component Examined Description of Component Size- Sched.- ISI Dwg. No.ASME Category ASME Item No.Exam Method Exam Report No. Status Remarks 1B13-H3-T RPV SHELL, THREADS IN FLANGE AREA 5" N/A 305-006-112 1813-H3-W RPV CLOSURE HEAD WASHER 5" N/A 305-006-112 1B13-H4-N RPV CLOSURE HEAD NUT 5" N/A 305-006-112 11313-H4-S RPV CLOSURE HEAD STUD 5" N/A 305-006-112 1B13-H4-S RPV CLOSURE HEAD STUD 5" N/A 305-006-112 11313-H4-T RPV SHELL, THREADS IN FLANGE AREA 5" N/A 305-006-112 18133-H4-W RPV CLOSURE HEAD WASHER 5" N/A 305-006-112 1B13-H5-N RPV CLOSURE HEAD NUT 51 N/A 305-006-112 18133-H5-S RPV CLOSURE HEAD STUD 5" N/A 305-006-112 1113-H5-S RPV CLOSURE HEAD STUD 5" N/A 305-006-112 B-G-1 B6.40 UT 0944-07-E084 NRI Achieved approximately 92% coverage.B-G-1 B6.50 B-G-1 B6.10 VT-1 1042-07-069 VT-1 1042-07-084 SAT None.SAT None.B-G-1 B6.20 B-G-1 B6.20 B-G-1 B6.40 UT 0944-07-E056 UT 0944-07-E055 UT 0944-07-E085 NRI Zone 2 Exam.NRI Zone 1 Exam.NRI Achieved approximately 92% coverage.B-G-1 B6.50 B-G-1 B6.10 VT-1 1042-07-070 VT-1 1042-07-085 SAT None.SAT None.B-G-1 86.20 B-G-1 86.20 UT 0944-07-E057 UT 0944-07-E058 NRI Zone 1 Exam.NRI Zone 2 Exam.Friday, July 13, 2007 Page 12 of 54 REPORT NO. P0059-011 ID of Component Examined Description of Component Size -Sched. -ISI Dwg. No.ASME Category ASME Rem No.Exam Method Exam Report No. Status Remarks 1813-H5-T RPV SHELL, THREADS IN FLANGE AREA 5" N/A 305-006-112 1813-HS-W RPV CLOSURE HEAD WASHER 5" N/A 305-006-112 1813-H6-N RPV CLOSURE HEAD NUT 5" N/A 305-006-112 1813-H6-S RPV CLOSURE HEAD STUD 5" N/A 305-006-112 1813-H6-S RPV CLOSURE HEAD STUD 5" N/A 305-006-112 1813-H6-T RPV SHELL, THREADS IN FLANGE AREA 5" N/A 305-006-112 1B13-H6-W RPV CLOSURE HEAD WASHER 5" N/A 305-006-112 1B13-H7-N RPV CLOSURE HEAD NUT 5" N/A 305-006-112 18133-H7-S RPV CLOSURE HEAD STUD 5" N/A 305-006-112 1B13-H7-S RPV CLOSURE HEAD STUD 5" N/A 305-006-112 B-G-1 B6.40 UT 0944-07-E086 NRI Achieved approximately 92% coverage.B-G-1 B6.50 B-G-1 86.10 VT-1 1042-07-071 VT-1 1042-07-054 SAT None.SAT None.B-G-1 86.20 B-G-1 B6.20 B-G-1 86.40 UT 0944-07-E059 UT 0944-07-E060 UT 0944-07-E087 NRI Zone 1 Exam.NRI Zone 2 Exam.NRI Achieved approximately 92% coverage.8-G-1 86.50 8-G-1 86.10 VT-1 1042-07-044 VT-1 1042-07-055 SAT None.SAT None.B-G-1 B6.20 8-G-1 B6.20 UT 0944-07-E061 UT 0944-07-E062 NRI Zone 1 Exam.NRI Zone 2 Exam.Friday, July 13, 2007 Page 13 of 54 24 ID of Component Examined Description of Component Size -Sched. -ISI Dwg. No.ASME Category ASME Exam Item No. Method Exam Report No. Status Remarks 11313-H7-T RPV SHELL, THREADS IN FLANGE AREA 5" N/A 305-006-112 1B13-H7-W RPV CLOSURE HEAD WASHER 5" N/A 305-006-112 1B13-H8-N RPV CLOSURE HEAD NUT 5" N/A 305-006-112 1813-H1-S RPV CLOSURE HEAD STUD 5" N/A 305-006-112 18133-H8-S RPV CLOSURE HEAD STUD 5" N/A 305-006-112 18133-H8-T RPV SHELL, THREADS IN FLANGE AREA 5" N/A 305-006-112 1813-1HR-W RPV CLOSURE HEAD WASHERS 5" N/A 305-006-112 1B13-H9-N RPV CLOSURE HEAD NUT 5" N/A 305-006-112 1B13-H9-S RPV CLOSURE HEAD STUD 5" N/A 305-006-112 1B13-H9-S RPV CLOSURE HEAD STUD 5" N/A 305-006-112 B-G-1 B6.40 UT 0944-07-EO88 NRI Achieved approximately 92% coverage.B-G-1 B6.50 B-G-1 B6.10 VT-1 1042-07-045 VT-1 1042-07-056 SAT None.SAT None.B-G-1 B6.20 B-G-1 B6.20 B-G-1 B6.40 UT 0944-07-E063 UT 0944-07-E064 UT 0944-07-EO89 NRI Zone 1 Exam.NRI Zone 2 Exam.NRI Achieved approximately 92% coverage.B-G-1 B6.50 B-G-1 B6.10 VT-1 1042-07-046 VT-1 1042-07-057 SAT None.SAT None.B-G-1 B6.20 B-G-1 B6.20 UT 0944-07-E065 UT 0944-07-E066 NRI Zone 1 Exam.NRI Zone 2 Exam.Friday, July 13, 2007 Page 14 of 54 Friday, July 13, 2007 Page 14 of 54 REPORT NO. P0059-011 ID of Component Examined Description of Component Size -Sched. -IS Dwg. No.ASME Category ASME Item No.Exam Method Exam Report No. Status Remarks 1B13-H9-T RPV SHELL, THREADS IN FLANGE AREA 5" N/A 305-006-112 1B13-H9-W RPV CLOSURE HEAD WASHERS 5" N/A 305-006-112 1B13-N1A-IR RECIRC OUTLET NOZZLE NIA INNER RADIUS 22" N/A 305-006-107 1B13-N1A-KA RECIRC OUTLET NOZZLE N1A TO VESSEL 22" N/A 305-006-107 1B13-NlA-KB RECIRC OUTLET NOZZLE N1A TO SAFE-END 22" 1.51" 305-006-107 1813-N2A-KB RECIRC. INLET NOZZLE N2A TO SAFE-END 12" 1.125" 305-006-107 1813-N2B-IR RECIRC INLET NOZZLE N2B INNER RADIUS 12" N/A 305-006-107 1B13-N2B-KA RECIRC INLET NOZZLE N2B TO VESSEL 12" N/A 305-006-107 1813-N2B-KB RECIRC. INLET NOZZLE N2B TO SAFE-END 12" 1.125" 305-006-107 1813-N2C-KB RECIRC INLET NOZZLE N2C TO SAFE-END 12" 1.125" 305-006-107 B-G-1 B6.40 UT 0944-07-E090 NRI Achieved approximately 92% coverage.B-G-1 B6.50 VT-1 1042-07-047 SAT None.B-D 83.100 8-D B3.90 VT-1 10800-07-027 UT 10800-07-007 NRI VT-1 with 1 mil wire resolution. 100% coverage and no indications. NRI 96.4% coverage and no indications. R-A R3.ND R-A R2.14 B-D B3. 100 A-UT 10800-07-025 A-UT 1Q800-07-015 A-UT 10800-07-009 GEO None.GEO None.NRI None.B-D B3.90 A-UT 1Q800-07-014 IND 94.6% coverage. One acceptable subsurface indication. R-A R2.14 R-A R2.14 A-UT 10800-07-016 A-UT 10800-07-017 GEO None.GEO None.Friday, July 13, 2007 Page 15 of 54 25 ID of Component Examined Description of Component Size -Sched.- ISl Dwg. No.ASME Category ASME Exam Item No. Method Exam Report No. Status Remarks 1813-N2D-KB RECIRC. INLET NOZZLE N2D TO SAFE-END 12" 1.125" 305-006-107 1B13-N2E-IR RECIRC INLET NOZZLE N2E INNER RADIUS 12" N/A 305-006-107 1B13-N2E-KA RECIRC INLET NOZZLE N2E TO VESSEL 12" N/A 305-006-107 1B13-N2E-KB RECIRC. INLET NOZZLE N2E TO SAFE-END 12" 1.125" 305-006-107 1B13-N2F-KB RECIRC. INLET NOZZLE N2F TO SAFE-END 12" 1.125" 305-006-107 1B13-N2G-KB RECIRC. INLET NOZZLE N2G TO SAFE-END 12" 1.125" 305-006-107 1B13-N2H-KB RECIRC. INLET NOZZLE N2H TO SAFE-END 12" 1.125" 305-006-107 R-A R2.14 B-D B3.100 A-UT 10800-07-018 A-UT 10800-07-010 GEO None.NRI None.B-D B3.90 A-UT 10800-07-011 NRI 94.6% coverage. No relevant indications. R-A R2.14 R-A R2.14 R-A R2.14 R-A R2.14 A-UT 1Q800-07-019 A-UT 1Q800-07-020 A-UT 1Q800-07-021 A-UT 1Q800-07-022 A-UT 1Q800-07-023 A-UT 1Q800-07-012 GEO None.GEO None.GEO None.GEO None.GEO None.NRI None.1813-N2J-KB R-A RECIRC INLET NOZZLE N2J TO SAFE- R2.14 END 12" 1.125" 305-006-107 1813-N2K-IR B-D RECIRC INLET NOZZLE N2K INNER B3.100 RADIUS 12" N/A 305-006-107 1B13-N2K-KA RECIRC INLET NOZZLE N2K TO VESSEL 12" N/A 305-006-107 B-D B3.90 A-UT 10800-07-013 NRI 94.6% coverage. No relevant indications. Friday, July 13, 2007 Page 16 of 54 Friday, July 13, 2007 Page 16 of 54 REPORT NO. P0059-011 ID of Component Examined Description of Component Size -Sched. -ISI Dwg. No.ASME Category ASME ftem No.Exam Method Exam Report No. Status Remarks iB13-N2K-KB RECIRC INLET NOZZLE N2K TO SAFE-END 12" 1.125" 305-006-107 1B13-N4E-KB FEEDWATER NOZZLE N4E TO SAFE-END 12" 1.16" 305-006-108 1813-N9A-KB JET PUMP NOZZLE N9A TO SAFE-END 4" N/A 305-006-106 1B13-N9A-KB JET PUMP NOZZLE N9A TO SAFE-END 4" N/A 305-006-106 1B13-N9A-KB JET PUMP NOZZLE N9A TO SAFE-END 4" N/A 305-006-106 1B13-N9A-KB JET PUMP NOZZLE N9A TO SAFE-END 4" N/A 305-006-106 1B13-N9A-KC JET PUMP INSTR. NOZZLE N9A SAFE-END TO PENE. SEAL 4" N/A 305-006-106 1B13-N9A-KC JET PUMP INSTR. NOZZLE N9A SAFE-END TO PENE. SEAL 4" N/A 305-006-106 1B13-N9B-IR JET PUMP NOZZLE N9B INNER RADIUS 4" N/A 305-006-106 1B13-N9B-KA JET PUMP NOZZLE N9B TO VESSEL 4" N/A 305-006-106 R-A R2.14 A-UT 1Q800-07-024 GEO None.R-A R2.11 R-A R3.ND R-A R3.ND R-A R3.ND R-A R3.ND R-A R3.ND R-A R3.ND A-UT 10800-07-026 UT 0944-07-E136 UT 0944-07-E 135 UT 0944-07-E134 UT 0944-07-E133 UT 0944-07-E194 UT 0944-07-EI95 IND Two flaws sized essentially same as RFO7.NRI 600 RL exam.NRI 45° RL exam.NRI 45' S exam.NRI 380 RL exam.NRI 45' S exam.NRI 70' S exam.B-D 83.100 UT 10800-07-006 NRI None.B-D 83.90 UT 1Q800-07-008 NRI 94.8% coverage.. Friday, July 13, 2007 Page 17 of 54 26 ID of Component Examined Description of Component Size -Sched. -ISI Dwg. No.ASME Category ASME Item No.Exam Method Exam Report No.Status Remarks 1B13-N9B-KB JET PUMP NOZZLE N9B TO SAFE-END 4" N/A 305-006-106 1B13-N9B-KB JET PUMP NOZZLE N9B TO SAFE-END 4" N/A 305-006-106 1B13-N9B-KB JET PUMP NOZZLE N9B TO SAFE-END 4" N/A 305-006-106 1B13-N9B-KB JET PUMP NOZZLE N9B TO SAFE-END 4" N/A 305-006-106 1B13-N9B-KC JET PUMP INSTR. NOZZLE N9B SAFE-END TO PENE. SEAL 4" N/A 305-006-106 1B13-N9B-KC JET PUMP INSTR. NOZZLE N9B SAFE-END TO PENE. SEAL 4" N/A 305-006-106 1B13-CRGT-1b 9 CRD GUIDE TUBE SLEEVE TO ALIGNMENT LUG WELDS N/A N/A 305-006-120 1B13-CRGT-2b 9 CRD GUIDE TUBE BODY TO SLEEVE WELDS N/A N/A 305-006-120 1813-C RGT-3b 9 CRD GUIDE TUBE BASE TO BODY WELDS N/A N/A 305-006-120 1B13-CSPT-SL-04 CORE SUPPORT STRUCTURE, SHROUD LEG N/A N/A 305-006-121 R-A R3.ND R-A R3.ND R-A R3.ND R-A R3.ND R-A R3.ND R-A R3.ND X-A X9.10 X-A X9.20 X-A X9.20 B-N-2 B13.40 UT 0944-07-E137 UT 0944-07-E140 UT 0944-07-E138 UT 0944-07-E139 UT 0944-07-E197 UT 0944-07-E196 VT-3 1Q800-07-029 EVT1 1Q800-07-030 EVT1 10800-07-031 EVT1 10800-07-131 NRI 38' RL exam..NRI 6 0* RL exam.NRI 450 S exam.NRI 450 RL exam.NRI 70° S exam.NRI 450 S exam.SAT Examined CRGT-2 weld of CRGTs 14/23, 14/39, 46/23, and 46/39. 100% coverage and no indications. SAT Examined CRGT-2 weld of CRGTs 14/23, 46/23, 46/39 and 54/31. 100% coverage on 3 & 80% on one, no relevant indications. SAT Examined CRGT-3 weld of CRGTs 14/23, 14/39, 46/23, and 46/39. 100% coverage and no relevant indications. SAT Approx 50% of H-10 & H-12 welds and 35% of H-11 from diffuser hole at 98 degrees. No indications. Friday, July 13, 2007 Page 18 of 54 Friday, July 13, 2007 Page 18 of 54 REPORT NO. P0059-011 ID of Component Examined Description of Component Size- Sched. -ISI Dwg. No.ASME Category ASME Item No.Exam Method Exam Report No.Status Remarks 1B13-CSPT-SL-05 CORE SUPPORT STRUCTURE, SHROUD LEG N/A N/A 305-006-121 1B13-CSHFP-CW-P2 HP CORE SPRAY FLOW DIVIDER REDUCER WELDS 6" 120/40 305-006-113 1B13-CSHP-CW-P3b HP CORE SPRAY HORIZONTAL PIPE TO COUPLING 6" 40 305-006-113 1B13-CSHP-CW-P3a HP CORE SPRAY COUPLING TO HORIZONTAL PIPE 6" 40 305-006-113 1B13-CSHP-CW-P5 HP CORE SPRAY UPPER RISER PIPE TO COUPLING 6" 40 305-006-113 1B13-CSHP-CW-P6 HP CORE SPRAY COUPLING TO LOWER RISER PIPE 6" 40 305-006-113 1B13-CSHP-CW-P4c HP CORE SPRAY LOWER RISER PIPE TO ELBOW 6" 40/120 305-006-113 1B13-CSH P-CW-P4d HP CORE SPRAY ELBOW TO SHROUD FLANGE 6" 120140 305-006-113 1B13-CSHP-CCW-P3a HP CORE SPRAY COUPLING TO HORIZONTAL PIPE 6" 40 305-006-113 1B13-CSHP-CCW-P5 HP CORE SPRAY UPPER RISER PIPE TO COUPLING 6" 40 305-006-113 B-N-2 813.40 X-A X3.11 X-A X3.11 X-A X3.10 X-A X3.10 X-A X3.11 X-A X3.11 X-A X3.11 X-A X3.10 X-A X3.10 EVT1 10800-07-132 EVT1 10800-07-033 EVT1 1Q800-07-034 EVTr 1Q800-07-035 EVT1 1Q800-07-036 EVT1 10800-07-037 EVT1 1Q800-07-038 EVT1 10800-07-039 EVT1 10800-07-040 EVT1 1Q800-07-041 SAT Approx 25% of H-10, H-11, and H-12 welds. No indications. SAT 50% coverage for P2 and P2a welds, no indications. SAT 45% coverage and no indications. SAT 45% coverage and no indications. SAT 45% coverage and no indications. SAT 45% coverage and no indications. SAT 40% coverage and no indications. SAT 80% coverage and no indications. SAT 45% coverage and no indications. SAT 45% coverage and no indications. Friday, July 13, 2007 Page 19 of 54 27 ID of Component Examined Description of Component Size- Sched. -ISI Dwg. No.ASME Category ASME Item No.Exam Method Exam Report No.Status Remarks 1B13-CSHP-CCW-P8 HP CORE SPRAY SHROUD FLANGE TO SHROUD 6" 40 305-006-113 1613-CSLP-P1 LP CORE SPRAY THERMAL SLEEVE TO FLOW DIVIDER WELDS (2)10" 120 305-006-113 1B13-CSLP-CW-P3a LP CORE SPRAY COUPLING TO HORIZONTAL PIPE 6" 40 305-006-113 1B13-CSLP-CW-P5 LP CORE SPRAY UPPER RISER PIPE TO COUPLING 6" 40 305-006-113 1813-CSLP-CCW-P3a LP CORE SPRAY COUPLING TO HORIZONTAL PIPE 6" 40 305-006-113 1B13-CSLP-CCW-P5 LP CORE SPRAY UPPER RISER PIPE TO COUPLING 6" 40 305-006-113 1B13-CSLP-CCW-P6 LP CORE SPRAY COUPLING TO LOWER RISER PIPE 6" 40 305-006-113 1B13-CSS-7-SB CORE SPRAY SPARGER BRACKETS X-A X3.13 X-A X3.11 X-A X3.10 X-A X3_10 X-A X3.10 X-A X3.10 X-A X3.11 X-A X3.22 VT-1 1Q800-07-042 EVT1 1Q800-07-043 EVT1 10800-07-044 EVT1 1Q800-07-045 EVT1 10800-07-046 EVT1 1Q800-07-047 EVT1 10800-07-048 VT-1 10800-07-049 SAT 100% coverage and no indications. SAT No credible EV-l coverage for P1 and only 10%coverage for Pla. No indications. SAT 40% coverage and no indications. SAT 40% coverage and no indications. SAT 45% coverage and no indications. SAT 45% coverage and no indications. SAT 45% coverage and no indications. SAT 80% coverage of brackets at 32 and 50 degrees and 90-100% coverage of their bolting on the outside of the shroud. No indications. SAT 35% coverage on counter-clockwise side and 50%coverage on clockwise side. No indications. SAT 50% coverage and no indications. N/A 305-006-116 1B13-CSS-173-$2 CORE SPRAY SPARGER TEE TO SPARGER PIPE WELDS (2)5" 305-006-115 1B13-CSS-173-S3ab CORE SPRAY SPARGER SPRAY NOZZLE WELDS (2 EA NOZZ)5" 305-006-115 X-A X3.20 X-A X3.21 EVT1 10800-07-050 VT-1 1Q800-07-051 Friday, July 13,2007 Page 20 of 54 Friday, July 13, 2007 Page 20 of 54 REPORT NO. P0059-011 ID of Component Examined Description of Component Size -Sched.- ISI Dwg. No.ASME Category ASME Item No.Exam Method Exam Report No. Status Remarks 1B13-CSS-173-$4 CORE SPRAY SPARGER PIPE TO END CAP WELDS (2)5" 305-006-115 1B13-CSS-173-SB CORE SPRAY SPARGER BRACKETS N/A N/A 305-006-116 1B13-CSS-187-$2 CORE SPRAY SPARGER TEE TO SPARGER PIPE WELDS (2)5" 305-006-115 1B13-CSS-187-S4 CORE SPRAY SPARGER PIPE TO END CAP WELDS (2)5" 305-006-115 1B13-CSS-187-SB CORE SPRAY SPARGER BRACKETS N/A N/A 305-006-116 1B13-CS-H8 SHROUD SUPPORT CYLINDER TO SHROUD SUPPORT PLATE N/A N/A 305-006-121 1B13-CS-H9 SHROUD SUPPORT PLATE TO RX VESSEL WALL N/A N/A 305-006-121 1B13-FSGT-AP1b 9 CRD GUIDE TUBE & FUEL SUPPORT ALIGNMENT PINS N/A N/A 305-006-120 1B13-FWS-DAM 150 DEGREE FW SPARGER DAMAGE, NOZZ 5-8 FROM CCW N/A N/A 305-006-118 1B13-INTERIOR REACTOR VESSEL INTERIOR REGION N/A N/A 305-006-101 X-A X3.20 X-A X3.22 EVT1 10800-07-052 EVT1 10800-07-053 X-A X3.20 X-A X3.20 X-A X3.22 EVTI 10800-07-054 EVT1 10800-07-055 VT-i 10B00-07-056 SAT 50% coverage for both welds and no indications. SAT 70-80% coverage for each of the len (10) brackets and 100% coverage for the bracket bolting on the outside of the shroud. No indications. SAT 45% coverage for the counter-clockwise weld and 50%coverage for the clockwise weld. No indications. SAT 45% coverage for the counter-clockwise weld and 40%coverage for the clockwise weld. No indications. SAT 70-80% coverage for each of the ten (10) brackets and 100% coverage for the bracket bolting on the outside of the shroud. No indications. SAT Approx. 10 degrees of the underside from JP-6 diffuser hole. No indications. SAT Approx, 10 degrees of the underside from JP-6 diffuser hole. No indications. SAT Examined alignment pins of CRGTs 14/23, 46/23, 46/39 and 54/13. 80% coverage and no indications. SAT 100% coverage and no evidence of further degradation. SAT 100% coverage of accessible areas above the top guide flange. No relevant indications beyond previously addressed RPV crud.X-A X5.21 X-A X5.20 X-A X9.10 X-A X6.13 B-N-1 B13.10 EVT1 1Q800-07-133 EVT1 10800-07-134 VT-3 10800-07-032 VT-3 10800-07-057 VT-3 10800-07-058 Friday, July 13, 2007 Page 21 of 54 28 ID of Component Examined Description of Component Size -Sched.- ISI Dwg. No.ASME Category ASME Item No.Exam Method Exam Report No. Status Remarks 1B13-UPPER-INT VESSEL INTERIOR ABOVE FW SPARGERS N/A N/A 305-006-101 1B13-IRM-16/13 IRM INSTRUMENT DRY TUBE B N/A N/A 305-006-117 1B13-IRM-16/53 IRM INSTRUMENT DRY TUBE A N/A N/A 305-006-117 11B13-IRM-24/29 IRM INSTRUMENT DRY TUBE D N/A N/A 305-006-117 1B13-IRM-24/37 IRM INSTRUMENT DRY TUBE C N/A N/A 305-006-117 1 B13-JPA-P3/P4 JET PUMP NOZZLE TO MIXER ASSEMBLY N/A N/A 305-006-126 1B13-JPA-P13/P14 JET PUMP NOZZLE TO MIXER ASSEMBLY N/A N/A 305-006-126 1B13-JPDF-P1 1/P12 JET PUMP DIFFUSER WELDS (10)N/A N/A 305-006-126 1B13-JPDF-P13/P14 JET PUMP DIFFUSER WELDS (10)N/A N/A 305-006-126 1B13-JPDF-P15/P16 JET PUMP DIFFUSER WELDS (10)N/A N/A 305-006-126 X-A X6.15 X-A X2.10 VT-3 10800-07-059 VT-3 1Q800-07-060 SAT Inspection of upper vessel interior areas for RPV crud issue. No significant changes noted. See INR PNPP-RI 1-IVVI-07-08 for crud deposits comparison. SAT 100% coverage of upper 2ft from two opposing quadrants. No indications. X-A X2.10 VT-3 10800-07-061 SAT 100% coverage of upper 2ft from two opposing quadrants. No indications. X-A X2.10 VT-3 10800-07-062 SAT 100% coverage of upper 2ft from two opposing quadrants. No indications. X-A X2.10 VT-3 10800-07-063 SAT 100% coverage of upper 2ft from two opposing quadrants. No indications. X-A X1.30 X-A X1.30 X-A X1.90 VT-3 1Q800-07-064 VT-3 1Q800-07-065 EVT1 10800-07-066 SAT Examined mixer throat of JP-3. No excessive crud build-up noted.SAT Examined mixer throat of JP-13. No excessive crud build-up noted.SAT Examined DF-1, 2, 3a, 3b and AD-2 welds of JPs 11 &12. 25-40% coverage on DF welds, 25% coverage on AD-2 welds. No indications. SAT Examined DF-1, 2, 3a, 3b and AD-2 welds of JPs 13 &14. 25-30% coverage on DF welds, 40% coverage on AD-2 welds. No indications. SAT Examined DF-1, 2, 3a, 3b and AD-2 welds of JPs 15 &16. 15-35% coverage on DF welds, 20-40% coverage on AD-2 welds. No indications. X-A X1.90 EVT1 1Q800-07-067 X-A X1.90 EVT1 1Q800-07-068 Friday, July 13, 2007 Page 22 of 54 Friday, July 13, 2007 Page 22 of 54 REPORT NO. P0059-011 ID of Component Examined Description of Component Size -Sched. -ISI Dwg. No.ASME Category ASME Item No.Exam Method Exam Report No. Status Remarks 1B13-JPDF-P17/P18 JET PUMP DIFFUSER WELDS (10)N/A N/A 305-006-126 1B13-JPDF-P19/P20 JET PUMP DIFFUSER WELDS (10)N/A N/A 305-006-126 1B13-JPIN-P1 1/P12 JET PUMP INLET WELDS (4)N/A N/A 305-006-126 1B13-JPIN-P13/P14 JET PUMP INLET WELDS (4)N/A N/A 305-006-126 1B13-JPIN-P15/P16 JET PUMP INLET WELDS (4)N/A N/A 305-006-126 1B13-JPIN-P17/P18 JET PUMP INLET WELDS (4)N/A N/A 305-006-126 1B13-JPIN-P19/P20 JET PUMP INLET WELDS (4)N/A N/A 305-006-126 1B13-JPLAW-P11 JET PUMP SENSING LINE ATTACHMENT WELDS N/A N/A 305-006-125 1B13-JPLAW-P12 JET PUMP SENSING LINE ATTACHMENT WELDS N/A N/A 305-006-125 1B13-JPLAW-P13 JET PUMP SENSING LINE ATTACHMENT WELDS N/A N/A 305-006-125 X-A X1.90 EVT1 1Q800-07-069 X-A X1.90 EVT1 1Q800-07-070 SAT Examined DF-1, 2, 3a, 3b and AD-2 welds of JPs 17 &18. 10-40% coverage on DF welds, 20% coverage on AD-2 welds. No indications. SAT Examined DF-1, 2, 3a, 3b and AD-2 welds of JPs 19 &20. 20-40% coverage on DF welds, 20% coverage on AD-2 welds. No indications. SAT Examined IN-1 and IN-2 welds of JPs 11 & 12. 20-40%coverage and no indications. X-A X1.80 EVT1 10800-07-071 X-A X1.80 EVT1 10800-07-072 SAT Examined IN-i and IN-2 welds of JPs 13 & 14. 20-25%coverage and no indications. X-A Xl.80 EVT1 1Q800-07-073 SAT Examined IN-1 and IN-2 welds of JPs 15 & 16. 25%coverage and no indications. X-A X1.80 EVT1 10800-07-074 SAT Examined IN-1 and IN-2 welds of JPs 17 & 18. 25%coverage and no indications. X-A X1.80 EVT1 10800-07-075 SAT Examined IN-i and IN-2 welds of JPs 19 & 20. 25%coverage and no indications. X-A X1.20 X-A X1.20 X-A X1.20 VT-3 1Q800-07-076 VT-3 10800-07-077 VT-3 10800-07-078 SAT Examined the 3 sensing line brackets of JP-1 1 and they were all intact.SAT Examined the 3 sensing line brackets of JP-12 and they were all intact.SAT Examined the 3 sensing line brackets of JP-13 and they were all intact.Friday, July 13, 2007 Page 23 of 54 29 ID of Component Examined Description of Component Size- Sched. -ISI Dwg. No.ASME Category ASME Item No.Exam Method Exam Report No.Status Remarks 1B13-JPLAW-P14 JET PUMP SENSING LINE ATTACHMENT WELDS N/A N/A 305-006-125 1B13-JPLAW-P15 JET PUMP SENSING LINE ATTACHMENT WELDS N/A N/A 305-006-125 1B13-JPLAW-P16 JET PUMP SENSING LINE ATTACHMENT WELDS N/A N/A 305-006-125 1B13-JPLAW-P17 JET PUMP SENSING LINE ATTACHMENT WELDS N/A N/A 305-006-125 1B13-JPLAW-P18 JET PUMP SENSING LINE ATTACHMENT WELDS N/A N/A 305-006-125 1B13-JPLAW-P19 JET PUMP SENSING LINE ATTACHMENT WELDS N/A N/A 305-006-125 1B13-JPLAW-P20 JET PUMP SENSING LINE ATTACHMENT WELDS N/A N/A 305-006-125 1B13-JPRB-P1 1/P12 JET PUMP RISER BRACE WELDS (8)N/A N/A 305-006-125 1B13-JPRB-P13/P14 JET PUMP RISER BRACE WELDS (8)N/A N/A 305-006-125 1B13-JPRB-P15/P16 JET PUMP RISER BRACE WELDS (8)N/A N/A 305-006-125 X-A X1.20 X-A X1.20 X-A X1.20 X-A X1.20 X-A X1.20 X-A X1.20 X-A X1.20 X-A X1.40 VT-3 10800-07-079 VT-3 1 Q800-07-080 VT-3 1Q800-07-081 VT-3 10800-07-082 VT-3 1Q800-07-083 VT-3 1Q800-07-084 VT-3 10800-07-085 EVT1 10800-07-086 SAT Examined the 3 sensing line brackets of JP-14 and they were all intact.SAT Examined the 3 sensing line brackets of JP-15 and they were all intact.SAT Examined the 3 sensing line brackets of JP-16 and they were all intact.SAT Examined the 3 sensing line brackets of JP-17 and they were all intact.SAT Examined the 3 sensing line brackets of JP-18 and they were all intact.SAT Examined the 3 sensing line brackets of JP-19 and they were all intact.SAT Examined the 3 sensing line brackets of JP-20 and they were all intact.SAT Examined RB-la-d and RB-2a-d welds. 45-100%coverage and no indications. X-A X1.40 EVT1 1Q800-07-087 SAT Examined RB-la-d and RB-2a-d welds. 40-100%coverage and no indications. X-A X1.40 EVT1 1Q800-07-088 SAT Examined RB-la-d and RB-2a-d welds. 40-100%coverage and no indications. Friday, July 13, 2007 Page 24 of 54 REPORT NO. P0059-011 ID of Component Examined Description of Component Size -Sched.- ISI Dwg. No.ASME Category ASME hem No.Exam Method Exam Report No. Status Remarks 1B13-JPRB-P17/P18 JET PUMP RISER BRACE WELDS (8)N/A N/A 305-006-125 1B13-JPRB-P19/P20 JET PUMP RISER BRACE WELDS (8)N/A N/A 305-006-125 1B13-JPRBA-P11/P12 JET PUMP RISER BRACE ARM/VESSEL ATTACHMENT WELDS N/A N/A 305-006-125 1B13-JPRBA-P13/P14 JET PUMP RISER BRACE ARMNESSEL ATTACHMENT WELDS N/A N/A 305-006-125 1B13-JPRBA-P15/P16 JET PUMP RISER BRACE ARM/VESSEL ATTACHMENT WELDS N/A N/A 305-006-125 1B13-JPRBA-P17/P18 JET PUMP RISER BRACE ARM/VESSEL ATTACHMENT WELDS N/A N/A 305-006-125 1B13-JPRBA-P19/P20 JET PUMP RISER BRACE ARM/VESSEL ATTACHMENT WELDS N/A N/A 305-006-125 1B13-JPREW-PI/P2 JET PUMP RISER ELBOW WELDS (2)N/A N/A 305-006-126 1B13-JPREW-P3/P4 JET PUMP RISER ELBOW WELDS (2)N/A N/A 305-006-126 1B13-JPRS6-P11/P12 JET PUMP RISER PIPE TO RESTRAINER BRACKET WELDS (2)N/A N/A 305-006-126 X-A X1.40 EVT1 1Q800-07-089 SAT Examined RB-la-d and RB-2a-d welds. 50-60%coverage and no indications. X-A X1.40 EVT1 1Q800-07-090 SAT Examined RB-i a-d and RB-2a-d welds. 50% coverage and no indications. B-N-2 B13.20 B-N-2 B13.20 B-N-2 B13.20 B-N-2 B 13.20 B-N-2 B13.20 X-A X1.70 EVT1 10800-07-091 EVT1 1Q800-07-092 EVT1 1Q800-07-093 EVT1 1Q800-07-094 EVT1 1Q800-07-095 EVT1 1Q800-07-096 SAT Exams pertormed in conjunction with BWRVIP-41 riser brace to vessel exams. No indications. SAT Exams performed in conjunction with BWRVIP-41 riser brace to vessel exams. No indications. SAT Exams performed in conjunction with BWRVIP41 riser brace to vessel exams. No indications. SAT Exams performed in conjunction with BWRVIP-41 rser brace to vessel exams. No indications. SAT Exams performed in conjunction with BWRVIP-41 riser brace to vessel exams. No indications. SAT 100% coverage on RS-1, 50% on RS-2. No indications. X-A X1.70 EVT1 10800-07-097 SAT 100% coverage on RS-1, 50% on RS-2. No indications. X-A X1.72 EVT1 10800-07-098 SAT Examined RS-6 (JP-12 side) and RS-7 (JP-11 side)welds. 60% coverage RS-6 and 65% coverage RS-7.No indications. Friday, July 13, 2007 Page 25 of 54 30 ID of Component Examined Description of Component Size- Sched.- ISl Dwg. No.ASME Category ASME Item No.Exam Method Exam Report No. Status Remarks 1B13-JPRS6-P13/P14 JET PUMP RISER PIPE TO RESTRAINER BRACKET WELDS (2)N/A N/A 305-006-126 1B13-JPRS6-P15/P16 JET PUMP RISER PIPE TO RESTRAINER BRACKET WELDS (2)N/A N/A 305-006-126 1B13-JPRS6-P17/P18 JET PUMP RISER PIPE TO RESTRAINER BRACKET WELDS (2)N/A N/A 305-006-126 1B13-JPRS6-P19/P20 JET PUMP RISER PIPE TO RESTRAINER BRACKET WELDS (2)N/A N/A 305-006-126 1B13-JPRS8-P1 1/P12 JET PUMP RISER PIPE TO RISER BRACE YOKE WELDS (2)N/A N/A 305-006-125 1B13-JPRS8-P13/P14 JET PUMP RISER PIPE TO RISER BRACE YOKE WELDS (2)N/A N/A 305-006-125 1B13-JPRS8-P15/P16 JET PUMP RISER PIPE TO RISER BRACE YOKE WELDS (2)N/A N/A 305-006-125 1B13-JPRS8-P17/P18 JET PUMP RISER PIPE TO RISER BRACE YOKE WELDS (2)N/A N/A 305-006-125 1B13-JPRS8-P19/P20 JET PUMP RISER PIPE TO RISER BRACE YOKE WELDS (2)N/A N/A 305-006-125 1B13-JPTW-P06 JET PUMP RESTRAINER ADJUSTING SCREW TACK WELDS N/A N/A 305-006-125 X-A X1.72 X-A X1.72 X-A X1.72 X-A X1.72 X-A X1.72 X-A X1.72 X-A X1.72 X-A X1.72 X-A X1.72 X-A X1.50 EVT1 10800-07-099 EVT1 1Q800-07-100 EVT1 1Q800-07-101 EVT1 1Q800-07-102 EVT1 1Q800-07-103 EVT1 10800-07-104 EVT1 1Q800-07-105 EVT1 10800-07-106 EVT1 10800-07-107 VT-1 10800-07-028 SAT Examined RS-6 (JP-14 side) and RS-7 (JP-13 side)welds. 60% coverage for both RS-6 and RS-7. No indications. SAT Examined RS-6 (JP-16 side) and RS-7 (JP-15 side)welds. 60% coverage for RS-6 and 50% for RS-7. No indications. SAT Examined RS-6 (JP-18 side) and RS-7 (JP-17 side)welds. 80% coverage for for both RS-6 and RS-7. No indications. SAT Examined RS-6 (JP-20 side) and RS-7 (JP-19 side)welds. 60% coverage for for both RS-6 and RS-7. No indications. SAT Examined RS-8 (lower) and RS-9 (upper) riser brace to yoke welds. 90% coverage for for both RS-8 and RS-9.No indications. SAT Examined RS-8 (lower) and RS-9 (upper) riser brace to yoke welds. 90% coverage for for both RS-8 and RS-9.No indications. SAT Examined RS-8 (lower) and RS-9 (upper) riser brace to yoke welds. 90% coverage for for both RS-8 and RS-9.No indications. SAT Examined RS-8 (lower) and RS-9 (upper) riser brace to yoke welds. 80% coverage for RS-8 and 60% for RS-9.No indications. SAT Examined RS-8 (lower) and RS-9 (upper) riser brace to yoke welds. 70% coverage for RS-8 and 80% for RS-9.No indications. SAT Pre-disassembly found a small gap (< 0.010) on vessel side set screw, none upon re-assembly. Friday, July 13, 2007 Page 26 ot 54 Friday, July 13, 2007 Page 26 of 54 REPORT NO. P0059-011 ID of Component Examined Description of Component Size- Sched. -ISl Dwg. No.ASME Category ASME Item No.Exam Method Exam Report No.Status Remarks 1B13-JPWD-P1(P2 JET PUMP RESTRAINER BRACKET WEDGE BEARING SURFACE N/A N/A 305-006-125 1B13-JPWD-P3/P4 JET PUMP RESTRAINER BRACKET WEDGE BEARING SURFACE N/A N/A 305-006-125 1B13-JPWD-PS/P6 JET PUMP RESTRAINER BRACKET WEDGE BEARING SURFACE N/A N/A 305-006-125 1B13-JPWD-P7/P8 JET PUMP RESTRAINER BRACKET WEDGE BEARING SURFACE N/A N/A 305-006-125 1B13-JPWD-P9/P1O JET PUMP RESTRAINER BRACKET WEDGE BEARING SURFACE N/A N/A 305-006-125 1B13-JPWD-P1 1/P12 JET PUMP RESTRAINER BRACKET WEDGE BEARING SURFACE N/A N/A 305-006-125 1B13-JPWD-P13/P14 JET PUMP RESTRAINER BRACKET WEDGE BEARING SURFACE N/A N/A 305-006-125 1B13-JPWD-P15/P16 JET PUMP RESTRAINER BRACKET WEDGE BEARING SURFACE N/A N/A 305-006-125 1B13-JPWD-P17/P18 JET PUMP RESTRAINER BRACKET WEDGE BEARING SURFACE N/A N/A 305-006-125 1 B13-JPWD-Pl9/P20 JET PUMP RESTRAINER BRACKET WEDGE BEARING SURFACE NIA NIA 305-006-125 X-A X1.51 X-A X1.51 X-A X1.51 X-A X1.51 X-A X1.51 X-A X1.51 X-A X1.51 X-A X1.51 X-A X1.51 X-A X1.51 VT-1 10800-07-108 VT-1 10800-07-109 VF-1 1Q800-07-110 VT-1 10800-07-111 VT-1 10800-07-112 VT-1 1Q800-07-113 VT-1 10800-07-114 VT-1 10800-07-115 VT-1 1 Q800-07-116 VT-1 10800-07-117 SAT Examined wedge assemblies of JPs 1 and 2. No signs of wear.SAT Examined wedge assemblies of JPs 3 and 4. No signs of wear. Minor rub marks on wedge rod of JP-4.SAT Examined wedge assemblies of JPs 5 and 6. No signs of wear.SAT Examined wedge assemblies of JPs 7 and 8. No signs of wear.SAT Examined wedge assemblies of JPs 9 and 10. Minor wedge rod wear on JP-10 (see CR 07-18581). SAT Examined wedge assemblies of JPs 11 and 12. No signs of wear.SAT Examined wedge assemblies of JPs 13 and 14. No signs of wear.SAT Examined wedge assemblies of JPs 15 and 16. No signs of wear on JP-16 and wedge wear found on JP-15 in RFO10 is unchanged (see CR 07-18578). SAT Examined wedge assemblies of JPs 17 and 18. Minor wedge rod wear on JP-17 (see CR 07-18581). SAT Examined wedge assemblies of JPs 19 and 20. No signs of wear.Friday, July 13, 2007 Page 27 of 54 31 ID of Component Examined Description of Component Size -Sched.- ISI Dwg. No.ASME Category ASME Item No.Exam Method Exam Report No. Status Remarks 1813-LPRM-SAMP LPRM INSTRUMENT DRY TUBES 10%SAMPLE N/A N/A 305-006-117 1B13-LPCI-B61 LOOP B LPCI COUPLING PIPE WELDS (4)N/A N/A 305-006-124 1B13-LPCI-BST LOOP B LPCI COUPLING STRUT WELDS (3)N/A N/A 305-006-124 1B13-LPCI-B66 LOOP B LPCI SHROUD ATTACHMENT RING WELD N/A N/A 305-006-124 1B13-SD-STRUCT STEAM DRYER STRUCTURAL N/A N/A 305-006-119 1B13-SHSAM SHROUD HEAD STUD ASY MOD LOCKING PINS N/A N/A 305-006-119 1B13-SRM-16/45 SRM INSTRUMENT DRY TUBE A N/A N/A 305-006-117 1B13-SRM-40/21 SRM INSTRUMENT DRY TUBE C N/A N/A 305-006-117 1B13-SSAHC SHROUD SUPPORT ACCESS HOLE COVER WELD N/A N/A 305-006-121 1B13-SSL SHROUD SUPPORT LEG WELDS N/A N/A 305-006-101 X-A X2.11 X-A X8.10 X-A X8.20 X-A X8.30 X-A X4.11 VT-3 10800-07-118 EVT1 10800-07-119 EVT1 10800-07-120 VE 1Q800-07-121 VT-3 1 Q800-07-122 SAT Examined LPRMs 24/41, 32/57, 40/57, 41/16, 48/17 and 48/41 from one quadrant, and 40/49 and 48/25 from two quadrants. No indications. SAT BWRVIP-42 6-1a through 6-1d welds. Best effort exam for 6-1a weld as it is within nozzle bore. 40-50%coverage on other welds. No indications. SAT BWRVIP-42 6-4, 6-5a and 6-5b welds. 75-90%coverage and indications. SAT BWRVIP-42 6-6b weld. 90% coverage and indications. SAT Examined 90 and 270 degree sides for comparison of crud to previous outage. No significant changes noted.X-A X6.14 X-A X2.10 VT-3 1Q800-07-123 VT-3 1Q800-07-124 SAT Examined the 16 SHSAMs for anti-rotation pin wear.The worst was the counter-clockwise side of #2 with 45% wear (see CR 07-18329). SAT Examined upper 2 feet of SRM from two opposing quadrants. No indications. X-A X2.10 VT-3 1Q800-07-125 SAT Examined upper 2 feet of SRM from two opposing quadrants. No indications. X-A X5.30 X-A X5.40 EVT1 1Q800-07-126 EVT1 10800-07-135 SAT Examined cover plate to cylinder and cylinder to shroud support plate welds. 40% coverage and no indications. SAT Portions of H-10, H-1I and H-12 Shroud Support leg welds of legs 4 and 5. No indications. Friday, July 13, 2007 Page 28 of 54 REPORT NO. P0059-011 ID of Component Examined Description of Component Size -Sched. -ISl Dwg. No.ASME Category ASME Exam Item No. Method Exam Report No. Status Remarks 1B21-0129 26' PEN. P124 PROCESS PIPE TO VALVE F028A 26' 1.196" 305-605-107 1B21-F0028C-IS 26' GLOBE, MSIV,INTERNAL SURFACE (GROUPING NO. II)26' N/A 305-605-109 R-A R2.ND UT 0944-07-E141 B-M-2 VT-3 1042-07A-023 B12.50 GEO Counterbore located 1.8" DNST valve side from Weld CL.SAT Internal inspection performed when valve was reworked due to failed LLRT. Interior exan acceptable, but CR 07-18780 written for seat indications. NRI Additional exams for indications found in 1821-F028A-18B that were later proven to be non-relevant. NRI Additional exams for indications found in 1B21-F028A-18B that were later proven to be non-relevant. 1B21-F028A-IB MSIV STUD B-G-1 UT B6.210 N/A N/A 305-605-111 0944-07-E106 0944-07-E105 1B21-F028A-1B MSIV STUD B-G-1 UT B6.210 N/A N/A 305-605-111 1B21-F028A-2B MSIV STUD B-G-1 UT B6.210 0944-07-E107 NRI Additional exams for indications found in 1B21-F028A-18B that were later proven to be non-relevant. N/A N/A 305-605-111 11321-F028A-2B MSIV STUD B-G-1 UT B6.210 0944-07-E108 NRI Additional exams for indications found in 1B21-F028A-18B that were later proven to be non-relevant. N/A N/A 305-605-111 1B21-F028A-3B MSIV STUD B-G-1 UT B6.210 0944-07-E109 NRI Additional exams for indications found in 1B21-F028A-18B that were later proven to be non-relevant. N/A N/A 305-605-111 1621-F028A-3B MSIV STUD N/A N/A 305-605-111 1B21-F028A-4B MSIV STUD N/A N/A 305-605-111 B-G-1 UT B6.210 B-G-1 UT B6.2 10 0944-07-El 10 0944-07-E 111 NRI Additional exams for indications found in 1B21-F028A-18B that were later proven to be non-relevant. NRI Additional exams for indications found in 1B2 1-F028A-18B that were later proven to be non-relevant. 1B21-F028A-4B MSIV STUD B-G-1 UT B6.210 0944-07-El 12 NRI Additional exams for indications found in 1B21-F028A-18B that were later proven to be non-relevant. N/A N/A 305-605-111 Friday, July 13, 2007 Page 29 of 54 32 ID of Component Examined Description of Component Size- Sched. -IS[ Dwg. No.ASME Category ASME Item No.Exam Method Exam Report No. Status Remarks 1B21-F028A-5B MSIV STUD B-G-1 B6.210 UT 0944-07-E 114 NRI Additional exams for indications found in 1B21-F028A-188 that were later proven to be non-relevant. N/A N/A 305-605-111 1B21-F028A-5B MSIV STUD B-G-1 86.210 UT 0944-07-El13 NRI Additional exams for indications found in 1B21-F028A-18B that were later proven to be non-relevant. N/A N/A 305-605-111 1B21-F028A-6B MSIV STUD B-G-1 B6.210 UT 0944-07-E115 NRI Additional exams for indications found in 1B21-F028A-18B that were later proven to be non-relevant. N/A N/A 305-605-111 1B21-F028A-6B MSIV STUD B-G-1 B6.210 UT 0944-07-El 16 NRI Additional exams for indications found in 1B21-F028A-18B that were later proven to be non-relevant. N/A N/A 305-605-111 1B21-F028A-13B MSIV STUD N/A N/A 1B21-F028A-13B MSIV STUD B-G-1 B6.210 UT 0944-07-E094 GEO Zone 2 Exam.305-605-111 B-G-1 B6.210 UT 0944-07-E093 NRI Zone 1 Exam.N/A N/A 305-605-111 1B21-F028A-148 MSIV STUD N/A N/A 1B21-F028A-14B MSIV STUD B-G-1 B6.210 UT 0944-07-E096 NRI Zone 2 Exam.305-605-111 B-G-1 86.210 UT 0944-07-E095 NRI Zone 1 Exam.N/A N/A 305-605-111 1B21-F028A-15B MSIV STUD N/A N/A 1621-F028A-15B MSIV STUD B-G-1 B6.210 UT 0944-07-E098 NRI Zone 2 Exam.305-605-111 B-G-1 86.210 UT 0944-07-E097 NRI Zone 1 Exam.N/A N/A 305-605-111 Friday, July 13, 2007 Page 30 of 54 REPORT NO. P0059-011 ID of Component Examined Description of Component Size -Sched.- ISI Dwg. No.ASME Category ASME Item No.Exam Method Exam Report No.Status Remarks 1821-F028A-16B MSIV STUD B-G-1 B6.210 UT 0944-07-El1O NRI Zone 2 Exam.N/A N/A 305-605-111 1B21-F028A-16B MSIV STUD B-G-1 B6.210 UT 0944-07-E099 NRI Zone 1 Exam.N/A N/A 305-605-111 1821-F028A-17B MSIV STUD B-G-1 B6.210 UT 0944-07-E102 NRI Zone 2 Exam.N/A N/A 305-605-111 1821-F028A-17B MSIV STUD B-G-1 B6.210 UT 0944-07-ElOl NRI Zone 1 Exam.N/A N/A 305-605-111 1B21-F028A-18B MSIV STUD B-G-1 B6.210 UT 0944-07-E104 GEO Zone 2 Exam. Reference Report No. 0944-07-E094 (Page 2) for Indications 1 and 2.N/A N/A 305-605-111 1B21-F028A-18B MSIV STUD B-G-1 B6.210 UT 0944-07-E103 NRI Zone 1 Exam.N/A N/A 305-605-111 1 B21-H0004 MECHANICAL SNUBBER F-A F3.SN VT-3 VT-07-0202 SAT None.14" N/A 305-605-128 1 B21-H0053 VARIABLE SPRING (WA)14" N/A 305-605-130 1821-1H0053-WA INTEGRAL ATTACHMENT VARIABLE SPRING 14" N/A 305-605-130 1B21-HO 119 MECHANICAL SNUBBER (WA)(TANDEM)12" N/A 305-605-122 F-A F3.SP VT-3 1042-07-033 SAT None.D-Ac D1.20 F-A F3.SN VT-1 1042-07-034 VT-3 VT-07-0207/0208 SAT None.SAT None.Friday, July 13, 2007 Page 31 of 54 33 ID of Component Examined Description of Component Size- Sched. -ISI Dwg. No.ASME Category ASME Rlem No.Exam Method Exam Report No.Status Remarks 1B21-H0119-WA INTEGRAL ATTACHMENT MECHANICAL SNUBBER 12" N/A 305-605-122 1B21-H0161 RIGID STRUT (WA)12" N/A 305-605-124 D-Ac D1.20 VT-1 1042-07-086 VT-3 1042-07-016 SAT None.SAT None.F-A F3.ST 1821--H0489 RIGID GUIDE F-A F1.G VT-3 1042-07-013 SAT None.2" N/A 305-605-105 1B21-P124-WA P124 FLUED HD FITTING TO PROCESS PIPE ATTACH WELD 26" 1.196 305-605-107 1B21-P124-WA @P124 FLUED HD FITTING TO PROCESS PIPE ATTACH WELD 26" 1.196 305-605-107 1B21-P124-WA @P124 FLUED HD FITTING TO PROCESS PIPE ATTACH WELD 26" 1.196 305-605-107 1B21-P124-WA @P124 FLUED HD FITTING TO PROCESS PIPE ATTACH WELD 26" 1.196 305-605-107 1B21-S102A HYDRAULIC SNUBBER MPL 1B21G7072 26" N/A 305-605-101 1B21-$107C HYDRAULIC SNUBBER MPL 1B21G7091 26" N/A 305-605-103 B-Kc B10.20 X-E X10.20 X-E X10.20 X-E X10.20 MT 0942-07A-014 UT 0944-07-E131 UT 0944-07-E130 UT 0944-07-E132 SAT Examined the outside surfaces, equalling 50% coverage (IR-007), of the Flued Head Penetration attachment weld.NRI Augmented exam for High Energy Break Exclusion Region requirements. NRI Augmented exam for High Energy Break Exclusion Region requirements. NRI Augmented exam for High Energy Break Exclusion Region requirements. F-A FI.SN VT-3 VT-07-0436 SAT None.F-A FI.SN VT-3 VT-07-0437 SAT None.1833-C0013-11B PUMP BOLTING B-G-1 B6.180 UT 0944-07-E155 NRI Zone 2 Exam.N/A N/A 305-602-105 Friday, July 13, 2007 Page 32 of 54 Friday, July 13, 2007 Page 32 of 54 REPORT NO. P0059-011 ASME ID of Component Examined Category Description of Component ASME Exam Size- Sched. -ISI Dwg. No. Item No. Method Exam Report No. Status Remarks 1B33-C001B-1B B-G-1 UT 0944-07-E154 NRI Zone 1 Exam.PUMP BOLTING B6.180 N/A N/A 305-602-105 1B33-C001B-2B B-G-1 UT 0944-07-E156 NRI Zone 1 Exam.PUMP BOLTING B6.180 N/A N/A 305-602-105 1B33-C001B-2B B-G-1 UT 0944-07-E157 NRI Zone 2 Exam.PUMP BOLTING 86.180 N/A N/A 305-602-105 1B33-C001B-3B B-G-1 UT 0944-07-E159 NRI Zone 2 Exam.PUMP BOLTING B6.180 N/A N/A 305-602-105 1B33-C001B-3B B-G-1 UT 0944-07-E158 NRI Zone 1 Exam.PUMP BOLTING B6.180 N/A N/A 305-602-105 1B33-CO01B-4B B-G-1 UT 0944-07-E160 NRI Zone 1 Exam.PUMP BOLTING B6.180 N/A N/A 305-602-105 1B33-C001B-4B B-G-1 UT 0944-07-E161 NRI Zone 2 Exam.PUMP BOLTING B6.180 N/A N/A 305-602-105 1B33-C001B-5B B-G-1 UT 0944-07-E163 NRI Zone 2 Exam.PUMP BOLTING B6.180 N/A N/A 305-602-105 11B33-C0011B-5B B-G-1 UT 0944-07-E162 NRI Zone 1 Exam.PUMP BOLTING B6.180 N/A N/A 305-602-105 1B33-COO1B-6B B-G-1 UT 0944-07-E165 NRI Zone 2 Exam.PUMP BOLTING 86.180 N/A N/A 305-602-105 Friday, July 13, 2007 Page 33 of 54 34 ID of Component Examined Description of Component Size -Sched. -ISI Dwg. No.1B33-CO01 B-6B PUMP BOLTING N/A N/A 305-602-105 1B33-CO01B-7B PUMP BOLTING N/A N/A 305-602-105 1B33-CO01B-7B PUMP BOLTING N/A N/A 305-602-105 1B33-CO01B-8B PUMP BOLTING N/A N/A 305-602-105 1 B33-CO01B-8B PUMP BOLTING N/A N/A 305-602-105 1B33-CO01 B-9B PUMP BOLTING N/A N/A 305-602-105 1 B33-CO01B-9B PUMP BOLTING N/A N/A 305-602-105 1B33-CO01B-10B PUMP BOLTING N/A N/A 305-602-105 1B33-CO01B-10B PUMP BOLTING N/A N/A 305-602-105 1B33-CO01B-11B PUMP BOLTING N/A N/A 305-602-105 Friday, July 13, 2007 ASME Category ASME Item No.B-G-1 B6.180 B-G-1 B6.180 B-G-1 B6.180 B-G-1 B6.180 B-G-1 B6.180 B-G-1 B6.180 B-G-1 B6.180 B-G-1 B6.180 B-G-1 B6.180 B-G-1 B6.180 Exam Method Exam Report No. Status Remarks UT 0944-07-E164 NRI Zone 1 Exam.UT 0944-07-E166 UT 0944-07-E167 UT 0944-07-E168 UT 0944-07-E169 LIT 0944-07-E170 UT 0944-07-El7l UT 0944-07-E 172 UT 0944-07-E173 UT 0944-07-E175 NRI Zone 1 Exam.NRI Zone 2 Exam.NRI Zone 1 Exam.NRI Zone 2 Exam.NRI Zone 1 Exam.NRI Zone 2 Exam.NRI Zone 1 Exam.NRI Zone 2 Exam.NRI Zone 2 Exam.Page 34 of 54 REPORT NO. P0059-011 ID of Component Examined Description of Component Size- Sched. -ISI Dwg. No.11B33-C001B-116 PUMP BOLTING N/A N/A 305-602-105 1833-COOIB-11N NUT N/A N/A 305-602-105 1B33-COO1B-12B PUMP BOLTING N/A N/A 305-602-105 1B33-C001B-12B PUMP BOLTING N/A N/A 305-602-105 1B33-CO01B-12N NUT N/A N/A 305-602-105 1633-COO11B-13B PUMP BOLTING N/A N/A 305-602-105 1B33-C001B-13B PUMP BOLTING N/A N/A 305-602-105 1633-C001B-13N NUT N/A N/A 305-602-105 1833-CO01B-14B PUMP BOLTING N/A N/A 305-602-105 1B33-CO01B-14B PUMP BOLTING N/A N/A 305-602-105 ASME Category ASME Item No.B-G-1 86.180 B-G-1 B6.200 B-G-1 B6.180 B-G-1 B6.180 B-G-1 B6.200 B-G-1 B6.180 B-G-1 B6.180 B-G-1 B6.200 B-G-1 B6.180 B-G-1 86.180 Exam Method Exam Report No. Status Remarks UT 0944-07-E 174 NRI Zone 1 Exam.VT-i 1042-07-091 UT 0944-07-E177 UT 0944-07-E176 VT-i 1042-07-092 UT 0944-07-E179 UT 0944-07-E178 VT-1 1042-07-093 UT 0944-07-E181 UT 0944-07-ElBO SAT None.NRI Zone 2 Exam.NRI Zone 1 Exam.SAT None.NRI Zone 2 Exam.NRI Zone 1 Exam.SAT None.NRI Zone 2 Exam.NRI Zone 1 Exam.Friday, July 13, 2007 Page 35 of 54 35 ID of Component Examined Description of Component Size -Sched.- ISI Dwg. No.ASME Category ASME Item No.Exam Method Exam Report No.Status Remarks 1B33-C0018-14N NUT N/A N/A 1B33-C001B-15B PUMP BOLTING N/A N/A 1B33-CO018-15B PUMP BOLTING B-G-1 B6.200 VT-1 1042-07-094 SAT None.305-602-105 B-G-1 B6.180 UT 0944-07-E182 NRI Zone 1 Exam.305-602-105 B-G-1 B6.180 UT 0944-07-E183 NRI Zone 2 Exam.N/A N/A 305-602-105 1B33-C001B-15N NUT N/A N/A 1B33-CO01B-16B PUMP BOLTING N/A N/A 1B33-COOIB-16B PUMP BOLTING N/A N/A 1B33-CO01B-16N NUT N/A N/A B-G-1 B6.200 VT-1 1042-07-095 SAT None.305-602-105 B-G-1 86.180 UT 0944-07-E185 NRI Zone 2 Exam.305-602-105 B-G-1 B6.180 UT 0944-07-E184 NRI Zone I Exam.305-602-105 B-G-1 B6.200 VT-1 1042-07-096 SAT None.305-602-105 1B33-H353B F-A VARIABLE SPRING, MPL 1B33G7021B F1.SP 16" N/A 305-602-103 VT-3 1042-07-087 SAT None.1833-S371A HYDRAULIC SNUBBER, PUMP MOTOR, MPL 1B33G7066A N/A N/A 305-602-102 F-A F1.40 VT-3 VT-07-0416 SAT None.1Cll-0033 8" PIPE TO TEE C-F-2 C5.51 UT 0944-07-E091 NRI ID geometry observed intermittently 360' below recordable levels.8" 100 305-871-104 Friday, July 13, 2007 Page 36 of 54 Friday, July 13, 2007 Page 36 of,54 REPORT NO. P0059-011 ID of Component Examined Description of Component Size -Sched. -IS Dwg. No.ASME Category ASME Item No.Exam Method Exam Report No.Status Remarks IC 11-0047 lCll-0047 8" X 12" REDUCING ELBOW TO PIPE 12" 100 305-871-101 C-F-2 C5.51 UT 0944-07-E092 NRI ID geometry observed intermittently 360° below recordable levels.IC11-H0040 RIGID GUIDE (WA)F-A F2.G VT-3 1042-07-019 SAT None.8" N/A 305-871-104 ICI 1-H0040-WA PIPING SUPPORT WELDED ATTACHMENT 8" N/A 305-871-104 C-Cc C3.20 PT 0941-07A-003 SAT None.1CI -H0050 RIGID STRUT F-A F2.ST VT-3 1042-07-018 SAT None.8" N/A 305-871-101 1C1l-H0663 MECHANICAL SNUBBER F-A F2.SN VT-3 VT-07-0065 SAT None.8" N/A 305-871-103 1E12-0055 18" PIPE TO VALVE F067 C-F-2 C5.51 UT 0944-07-E016 NRI None.18" 40 305-642-110 1E12-0056 VALVE F067 TO 18" PIPE C-F-2 C5.51 UT 0944-07-E017 NRI None.18" 40 305-642-110 1E12-0086 24" PIPE TO FLANGE C-F-2 C5.51 UT 0944-07-E014 NRI None.24" 40 305-642-114 1E12-0086 24" PIPE TO FLANGE C-F-2 C5.51 UT 0944-07-E013 NRI None.24" 40 305-642-114 1E12-0205 20" PIPE TO HEAT EXCHANGER B001D INLET NOZZLE 20" 40 305-643-113 C-F-2 C5.51 UT 0944-07-E003 NRI None.Friday, July 13, 2007 Page 37 of 54 36 ID of Component Examined Description of Component Size -Sched. -ISl Dwg. No.ASME Category ASME Item No.Exam Method Exam Report No. Status Remarks 1E12-0215 18" PIPE TO VALVE F029C C-F-2 C5.51 HIT og44-07-E015 NRI None.18" 40 305-643-117 1E12-0638 ELBOW TO 18" PIPE C-F-2 C5.51 UT 0944-07-E004 NRI Previous geometry noted below recording levels.18" STD 305-643-109 1E12-0688 12"ELBOW TO PIPE C-F-2 C5.51 UT 0944-07-E009 GEO Observed root geometry above and below recordable levels intermittently 360'.12" 40 305-642-136 1E12-0688 12" ELBOW TO PIPE C-F-2 C5.51 UT 0944-07-EO10 GEO Observed root geometry at varying amplitudes intermittently 360* as previously recorded.12" 40 305-642-136 1E12-0696 12" ELBOW TO PIPE R-A R2.ND UT 0944-07-E127 NRI None.12" 80 305-642-137 1E12-0696 12" ELBOW TO PIPE R-A R2.ND UT 0944-07-E128 NRI None.12" 80 305-642-137 1E12-0696 12" ELBOW TO PIPE R-A R2.ND UT 0944-07-E129 GEO Root and Counterbore. 12" 80 305-642-137 1E12-0718 12" PIPE TO ELBOW R-A R2.ND UT 0944-07-E126 GEO Previously recorded geometry observed with no significant change.12" 80 305-642-141 1E12-0839 18" PIPE TO 18" X 18" X 18" TEE C-F-2 C5.51 UT 0944-07-E018 GEO Previously recorded geometry observed with no significant changes.18" 40 305-643-120 1E12-C002C-004 HEAD FLANGE TO HEAD SHELL N/A N/A 305-643-122 C-G C6.10 MT 0942-07A-010 SAT None.Friday, July 13, 2007 Page 38 of 54 Friday, July 13, 2007 Page 38 of 54 REPORT NO. P0059-011 ID of Component Examined Description of Component Size -Sched.- ISI Dwg. No.ASME Category ASME Item No.Exam Method Exam Report No. Status Remarks IE12-CO02C-009 HEAD SHELL TO HEAD COVER N/A N/A 305-643-122 1E12-C002C-009 HEAD SHELL TO HEAD COVER N/A N/A 305-643-122 1E12-C002C-010 HEAD SHELL LONGITUDINAL SEAM N/A N/A 305-643-122 C-G C6.10 C-G C6.10 C-G C6.10 F-A F1.R PT 0941-07A-002 MT 0942-07A-01 1 MT 0942-07A-012 VT-3 1042-07-023 SAT None.SAT None.SAT None.SAT None.1E12-H0027 RIGID SUPPORT 12" N/A 305-642-142 1E12-H0036 MECHANICAL SNUBBER 12" N/A 305-642-135 1E12-H0051 MECHANICAL SNUBBER 12" N/A 305-642-137 F-A Fl.SN VT-3 VT-07-0092 SAT None.F-A F1.SN VT-3 VT-07-0118 VT-3 1042-07-036 SAT None.SAT None.1E12-H0062 RIGID GUIDE (WA)12" N/A F-A F3.G 305-642-149 1E12-H0062-WA INTEGRAL ATTACHMENT RIGID GUIDE 12" N/A 305-642-149 D-Ac D1.20 VT-1 1042-07-037 SAT None.1E12-H0084 RIGID STRUT 10" N/A F-A F2.STm VT-3 1042-07-021 SAT None.305-642-133 1E12-H0102 ANCHOR (WA <.75" T)8" N/A 305-641-117 F-A F2.A VT-3 1042-07-008 SAT None.Friday, July 13, 2007 Page 39 of 54 37 ID of Component Examined Description of Component Size -Sched. -ISI Dwg. No.ASME Category ASME Item No.Exam Method Exam Report No. Status Remarks 1E12-H0123 RIGID STRUT F-A F2.ST VT-3 1042-07-007 SAT Reference Condition Report Number 07-16400.12" N/A 305-642-132 1E12-H0154 RIGID GUIDE F-A F2.G VT-3 1042-07-011 SAT None.N/A 305-641-116 1E12-H0185 RIGID STRUT F-A F2.ST VT-3 1042-07-006 SAT None.N/A 305-643-101 1E12-H0190 MECHANICAL SNUBBER F-A F2.SN VT-3 VT-07-0071 SAT None.N/A 305-643-111 1E12-H0237 VARIABLE SPRING F-A F2.SP VT-3 1042-07-002 SAT None.18" N/A 305-643-113 1E12-H0304 RIGID STRUT F-A F2.ST VT-3 1042-07-004 SAT None.8" N/A 305-641-115 1E12-H0365 MECHANICAL SNUBBER F-A F2.SN VT-3 VT-07-0079 SAT None.24" N/A 305-642-114 1E12-H0369-WA PIPING SUPPORT WELDED ATTACHMENT 24" N/A 305-642-114 C-Cc C3.20 MT 0942-07A-009 SAT None.1E12-H0382 MECHANICAL SNUBBER F-A F2.SN VT-3 VT-07-0078 SAT None.N/A 305-642-114 1E12-H0384 VARIABLE SPRING (WA <.75"T)10" N/A 305-642-114 F-A F2.SP VT-3 1042-07-010 SAT Reference Condition Report Number 07-16404.Friday, July 13, 2007 Page 40 of 54 Friday, July 13, 2007 Page 40 of 54 REPORT NO. P0059-011 ID of Component Examined Description of Component Size -Sched.- ISl Dwg. No.ASME Category ASME Item No.Exam Method Exam Report No. Status Remarks 1E12-H0556 MECHANICAL SNUBBER (TANDEM)18" N/A 305-643-109 1E12-H0565 MECHANICAL SNUBBER (TANDEM)6" N/A 305-643-109 F-A F2.SN F-A F2.SN F-A F2.SP VT-3 VT-07-0055/0056 VT-3 VT-07-0053/0054 VT-3 1042-07-032 SAT None.SAT None.SAT None.1E12-H0661 VARIABLE SPRING 12" N/A 1E12-H0693 RIGID GUIDE 12" N/A 305-642-137 F-A F2.G VT-3 1042-07-017 SAT None.305-642-137 1E12-H0694 MECHANICAL SNUBBER 12" N/A 305-642-149 1E12-H0708 RIGID STRUT (WA)18" N/A 305-643-117 1E12-H0708-WA PIPING SUPPORT WELDED ATTACHMENT 18" N/A 305-643-117 F-A F3.SN VT-3 VT-07-0066 VT-3 1042-07-012 SAT None.SAT None.F-A F2.ST C-Cc C3.20 MT 0942-07A-013 SAT None.1E12-H0718 RIGID STRUT N/A F-A F2.ST VT-3 1042-07-022 SAT None.305-642-133 1E12-H0726 HYDRAULIC SNUBBER 12" N/A 305-642-141 F-A F1.SN VT-3 VT-07-0119 SAT None.1E12-H0748 RIGID GUIDE 12" N/A F-A F1.Gs VT-3 1042-07-035 SAT None.305-642-141 Friday, July 13, 2007 Page 41 of 54 38 ID of Component Examined Description of Component Size- Sched. -ISl Dwg. No.ASME Category ASME Item No.Exam Method Exam Report No. Status Remarks 1E12-H0787 MECHANICAL SNUBBER N/A 305-642-132 1E12-P407-SP ANCHOR, PEN TO CONTAINMENT (WA)305-642-133 1E22-0002 12" ELBOW TO PIPE 12" 80 305-701-111 1E22-0055 16" FLANGE TO PIPE 16" 100 305-701-103 1 E22-0056 24" PIPE TO FLANGE 24" STD 305-701-103 1 E22-0087 12" PIPE TO ELBOW 12" 100 305-701-105 1E22-CO01-008 24" SUCTION FLANGE TO 24" SUCTION PIPE 24" N/A 305-701-114 1E22-C001-009 24" SUCTION PIPE TO HEAD SHELL N/A N/A 305-701-114 lE22-CO01-010 HEAD SHELL TO HEAD COVER N/A N/A 305-701-114 1E22-CO01-012 24" SUCTION PIPE LONGITUDINAL SEAM N/A N/A 305-701-114 F-A F2.SN F-A F2.A VT-3 VT-07-0057 VT-3 1042-07-026 SAT None.SAT None.R-A R2.ND UT 0944-07-E125 GEO Previously recorded geometry observed with no significant change.C-F-2 C5.51 C-F-2 C5.51 C-F-2 C5.51 C-G C6.10 C-G C6.10 C-G C6.10 C-G C6.10 UT 0944-07-E007 UT 0944-07-E008 UT 0944-07-E005 MT 0942-07A-004 MT 0942-07A-005 MT 0942-07A-006 MT 0942-07A-007 NRI None.NRI None.NRI None.SAT None.SAT None.SAT None.SAT None.Friday, July 13, 2007 Page 42 of 54 Friday, July 13, 2007 Page 42 of 54 REPORT NO. P0059-011 ID of Component Examined Description of Component Size -Sched. -ISl Dwg. No.ASME Category ASME Item No.Exam Method Exam Report No. Status Remarks 1E22-F026-SEAM 6" GATE VALVE BODY WELD 6" N/A 305-701-114 1E22-F036-SEAM 12" GATE VALVE BODY WELD (GROUPING NO. XVIII)12" N/A 305-701-111 1E22-F036-SEAM 12" GATE VALVE BODY WELD (GROUPING NO. XVIII)12" N/A 305-701-111 1 E22-H0005 MECHANICAL SNUBBER 12" N/A 305-701-111 C-G C6.20 MT 0942-07A-001 SAT None.B-M-1 B12.40 UT 0944-07-E124 GEO Previously recorded geometry noted. No changes observed.B-M-1 B12.40 F-A F1.SN UT 0944-07-E123 VT-3 VT-07-0120 NRI None, SAT None.1 E22-H0006 VARIABLE SPRING F-A F1.SP VT-3 1042-07-025 SAT None.12" N/A 305-701-111 1E22-H0039 VARIABLE SPRING (WA <.75" T)24" N/A 305-701-101 F-A F2.SP VT-3 1042-07-005 SAT None.1E22-H0043 RIGID GUIDE F-A F2.Gs VT-3 1042-07-009 SAT None.24" N/A 305-701-103 1E22-H0057 MECHANICAL SNUBBER F-A F2.SN VT-3 VT-07-0045 SAT None.16" N/A 305-701-106 1E22-H0063 RIGID STRUT F-A F2.ST VT-3 1042-07-001 SAT None.16" N/A 305-701-107 1E22-H0085-WA PIPING SUPPORT WELDED ATTACHMENT 12" N/A 305-701-112 C-Cc C3.20 MT 0942-07A-008 SAT None.Friday, July 13, 2007 Page 43 of 54 39 ID of Component Examined Description of Component Size -Sched.- ISI Dwg. No.ASME Category ASME Item No.Exam Method Exam Report No.Status Remarks 1E22-H0133 RIGID STRUT (WA)F-A F3.ST VT-3 1042-06-023 SAT None 24" N/A 305-355-101 lE22-HO133-WA INTEGRAL ATTACHMENT RIGID STRUT 24" N/A 305-355-101 1E22-S004B-SP AIR RECEIVER TANK (AO04B)SUPPORT (WA)N/A N/A 305-351-101 1E22-S004B-WA INTEGRAL ATTACHMT AIR RECEIVER TANK (A0O4B) SUPPORT N/A N/A 305-351-101 1E32-0215 2" SOCKET COUPLING ON VALVE F028A TO PIPE 2" 160 305-605-107 1E32-0215 2" SOCKET COUPLING ON VALVE F028A TO PIPE 2" 160 305-605-107 1E32-0215 2" SOCKET COUPLING ON VALVE F028A TO PIPE 2" 160 305-605-107 IE32-0216 2" PIPE TO ELBOW SOCKET WELD 2" 160 305-605-107 1 E32-0216 2" PIPE TO ELBOW SOCKET WELD 2" 160 305-605-107 1E32-0216 2" PIPE TO ELBOW SOCKET WELD 2" 160 305-605-107 D-Ac D1.20 VT-1 1042-06-022 SAT Not scheduled for credit, but WA was examined at same time the support was examined.F-A F1.40 D-Ac D1.10 VT-3 1042-06-020 VT-1 1042-06-019 SAT None.SAT None.R-A R2.ND UT 0944-07-E119 NRI UT of piping base material HAZ.R-A R2.ND VT-1 1042-07-029 NRI None.R-A R2.ND UT 0944-07-E120 NRI UT of piping base material HAZ.R-A R2.ND VT-1 1042-07-028 NRI None.R-A R2.ND UT 0944-07-El17 NRI UT of piping base material HAZ.R-A R2.ND UT 0944-07-El18 NRI UT of piping base material HAZ.Friday, July 13, 2007 Page 44 of 54 Friday, July 13, 2007 Page 44 of 54 REPORT NO. P0059-011 ID of Component Examined Description of Component Size -Sched.- ISl Dwg. No.ASME Category ASME Item No.Exam Method Exam Report No. Status Remarks 1E51-0039 6" PIPE TO TEE C-F-2 C5.51 UT 0944-07-E006 NRI None.6" 120 305-631-102 1E51-0097 8" X 12" X 12" TEE TO 12" PIPE BEND 12" STD 305-632-103 1E51-0097 8" X 12" X 12" TEE TO 12" PIPE BEND 12" STD 305-632-103 1E51-C001-002 RCIC PUMP CASING TO SUCTION NOZZLE 6" N/A 305-631-109 1E51-COO 1-A-WA PUMP SUPPORT WELDED ATTACHMENT N/A N/A 305-631-109 1E51-C001-SP ANCHOR, PUMP (WA)N/A N/A 305-631-109 1E51-F0013-SEAM 6" GATE VALVE BODY WELD (GROUPING NO. XXI)6" 1.500" 305-631-109 1E51-F0013-SEAM 6" GATE VALVE BODY WELD (GROUPING NO. XXI)6" 1.500" 305-631-109 1E51-F0064-SEAM 10" GATE VALVE BODY WELD (GROUPING NO. XXII)10" 2.200" 305-632-102 1E51-F0064-SEAM 10" GATE VALVE BODY WELD (GROUPING NO. XXII)10" 2.200" 305-632-102 C-F-2 C5.51 UT 0944-07-EO11 NRI Scans from pipe side of weld.C-F-2 C5.51 UT 0944-07-E012 NRI Scans from tee side of weld.C-G C6.10 C-Cc C3.30 PT 0941-07A-001 MT 0942-07A-002 SAT One acceptable rounded indication. SAT Only 82.6% coverage due to support assembly F-A F1.40 VT-3 1042-07-003 SAT None.B-M-1 B12.40 B-M-1 B12,40 B-M-1 B12.40 B-M-1 B12.40 UT 0944-07-E002 UT 0944-07-EO01 UT 0944-07-E122 UT 0944-07-E121 GEO 94% coverage with 70 deg angle. Previously recorded geometry noted. No changes apparent.NRI 100% coverage with 45 deg angle.GEO 94% coverage with 70 deg angle. Previously recorded geometry noted. No changes apparent.NRI 100% coverage with 45 deg angle.Friday, July 13, 2007 Page 45 of 54 40 ID of Component Examined Description of Component Size -Sched.- ISI Dwg. No.ASME Category ASME Item No.Exam Method Exam Report No.Status Remarks 1E51-F0066-IS 6"CHECK VALVE INTERNAL SURFACE(GROUPING NO. XXIII)6" N/A 305-631-108 1E51-F0502-SEAM 6" GATE VALVE BODY WELD 6" 1.500" 305-631-109 B-M-2 B12.50 VT-3 1042-07A-024 SAT Performed valve internal inspection while vavle was apart to replace Kalrez seat. No indications. C-G C6.20 MT 0942-07A-003 SAT None.1E51-H0056 F-A MECHANICAL SNUBBER (WA <.75" T) F2.SN VT-3 VT-07-0042 SAT None.12" N/A 305-632-104 1E51-H0141 VARIABLE SPRING F-A F2.SP VT-3 1042-07-030 SAT None.10" N/A 305-632-102 1E51-H0151 RIGID STRUT F-A FI.ST VT-3 1042-07-020 SAT None 6" N/A 305-631-107 1E51-P123-SP F-A ANCHOR, PEN TO SHIELD BLDG (WA) F1.A 305-631-106 VT-3 1042-07-031 SAT None.1G33-0063 6" P131 PROCESS PIPE TO PIPE 6" 80 305-671-104 R-A R2.ND UT 0944-07-E 199 NRI None.1G33-0064F 6" ELBOW TO PIPE X-B X10.10 UT 0944-07-E200 NRI None.6" 120 305-671-104 1G33-0122 6" X 6" X 6" TEE TO VALVE F051A 6" 120 305-672-101 1G33-H0146 MECHANICAL SNUBBER (AUGMENTED HEPIBER)6" N/A 305-671-104 C-F-2 C5.51 UT 0944-07-E198 NRI None.F-A aug F5.0 VT-3 VT-07-0383 SAT None.Friday, July 13, 2007 Page 46 of 54 Friday, July 13, 2007 Page 46 of 54 REPORT NO. P0059-011 ID of Component Examined Description of Component Size -Sched. -ISI Dwg. No.ASME Category ASME item No.Exam Method Exam Report No. Status Remarks 11N22-0037 2" PIPE TO 3" X 3" X 2" TEE BUTT WELD 2" 160 305-121-102 1 N22-0037 2" PIPE TO 3" X 3" X 2" TEE BUTT WELD 2" 160 305-121-102 1N22-0037 2" PIPE TO 3" X 3" X 2" TEE BUTT WELD 2" 160 305-121-102 1N22-0067 2" X 3" REDUCER TO 3" PIPE BUTT WELD 3" 160 305-121-101 1N22-0067 2" X 3" REDUCER TO 3" PIPE BUTT WELD 3" 160 305-121-101 1 N22-0068 3" PIPE TO 3" X 3" X 2" TEE BUTT WELD 3" 160 305-121-101 1N22-0068 3" PIPE TO 3" X 3" X 2" TEE BUTT WELD 3" 160 305-121-101 1N22-0073 3" X 3" X 2" TEE TO 3" PIPE BUTT WELD 3" 160 305-121-103 1N22-0073 3" X 3" X 2" TEE TO 3" PIPE BUTT WELD 3" 160 305-121-103 1 N22-0076 3" P423 PROCESS PIPE TO PIPE BUTT WELD 3" 160 305-121-103 R-A R2.11 R-A R2.11 R-A R2.11 R-A R2.11 R-A R2.11 R-A R2.11 R-A R2.11 R-A R2.11 R-A R2.11 R-A R1.11 UT 0944-07-E188 UT 0944-07-E186 UT 0944-07-E187 UT 0944-07-E151 UT 0944-07-EO50 UT 0944-07-E152 UT 0944-07-E153 UT 0944-07-E143 UT 0944-07-E142 UT 0944-07-E148 GEO 70° exam.NRI 0' Exam.NRI 45" exam.NRI No counterbore observed.NRI UT ot piping base material HAZ.NRI UT of piping base material HAZ.NRI No counterbore observed.Scanned to maintain a 5-20% ID roll.NRI No counterbore observed.Scanned to maintain a 5-20% ID roll.NRI UT of piping base material HAZ.NRI UT of piping base material HAZ.Friday, July 13, 2007 Page 47 of 54 41 ID of Component Examined Description of Component Size -Sched.- ISI Dwg. No.ASME Category ASME Item No.Exam Method Exam Report No. Status Remarks 1N22-0076 3" P423 PROCESS PIPE TO PIPE BUTT WELD 3" 160 305-121-103 1N22-0106 2" PIPE TO ELBOW SOCKET WELD 2" 160 305-121-101 1N22-0106 2" PIPE TO ELBOW SOCKET WELD 2" 160 305-121-101 1N22-0106 2" PIPE TO ELBOW SOCKET WELD 2" 160 305-121-101 1N22-0107 2" ELBOW TO PIPE SOCKET WELD 2" 160 305-121-101 1N22-0107 2" ELBOW TO PIPE SOCKET WELD 2" 160 305-121-101 1N22-0107 2" ELBOW TO PIPE SOCKET WELD 2" 160 305-121-101 iN22-0147 2" PIPE TO 3" X 3" X 2" TEE BUTT WELD 2" 160 305-121-102 1N22-0147 2" PIPE TO 3" X 3" X 2" TEE BUTT WELD 2" 160 305-121-102 1N22-0147 2" PIPE TO 3" X 3" X 2" TEE BUTT WELD 2" 160 305-121-102 R-A R1.11 R-A R2.11 UT 0944-07-E149 UT 0944-07-E145 GEO Root geometry observed 360" at varying amplitudes. IND Spot ind. observed in the second leg outside of exam volume. Scanned to maintain a 5-20% ID roll.R-A R2.11[IT 0944-07-E 144 NRI UT of piping base material HAZ.R-A R2.11 VT-1i 1042-07-089 NRI None.R-A R2.11 UT 0944-07-E146 NRI UT of piping base material HAZ.R-A R2.11 VT-1 1042-07-090 NRI None.R-A R2.11 UT 0944-07-E147 IND Spot indication observed in the second leg outside of exam volume. Scanned to maintain a 5-20% ID roll.R-A R2.11 R-A R2.11 R-A R2.11 UT 0944-07-EI91 UT 0944-07-E190 UT 0944-07-E189 GEO 70' exam.0944-07-E190 (45" S)NRI 45" exam.NRI 0" exam.Friday, July 13, 2007 Page 48 of 54 REPORT NO. P0059-011 ID of Component Examined Description of Component Size -Sched.- ISI Dwg. No.ASME Category ASME Item No.Exam Method Exam Report No. Status Remarks 1N22-H0129 MECHANICAL SNUBBER 2" N/A 305-121-102 F-A F1.SN VT-3 VT-07-0467 SAT None.1N27-H0032 RIGID GUIDE (WA)20" N/A F-A F2.G VT-3 1042-07-027 SAT VT-1 examination perfomed in lieu of Surface examination in accordance with IR-026.305-082-101 1N27-H1 127 RIGID GUIDE (AUGMENTED HEPIBER)1-1/2" N/A 305-971-101 1N27-H1129 RIGID GUIDE (AUGMENTED HEPIBER)1-1/2" N/A 305-971-101 1P42-HO 112 VARIABLE SPRING (WA)10" N/A 305-621-106 1P42-H0112-WA INTEGRAL ATTACHMENT VARIABLE SPRING 10" N/A 305-621-106 F-A aug F5.0 F-A aug F5.0 F-A F3.SP D-Ac D1.20 F-A F3.G VT-3 1042-07-015 VT-3 1042-07-014 VT-3 1042-06-025 VT-i 1042-06-024 VT-3 1042-06-027 SAT None.SAT None.SAT None.SAT None.SAT None.1P42-H0163 RIGID GUIDE 12" N/A 1 P42-H0210 ANCHOR (WA)10" N/A 1P42-H0215 RIGID STRUT 10" N/A 305-621-110 F-A F3.A VT-3 1042-06-042 SAT None.305-621-103 F-A F3.STm VT-3 1042-06-043 SAT None.305-621-102 1P45-D003-SP ANCHOR, FILTER SUPPORT (WA)N/A N/A 305-791-107 F-A F1.40 VT-3 1042-06-039 SAT None.Friday, July 13, 2007 Page 49 of 54 42 ID of Component Examined Description of Component Size -Sched. -ISI Dwg. No.ASME Category ASME Item No.Exam Method Exam Report No. Status Remarks 1 P45-H0063 RIGID GUIDE 16" N/A 1P45-H0201 RIGID SUPPORT 14' N/A F-A F3.G VT-3 1042-06-012 SAT None.305-792-112 F-A F3.R VT-3 1042-06-009 SAT None.305-791-113 1P45-H0216 MECHANICAL SNUBBER 24" N/A 305-791-112 F-A F3.SN VT-3 1042-06-011 VT-3 1042-06-006 SAT None.SAT None.1P45-H0360 RIGID GUIDE 14" N/A 1P45-H0405 RIGID STRUT 8" N/A 1P45-H0605 RIGID GUIDE 14" N/A 1P45-H0683 RIGID ROD 14" N/A F-A F3.G 305-792-116 F-A F3.ST VT-3 1042-06-033 SAT None.305-791-101 F-A F3.Gs 305-791-113 VT-3 1042-06-014 VT-3 1042-06-028 SAT None.F-A F3.R SAT None.305-792-105 1P45-H5003 RIGID STRUT (WA)24" N/A F-A F3.ST VT-3 1042-06-017 SAT None.305-791-112 1P45-H5003-WA INTEGRAL ATTACHMENT RIGID STRUT 24" NIA 305-791-112 D-Ac D1.20 VT-1 1042-06-013 SAT None.1P47-H0027 RIGID STRUT 10" N/A F-A F3.STm VT-3 1042-06-041 SAT None.305-002-107 Friday, July 13, 2007 Page 50 of 54 Friday, July 13, 2007 Page 50 of 54 REPORT NO. P0059-011 ID of Component Examined Description of Component Size -Sched.- ISI Dwg. No.ASME Category ASME hem No.Exam Method Exam Report No. Status Remarks 1P47-H0031 RIGID SUPPORT (WA)10" N/A 305-002-103 1P47-H0031-WA INTEGRAL ATTACHMENT RIGID SUPPORT 10" N/A 305-002-103 F-A F3.R VT-3 1042-06-008 SAT None.D-Ac D1.20 VT-1 1042-06-007 VT-3 1042-06-026 SAT None.SAT None.1P47-H0053 RIGID STRUT F-A F3.ST 10" N/A 305-002-102 1 P47-H0280 RIGID GUIDE F-A F3.G VT-3 1042-06-044 SAT None.10" N/A 305-002-105 1P47-H0385 RIGID STRUT F-A F3.STm VT-3 1042-06-005 SAT None.8" N/A 305-002-113 0P49-CO02A-SP F-A ANCHOR, SCREEN WASH PUMP (WA) F1.40 N/A N/A 305-214-101 0P49-CO02A-WA D-Ac INTEGRAL ATTACHMENT SCREEN D1.30 WASH PUMP ANCHOR N/A N/A 305-214-101 1R44-AO01A-SP F-A ANCHOR, STARTING AIR RECEIVER F1.40 TANK (WA)N/A N/A 305-351-102 1R44-A001A-WA D-Ac INTEGRAL ATTACHMENT STARTING D1.10 AIR RECEIVER TANK ANC N/A N/A 305-351-102 1R45-A003A-SP F-A ANCHOR, FUEL OIL DAY TANK (WA) F1.40 N/A N/A 305-355-110 VT-3 1042-06-016 SAT None.VT-i 1042-06-015 SAT None.VT-3 1042-06-031 VT-1 1042-06-032 VT-3 1042-06-051 SAT None.SAT None.SAT None.Friday, July 13, 2007 Page 51 of 54 43 ID of Component Examined Description of Component Size -Sched. -ISl Dwg. No.ASME Category ASME Item No.Exam Method Exam Report No. Status Remarks 1 R45-A003A-WA INTEGRAL ATTACHMENT FUEL OIL DAY TANK ANCHOR N/A N/A 305-355-110 1R46-A003A-SP ANCHOR, JACKET WATER STAND PIPE (WA)N/A N/A 305-354-105 1R46-A003A-WA INTEGRAL ATTACHMENT JACKET WATER STAND PIPE ANCHOR N/A N/A 305-354-105 1R47-A001A-SP STANDBY DIESEL GENERATOR LUBE OIL TANK ANCHOR (WA)N/A N/A 305-353-103 IR47-AO01A-WA INTEGRAL ATTACHMENT LUBE OIL TANK ANCHOR N/A N/A 305-353-103 1R48-D001B-SP ANCHOR, STANDBY DIESEL SILENCER (WA)N/A N/A 305-355-104 1 R48-D001B-WA INTEGRAL ATTACHMENT STANDBY DIESEL SILENCER ANCHOR N/A N/A 305-355-104 1R48-DO02B-SP ANCHOR; STANDBY DIESEL SILENCER (WA)N/A N/A 305-355-102 1R48-D003B-SP ANCHOR; STANDBY DIESEL SILENCER (WA)N/A N/A 305-355-102 1R48-D010B-SP ANCHOR; STANDBY DIESEL SILENCER N/A N/A 305-355-106 D-Ac D1.10 F-A F1.40 D-Ac D1.10 F-A F1.40 D-Ac D1.10 F-A F1.40 D-Ac D1.20 F-A F1.40 F-A F1.40 F-A F1.40 VT-1 1042-06-050 VT-3 1042-06-029 VT-1 1042-06-030 VT-3 1042-06-049 VT-i 1042-06-048 VT-3 1042-06-046 VT-1 1042-06-045 VT-3 1042-06-047 VT-3 1042-06-036 VT-3 1042-06-035 SAT None.SAT None.SAT None.SAT None.SAT None.SAT None.SAT None.SAT None.SAT None.SAT None.Friday, July 13, 2007 Page 52 of 54 Friday, July 13, 2007 Page 52 of 54 REPORT NO. P0059-011 ID of Component Examined Description of Component Size -Sched. -ISI Dwg. No.ASME Category ASME Exam Item No. Method Exam Report No. Status Remarks 11R48-H0022 RIGID GUIDE F-A F3.G VT-3 1042-06-034 SAT None.24" NIA 305-355-102 1R48-H0027 MECHANICAL SNUBBER (WA)(TANDEM)36" N/A 305-355-105 1R48-H0027-WA INTEGRAL ATTACHMENT MECHANICAL SNUBBER 36" N/A 305-355-105 1R48-H0033 VARIABLE SPRING 26" N/A 305-355-104 F-A F3.SN D-Ac D1.20 F-A F3.SP VT-3 1042-06-053 VT-1 1042-06-052 VT-3 1042-06-018 SAT None.SAT None.SAT None.1R48-PH005 RIGID ROD F-A F3.R VT-3 1042-06-021 SAT None.6" N/A 305-355-108 2P42-H0026 RIGID STRUT (WA)12" N/A 305-623-110 F-A F3.ST VT-3 1042-06-040 SAT None.2P42-H0148 RIGID SUPPORT (WA)F-A F3.R VT-3 1042-06-038 SAT None.10" N/A 305-623-104 2P42-H0148-WA INTEGRAL ATTACHMENT RIGID SUPPORT 10" N/A 305-623-104 CLASS 1, PIPING PIPING-SYSTEM LEAKAGE TEST N/A N/A 305-NO-DWG CLASS 1, PUMPS PUMPS-SYSTEM LEAKAGE TEST N/A N/A 305-NO-DWG D-Ac D1.20 VT-1 1042-06-037 SAT None.B-P B 15.50 VT-2 10800-07-127 SAT Pressure testing accomplished by various ISI instructions. B-P B15.60 VT-2 10800-07-128 SAT Pressure testing accomplished by various ISI instructions. Friday, July 13, 2007 Page 53 of 54 44 ID of Component Examined Description of Component Size- Sched. -ISI Dwg. No.ASME Category ASME ftem No.Exam Method Exam Report No. Status Remarks CLASS 1, VALVES VALVES-SYSTEM LEAKAGE TEST N/A N/A 305-NO-DWG CLASS 1, PR COMP REACTOR VESSEL-SYSTEM LEAKAGE TEST N/A N/A 305-NO-DWG 1T23-017-EM CTMT EXT INTERFACE WITH ANNULUS POUR AZ 0-360 N/A N/A 305-503-139 1T23-017-EC ANNULUS CONCRETE SURFACE BENEATH E32 LEAKOFF LINES N/A N/A 305-503-139 B-P B15.70 VT-2 10800-07-129 SAT Pressure testing accomplished by various ISI instructions. B-P B15.10 E-C E4.11 L-A L1.12 VT-2 10800-07-130 VT-1 1042-07-097 VT3C 1042-06-0002 SAT Pressure testing accomplished by various ISI instructions. SAT Some surface rust, but no signs of recent moisture intrusion and no significant material loss.SAT This report addresses "suspect areas" of concrete surface annulus pour @ 340 degrees 598'4" beneath the E32 leakoff line. Area was previously reported on 6/9/99 (rpt 1042-99-104) and 11/13/02 (rpt 1042-02-0013). No increased degradation noted.Table Notes: 1. Status codes are "SAT" or "UNSAT" for visual and surface examinations. For ultrasonic examinations they are "IND" for indication, "GEO" for geometry, and "NRI" for no recordable indications.

2. The above exam listing is all the inservice examinations that were performed during Cycle 11 or RFO1 1 in accordance with Perry's Inservice Examination Plan (ISEP).Friday, July 13, 2007 Page 54 of 54 REPORT NO. P0059-011 First Energy Nuclear Operating Company Perry Nuclear Power Plant ISI Summary Report No. P0059-0011 Second Interval, Third Period, First Outage (RFO11)Cycle 11 and RFOII Preservice Examinations Prepared by: Reviewed by: A %A A 'Date: SI lnginee u'h-ize N e e oate: Authorized Nuclear Inservice lnskejor I ~ ~- --~t~1 l~~(Friday, July 13, 2007 Page I of 5 45 ID of Component Examined Description of Component Size -Sched.- ISI Dwg. No.ASME Category ASME Item No.Exam Method Exam Report No. Status Remarks 1B21-F041B-B SRV BOLTING, 12 EACH 10" N/A 305-605-102 1B21-F041B-B SRV BOLTING, 12 EACH 10" N/A 305-605-102 1B21-F041D-B SRV BOLTING, 12 EACH 10" N/A 305-605-104 1B21-F041D-B SRV BOLTING, 12 EACH 10" N/A 305-605-104 1B21-F041F-B SRV BOLTING, 12 EACH 10" N/A 305-605-102 1B21-F041F-B SRV BOLTING, 12 EACH 10" N/A 305-605-102 1B21-F041K-B SRV BOLTING, 12 EACH 10" N/A 305-605-102 1B21-F041K-B SRV BOLTING, 12 EACH 10" N/A 305-605-102 1B21-F0471B-B SRV BOLTING, 12 EACH 10" N/A 305-605-102 1B21-F047B-B SRV BOLTING, 12 EACH 10" N/A 305-605-102 B-G-2 B7.50 B-G-2 B7.50 B-G-2 B7.50 B-G-2 B7.50 B-G-2 B7.50 B-G-2 B7.50 B-G-2 B7.50 B-G-2 B7.50 B-G-2 B7.50 B-G-2 B7.50 VT-1 1042-07A-0012 VT-1 1042-07A-0005 VT-1 1042-07A-0006 VT-1 1042-07A-0013 VT-1 1042-07A-0002 VT-1 1042-07A-0020 VT-1 1042-07A-0019 VT-1 1042-07A-0003 VT-1 1042-07A-0009 VT-1 1042-07A-0015 SAT Examined 12 replacement hydro-nuts; heat number 623A.SAT Examined 12 replacement studs; heat number K745.SAT Examined 12 replacement studs; heat number K745.SAT Examined 12 replacement hydro-nuts; heat number 623A.SAT Examined 12 replacement studs; heat number K745.SAT Examined 12 replacement hdro-nuts; heat number 623A.SAT Examined 12 replacement hydro-nuts; heat number 623A.SAT Examined 12 replacement studs; heat number K745.SAT Examined 12 replacement studs; heat number K745.SAT Examined 12 replacement hydro-nuts; heat number 623A.Friday, July 13,2007 Page 2 of 5 Friday, July 113, 2007 Page 2 of 5 REPORT NO. P0059-011 ID of Component Examined Description of Component Size -Sched. -ISI Dwg. No.ASME Category ASME fhem No.Exam Method Exam Report No. Status Remarks 1B21-F0470-B SRV BOLTING, 12 EACH B-G-2 B7.50 VT-1 1042-07A-0004 SAT Examined 12 replacement studs; heat number K745.10" N/A 305-605-104 1B21-F047D-B SRV BOLTING, 12 EACH B-G-2 B7.50 VT-1 1042-07A-0014 SAT Examined 12 replacement hydro-nuts; heat numbers 590A (6) and 623A (6).10" N/A 305-605-104 1B21-F047F-B SRV BOLTING, 12 EACH B-G-2 B7.50 VT-1 1042-07A-001 I SAT Examined 12 replacement studs; heat numbers K745 (8) and OG84 (4).10" N/A 305-605-102 1B21-F047F-B SRV BOLTING, 12 EACH B-G-2 B7.50 VT-1 1042-07A-0021 SAT Examined 12 replacement hydro-nuts; heat number 590A.10" N/A 305-605-102 1B21-F047H-B SRV BOLTING, 12 EACH B-G-2 87.50 VT-1 1042-07A-0017 SAT Examined 12 replacement hydro-nuts; heat number 590A.10" N/A 305-605-104 1B21-F047H-B SRV BOLTING, 12 EACH B-G-2 B7.50 VT-1 1042-07A-0010 SAT Examined 12 replacement studs; heat number OG84.10" N/A 305-605-104 1B21-F051B-B SRV BOLTING, 12 EACH B-G-2 B7.50 VT-1 1042-07A-0008 SAT Examined 12 replacement studs; heat number OG84.10" N/A 305-605-102 1B21-F051B-B SRV BOLTING, 12 EACH B-G-2 B7.50 VT-1 1042-07A-0018 SAT Examined 12 replacement hydro-nuts; heat number 590A.10" N/A 305-605-102 1B21-F051D-B SRV BOLTING, 12 EACH 10" N/A 305-605-104 B-G-2 B7.50 VT-1 1042-07A-0007 SAT Examined 12 replacement studs; heat number OG84.1B21-F051D-B SRV BOLTING, 12 EACH B-G-2 B7.50 VT-1 1042-07A-0016 SAT Examined 12 replacement hydro-nuts; heat number 590A.10" N/A 305-605-104 Friday, July 13, 2007 Page 3 of 5 46 ID of Component Examined Description of Component Size- Sched. -ISI Dwg. No.ASME Category ASME Item No.Exam Method Exam Report No.Status Remarks 1B21-H0445 HYDRAULIC SNUBBER F-A F1.SN VT-3 VT-07-0639 SAT Preservice exam of replacement snubber Serial No.04616533/10 2" N/A 305-605-106 18211-H0449 HYDRAULIC SNUBBER F-A F1.SN VT-3 VT-07-0642 SAT Preservice exam of replacement snubber Serial No.04616533/017 2" N/A 305-605-106 1B21-H0450 HYDRAULIC SNUBBER F-A F1.SN VT-3 VT-07-0640 SAT Preservice exam of replacement snubber Serial No.03615883/020 2" N/A 305-605-106 1B21-H0471 HYDRAULIC SNUBBER F-A F1.SN VT-3 VT-07-0641 SAT Preservice exam of replacement snubber Serial No.30400009/017 2" N/A 305-605-106 1B21-$107C HYDRAULIC SNUBBER MPL 1B21G7091 26" N/A 305-605-103 1B33-S369B HYDRAULIC SNUBBER, PUMP MOTOR, MPL 1B33G7064B N/A N/A 305-602-104 1B33-S370B HYDRAULIC SNUBBER, PUMP MOTOR, MPL 1B33G7065B N/A N/A 305-602-104 1B33-S371B HYDRAULIC SNUBBER, PUMP MOTOR, MPL 1B33G7066B N/A N/A 305-602-104 1E12-H5002 MECHANICAL SNUBBER 12" N/A 305-642-138 F-A F1.SN VT-3 VT-07-0531 SAT Preservice exam of replacement snubber Ser No. 043.F-A F1.40 VT-3 VT-07-0545 SAT Preservice exam of replacement snubber Ser No. 057.F-A F1.40 F-A F1.40 F-A F2.SN VT-3 VT-07-0581 VT-3 VT-07-0532 VT-3 VT-07-0019 SAT Preservice exam of replacement snubber Ser No. 063.SAT Preservice exam of replacement snubber Ser No. 026.SAT Preservice exam of replacement snubber Ser No. 42858 1E51-H0073 HYDRAULIC SNUBBER F-A F1.SN VT-3 VT-07-0643 SAT Preservice exam of replacement snubber Ser No.04616533/011 6" N/A 305-631-108 Friday, July 13, 2007 Page 4 of 5 REPORT NO. P0059-011 ID of Component Examined Description of Component Size- Sched. -ISI Dwg. No.ASME Category ASME Exam Item No. Method Exam Report No.Status Remarks 1E51-H0074 HYDRAULIC SNUBBER F-A FI.SN VT-3 VT-07-0644 SAT Preservice exam of replacement snubber Ser No.04616533/001 6" N/A 305-631-108 1G33-H0144 MECHANICAL SNUBBER (AUGMENTED HEPIBER)6" N/A 305-671-104 F-A aug F5.0 VT-3 VT-07-0631 SAT Preservice exam of replacement snubber Ser No.27529.1G41-H0051 MECHANICAL SNUBBER F-A F3.SN VT-3 VT-07-0026 SAT Preservice exam of replacement snubber Sef No.26019.10" N/A 305-655-107 Table Notes: 1. Status codes are "SAT" or "UNSAT" for visual and surface examinations.

For ultrasonic examinations they are "IND" for indication, "GEO" for geometry, and "NRI" for no recordable indications.

2. The above exam listing is all the preservice examinations that were performed during Cycle 11 or RFO1 1 due to repair, replacement, or modification activities.

Friday, July 13,2007 Page 5 of 5 47 REPORT NO. P0059-011 APPENDIX B"CYCLE 11 & RFOIl NIS-2/NR-1 FORMS" INSERVICE INSPECTION

SUMMARY

REPORT FOR PERRY NUCLEAR POWER PLANT (PNPP)UNIT 1 48 REPORT NO. P0059-011 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 10 Center Road. Perrv Ohio 44081 Date 5/9/07 Sheet 1 of 3/Unit 1 see attached chart (Repair Org. P.O. No., etc.)2. Plant: Perry Nuclear Power Plant (PNPP)10 Center Road, Perry, Ohio 44081 3. Work Performed By: FIRSTENERGY Nuclear Operating Company PNPP 10 Center Road. Perrv. Ohio 44081 Type Code Symbol Stamp NR Authorization No. 33 Expiration Date 9/28/08 4. Identification of System: 1B13 Reactor and Internals 5. (a) Applicable Construction Code: ASME SECTION III CLASS 1 NAMEJSECTION/DIVISION/CLASS 19 75 Addenda Code Case(s) N207, 1361-2, ,1974 Edition 1728, 1644-4. N272 WINTER (b) Construction Code used for repairs, modifications, or replacements: 1974 W75 Edition Addenda (c ) ASME Code Section XI applicable for Inservice Inspection: 1989 NONE Edition Addenda (d) Applicable Edition of Section XI Utilized for Repairs, Modification, or Replacements: 1989__ 19 N/A Addenda N/A Code Case(s)(e) Design Responsibilities First Energy Corp 6. Identification of Components Repaired, Modified, or Replacement Components Code Case(s)N/A Code Case(s)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 1B13 64077 1B13D008 1984 REPLACEMENT YES SYSTEM ELECTRIC 7. Description of Work: Replaced 14 control rod drives and 1" cap screws see attachment for details.8. Test Conducted: Hydrostatic- ] Pneumatic-El Nominal Operating Pressure-0 Other- E]Pressure 1032 psi Test Temperature 142 degrees F Code Case(s) N/A 49 REPORT NO. P0059-011 P4 6- r. '2- :v/-- /NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back)PNPP No. 9308 Rev. 9/11/00 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, 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 9 may , 20 07 Signed FENOC-PNPP .',7 " -. QC Tech.(name of repair organization) (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 t0/N 10 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 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 .0, 20 b" Signed Wtz- Commissions NB 9330 "N" "I" "A" Ohio Comm.(inspector) (National Board (include endorsements), and jurisdiction, and no.)50 REPORT NO. P0059-011-3!PAGE 3OF i NIS-2iNR-11B13-052 1. Owner: FIRSTENERGY CORP 10 CENTER ROAD. PERRY. OH 44081 2. Plant: Perry Nuclear Power Plant (PNPP)10 Center Road, Perry, Ohio 44081 Unit one WO # See below.(Repair Org P.O. No., etc.)3. Work Performed By: FIRSTENERGY NUCLEAR OPERATING COMPANY (PNPP)10 Center Road. Perry. Ohio 44081 Type Code Symbol Stamp NR Authorization No. 33 Expiration Date 9/28/08 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 XI Utilized for Repairs or Replacements: 19 89 19 NO Addenda 6. Identification of Components Repaired, Modified, or Replacement Components WO NUMBER CORE LOCATION NEW CRD[I S/N I NUMBER OF CAPSCREWS REPLACED HT NUMBERS OF NEW CAPSCREWS 200079521 22-27 A5054 8 R707 200079533 46-27 A5510 8 TRR 200079535 50-19 A4531 8 TRR 200079530 42-15 A3730 8 R707 200079527 34-47 A5472 8 R707 200079526 42-51 A5183 8 TRR 200010200 50-23 A5427 8 255A 200079532 46-15 A3895 8 TRR 20019524S 42-27 A5122 8 R707 200079534 46-43 A5684 8 TRR 200195247 54-23 A25718 TRR 200195249 42-39 A34988 (1) TRR (6) 13358 (1) R707 200079515 10-35 A4502 (7)255A (I)R707 200174378 42-31 N/A 8 255A 200079536 50-27 N/A 8 R707 200174377 14-19 N/A 8 R707 200174379 26-35 N/A 8 TRR 200260599 50-31 A5416 0 N/A 200079537 50-31 N/A 8 TRR 51 REPORT NO. P0059-011 V M E.. ' I I- ' I !! ...... ........ ...ýý/ -'- Sheet i of 2 3/FORM N-1 NP CEARTMICATE HOLDERS' DATA REPORT FOR NUCLEAR PART AND APPURTENANCES° As "Ilmied by the Pr-oviion of the ASME Code Rules. Section -1. Div. I.W.g.(by General Electric Company, Castle Hayne Rd., Wilmington, N.C.tH .and a"dre-i g. NWP Cef--zcate Hoid.a (b) Mtuafactrew for General Electric Company, San Jose, California (NEBG)(NmaN* ad add ati X Cwfrlfet. Holder tte CrI ae levst ý, .u 2. ldt ,lillcatloo-CertleateHolder'sSertalNo. ofP',t M "I Bi .No.(a) Cooen &od m D, .768E.534G001 BD. L. Paterson (a) Orawwit_______ccdigto Dtawring No by (b) Descripion of Pt Control Rod Drive, Model #7RDBl44DG00 NM 1974 W'75_ 1361__C2a 1 () AppLcubLe ASMECode.Section L, Editoo n Adedad-te --W' Cas,,.o._1361-2C, 3. R,.,,k. Standard part for use with Reactor. Hydrostatically tested at 1820 psi.rti, me 4aropI ot ..-,c. tof ktl cp .t -a de-mI d Total number of sheets -2 We certify thatdze staxesets =ade in this report are correct and this vessel part or as defined in the Code cotI foams to the rles of camrcrica of te A96E Cd Section UL ThMe apDl1cable and Slres Rport am roý th. rerponibtllty ot the NPT Certflenate Holder for paxts. An NPT Certlf-icate Holdkr for ppu ces is for frnerian a sepa-te Design Specaicatica zd Strms Report if the '3 DOt Included In the caornpoent Deal=; ___tled An -- apt SCortific~ae of Auhcii EX Ce~rtiricsrn of Oeiaz-alion No TN-=CEREMFICATION OF DESIGN FOR APPURTENANCE (wien applicable) Deisn tfooa- ioa 0a fi.e -GE, NEPD-WMD-OA, Castle Hayne Ad. , Wilminaton,. N;C.22A5556, Rev. Z Streasmalysis reportonfileat GE, NEPD, San Jose, Calif.22A4912, Rev. 2 D1sign speiiicauions certniied B. N. Sr+/-dhar Prof. Ent.oStateCalif Rea.NoJ 8 3 4 5 SCess mnalysis report Certified b B. N. Sridhar Prof. Eig- 5 tateCalif Re 1 No1 8 3 4 5 Prof. Eng -ccSL Re .-a CERTIFICATE OF SMOP INSPECTION I, cthe ndatsiinzed, &olding a Yalid coesimjsion issued br the National Board of Boiler and Pressure Vessel lnpectocs 90410C the Scam o, Province o North Carolina nd employed byDepartment of Labor of State of North Carolina have inspected the part c' -,re vestel described in, this Partial Data Rep-rt on _ _?_,/,t to the best e ofmyu owlfwtse&Ad belle, the NhT Certificate Hoider has e t-ucad ,lils part In- acct1,rance with the , ... ..s Sectionw (I.By signing this certificate, neixher the Inspector nor his ernploy ma-kes may expressed or implied. concern-ring the part described In this Partial Data Report. Furthermore, neither the Inspector nor his employer*hall be liable in any nnaer for any personal injury or praprr" damage or a loss of any kiad arising lroam ot connected with this inspctioe. Date .19. ....-, 0 ..1010 znsp.$~~a~p,.os Ccotxi~s~onsN.C. 123,A.W I6,(1U LnpGY1 3Inaw .SIoml Boead, UIzs.. P~ovmnce enot K-. I 9o. PZ.:.: -tw, 1. -- 1 dor, (O. 4y b ro-d- 12# ýsIr. from b5W I' (OrA { .*O t.. A : 35 .4 ., 1 (2) W 0LI (107)This form (2000401 may bo cbzi.,d from the order Dtot.. ASMS, 345 E. 47th St.. Now YorpN, N.Y. 10017 52 It~.ass 4-8 ladt.t FORM- N-2 (back)o be complet"- for siaefq wa-1 ..edII. l... e g retd_ Cevsef t .h.11. -( heeg r.ch".ercs, 4. Shell: A oal. Croweiacc -in ,..... Dt.....in. Len 't .ft.-____is.

5. Seevett: Loag_______

ft. ____T._ R. T. Efficicfcy A Gard H.T'__________R.T. _______No. of Cowsee ___________

6. He-adet T.&. (b),Material Ts________

LeaiaCr..,. K~u.U. 9Kt~iieai CtdeaS Fit" ii4o to Pr....b(1# e. W ~ h~s .411" no-1i.0 Ittio A~.- A.4.12 11.i1.6 ota..t.r (Coet. CO.t..)If reerovsbe,. bolt used -____________________Other (attZCia2 (bts4.e... 39s.q. No., T.L. .rIooh.(V..erl-r a- .ttih aketch)J W W L...........7. Jacket Closure: (D~s~ceit.a %*os and -t1. ba, StC-U be Nilczrd1s.isniso. If b-tt-d, d- 'Cib- -t sketch)Drop Weithc Chirpy Iatpacit I 8. Decigii pev-Ae 1230 575 OF a temp. of_________ Ite'mx 9 ard 10 co 4v comupletedl for tu!>s sections 9. Tube Sbeerut Staxi_ý.ar. Material Die._ _____ Thickttcss..itt Arach-mcen______(Z"c & spee. He.) (S.b.e to P---.*) (Welded. 11.tted)Floo~ring. Material ________Dix. ThiSckncss-iu. Attscdtrant________ t0_Tue=Maeril____ ý in Thickness ...o .Nsaber -Typec t~ar. ot U1)Ij 1oc.a 1-4 [;AcL to be c -ý 1 1 S.'~-~.-~r~g -~ia~ Z~cl~.~nt. '.. ~ ~ -~ -~cr ~ ~12. SIta~ Loce~_____ H.ET______

LT. E~ffklciii~

Girth___ 11.T. ILT. I______N.a Coueses _________13. Heads (.1 5at.1rsia (__________T&____ b) MmrerI C-o~ K-I&Ik. Iltittical C-1-i~ X.ec..h-et-A Fist 516 1 Pr...L-cti.. ThIUkoo.. PodMot Radio. Ratio Apes Ao1 4 L. Ritdt. 01t., (Co.- at Co If resuovablc.. boics useed (eo________ (b) __________ (cf_______O at(ztm-ing ,O..c*-1. at a1tth sketchl Drop Weirhe C-harpy lempact 14. Design pressure' Pai at F____________ at temnp. of__________ Items below to be completed for all vssels *beer applicable. i1. SeferY Valve Outlie-t: Number Size -16. Noxzlos: O-.ttl. Dreai n traba Die. or StIs Tyv--Location P..va-ccc.nt U.-I.1s Thic"...s wto~t..l K.- Attoch..17. Inspection M4anholes, No. ______ Size -.______ Location________________________ Openings: Ilsodholc2, No._______ Size-____ Lo-cstion Threaded, No.-______ Size-______ Location li S5pp-ocrr: Sltsrt -Lugs Lc&o Other _______Attached ____________(Y-6e 4- (NT?_4tbo) (4-bo.0 (L(tt wh*. .o.1 34 4oth~rs Ho44,-n* co4t L cttdn we.Vj~cb--------------------------- REPORT NO. P0059-011--Shot 2 of 2 FORM N-2 ,NPT CERTIFICATE HOLDFRJS' DATA REPORT FOR NUCLEAR PART AND A"PURTENANCESM As required by the Provision of Lhe ASME Code Ruls., 111, Div. I wa(,J u by General Electric Company, Castle Hnyne Rd., Wilmington, N.C.War. M~d a4 o NTW C"dt. H.Wdat (b) foc General Electric Company, San Jose, California (NEBc)mKx* Wad d~rem d 0 C.rMflta Haldwr ftr cc=P-t-, -zxe cPor~aotu 2. WbdncsUon-Cerncat, Hold.f, SeialNo. Pan -A5416 -. -N. Bd. No.D. L. Paterson (a) Coaaructed AccoediAnB to Dramsg No. 768_ -%14_1 Drwwarig Prepared by (b) Deactipt;.m 0f Pma lampected Control Rod Drive, Model 07RDBI44DGO01 14207 W) ApplicnbI ASWE -197 .Ajdoja4.. V1'75 CmaNo. 1361-2 Class 1 I. Cap 16689274P1 (167A2343) 5A182 F316 3/8 thick x 1 1/16 OD 2. Indicator Pipe 16689313PI SA31Z-TP316 1.065 max. dla.3. Plug 159A1176P1 SA182-F304 1/4 thick x 0.812 0D 4. Flange 9190610PI (719E474)SA182-F304 3.37 thick x 9 5/8 OD neck 1 1/16 thick x 5.0 00 2.875 10 5. Base 137C5311P1 XM-19 AS1E SA479 3.0 0D x .884 ID 6. Ring Flange 11485122P2 SA182-F304 I' thick x 5.0 00 x 1.75 ID 7. C3p Screw 117C4516P2 SA193-86 6 ea. 1/2 dia. on 4 1/8 bolt circle 8. Plug 175A7961P] SA182-F304 0.38 thick x 1.307 dia.CONTROL ROD DRIVE DWG -768E534 9. Nut 137C5934PI 001 pM-19 S.A479 1.30 thick x 2.62 dia.53 REPORT NO. P0059-011 Sheet 1 of 6 'oF 3/FORM N-2 NPT CERTIFICATE HOLDERS' DATA REPORT FOR NUCLEAR PART AND APPURTENANCES" As required by the Provision of the ASMdE Code Rules, Section III. Div. I 1. (a) Maufactired by General Electric Company, Castle Hayne Rd., Wilmington, N.C.irlmn and add- of NP'r CetIcfleat, Hol-eri (b) Manufactured for General Electric Company, San Jose, California (NEBG)(Name and bddrv- of N Holder foe ecrnplrted nuclear 2- Identiflcaolon-Certlflcate Holder's Serial No. of Part A3730 Nat'l Bd. No.768E-534G001 D. L. Peterson (a) Constructed According to Drawing No. 768_34G00I_ Drasing Prepared by Control Rod Drive, Model #7RDB144DG001 (b) Description of part Inspected NO (c) Applicable ASME Code: Section I11, Edition 1974 Addendadare ,dCaseWNo. 1361-2________I _______ _______Class-_______

3. Remarks: Standard part for use with Reactor. Hydrostatically tested at 1820 psi.(] .ior deaarrption of -.r1- for wh ,ch r-pooent was dati~ned)* Total number of sheets -2 We certify tht the statements emade in this report are correct and this vessel patr or appurtenance as defined in the Code con-forms to dhe rules of constrructioa of the ASME Code Section I1I.(The applicable Design Specification and Stesv's Report are not the responsibility of the NPT Certificate Holder for parts. An NPT Certlf-ica5t Holder for appurtenances is responsible foe furnishing a separate Design Specificatio an SrsReport if thme appurtenance is not Included In the component Design Specification and Stress Report.)D)ate 7-11 19 80 Sind GE, NEPD-WMD-QA_______________

19 -_ Signed By .NPFT Cer~~ticatt Holderi /Certificate of Authorization Expirea June 16, 1981 Certificate of /uhorization No. NPT N-1151 CERTIFICATION OF DESIGN FOR APPURTENANCE (when applicable) GE, NEPD-WhD-QA, Castle Hayne Rd., Wilmington, N.C.Design information on file at 22A5556, Rev. 1 Stess analysis repor, on file at GE, NEPD-WMD-QA, Castle Hayne Rd., Wilmington, N.C.22A4912, Rev. 2 Design specifications certified by B. N. Sridhar Prof. Eng. StareCalif Reg. No)8 3 4 5 Stress analysis report cetifed by B. N. Sridhar Prof. Eng. State Calif Reg. No.18345 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 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 7-11 9 _.8 0 and state that to Ue best of my knowledge and belief, the NPT Certineate Holder has constructed this part In accordance with the ASME Code Section Ill.By signing this certificate, neither the Inspector not his employer makes amy ,warranty, expressed or implied, concern.-Int 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 Irom or connected with this inspection. Dot- _+ 19 80 W 0NC 779,PA.WC2L60, OHIO Commissions Bigrsat .National Soard. Stat.. Province and No."Sos -n-1tn l .0.., o, tohM of li-. .k.tcbh or dr..inga .m r ..,d p.o .do. u. .., F-r'" I I". .21 o tooro i n ,m.. 1 .? -n "hi, 010/77) 1 This form (E00040)may be obtained from the Order Oeot.. ASME, 345 E 47th St. IN4ew' Yrk. N.Y'! 10017 54 FORM N-2 (back)Items 4-8 Incl. to be completed for single sall vessels. jackets of jacketed vessels. or ,hells of heat exchangers. Nominal Corrosion*I. Shell: Material T.S.___ Thickness._ in. Allow'ance.-_in. Dia.__ ft.-. in. Length- It. -in.(KLnd I Sp.O. No.) (Mi.. of Rante Sp(c li e d)5 Seams: Long H.T.' R.T. Efficiency 7.Girth -H.T.'_ R.T. No. of Courses 6. Heads: (a) Material T.S. (b) Material T.S.Loat.ion Crown Knuoi.Lx Eliliptie. Conieal H-iitnphxric.i Flat Sid. to Pr...(Top. bottom. end.) Thickin..a Radioa Radius Ratio Apes Angle Radius Dli-.,ra, (Con,. or Conc.)(b)If removable, bolts used Other fastening (Idoterial. Spec. No., T.S.. 31.,. Nt.ber) (Describe o attach k.etch)7. J ackiet Closure: (Describe -Ce olo and ftd. bar, 9tc. f brit Liv, dirxenaona. i( bolted. de scribe oe aisetch)Drop Weight Cha(rpy Impact ft-lb 8. Design pressure 1.250 psi at _ ___ ___ F at temp. of OF Items 9 and 10 to be completed for tube sections 9. Tube Sheets: Stationary. Material Di a. Thickness-_ in. Attachment (Kind & Spec. No.) (Subjxot to pre -ree (vtded. Bolted)Floating. Material Dia. Thickness-in. Attachment ,riche, 10. Tubes: Material 0.0. _- in. Thickness S _or g-te. Nuo'nbcr Type -(Sir. or U)Items 11-14 incl. to be completed for inner chambers of jacketed vessels, or channels of heat exchangers. Nominal Corrosion II. Shell: Material -__ T.S -hickness ...Jn. Allowance -in. Dia..__ ft.. in. LengihfIt. -in.ind& Spec. No.) (1MJ. or R*n* Speoiied)12. Seams: Long H.T. R.T. Efficiency 7 Girth H.T.t R.T. No. of Courses 13. Heads (a) Material T.S. (b) T.latetal _TS.Cro-n Knockix E11,ti6-1 Conic L He1- itphexica) Ft., Sid. to Pr..Lo--t-n Thickness Radiu. Pad,.u R.to Apex A,,1e Radio. Diacrie- (Con. or Cc.-)(a) Top, bottom, ends (b) ChsLnntrl If removable, bolts used Ia) tb) (c) _ Other fastening iDet0 -ibe .o .ttach ikitch)Drop Weight c(harpy Impact ft-lb 14. Design pressure' psi At _F at temp. of OF Items below to be completed for all vessels where applicable. IS. Safety Valve Outlets: Number _ Size Location 16. Nozzdes: Popo.e (Intex. Rxitrfo*c trenr Olxt". Orsln) Ntntbee Dta. or Sine Type Thickne a Material How Alltched 17. Inspection 4aenhole , No. Size Locatiotn Openings: Handhole s, No. Size .Location Threaded, No. _ Size Location 18. Supports: Skirt -Lugs -[.egs _ Other _ Attached (Y.. or No) 1N -b, r) (N mber) (D, crlbe) (Where & Ho .)'Ir Po.tv.Id Heat-Treted. Liar other Ivt-rnai or Vxrxrnat prraaorey iil coi-- d-nt -cmprltlrrea n Vpplcxble. REPORT NO. P0059-011 Sheet 2 of 2 -FORM N-2 NPT CERTIFICATE HOLDERS' DATA REPORT FOR NUCLEAR PART AND APPURTENANCES-7 3 A 3 As required by the Provision of the ASM E Code Rules. Section I11. Div. I 1. (.)Manuflctued by General Electric Company, Castle Hayne Rd., Wilmington, N.C.ipl* and ddircue ol FT CenUllc.1 HodcTr (b) Manufactured lot General Electric Company, San Jose, California (NEBG)INane and addr-a oN Cer Hol"der fo coýnpltrtd nuclear cornmPonocnt

2. IdentincaLlon-Certlflcate Holder's Serial No. o Part A3730 Nat'l Bd. No.D. L. Peterson (a) Constructed According to Drawing No. 768E534G001 Drawing Prepa.ed by.(b) Description ol Part Inspected Control Rod Drive, Model #7RDBl44DG001 N207 (c) Applicable ASMECode:Secrionll, Edition 1974 , Addendadate W'75 , CaseNo. 1361-2 Class). Cap 16689274PI (167A2343)

SA182 -F316 Code weld-----3/8 thick x 1 1/16 OD P50YPI02 2. Indicator Pipe 166B9313Pl 2 I SA31 2-TP316 3/4 sch 40-seamless pipe 0.113 wall thickness 1.065 max. dia. Reactor vesselI thimble I 3. Plug 159AI176PI -SAl82-F304-L___1/4 thick x 0.812 OD 4. Flange 919D610PI (719E474) Code weld SAl82-F304 ..P50YP102 I, T 3.37 thick x 9 5/8 0D 8.neck 1 1/16 thick x 5.0 00D4 2.875 ID 5 5. Base 137C5311P1 6 XM-19 ASHE SA479 3.0 00 x .884 ID /6. Ring Flange 11485122P2 SA182-F304 Code weld 1" thick x 5.0 00 x 1.75 ID P5OYP102 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 137C5934P1 SA182-F304 PXM-19 SA479 0.38 thcx131.30 thick x 2.62 dcla.0.33 thick x 1.307 dia.55 REPORT NO. P0059-011 Sh ee t 1 of 2 ,-.ýFORM N-2 NPT CERTIFICATE HOLDERS' DATA REPORT FOR NUCLEAR PART AND APPURTENANCES- cf 31 As required by the Provision o, the ASME Code Rules. Section III. Div. I 1. (a) Manufactured by General Electric Company, Castle Hayne Rd., Wilmington, N.C.iNAr rod addet-os of NPT CeruSfcaLe Holdrrr (b) Manufaccured for General Electric Company, San Jose, California (NEBG)INa.,a a..d d- o. N CetrUnCat" Hold,, tor -otPIr,-cd atuici r rcs -on t 2. Identnlcatlon-Certlflcate Holder's Serial No. of Part A34 98 Na-'I Bd. No.768E54GO01D.

L. Peterson (a) Constructed According to Drawing No. 768E534G01 Drawing Prpaed by Control Rod Drive, Model #7RDBl44DG001 (b) Description of Parr Insp:ected N 2U/tin194W'51361-2 1 (c) Applicable ASME Code: Section III, Edition 1974 , Addenda date Wt , CaseNo. 1361-2 Class 3. Remarka: Standard part for use with Reactor. Hydrostatically tested at 1820 psi.(BDr-ta dea-lpttlo of at-yvc. for which coponant wea daslbgnad)

Total number of sheets -2 We certify that the statements made in this report awe correct and this vessel part or apputenance as defined in the Code con-forms to the rules of constructioa of the ASME Code Section IlI.(The applicable Design Specification and Stress Report are not the responsibility of tbe NPT CertLqcate Holder for parts. An NPT Certlf-icae Ho~dcr for appurtenances is responsible for furnishing a separate Design Specification Stries Report if the appurtenance is not Include-d t the component Design Specification and Stress Report.) /Date- 7-11 19 80 Signed GE, NEFD-WMD-QA 13,.(NPT Certiniate Holdert Certific ate of Authorization Expires June 16, 1981 Certificate of uthorizatiort No. NPT N-1151 CERTIFICATION OF DESIGN FOR APPURTENANCE (when applicable)

GE, NEPD-WMD-QA, Castle Ray-ne Rd., Wilmington, N.C.Design information on file at 22A5556, Rev. 1 Stes, analysis report on file at GE, NEPD-WM1D-QA, Castle Hayne Rd. , Wilmington, N.C.22A4912, Rev. 2 Design specifications certified by B. N. Sridhar Prof. Eng.S.tweCalif Reg. No.1 8 3 4 5 Stress analysis report certified by B, N. Sridhar Prof. Eng. &.cc Calif Reg. No.1834 5 CERTIFICATE OF SHOP INSPECTION 1, the undersigned, holding a valid comnmis sion issued by the National Board of Boiler snd 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 PartWal DatLa Report on 7-11 -19 80 and state that to the best ti my knowledge and belef, the NPT Certficate Holder has constructed this part In accordance with the ASME Code Section IllI.By signing this certificate, neither the Inspector nor his employer makes any warranry, expressed or implied, concern-Ins 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 with this inspection. Date -- 19 80 NC 723, PA WC1766, OHIO.1Commissions -nort, .ll*Saturg Nationa Board, Sta,., Proi- -..nd No.(10cm) Thks ':2rMr (EOOO 1,0)mray t~e obtainied fr am the Order Dbiri. ASNIE. 3a5 E. 47th, St.. Neoi York. N.Y 10017 56 FORM N-2 (baci)Items 4-8 Incl. to be completed ior single wall vessels, aickets of iackered vessls, or shells of heat exchangers. Nominal Corrosion 4. Shell: Material T.S... .Th)ckne ss.. in. AllowanceC in. Di. la..-I- in. Length_ N.__ -in.(KLnd & Spec. No.) (Min. .1 Ran%. Sp-ecified)

5. Seams: Long H.T.' R.T. Efficiency Girth H.T._ R.T. No. of Courses 6. Heads: (a) Material T.S. (b) Material T.S.Location Cro-n Knuckle Elliptical Conic.! "-Irtph.et¢.I Flat Sid. iv Pr,...(Top. end.) Thick.n..

Radium Radli. Ratio Ap-a Ang.l Radium DOlitar (Co.- o Cone.)( a) .. ..- --(b)If removable. bolts uzed Other fastening (idaloriel. c.e. No.. T.S., Si.e. Nube-) (Deaveib. or arttch a.seth)7. Jacket Closure: (Deaceib. .. osee -ndnwetd. ba, etc. If bargIe. dimnsnona. ii boIted. deat-ribe or -k-soh)Drop Weight Charpy Inspact fr-lb 8 .D e s ig n p r e s s u re ' 1 2 5 0 p _ _ _5 7 5 _O F a l e o r _Ip a c t-F Items 9 and 10 to be completed for rube sections 9. Tubc Shiets: Stationary. Material Dia. _Thickness-in. Arachment (K-d A, Spec. No-) (Subjeci 1. pee- -vc) (Welded, Boiled)Floating. Material Dia. Thickness__ in. Attachment inchea 10. Tubes: Material 0. D. -in. Thickness or gafe. Number -Type (Sir. or U)Items 11-14 incl. to be completed for inner chabbers of jacketed vessels, or channels of hear exchangers. Nominal Corrosion II. Shell: Material _T.S. __ Thickness .. n. Allowance -in. Dia. -ft.__in. Length- ft. -in.(Kind & Spec. No.) (Mis. o( R a.,e Speciried)

12. Seams: Long H.T.' R.T. Efficiency Girth H.T.V__ __ R.T. No. of Courses 13. Hevds (a1 Material 1.S._ Ibl .aeral (b) T.S.Cro- Kn uckle. icai Conical HtrIsiph-tic.t Fftt Side to P -.aa.Lo.a- o- ThJikne.a R Rdlu. tadiua Raiv ApeS An.le Radiva Diameter (Cony. -Covc.)(a) Top, bottom, ends_(b) Channel If removable, bolts used (a) -h) t) (Other fastening (D macrib. oveattach iv *tch(Drop Weight Charpy Impact ft-lb 14. Design pressure' psi at hF at inep. ac OF Items below to be completed for all vessels where applicable.

15. Safety Valve Outlets: Number_ Size Location 16. Nozzles: P up.o. (Intel. R -,eJor-mre-nt Drte .Dr in) Niber D .. or St.e Type Material Thricner.

a U aerill Ho. Attached I7. Inspection Manholes, No. Size _ _ Location Openings: Handholes, No. _ Size _ _ Location Threeaded No. Size Location 18. Supports: Skirt Lugs l-egs Other _______ Attached (whereH ___(Yea or No) (Nuiber) (N-mbert (Deacrtbe) (Wirer. b (on If Poet...td Her-T-reated. Llta other Internan or err -rn-t praavrr oit, Cv cheni i.l.pet -e -1h --4-PDiCabLe. REPORT NO. P0059-011 Sheet 2 of 2 FORM N-2 NPT CERTIFICATE HOLDERS' DATA REPORT FOR NUCLEAR PART AND APPURTENANCES-oY .F 31 As required by the Provision of the ASME Code Rules. Section Ill. Div. I 1. (a) Manufactured by General Electric Company, Castle Hayne Rd., Wilmington, N.C.N1m4 sod .4d-, o NPT CerrfJntle Ho.d.,t (b) Manufactured for General Electric Company, San Jose, California (NEBG)IN.. and addýr,- oi N Cet1"rate Hotder to.r nualr comtop nt)2. Identflcation-Certtflcate Holder's Serlal No. of Part A34 98 Nat'l Bd. No.D. L. Peterson (a) Constructed According to Draing No. 768ES34GO01 Dr.ing Prepared by.(b) Description of Pat Inspected Control Rod Drive, Model #7RDBl44DG001 N207 (c) Applicable ASMECode:SectionlIII, EdLition 1974 , Addendadaze W'7 5 , CaseNo. 1361-2 Class 1. Cap 16659274PI (167A2343) SA182 -F316 3/8 thick x 1 1/16 OD 2. Indicator Pipe 166B9313Pl SA312-TP316 3/4 sch 40-seamless pipe 0.113 w:all thickness 1.065 max. dia.3. Plug 159A1176P1 SA182-F304 1/4 thick x 0.812 0D 4. Flange 919D610P1 (719E474).SA182-F304 3.37 thick x 9 5/8 0D 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 11485122P2 SA182-F304 I" thick x 5.0 00 x 1.75 ID 7. Cap Screw 117C4516P2 SA193-B6 6 ea. 1/2 dia. on 4 1/8 bolt circle 8. Plug 175A7961P1 SA182-F304 0.38 thick x 1.307 dia.CONTROL ROD DRIVE DWG -768E534 9. Nut 137C5934P1 XM-19 SA479 1.30 thick x 2.62 dia.57 REPORT NO. P0059-011 Sheet I of 2--e FORM N-2 NPT CERTIFICATE HOLDERS' DATA REPORT FOR NUCLEAR PART AND APPURTENANCES- /0 As required by the Provision of the ASME Code Rules. Section I11. Div. I I. (a) Manufacturedby General Electric Company, Castle Hayne Rd., Wilmington, N.C.Otmns Mnd Addresl a NpT Certmttcate Holder)(b) Manufactured for General Electric Company, San Jose, California 1Name AMd adde of. N Crrtlunct. Holder Pur sornplerd ntu),. on,-nt?2 Ident:Ilrcatlc-Certlflcate Holder's Serital No. st 0 pri A2571 Nat'l Bd. No.(a) Constructed According to DraOing No. 768E534G001 Draseing Prepared by D. L. Peterson Control Rod Drive, Model #T7RDBI44DG001 (b) Description of Part Inspected N0 N 207 (c) ApplicableASMECode:SrectionIl, Edition 1974 .Addendadare W',75 CaseNo. 1361-2_1C_ _3. R Standard part for use with Reactor. Hydrostatically tested at 1820 psi.(lsi8.. d. rLptJ at -1rv1c. f., o-haih nnt -. d ltainrd)* Total number of sheets -2 We certify chatzthe stattemients made in this repots are correct and this vessel part or appurtenance as defined in the Code con-forms to the rules of construction of the ASME Code Section Ill.(The applicable Desltn Specification and Stress Report are not the responsibility of the NPT" CertIfcate Holder for parts%. An NPTl Certif-ic.ate Holder for applurtn.ances is responsible for furnishing a separate Design Specification and Stress Report if the pp ftace is not included In the component Design Specification and Stres- Report.)Date 1i- 11979 Signed GE, NEPD-WMD-QA B 4N5"T Crroneat. Ho4&t11 Certificate of Authorizaton Expires June 16, 1981 Certificate of Authorization No. __PT N-1151 CERTIFICATION OF DESIGN FOR APPURTENANCE (-hen a-pplIcable) GE, NEPD-WMD-QA, Castle Flayne Rd., Wilmington, N.C.Design, inforrmation on file A 22A5556, Rev. 1 Stress analyaia repo"t on file At GE, NEPD-WMfD-QA, Castle HFayne Rd. , Wilmington, N.C.22A4912, Rev. 2 Design specifications certified by B. N. Sridhar Prof. Eng.StateCalif Reg. No 1 8-34 5 Stress analysis repvo" certified by B. N. Sridhar Prof. Eng. Sate Calif Reg. No18345 CERTIFICATE OF SHOP INSPECTION 1, the undersigned, holding a valid commission issued by the Natioial Board of Boiler and Presauxe Vessel Inapectoga and/or the Stare or Province of North Carolina And employed byDepartment of Labor of State of North Carolina have inspected the part of a pressure vessel descri bed in this pCrrial Dt Report o 11-1 -,sL9. and state that to the best o4 my itziowledze 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 etmploye makes Any sae'ry, exptessed or implied, coicern-Ing the part described in this Partial Data Report. Furthermore. neither the Inspector nor his employer shall be liable in my manner for "ay personal injury or property damage or a loss of any kind arising frotm or connected ith this inspection. Doatet 11-1 19 79 NC 723, PA WC1766t , Oln IO.",dCotnmiss;.ios ________'tnJdp)-+e. igs t Natlont 8o-d. State, Pm-vinc. aetd No.* 1.5.,,enlll ,4.et* in .o v .04 llltl, tch,3m,

dr a tl) V- 0" I I 1". (7) 04 .rmoti if It... 1-7 .th, , 110177) This form (E000 40),nay be obtained fromm he Order )ext.. ASl`AE. 345 E. 4 7th St.. New York. N.Y. 10017 58 FORM -N-2 (bacL)Items 4-- Intl. to be completed for single wall v -sel -. Aack'ers ,f acketed vessel h. or -hells of hear echanger,.

Nominal Corrosion' Shell; atert .T.S.. ..Thickinec .s in. Allowance -in. O)il .t. -tn. Length -It. -in.(KUnd & Span. No.) (JlIn. o. Ranq. Spec lled)S. Scams: Long H.T. R.T. EIficiency ___........ Girth _ _ _ T._ _ R.T. No. ol Courses 6. Heads: (I) Material____ .T.S. -(b) Material T.S.Lorcton Crown Knuckl Ell ip-tre Con1-al H-elr ph-rlr.l FlI. Sid. to Pr ..(Top,. horrorr nd.) Ticrekrtra Radiu. R.dtua Rario Ape- Anile Radli. Dra--er, (Con.- or Conc.)(b)If removable, bolts used Oher fastening (M r.t... 1. Spec. No.. T.S.. Si... Numrber) (D0 aCrlb. .r ., be, h 7. jacket Closure: (0-)ertbe

a. o.Ce, and weld. ba-, ,Ie. If bar gi-e die ..n.ona, if bolted. dacetbe or Iketrh)Drop Weigh, Charpy lmpacr ft-lb 8. Design pressure' 1250 psi at _7_ _ OF at temp. of OF Irems 9 and 10 to be completed for tube sections 9. Tube Sheers: Stationar"y.

Material Dia. Thickness -in. At.tchmenr (Kind It Spec. No.) (Subtrje to pcr- -(Werdod. Bolted)Floaring. Material Dia. Thickness __ in. Attachmerne

10. Tubes: Material .OD. -- in. Thickness

_ o, _-io .Number _Type (Sir. or U)Items 11-14 incl. to be completed for inner chambers of jacketed vessels, or channels of heat enchangers. Nominal Corrosion 1 1. Shell: M.acerial__ ___ T.S. __ Thickness tn. Allowance oin. Di, a fr.-in. Length...... ____in.(Kind & Spec. No.) (Ma-. o R ant[ SPtrrcttd)

12. Seams: Long H.T.t R.T. Efficiency

.7.Girth H.T.'_ R.T. No. of Courses I13 Heads (a) Material _ T.S. (bI T.ateral T S.Cow-n Knu-1le Ellitic a Co-c-t Hel apharicatl Flt. Sid. to Pr-..Locates ThJrkrt.- Radto. Wadl. R.ttO Ace. ,nall R.diaa Otm-ter (Coon. orCone.)a) Top. bottom, ends__(b) Channel If remoeable. boh s used Ia) fbI c) , Oher fastening 10 errtbe or .1t-ch .k.rch)Drop Wcigh: (harpy Impact fr-lb 14. Design pressure t psr o_ OF or temp. of OF Items below to re completed for all vessels where applicable.

15. Safety Valve Outlets: Number -Size Location 16. NozzJe s: P uP... Int". Remntorernn Ourlert Drain) Numb-. 0.. ne Stl. Tepe Mater,. Thpctnr 5 arena t Ho- Artcrhed 1'. Inspection Manholes.

No. _ Sze Location Opentogs: Handhole s. No. Size. Lociatton, Threaded. No. Size Location IS. Sopport s: Skir -Lugs [.es _ Other Ar acthed (ye or No) ,,Nu re e (Nu.mbrt) (Deerb,) (Wh-r & HowI It Poat. ltd He-lT-e' red.Li-r o.her internal or -.1 ra: o-n tts cn taenr tetrt ln t ac e n --l -11h. REPORT NO. P0059-011 Sheet 2 of 2 FORM %4-2 XFT CERTIMCATE HOLDERS' DATA REPORT FOR NUCLEAR PART A.ND .,IT' oNCE OF 3/As requircd by the Provision of the A.SME Code Rules. Scction Ill. Div. I (a).Mnubw,, y General Electric Company, Castle Hayne Rd., Wilmington, N.C.41a6,n and a4dm a Of M" Ctrtlflcai. Mulder?(b) Maauf.cturd fot General Electric Company, San Jose, California (NEBG)OHam, and "drewm of It Cerefctal Ho1dde tr -wi.ld mn.., c-Po.,ou 2- Idendflcadon-Certl¢ate Holders No. a( Part NN&, I a d. No.D. L. Peterson (a) constructedi According to Dtwa-ng No. 768F934GQ(11 Drawing Prepaied by D .Ptro (b) Description of Pan Inspected. Control Rod Drive, Modal 17RDB144DG001 N207 (c) ApplIicable AS4ECod.eS:ctioaEdi6e 1974 Addndadae W'75 Caa-No. 1361-2 Class 1. Cap 166B9274P1 (167A2343) SA182 -F316 3/8 thick x 1 1/16 OD 2. Indicator Pipe 16699313P] SA312-TP316 3/4 sch 40-seamless pipe 0.113 wall thickness 1.065 max. dia.3. Plug 159A1176P1 -SAl82-F304 1/4 thick x 0.812 0O 4. Flange 919D610P1 (719E474).SA182-F304 3.37 thick x 9 5/8 0D 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 I" thick x 5.0 0D x 1.75 ID 7. Cap Screw 117C4516P2 SA193-86 6 ea. 1/2 dia. on 4 1/8 bolt circle 8. Plug 175A7961P1 SA182-F304 0.38 thick x 1.307 dia.CONTROL ROD DRIVE 0WG -768E534 9. Nut 137C5934PI ,M I-19 SA479 1.30 thick x 2.62 dia.59 PEPORT NO. P0059-011/ Sheet 1 of 2 12 oF l FORII N-2 NXVT T=7CATE HOLDERS' DATA REPORT FON UCLF_1 PART AND APPLRTENANCES As required by the of the ASME Code Rules. Scvion 1l1. Div. I I. (2)Manufactuze by General Electric Company, Castle Hayne Rd., Wilmlingtqn, N.C.CN a.nd addzrss4 Nfl ol~(b) lanuacsrwed for General Electric Company, San Jose, California (NEBG)*(N6 an .fe4 t N C.,fist. Ho~d~r tott~r .c ,wpt~d n~ar d2. klebdcatdCertincate Holder's A3895 Neel Bd. No.(a) Conarrucred Aordw- n Da-ig No 768E534G001 D. L. PatersonRod Drive, Model #7RDB144DG001(b) Description of Pant inspected iW74 W'75 1361-2 1 (c) Applicable ASW E Code: SectionfIU, Edmitcn........ Addenida date *Case No. -CIA$a-a____).. Ram : Standard part for use with Reactor. Hydrostatically teasted at 1820 psi.* Total number of 3heets -2.e certify chat the dents m, in this report a corret an this vessml or appiternance

i. defused ini the Code con-forms to Lhe rules of coe-mction of die ASU4E Mod e .Section 111.(The applicable Det-i, Specification and Stres Report are not t[e respoaoibilltY of the M?1 Certlflicat Helder for parts- An NPT Cerlif-icate Holder roe epqrt~enances Is rrnponsibic for f-nishi-g a ieparale Design Specificzacf

=A Stcss Report it the apprurxtancc is not Included In use cromponew~ Depj Speeifcztiof r2-d StreSS Report_); aLL 8/26/ i9 81 sign" GE, ,--AD- D-NPT N-11-51 Certificate of ruxthorizsrion Expires Cer-h -5' T981 o oriz.mioa No.CERTIFICATION OF DESIG.N FOR APPURTENANCE (when applicable)

Ocigs i~famormic on file , GE, NEPD-W14D-OA, Castle Havne Rd., Wi Imington .N.C.RGE, NEPD, San dose, Calif.Srxess ,an,*ysi, ,eo<, ona fi!ý- v-22A4912, Rev, 2* Design specifcaticonn certified by 3-. N.

Rag. StateCalif Re;3. No 1 3 3 4 5 Stress analysis report certified by B. N. Sridhar prof. Egg. eCalif 'g401o3345 CERTIFICATE OF SHOP INSPECTION 1, the \-ndersigned, holding a coiwiazxioa issucd by the NrAional Board of Boiler and Presweur Vessel lnspectots and/or the Stare or Province of .Torth Carolina and employed byDepartneut of Labor o _ State of North Carolina have inspected the part of a pressure vessel describýd in Chis fptru al Dot o 8/26/ I'Pand sIate that to the best of =el knowledge and belief. the NPT Crrtlrcate Holder has constructed this part In accordanrce with the ASME Code Section Ill.By tigning Chia certificate, neither the inspecror not his employer tuaies may warranty, expressed or implied, concern-Ing the part described in this Partial Data Report. Furthermore. neither the Inspector nor his employer ishall be liable in any inauer for any iniury or property dam*ae or a loss of any kind arising from or connected ,ith this inapection. ___ -..omm___ _,, _,_-_C issions N.C. 723,PA.WC1766, OHIO C to-a N 13id. ita... Pr0 In-. *nd *Sottaanrn

[..r tn1,,, atII.,. i~th..r d'..nt r.y .ubd re.t~r ) .,. * '. ) a.,rmtto aster. [2 a ha'Sw t.ý.m l m~ll. lh,.-lol 1.- .1i~ 11-1 m , k.lch.. ,r dr-.gilo -a ~ ld 1r-dal) 1 1 , -1%"* ". [2) _J-t/rIo.

1 ~ m -+ m-* h,~.O .R .. .. ... ......- etaara a .. ......aan.~ .ar m t ,a LSm aaU.. a! ,. C f-tt '.-...e 4.ns..~ l -a , ...- .. .60 ON FORM N-2 (back)Items 4-a Incl. to beC cos..zleted for singile wall vessels. jackets of isck.ried ve ssels, Or 3hells of hcat csthang crs.Nosiotal Corrosion (Kitlnd&1 1 t..N.) (Motu.Rsn4 9aeLf .6)5. Sems:s: L--..________ __________ ________ Efficiency Girth H.T.'__ ____ R. T. _______No. of Courfses a__________

6. Heasc (a) Mdaterial

..-T.S. ___________ (b) M4arcrial_______ T..S.._______ L..smh-s Cr.... r..ckI. Clliptita) Co-dcal itsAshri " ish i t. P'....cr.9. bcitoos, -..d) Thrkn..*. rsdA..s Sadiue Ratio Av.. Angle. Radsius Dsntr (C-w. -Co-se)It trasovable.~ bolts u"e _____________________ Other fastenrintg (1.tdI.S...No.. T3.,..31... lunA.-l (D.serib. or ntt-h) k.tch)7. jacket Closure: D&b-c --tbwec.-kch Drop Weightt S. Designs presisure' 1250 psi At 575 OF at temp.sc ft-lb Icems 9 and 10 to be completed foe 9. Tube Shieets: Stationary. -Vacer Floating. Marer 10. Tubes: Material tube ections i.1_________ Dis-J Thickness -in. Atrachmrnt _________( 3P~ o.- No.)- 1~o.c toPeo---) (W.Ld~d. Batted)gal _________

s. ________ Thickness.

in. Axttachmoent________ -.D -__ in- hickncs s..... a*g*. Numnber ___________ I flc-,n 11 -14 incl. to be comspleted fcc maort chazbers o! jacckted vesL;hn~ats of b*As excartgerz. s 11. Shself: MSfaeei&Aj _ _ T-S.- _ __Thickness..ia. Allewaneils oit- ft. ia- Lcnbfi fz. ____12- Scams: Long_______ H-.T.'______ R.T. Efficizsicy Girth H.T.' R.T. _No. of Cout"Is 13. Heads (a) Mstcrialj T.S. (b) Mireixtl T.S.Cr-.. Knoobi. KIiptpic.l Conclc. H-prc,.h-oi-la riae SLd. to Prosa.Loaton Th~ick-. Rd.dl. Radip.. Ratio Ape. AnCL, Rl.di. 01-1-o (Co-. -Cn a.) Top. bottom, end 3 (b) Ch~um.e!If rem-ovable, holes used (a) (b) -(c) -Ocher fssrenins.srjbh. -.tt.ch .4.4ch)Drop Weight Charpy Impact ft-lb 14. Design pressure' psi at __F -t temp. of -F Items below to be completed for all vesocls whe-re applicable.

15. Safety Valve Outlets= Number-_ Size -Location 16 Nozdes:.Pueos. [khi It. tteiefoe'com.-nO

.Outiet, 0 it) Npob4 Di.. or1 -[31.. Typ.TV. Mh oIil Thick ... R.-a }-o. Attached 17 Inspection Manholes, No. -Size -Locotio_Openings:

Handholes. No. _ Sire -.. Loxction Threaded, No. -.Size -L<cation 19. Supports: Skirt Lugs Lgs. Other ______ Attached_(Y.5 op N.) (eum) (Numer) (De.cdtb.o (wh.r."- Hong 7 If Po-t1-id H.la-Trrte.d. -.. .. h. -4F, 'Interal .- *fsrnsi pr.a ury it h zotnc d.n, *hratu'- -.n *ppjj.-bj. REPORT NO. P0059-011 Sheet 2 of 2 3 ._N1 N-MFT CE1T1VCATE HOLDERS' DATA REPORT FOR NUCLEAR PART AND APFURTENANCES' A-% required by the Provision of the ASME Code Rules. Section III, Div. I I. (a) M 4:!,cw" by General Electric Company, Castle Hayne Rd., Wilmington, N.C.N .w and bd4 Oa r t I CKrr ctac .t HOdr) fo, General Electric Company, San Jose, California (NEBG)2. miduiricatloo-Ce-rtLIcat* Holdtes Seriai No. ot Part A3895 13d 3j. No.D. L. Peterson (a) to Drarwing No._ 768E534CQQ1 Drawing Prepaed by .(b) Dscription o Pun Inspected Control Rod Drive, Model 97RDBI44DG001 N207 (c) Applicable ASMECodetSecioaffl, Edition 1974- AddeadadAce W'75 Case No. 1361-2 Cl,,, 1!:./,>1. Cap 16689274P1 (167A2343) SA182 -F316 3/8 thick x 1 1/16 00 2. Indicator Pipe 166B9313PI SA31 2-TP316 3/4 sch 40-seamless pipe 0. 133 wall thickness 1.065 max. dia.3. Plug 159A1176P1 SA182-F304 1/4 thick x 0.812 00 4. Flange 91lD610Pl (719E474)SA182-F304 3.37 thick x 9 5/8 00 neck 7 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 11485122P2 SA182-F304 Im thick x 5.0 00 x 1.75 ID 7. Cap Screw 117C4516P2 SA193-B6 6 ea. 1/2 dia. on 4 1/8 bolt circle 8. Plug 17SA7961Pl SA182-4304 0.38 thick x 1.307 dia, CONTROL ROD DRIVE DWG -768E534 9. Nut 137C5934PI M-19 SA479 "3 i-J 1.30 thick x 2.62 d-ia.61 REPORT NO. P0059-011 FOWM N-2 NWf CERTIFICATE HOLDERS' DATA REPORT FOR NUCLEAR PART AND APPURTENANCESe Iq/DF-31 As required by the Provision of the A.SME Code Rules. S.ction III. Div. I 1 W-ouaetued I. General Electric Company, Castle Hay-ne Rd., Wilmington, N.C.irta a94 abddrSftg(NPT CemdcvA Hold.(b) ufacrrd for General Electric Company, San Jose, California (NEBG)tNan aad bdezs. of M Cnliflc~to )inwd fof ýr~ete.d -K).far tompau NendcfflCatdoo.Cer-tjlcate Hloder'sSerlatJNo.ofPan A5684 ht!Bd. No. ___________(a) Conatrintcd According to Drawi.ing No. 768E534GO01 Drcwa Ppared D. L. Peterson (b) Descrpcic, of Part Lampocred Control Rod Drive, Model #7RDBl44DG00l rizui PIZ95 1974 W'75 1361-2 1 (c) AWplicableASWECode-Ser lm ,1, Edirisn 94 Addetcdadaze , Cas -No. Class___3. Standard part for use with Reactor. Hydrostatically tested at 1820 psi.T* otal number of sheets -2 We certify that the statenrsis made in, this report axe correct and dthis vessel par= or appurtenance as defined in the Code con-forms to the rules of conscrtrctzio of the AS.4,E FAe sectioa III.(The aptjilcable Defsig Speciftcation and Strie are not the responalbility of the NPT Certificate Holder for Parts An NVr Cenitf-icaft Holder for appurtenances is respotrtble for a seprate Demgn Specificatiott and Stress RePort if the appurtemnce is not 111elhded In the component Design Speci,,catlon and Stre:;s Report-)--...".-. -. .' -"" ' _ _ _._ -Certificate of Aurbonizarioima Expire* Septem~ber_ 715, T987T Cerrificrte of a2srion No. I-15 CERTIFICATION OF DESIGN APPURTE74ANCE (when appliles e)Dea.ign an file ý GE, NEPO-U14[-OA, Castle Hayne Rd., Wilminaton. N.C.22A5556, Rev.Sress report on file a GE, NEPD, San Jose, Calif.22A4912, Rev. 2 Do.gn spepsciicaotioa cert~ifd by. 3. J. Sridhar prof. Eng. StaeCalif Rex.MoJ.5 2 3 4 5 Strssa analysis .port certified by B. N. Sridhar Prf. Es. Siate Calif Res. No.1_345 CERTIFICATE OF 9IOP INSPECTION 1, the undersigned, holding a vaid corrsnismion is;3-od by5 the Nati.n.as Bo,.r of Boiler and Pr-essuste Vesiel Inspectors and/or the State or Province ,j North Carolina and ,.l-.-d byDepartment of Labor of State of North Carolina baye inspected the part of a pressure vessel deicribed in this Nrin Dat

Vprt on /31 19QJ.and s~e that othe ben oimy knowledige

&d bs-tlef, the NPT CertUflctte Holder has constructed Uls pasrt In accordance wILh the ASME Code Section Ill.By signing this certi;cate, Oeither the lIapector nor his esrrployer mrakes my warranty, expressed cc implied, concert.Ins the part described in this Partial Data Report. Furthermore. neither the Inspector nor his employer shall be liable in imy manner for any persotal injury or protrrty da-sage or a loss of any arising Irons or connected with this inappection. Ose .3 ./31 7t N.C. 723,PA.WC1766, OHIO:L ~ p~sr Cocoiis~isonx o,*Saa rvneedtn to v,, of1.,, set~.. , d-ntnc 'ny b tt*d po.d.,(I)*l.

I .(f normrI~ uu.nd-2vNo.i 11007) This foarm i E00040) Ie? Ob obtained from the Or der C cot- ASM',E. 3,15 E. 47th St., Newe Y ork. N.Y. 10017 62 MPHM N-2 (backa)Items 4-8 InclI. to be completed (or single well vesse$ jackets of jadcketed v.~egzl., of shells of heat exchsnCeis.

Nossiias Corrosions

4. Shell: 4A9CIriAl- -l ___......YS,.____-TjjlCknejs_...

in. Allowance-i..~~n. Dia....... ft.-.....in. Leng k... ft.-____ in.5. Seemsa: Long 3 _________1.?.' -ft.. Efficaincy Girth 1I.T.'_ _____ R.T. _______No. cf Courses___________

6. He-dw. (a) Material ___________T.&.

N b Material ________T.&._________ Ceý W- K,.kI 0 Kztlvtvrie COnIe Flutpr1s 7. 2i4. is Pr.*..(T'p bet,. .sJ) hiissa 3di.0 Radius Ratio AII AagI. Radius VL..a-t.r (Csa.. or Con.)(A)__________________ __________ It rermovable. bolts used ______________________Other fastening~(MaI Spo.- No.. T.S.. SIM., cDeacdib* -.tach ksetoh)7. Jacket Closure: (Deaprs-b ... sn o e e th ... aive dimn~sniona. il bolted. delclribs es-sketch) Drop Weight Ctharpy IMpAct ft-lb 8. Design preasure' 1250 p se 575 OF az cemp. of OF lt-ms 9 and 10 to be completed for tube sectios 9. Tube See-is: Stationary. Maxerial DiI.__ Thickness-. is. (Lbid h 3PsC. N..) (..b-sct ts resi t) (Welded. Bettad)Floating. Material Diu. Thickness-;in. Acracheaent inch..10. Tubes: Macerial O.D. -ir. Thickness __ _or e. Number. Type (3t. ow 11)[Irai 11-14 incl. tobe co we Mc verpal5a .C of ent .b CeXc a .11. Shelf: l.. " A "'1 L 0-:ý'12. Seam: Lontg T.r

R-T. Effilciescy Girth H.V._ R.T. No. of Cour Mes 13. Heads (A) Material .T.S. (b) Material _ T.S.C -oer. Knokis Liliq¢Icot Conical R.-i h-tt -& f1i Si.e Do Press.Location Thick.. Rius Redi. BI R.1. AV..i4-5 Bedlua Dieter (Cons. co* Cor2..(a) Top, bottom, ends_____

___ ____ ____ ____(b) Cha nnel If rem~ovable. bolls used (&)-_______(bi -(______ c) _______ ther listening Drop veight ,.r e_ __C h a rp y I ofa ct __f_-ib14. Design pressure'- psi at oF .1 temp. of ý F ,y Items below to be completed for all veusels where applicable.

15. Safety Val-v Outlets: Number-_______

Sizre 16. Nozzles: O..ttý. Desk.) N-eb..s Ohs. e51A. T vr'*17. Inspection .'4..iholeso. ____40. _ Size ____Openings: Heodholes, No. -_________Threaded, No.-_______ Size -18. Supports: Skirt -Lugs Legs-(Y.. ., .4.)List oth., Intartial wr VIIte pwvssr with caincident tow.,.x Rs, V .Cts.ta thirkn..s Ha.. Attached Location Loc auion Location_ Other Attached (itoe* het iDpi(Where. REPORT NO. P0059-011 OF Sheet 2 of 2 / 7 -3 FORM N-2 NPT CERTIFICATE HOLDERS' DATA REPORT FOR NUCLEAR PART AND APPURTENANCES' A3 requir-d b 'r-"i'ici of Lb. , ," e Cod,! Rules. .!I. i 1. (a ailcu"b General Electric Company, Caatle Hlay-as Rd., .Wilmaington, N;G.(C4gs s W s "T5 1 Com~fitst. "4odm (1) ~General Electric Coiappay, San Jose, Californ-ia (zTM)(sNa~ sAd sddr. of M CýrU3csg* Hodider er c~~e madea c~mpo..,v(2. :d1tflcxdo-Ce91UacaA. Holdrs se~iaj No. oCPr A5684 sri-.ae Bd. No.(a) Coswmacted A&cocdwn to DravinS No. 768R7SI4 M01-Dm~wing Ptwe by L etro 0 Decito c! Past Control Rod Drive, Model #7RDBI44DGQGi (c)Apwsb.Aa4Eo~i ?~riaUJEd~ooJ2Z... A~cnd~M~t~.~..,N207 N295 1. Cap 166B9274P] (167A2343) SA182 -F316 3/8 thick x 1 1/16 OD 2. Indicator Pipe 16689313PI SA312-TP31 6 1.065 max. dia.3. Plug 159AI176PI SA182-F304 1/4 thick x 0.812 OD 4. Flange 91SD610Pl (719E474)SA182-F304 3.37 thick x 9 5/8 OD 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 11405122P2 SA182-F304 1" thick x 5.0 00 x 1.75 ID 7. Cap Screw 117C4516P2 SA1 93-86 6 ea. 1/2 dia. on 4 1/8 bolt circle 8. Plug 175,7961PI SAl 82-F304 0.38 thick x 1.307 dia.P5OYP1 02 CONTROL ROD DRIVE OWG -768E534 9. Nut 137C5934P1 9* M-19 SA479 1.30 thick x 2.62 dca.63 REPORT NO. P0059-011* OR4 l`NT C irFCATEHQ-ZCUD!LRt' DA~TA PEPORT FC0 NUCLEAR PART AND API'MEINANCE-04 ,C J/As reuired t~y the Provisjcn of the ASME Code Rules. Scztion 111. Div. I ,j.ict, y Central Electri Company, Castle Hay-na Rd., Wilmington, N.C.(b) Maostacwta"i foe General Zlsctric Company. San Jose., California (NMfl)(Mame x~d 4drA at M Caraticu. Head We rosiv&'tw aa J .IdunatIOcd-Cert~niente Holdeex Stlj Xo ce part A54 27 -Naei Bd No. __________(a) Ccauamted Ac~coring to Dmigw No 768ES34GO01 "r~a rpav .L Nt~rso (b) D ws ri t~o o P a I spa z" C on tro l R od D rive , Y!odel #7RD B l44DC 0O l __R7 7 (c) AppticaWeASECod~tS.ctc.,UI,Editica_1974 .'7 dasH. 1361-21 3 Standard part for use with Reactor. HydrostaticalIly caste-d at 1820 psi.(Ets do.*oo.~a t1 aw.~c* (s fAft ýa~ana -sea.t*'STotal nu~bar of 3heats -2 we certify that the ,tnze~asnt3 m~ade in tL'6 Mrn ara cog-sect &zd this vessel pwt oc zpperonsce a~s deflus- in bhe C-ode coo.fo~roa to the rades of conaszrutics oi dre ASWE (ý tioti ill.tTb* APPlkable Oest= SPtegcinatloct azd Stres ir~Pon an nat the mponz~b1iitY of the NP CcraUWUS Helder far pwl2. An xPT Cent!-icst Mi~de fro app tanamce is enpoamus lfor ftneský a ~arau Desips SPVefci:siou sad Swte.s RA~ol d the appasrtcoxxic is riC4 inci~~~OM-Led tz tXleopoti SP~tiftttl Wid StUvm Rcp~iL.)C~relke. o aaoejad~~ SP e .5T 19g Certiricate of 00 ýt._________ CERMSFCAMIOK OFL OE~SQ' FGH APPURTENANCE (whe* wpplisbe GE, UMf-WMD--4qA, Ca~tla Hayna Rd., Wilizlngton, NI.C.2lA5556, Rey. 2-.Nf-.M-A imntn C SXclds 2naLymia rrg-prqt amfles GE. ZFDqM:QCslRayeFd., imngo NC 22N4912, Rev. 2 Doig spcfcaia cvrtag by B. N. Sridhar Po.o5onCali~f Rg ~B scres. enaI?~aa retcrt cvtilni" 6 yB. N. Srldbar pIERrai ae4013~3 4 5 CERTIFICATE OF SH1OP INSPEMTON 1, the =zd*fxitaqd. holding a valid comaisaic= issurad by the Naciansl %ared of Boilei a=d Preassusi Vc,s-eI [%Pc-ctors xxco the state at ptavnc of North Carolina and mpcr ý,,Depzrtmenc of Labor State of North Carolina ~ ~ ~ * ~ vse ecie nti Pakrus Det.3 fl*Pot on 7/.1 23,. 1W VU. and mto at.it to Lucbete-a ~~ knowt~enae"ldbetsief. tLhe tIPT Cer%1ifLet tlopiej has coaxsnctor this srt In accordance with the ASUiE Code Stctloa inl.Itsth Pa~rnstt decertibedat thckis 8the 0 capeg r o his employer makes may wUaerrny. expremsed or im~plied. cojnccrn-1o~ he art escibedle hisPar-Iia Data Fteport. rurtherrmore. neither the In:Pector nor his rmipityer wnith thbis inblectrion. atnefo ~ personal iniurY' at proprty damage or a 03ss at any ktind Arising Iroma ot connected De. ~7/23 19 81 Cms'mrei.I. P-nion -d~ 3..AC~h~fl. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ L t.'. j a,-. sh.. .3 ..,s.... .O.~n ..:I C771 's"i Q*is oa.- ,rw' '-rO. '- i-: -r 64 III I 1 1 1 1 1, 1 ,1 11 ' 1'1 11 '1 1 0 1 111' 1 1 ! I j i j: r FORM N-2 (back)tt.aiOIncl. go beý comple~ted (ot ,tttxt wail -asels. iackert. 0j Isc ifed 't sas- S. of hr($ a oi beat exclanges.. Nominoal Corsn A. %ell: Mateia. in Allwace in MA-_ ft..i. .1 Rang. Sm Lii 5. Scenes; Long _________H.T.'________ R. T. _________Efficiency Girth Ii. T. III___ _ LT. _______No. of Couteze*6. He.ads (a) Sila.*criaj _ ________T.S. _ _____(b) Mactitil _____ T.S. _______L-selon. C..-. Stir.ki. 11:iaaitiiai C-14i.1 ?I.. 3114i~i Ft. Sa. to ..-"a.bi,..~I ThLkitoo. RaIo. Radi... Ratio A~e Angl. RadIu Dt-aa.,~ (C...-If eviocvable* bolts deaed Oth______________________01er fasteniog (O.s.,b. or tat.?h *.1tehl 7. jacket Closure: (Oa~~~~~~cvtb. ~~~~ ~ C as .g.. wyd0 [tfi. ac Wga -i.~~~t ft Istd d.eboofsa 575 OF~ yI&~c tl S. Designa pressure'. 125 ,i at 84__________ a Ce~p. of_________ ltens. 9 and 10 to b~e couopl~et" for tube sections 9. Tube Shecrta: Statio...cy. Mlateriasl_______ Diat._______ Thickness-cin. Aitachseor__________ Floating. 4ateri.1 11_______ I.._______ Thicknesa...au. Atexclittioec ________10. Tubes: Material _______ .0. -__ in. Thickekoa. -o ____.i~got*. Nuone _ Typ..(lzr. or tfl Itents 11-14 inc. to be completed for inner chainhe's of iaclcrted vessels. or channels of lteat exchangers-12- 5-imus Lonag fl.T.a_______ R.rT. Efficitacy 7 GrhH.T.a______ R. T. S______ o. a cowis" ___________

13. Head. aa (. 4atitrial

______________ T.S. L_________

.sr,,l__________

T-S. _________C -.. KnuL,1. 1Fza,IIIeI C--i.a ~ naaan~ FT.. 1*p gn Loctto. lue,... aal~a Rail,,. R.t". pe A,,41. Otduia OLe..t..- cc -. OrC...(a) Top, bartoom* ends ____________________________ _____ ______If remova.ble. boclts. used C) _________ fI ____f.________ Other fateming Drop Weight Charpy Iwtpact -fr-ilb 14. Detion prsue psi____________ _ at _ ____________F it cmnp. of ______F____ Itemsl b.'Io- to beC comnpleted for .11 ýcssrls ..nere Appiscable.

1. Safety Valve Outlets: Nurmbt.rf Size-____

_____Pun... I... T,.-Lo-cation IdW ...1-i4aet,.eJ H.- At,.th.4-a..OPen:ngas: H andhole , 1,.______ Sr ______ Li -uon -Y.. " N., No... D-~b ~ . REPORT NO. P0059-011 M! 1:11i 11 1111, 212C ,/2nc 3/Sheet 2 of 2 FORM N-2 NPT CZRTIFICATE HOLDERS' DATA REPORT FOR Nr3CLEAR PART AND APPURTENANCES-As required by the Provision of the ASME Code Rules. So:rion I11. Div. I 1. (aw ~ crmby Geranral Electric Company, Castle Hayne Rd., Wilmnington, N.C.Eflmma am4s. i w cema'W Kmrp (b) ~ ~ General Electric Company, San Jose, Californ2ia MUG~)9MNm. "~ 06drv of M CwOUcII HWA*" %r cowaq4."~ Pjcl.uj eminp.v 2- l~VdhC flcao-CerJ11cate Holders Se"0I No o(M- A.5427 NalBd. No.____________(a) Coastmeted According to Drawing No. 768F514GA1li Drawins Prepaced by D. L. Peterson (b) D*-44" of Palm laspectd Control Rod Drive, Model #7P.D14DG00' N207 (c) ApqlcsbiqrAgdE Code: Sezction 1. EdjtionL 9 7 4*Adjdv4udg.a W'75. :CA.eNo. 1361-2 cl~tag 1 1. Cap 166B9274Pl (167A2343) SA182 -F316 3/8 thick x 1 1/16 00* 2. Indicator Pipe 16689313P] SA312-TP316 3 pipe 3. Plugq 159AI176PI SA1822-F3304 1/4 thick x 0.812 OD 4. Flange 919D61OP1 (719E474)SA182-F304 3.37 thick x 9 5/8 00 neck 1 1/16 thick x 5.0 OD 2.875 ID 5. Base 137C5311P1 XM-19 AS,1E SA479 3.0 00D x .884 ID 6. Ring Flange 11485122P2 SA182-F304 1* thick x 5.0 00 x 1.75 10 7. Cap Screw 117C4516P2 SA193-86 6 ea. 1/2 dia. on 4 1/8 bolt circle 8. Plug 175A7961Pl SA182-F304 0.38 thic x. 1.,307 dia CON.TROL ROD DRIVE DVIG -76SE534 9. Nut 137C.5934P1 00)UI-l9 SA479 65 REPORT NO. P0059-011 FOWM -*2 NPT Ct:RrrnIcAsT-HOLDER.S' DATA RP'ORT FOR NLEtFAg PXRT A") ,PLRTFNA.CES-I '- 3.As requarcd by Lhe Provt-jon O. he .,ASME Code Rulcs. Sccrion Ill- Diý. I L (a) by General &1-_ctzIc Coaman7, Castle Ha)-ne Rd., Wi.m-ingtoa, 3.C.(b) f General Electrtc COMnan7, San Jose, California (NEBG)7_ .o, w -%tr,.'LFart A3 i83 Seel o. No.76aE534coo0. D. L. ?ecarson (4C-cra~mcud Accovding Dw'g So_ rs'n Prv-pard by'a put P. 5,-, Control Rod Drive, Model 17RD3144DGOOl N 1 U /1974 .4675 1361-2 1 (c) .%Pli~csbI-A-6CQOISISec-do. 11,Editioa____ tdiendxdt Cjiq N 0.__ _Cl ass___z __3. Standard par: for use --raith Raactor. Eydrostatically tested at 1820 psi.(EH a aOqt e4 tehorr Lvs --P STotal number of sh*Qcs -2[v 1- carrjfy chaccbm %rCve-nt -to-If LO ckiz rer,, &ve~ c~vrecr oýd dhis vos~el part ot spqu-r1unce "s d.Czixad in che Coo.$ coo-(Th* D R .. and S3af Rcrt ar not lte of Cho .NP" Certiicaw Hold"er fo part"M An NPT Ctr'Lf-icu Hokdkr (or Avvv"=Mn':2-za r=VaoNubd for fzrmshwg a xecarsc Design Specidicaono xad Srtrms Rcport if Lhe 20punenf)-cc si 104 Lac-Iuded La J)-a cmrnonvix Dez+/-gm S.ixacl.fit xmk and Suegalepr 12/19 80 GE, =, -Q1-M-OA June 16. 1981 ..PT N-LI-4 aui-e of Ao~xuaEprsCzrrf-icwvat zx ?.Zho1IIo. 3o. _________CERT1FIC.A'fO1 OF DE-IGN FOR APPURTENAUNCE (whes .pplic-.ble) CZ, CaaOLje HaLrne Rd., [;imIngron, S.C.Strasa sý1"iwx a~ f-I ic CG,. 'rE7-L-MD--')A, Caarl -'a J-ne 94, I'd:n N. C.7../.A4912, Rau. Z cectf{, 7ia 3. 5. Prof. .,i g. ____a 3. 1- Sridhar ...2,-Sty.-,I bTL~x Prof ___ng_________________ CERTIFICATE OF ýSHOP INSPECTION

1. dus 'Kfwdrsarn*A hoiding a -ldcoemsaisi iý 'ay tho.4maional 3ý0.44o of BoxLWT m.,4 Puc-ssuae Výý LnspeC-oc:

6,4t(h Scam o Pvo.Mcv of 'tor:h Carolfna ,j ,IaJdtyDeoar=qnz: of Labor of Stace oi Noriih Carolina L h o parr of a pr~esgwsz -osvmt decrixbcd inhi?V.rtw Ds, oan 12/10 1 80.n.4 ...I, to .Me a my, And NrIe(. .'{T Cernflcst. Hoider asj contmucted Zl1l p5 In acrarianvc witUh thr ASME Code W1.Bv ignng hi crc Ii~csn. ýtxhr Lb* aai,.-ctotrilot his evost-r Muakes ady wfzt, -z~ea ý t L'~ik-d' -cafce-IngL tre ,iart dticribed in this ?Irtial Oars Re.,orl-. Furth-ermore. aeltiher the (lnaDecor nor hisl e5 loyr"~ia t1b ijabfe ia wy issnnar jor av pvrsýmaa inpmqt or propc-ry asme at a [oo at any kind ,unsing tro a connecrrd S2/10 30.-- 723,PNUK , 66, -a .... .40fI. .I... .. .66 b- -I 1 -41 e -11 11,11. ack I 1 .; cketd Idins.- 1..4. -.ll: 'Is f r u ml .s .__ __ __ T ~ c kc1 no

_ so .4 II outo n c e -_ ,n .o) ,. .. fr.... .,n .L o n gi h .... Ii. __ _ _ _ _S. L., : Long H.T__ _ R.T. Elfinrncy GIrTh H.T.' R.T. No. of Coo,.._(, r ___ ___,_,______

TOItI r'evoo-bl. bo.gs us ed Other (.s ttr-zisa 7. J ackc.r Closo,,.:t~srb 5* ~s4b. f.i nj~AifUblo.i.ri.o .h~ic h eI Charpy iia. ct f t-lb S. Oruvign P'. .re 0 e 1250 p __i _e _ 75 F at temp. of _F Items ad 10 to be co .splcied foe cube sectioos 1~. I-u8e csho-,; S noiof. Wt~oOziss________ Os ni ________ .e.- 51. Acta__________(tine blI.... N..) 3*of0~*ffi.I

d. isf)Floating.

4mer-ihl -Di.. "_icknexoi

n. Artachmin

ýc i --l4 I i nC .(0 5> co nplrr d ior inner cham bers o t aclicrc d ve s e- l .or c o f heat excnange rs .I 1. Sh a ll a a rial ___41 1 T .S .__ _ _ T hick n e st ._-.n .S I lo s n c e __.n .O ... i r.. ..n .L eNs .'. .__ _ an....'.,: Lang Ff. T.'-- R.f. r.fi iamcy -G irib , _, _ .' T .-.o .Hd C o , , ., 3.He ad .'A .4aeri __ T .S. S. ".l .a_ r.s.-0-Do. Crio. reds _____I _____ _31 _ ________________ill

F ,5 Zc .0nn O d ,I -il , c a aro_ i nnihi ci. Notrlesa?..c.,is.

loiSi..0 o. cad is .a,. Sn Osisi,.. H.-s &ii.cai.O* fStiof -4tff~C \on _____._ c-t s,_____ ..eu n ______________________)poans: an hoe. ho._________ ic -_______ ..) baIN __________________________________ ian.dc! 'o.__________ -aon__________ sarsf II 1' 'g-g ,I -.* ..-:'1 ým,1 0 i1. REPORT NO. P0059-011 I FOR, .PT CERTIFICATE HOLDERIS' DATA REPORT FOR PART AaND "PMURTENA,'CES" / .3f -(As required by Lhe Provion A' the ASME Code Rul,3. Secuon Ill. Ois. I L General Electric CorDany, Casrle Ra,rnQ UR. , Wilmnqton, 'I.C.(bl)iz-d t General. Electric Company. San Joae, California (YEBG)I l'lI "mt aml ,izlI m"ýW ,Id C-I- "A rlil i -4l .¢* 'it 7.. Idauficom--Certlncs.- floidetr'3 Se1 W .o. cPaxt A51i 3 ,"N?! 5.d ._0. L. 04~ Ca..,ýced Accoý,iing m DiaigNo 6~3GO ing ngPr-pae~d bYy (bý Of pýtt Control Rod Drive, zodel ;JRDBI44DGGO01 N207 (C) ApkWbim A& Cod w- S~cEoa .Add..d75.a-...= c.7l CI 1361-2 a.. 1 T. Cap 16639274PT (167A2343) SA182 -F316 3/8 thick x 1 1/16 OD 2. Indicatcr Pippe .. 6 .93.?-SA312-TP315 3/4 sch 40-seamless pipe 0.113 t:all thickness 1.065 max. dia.3. Plun 159AI176PI SA182-F304 1/4 thick : 0.812 0D 4. Flange (719E474).SA132-F2C4 j.37 thick x 9 513 O0 neck I I/1/ thick x 5.0 0D 2.375 10 S. 3ase 137C5311P1 XN-19 ASIE SA479 3.0 OD x .384 ID 6. Ring Flance 11485122P2 SA182-F304 I" thick x 5.0 00 x 1.7S [0 7. Cap Scre'T 117C4516P2 SA193-ý6 5 ea. 712 dia. on 4 1/8 tolt circle 8. Pluq 17EA7?61PI SA 13 -) 0 3 a 0.33 týhcx x 1.307 dia.PSOYPIC2 CON:TROL ROD DR!R/E OWG -768ES34'. .u LJ7Rc924?1.Ul-L9 SA479 x).:. JIG 67 REPORT NO. P0059-Oil FOR-'%4 --Z -NI'T CERTIFICATE HOWLDERS DAT.N R.E.J'¶T FOR `4tJCLEASR ?PRT AND) AP71-JRINANCES 2 of, 31 As rt-quired by the Pmnivuon of ilic NSN4E Code Rukcs. Scti.jun Ill. Div.I 1. (S).yýbrW by Gftneral Electric Ccimpaov, CZastla qalln Rd. , WJilmingtcon, A.C.(b) Uajcul a General F-lectric Coirpau7, San Jo~a, C.111for-mia (L;EDG)-4&*r as C cN mý& ft,s r-w -,-1.-2. dc2Uc0Cert1csz.. Ho1dw, 3awo of5 0w N..e B4 N .o- ero (a) sCtterverw Acodn to Nwp o 76SZ534G001 Dr-.i pma~z by___D. ___. ____________(b) Oe'0cri- 04 Ps IAWrd Control Rond Drive, %lade-1 07RDBl44D"-01 A~~iabAECdet~~l1E~ti.1974 W'75 1361-2 3 (c) A*lc~l W dtSciail dto kddwaz~d a _mw__ CasiNo. -cmaa 3.~Standard part z~or uz. with R~accor. H-ydrostAtic-a-1l tasted at 1820 ?ni.(Ot. 4-tn'U.' j~ *.,.. Cs .hb- -*Total number of Zh"LeS -2 VR cervifYtyhactho rx~~tamd. in thi* nzscsr-tsd thjS ~TVS"I parc oe QVV 9 rtE1ýCV iC deCind in tbe C-ode can-t* the rules of --acu iio of-, rtS4~E=Co S~a'1ccrio LL CITho ap~icawo~ D.eita" Specinlrammo noqd Suvft R&POel amt not the gooxzibflly ot Lb* N4P? Cenrlrczis tlnltr tor at- #.n ixr cO ..t Cm--1-~i Ho~des Wa ~tes is rc,ýWw sjN ftarms a cprl Deszg, Spaecd1cacom and Stress Repart J the apiIrcozzem 5t* tLcjuded 10 L110 oe7m~noctt De&ak Stpertftc2aca and SO'tsS R&-pcrt.Dam 7/23 19 81 -nx GzI 4zD;--j TT ~I- LL5 I Ccmfiz.,. f ~ EpI.S September 15, L981 Caico. N._________ CER1IIC-AT!01OF OWEiGN FUR ,PURTENANCE (wkers aPPliC26le) G~,~Pf-~1l--ACasclea ay-ri Rd.,W -Lal ngton,'. iC.2-'k5336, Rev. 2-Z2~-1912' Rev. 2 r -sa.ýfcLo.c dt,3. N. Sr-dhar EgScC-1-i-z R __4____~et .f.. r~~ a~tfl.,~~__ __ ___ ___ __ ___ __ ___ __Prof. Esg. S- ______I h~ ~ ~din~~k~dCEIflFICATE OF i--HOP INSPECTION &n/o~,rt Po-wc , roTr arin Jeoar~rinc of "baro of S:.ate of Northa Caroliina ---'Pe-Lr.d the P*n of a P-x-t r"ae ieicr ind this urtw Do ca aon 7 '23 4-L ad SUtat Lha to the bent uem tnj oo edge&nd be4Ief. the '4PT Cl~rt~lcuwt ftk~d,- N& consnU~ed thuj tarl In aceardane, w~th the ASJE Code Section ill_3-f Signing this certifcact. Qejichw the -cp ~o hnis c'oqploye Mkes -Y' -aancar. exprelawA ar Ltlie-d. co~occr-Ing the Part 'Ieeribed I% this. P-vrtial Dam~ Report. Furthermore. o~tti1er the Inji~ector nor 'its ta iu AAfti b>c liable in MY casnee !or 07 pwrýoo. iniuy or pnopeexy d4age. at

Iasi of any kind ui~ng to,.itch thu2 ixp-tiorz.

Dae7/23 .981

JPW I~OI-Lo~ 78*0i ~ ~ ~ -~ *09OHIO)L~~~~~Oflhf~~~~~~I N.' Y'i~tfs 'Csrd r,,weC-~ Z t to 01 68
-._ -., loma 4-8 Inl. -b. c-91-j I*o t, -W u tC...l f -A. 4qt-1t: 4.-r -1r _ ___TýS.- 1cj ,rcsI C+ r.ao,_H.. T.C. o. -o .o- Ii...,.. .G. H .. 1.j ) mce --." ......._______1_____

n.. _____ .__.____ l I.ILIII ___________ No. ot Cao.se~l _ t_____1_1_______________ IT..b-,-i.. .-s.1 Th'.... .k. ..... A".4 An,,t. M.Jts.. OIsi. o.-.-C ot tf tvimoa.ble*. bolts aId Othe_ f__ _ _ _ _ _ Oi Itd... L. .Nso ... x .- *j.. 3j.,.. .. I rr cl. *k*4.Ct 7 .k.+ rc CIO.-.+1250 575 .eOF 1d 9.c IvOF:u.. zsr.npl,t, e pp. __________________ a _________________ ttmg. of ___________ Irt a 9 -d tO to be co~pLccrd fte whbe .,cjiott.9. Tb- Sh4s. Stz neriy. Wm4a.,,i.J________ Dis ________ Thickhsn.,- i.. Atrmchrý-n __________,_ _ T,<h c',0.r"['_____________ O.'4. ... .n. -,hccknvss______: ',.. Nu.tnb__ Typow.crns I-14U tnct. co w co-platr n od Lr in nner- chnbr of .acketeld s srfl,. a, ch-'netl oi he., nnchancqw.. (1* 'J scmon { Cz nmoes s-oin' s, o n a L o n g _H .T .' R .T .E lf i c s, n < _G _ir _ _ _ _ _._ R.T. "No. ,f Corn..,a 4.eia ____________ T.5.ll _____________ .s+rr lhA______________ TB.t P 3 top ?rT-g, Zes D+,+n >,,ininr: __ _ __ _ _ __ _ __ _ _ ,,s ti ___________ F ree1l-n,. f _________

F.,.J :,3] S.:7* .e c: qC -~n.,ntC c ti -c4enfýcc~i~Q in sS.

REPORT NO. P0059-011 W Iliti-mv: III ý I 1 1 11 1 111,11, 1 a l I I I I 0 2er ' orj ,~FORMI 4-2 N"T CERTIFICATE HOLDERS' DATA REPORT FOR NCLEAR PRT .NO N ui'tRrk.NA.N(L2- .-s requircd by the Pro n o w h .% SM, adh" Hule. ection IMII. f)x!. <- Mnnufoc:'c-by General Electric Comoanv. Castle Ravne Rd., W[[imnoon-N'4.C..H.., ..nddt, of .PTk nu.lol. HAdI.-(b) Mknujcrtired General Electric Company, San Jose. California (NEBG)fName n an ddr-., N C.it"ncase Hdc, t l of eiter~pl¢(, ri.,j('nucl earetlpwn ft)2-Holdec.sSerial No. o(P~art A5510 Na.,'l Bd. No.D. L. Peteraon (a) According to Drawing No. Dramnt Prepared by D (b) Description of Pa&n lapcaed Control Rod Drive, Model 07PflB144DG001 N207 (c) Applicable ASMECodet Scczion I1. Edition 1974 Addendadse W'75 .oeNo. 1361-2 Class I , Cap 166B9274P1 (167A2343) SA182 -F316 3/8 thick x 1 1/16 OD 2. Indicator Pipe 166B9313P1 SA312-TP316 3/4 sch 40-seamless pipe 0.1)3 thickness 1.065 max. dia.3. Pluo 159AI176P1 SA132-F304 1/4 thick x 0.812 OD 4. Flanqe 91SD610P1 (71E474)54A12-F234 3.37 thick x 9 5/8 0D neck 1 1/16 thick x 5.0 00 2.375 10 5. ase 137C521'P1 XM-19 ASNIE S479 3.9 0 x .a84 ID 6. Ring Flange 114B5122P2 SA132-F304 I" thick x S.0 00 x 1.7S 10 7. Cip Screw 117C4516P2 SAi93-36 6 ea. 1/2 oia. on 4 1/8 bolc circle 8. Plug 175A7361PI SA182-F304 0.33 thick x 1.307 din.CUrTP.0L ROD OP U/0111G -766E5E33'. ut 137C593,4PL 53:cM-19 SA479 1.30 rhick -- 2.62 eila.69 REPORT NO. P0059-011 FORM~-Z>~? CEFlfCATF I-1LDE.RS-DATA RE2-ORT FOR Y1,CLE.AR VART AND Akf'MRTENANCE.S. 2- c7F-~31 As require-d by die h-rovision of dhie .SME C_,,e Rules. Setitn Ill- Div.I General Ejeceric Company, Castle Ra ne Rd. Wilmington, NI.C.b y. ~ ~ o F r o f ..H 4 i r (b) 4ýfce fo General Electric Company, San Jose, California (NIEBG)7- d d c d -e O i a a a d r s s ~ j ~ A 4 S 0 2 N W 8 dl ~ .N o ._ _ _ _ _ _ _ _ _ _ _ _ _S768E,534,001 D* -L. Pcrson Ib) OvcripeOG t~Control Rod Drive. Xodel //7RDBl4L4DGOO1 (b)~~~ ~ ~ ~ ~ Dicitno PnIspce 1361-2 1.(c) App Iiciblit ASMECode: SectionfflEdrito I 7" ,ca~ e W 7 ~ .eNo. _ _ __ _Cla~ss_ _ _ _ _Standard part for use vrith P.Eactor. Rydroscaticaly ete a 82 pi 3.I. R~v~$i caml tested. aos 1820s psi.r ocal. number of sheets -2 Ire ce."f-y that the stiiqix eo s =*do in Lhi s e-oe a~evre -c co d diii vessel part at *pp t'n~artc as tief!.ed in die Code con-fornia to the %,lers o4 coonsjecion of the A-SUE Cee Stcdoo WI.(Tht ssPdlrnbie Deitgn 3PecillCEJ00e and Sb-ems Report are not5 the rresponsibillt-Y of the SE'T CertUlt-sts Holder for DiaxrtL ANr .NPT Certi!-ic2le HMaker for appuae oc-cs ti reaponrable for furnslubns a ieparuie DeýV Spccificaoan ma~d Stres% Iepouif tthe appurtenance 1 not Inclded In the cvronporse Des~gn Specineaicno anid SO-eu Reporti 7123 1931 Si Gd IE, NUE1D-WMfl-QA By _ _ __ _ _ __ _ __d_ _ _Qw'T Cari~eaw Mw oNP r-1 5 Cer if ce e f ud ori at co E~ p es S ep tem b er 1 5. 198 1 C -ificare of ?L s o ~ o M ._ __ _ _ _ _ _ _ _CEWIlFICAllnG4 OF D"~G.N FORA'PPURTENANCE (whei wpplicuble) S GE, NEPD-;Rfl-QA, Castla Ray-ne .1d., il.7dngtou.

N.C.Sn~us .o i~ii rep rt oo lie (,E, EC? -"Mf-]A , Castle H{ay-ne Rd. , '4Lt3-iAng ton, NI.C .22-\4912, Rev. 2 Desigo * ,,nri e 3. N. r'idhar Prof. E.x. S,at -C'?I if Rcs.N'o.;3_3 4 3 CERTnIiCATE OF SHOP INSPEC-nON

1. Lhc usnde-r~igned, holding a valid coeamtsmori 2.a-,ir ýy the 4acioniii Loasd of Boiler -nd Pre.,intrw Ve,i3 tri Inpec ors3'-d/g h Sat a sosn e f orth Car~l n Dn spoyd ~ epartment or Labor~f tat of N or h C rol na avc itispec- ed the part of a peei~urc vemsil de-scribed in thii* ~ ~~ ~ ~ ~ ~~7/2 3 98 o j 55 rn o a e e a&M h-cile, the NPT Cernfca~w Holder hisa cortszr-ucted this5 "rt In accocoance otiS dhe AS?4 Code Section Ill.By 2igning chin certificate.

ceisher die Inspector noar his employer rnlr any warrinry, espressrd ar imspt~e-d. cnncec-.Inrg die oarst delcs-ibed in this PisextttI Data Report. Fuart~herm~ore. neither die linspector noar hsis ermoloyce 3 l ', liable in any wranoer for ary Per sonl intory or properry damage or a loss of any kindl arisng trom o CooO5eitrd

illi t s iaspe-c ruon.Date .~ 7P .7 /2 3 9 8 1-~ ' 7 ~ -c 2 7 .-N.C. 2. , A .WC 17 6 6 , G H 1 O CoAnt j n 70 FORMI N-2 (6.c-u lhtniir 4--8 [np. t ob. coapliir.J I o* Sn'il al .c ,t li. 1.ieu if ,c,.cJ .-iie I .h --h elI s u i llrs.1i Il: iir,4 I -T.S._ ckn, sc.. sit. S. ,l,,,i,,.

n. fI. -in. Licgntb. .a, __4. S-c.t~v: Lct, _.T. R."_. Eifl.cccy.

G i r _h_ _._._ , __T .N o .o f C o w l -e*Laosl...e. Cevts £ll~tlittli Cei.va1"l H l Pri.4 :13,4.1 i* Pry,...)To"I. 0i0~. *S411) Thillisl... R54Jc*<L fllsOluJ+ R..+ Apiy Arnd). R.iJlul5 D slm~i..l (Cii.. -4 4Coo.i]# rgognavblo

s. cis~d .....__________________

Oi~hct fsmr+an 6 nl Lk ,- ClosinI:.. IOsnrcbv. soatls. sic. bol ts t dit~lli l. s bOthir. Jesob ,sttlsly Dec? Weighc a. D.Iii" p ______lr_.. __ Pi _ _ _ _ comp. of OF it"Is 9 1O to b4o c-pivhtl for -ube "cc.o*Tb. S*i- en, S"is-iio .4. Dis- Thick____ _ .. Iktm i Ft rrt.. b.. w4 _. 0 Ty _(,env.. beft.)4: ( mr'l 11--4 nclC. to bq coc tlrc (o~r antl,f clnampb-ert'l ,,1. v.c]ssv 5. or dianortis z f ii ll be i lczcbnl gat.." 1- 1 it. 5+h.1l: n40cri, _ _ _ T.5._ _ Thicluses _--. -llo m.,cc _ n. Di 2. JiL ,fn. Ltcdn i-- ._.+g______r__,___ .T.' R. r. NO. ,i Cownaes%inilwiie Ltt,outclt ' u uciet -iaol itct~ci 'ii. 3)05 iv i-ii-.t ia'. i .iir-ri T. i.Drop hr tC iiapv Ilii JCi _________ ti-lb i~. :rrct >4-tO. -o cl citcttttetd .'0 all -usieit31 c~ ," io: Oiul+iOlt, 0,0 ,{:. '.aidze s:-:J; ,ut i. D ..cIn ee .c u i ).. T ,* iii-u i i" 4 ..Sr**pe n qn.: H .-in <hOte V. '. _ _ _ _ c '__ ___ __,, S6.T ,c- it. "o. _,_ .- L .ii ,,iu* .jvoi: it ______ Li _____ .______ cc,______ t~~cS ~ 4-:* : -,o ,, .)- .x-"4 - REPORT NO. P0059-011 FoR'l N-2 Nv'r C'ER-171ICATE HOLMER2, DATA RlU)t)RT WflH NII LE%- 1'.H r \41) \1i'1' H il N Ntl A5 rcqurrcd I, :Sc Pr' c..... In m c \S .I. -I R Ic, -i.n i I, 1. (a) Manula~ctred by General El1ýzI~tc Comnpan';, Castle~ Hayne Rd. , 4ilmington , IN-m -fd addin,J NFT I -Ult.21 H-Ader, (b) .MmnýaIIcruarcd fo General Electric Company, San Jose, California (NEBC _____INm.. ar.] dd-r Ij 4 C "Inll.a, H,4Cr If- 'rPII,,M nu .r -n p-Ml 2. ldenUIlcxtdo-CerteflCate Ifoider'3 Ser1ia No. of N~r A4502_ _ .N,.r i d. -q..______________(a) co~nstructed Accordin-co Drrawig No. 768 Pr4Grfl1 DrbyaD. L. Peterson (b) Decrciption of Par Inpce Control Rod Drive, M!odel t#7RDB144DG0Ol N207 (C) Applicable ASME Code; S-ection, 111, Edfirion 1974 1 Addendsdate __HL__- Cale No. 1361-2 clanss K Cap 166B9274PI (167A2343) SA182 -F316 3/8 thick x 1 1/16 00 2. Indicator Pipe 15639313P1 SA312-TP315 3/4 sch 40-seamless pipe 0.1)3 wall thickness 1.065 max. dia.3. Pluq 159A1I17PI SAI32-F30d i/4 thick x 0.812 0D 4. Flange 9190610P] (719E474)SAl 82-FJC4 3.37 th-ick .( 9 S/8 00 neck I 1/16 thick x 3.30 00 2.875 10 5. 3ase ]37C5311PI 1- 1 9 75:.3E SA479 3.0 00 x .884 f0 6. Ping Flange 11485122P2 SA182-F304 P" thick x 5.0 00 x i.7S 10 7. C3p Screw 117C4516P2 SA 93-B6 6 ea. 1/2 dii .on 4 1/8 bolc circle 8. Plug 171]A7361PI SA132-F304 0.38 thicK x 1.307 dia.COCTROL ROD r!RVI3 MIG -1303'5341:21-19 SA479 1.30 thick x 2.62 dia..r 71 REPORT NO. P0059-011 RJR 0* I-i I FopiNa f" l CEATME CATE HOLDERS' DATA RE-PORT FOR WUCLEAR PAkRT AND A? JRTENALNCES' .2 V1 )/ 31 As rccquircA by the Proytison of the %.SME Co~de RulIc-. Scction MI. Div. I L ~-~"~'~" General Electric Company, Castle .ayne Rd., Wilmington, '4.C.General F-laccric Comrpany, Sarx Jose, Californis ('IEBG)Ima.aew "d r-of C."13..0 Kalie fur .4. 4" wt.4r a ss ii )L. Ide ~c=lmCetlc&I a~dda iSr INo. of Pan A5472 Nmaet E- mo.(a) C~o-aml~cs Acceedleg Drarmig No.______________ Dramiag Prmpaa.d by ) L atro ( b) D a c ri ti ia of a n Emi~ c m d C o n cr o l R od D r i v e , M1 od il L )7 R D B 1 4 ,4 D G O0 1 Y 17W751361-Z 1 (clj AppLica AMECd-ScmlEii Add..aaal .*Csi NIoc ~-za____3. ~maknzStandard part for uze waith~ R.accor. RydrostaticaLl~y cxsted ac 1320 pai.STocal numbnr of ihl -2 Yq ca,-tiriy diet tim sýwm-s toe Chiotzrr = t "Vcorrect maid Clais Vq2e( pal pac So)'*c a~uvaamt darfimel in, thc Code coo..toms; to tba rules ad cnam-ictiou of dia SA szcin. [I.i Tb appihm~l Deirsiiz 3vracttcmU~ xod Staw Report aii not the m-,iponalbiits of the 'IPT CurtlaMez Holdettr fWPerml Ain WT Ceritf-icmo H4_L&!r ror is-~e.apq~ r'--_-MLi fr ft-r 4 ,.nac Diu Sac=11al zed~ S&wwim R~cron 'r tb4 &OPalmizce rzt 1,ýýndrdd mn the copixwirat De4+/-m Spei~t&1do =d SM" '00(0.7/23, ilk G3. ~........ ...I I:.0.*Carr-Xca* of Anzatzatwll EzPirm. SEpt ermer IS 2 j.. Cinczmae 'lAkoisiem go. V__ N___11____1 CE"IIFICAMMG OF~ 0MQNG FOR APPURTENANCE (w~en apicablo)GZ, W1-1--OA CnraEane94, h iL~tn. N.C.*-l Sooa nlvsis mpvos ý, Me A ED~D- C~ascle Fýiynq Rd. , ;i~rmiagcon, N-C.22A4912, Rev. 2~ ,r~tine ~Sij ~ 3. S. Sr~dh3ar p~I a.wC-1 i+/- Reý.oý-3 4 5 3c~ea anb~.i ~-pt c~ifjc~ ~~. N Sri~~ Po13143~CERIMFICATE OF 5HOP !NSPECTON lo te ar vp. ewofNort::a Cablna, DPoarrxnsn cf Laboc st~ate Of N1orzh carcilia have ete cht pact of a pi-tsaerv ,-exel de,sczihlad in chits ftrnsd DaaRt~mo 71/23 ___ 1. an stt hit n ~nu ykwem Wd1 bel1cf. Lhe NP? CertItlcACe HGR4ef bas cotaamct" hsl Pmit

In Accurdznca with 1k. ASM4E Cad*e Socclao IU.BY. lijll Chi$ Cgr-ufkAlM, &Rifht tb* di. epe-o oat his etpo7.-f mMal -Y wVn-ny, -2prir3s4ýi c it1 ecunc.In 4 the Dart de~iCrlbad Is thll 1'Br~tal Oakta teaar-t. rurthertmare.

neither the IensoectaCma h 1ts ~implo~Iye 1baJI So liable in =Y matnlto-r lotr- pevionl injury or propeMt *iacsgw g a lss oaf LaLy kind ariisng Iroo. oe conaccre os e 7123 19 81 ~( 7 & V7 lI.................................(I <J*xnE00AUJryCao-uý C10Wf 1 Oft=___ __ __m 72 N-2 (b.rik lrema 4--S :-n .'. 6. co lsttd for sitogie I.,t! -Ache'. 4 .terd .e ucrs. or l' .6 ii h tchI' a e..4. .Sh-11: J lr;lr. .--¢I ' i -n. Io*i t _ .] ._ ( __ .Le $h .z..w,. .F,.T giiici-nCy Girth H.C. ILnT. No. o, Co ats 6. He"I at (aI) .%rJ of_____ Th .-(h. .m- tri.T1.e .Ed)(b)If remo-able. brolla gsxd _________________________O ir tsastts-an 7 Jacket Closý.( D*5141t.. 55l s.l .4~*e b. Il. ml. £f git .!1 6.4tdo J....sbe -r tSl.Stc DNo? gVetght Osarpy !&pcc fz-ib} Oi1250 me 575 U p ot _7.F a r -t* __of or It.,tt 9 n-d 10 to 64 CoýPittttd f~f csbe Sýtectcd 9. T.hq Sheettz ODi.___ _ fhicko<e-s .Allh~asot (I. ft sv... Md.) ~ 5.ot*~lod.~Ot~ 0O. To-b..: .'.cri~ _ _ O.D. -l. a _ _ .. __be _ _ Tyv._[Emma I t-14 incl. to be coeolreod for inact chami>ar of jactk eted -rst*. oa ch netLs of hitoas 1.JocairtM Collodion_1. _ _ a il.____.-_____e.t. 4 C0.. .. TIaAlloanceL_ _ --_in., .-i ________________ s ___________

...________._-_.___

-..._____ ......n+ .. ., .,.. fs a. ...t.. 2, .... no. .... .. ... JI... *.. C...._'in R.T a. 44 ma ol dc 13. H.o 9.bs: ro. coss _ _ _ _rIA-- -A~ k"" i. fn so~r S tt , o'tF o .',I _... c _ _ te.tc:CM .0i "o i*,, !or .1 'o -I, O- e .Dtt, sot.X,. \alel: Ov~7o. .....r.Op -1: 1if ohto.- U. _______~ r_______ s 50 Iftdc. o.-_______ t e_______ Loc t 3. :oor: 3. ~ L.slt-t A______)eer5"~- '. .-I REPORT NO. P0059-011 5hee: _, at 2 5 t3(FORM. N-.? ""P CERTIFICATE HOLDERS' DATA REPOtRT FOR NUCLEAR P'ART %~ND %PP1.RTE-NA.Nti )S-As ircquired by the PrO~sswn 'A ýh \SNIL RuiliRuV .Sc:ýriw Ill. 0,'.(*. b y, Gen zal El~zc Cmpd-i~y, Castle Hi'avne Rd. , tWilringtcn, ..C.(b) 44uame foK General. Electric Company, San Jose, California (NEBIG)'N.4- Pod .ddrft,)N CwstfC PER Ho~d~r fo. orJ-Plt nCeIt ,or opo..nl 2- ldertifllC2Uo-Ctrt~flcAte Holder's Serial No. o( Part A54 72 N a:1 Bd. N~o. ______________(A) Constructed Accordinig o Mowin No. Z68F534GQ01 Drawinfg Prcpareed hy D. L. Peterson (b) Decipit of Psjn It Control Rod Drive, Nodel #7RDBl44DG00l N 207 (c) Applicable ASME Code: Section Ul,Edition .Addenda date .C.,,.'io. _I1~ C... 1.1. Cap 166B9274P] (167A2343) SA182 -F316 3/8 thick x 1 1/16 OD 2. [ndlcator Pipe 166S9313P] SA31Z-TP316 3/4 sch 40-seamless pipe 3. Plug 159A1176P] SA182-F304 1/4 thick x 0.812 OD 4. Flange 9190610P1 (719E474) 4 3.37 thick x 9 5/8 00.... I ' ...... x .0 M 2.875 [0 B. ase 117C5311P! XM-19 ASIEý SA479 3.0 00 x .A84 10 6. Ring Flange 11405122P2 SAI82-F304 1" thick x 5.0 00 x 10 7. Cip Scre'w 117C4516P2 SA1 93-86 8. Plug 175A7961P1 SA132-F304 0.38 thicx x 1.307 dia.I.IL --~N C0TITRL ROD DR!VIE DWIG -7E&3E534 9.ft: Lj7C5q934?L >CM-49 SA479 o"6 1.30 thick x 2.6U dita.73 REPORT NO. P0059-011 PORM N-2, MT CERITrF7CATZE OLDERS' DATA F-F-7RT FOR fCL-PATAND-Zrcertd byy LhP ovon of be A52ME Ccod Rulm S czoa LU. Div.L. G.enez-31 F-lactrlc Coinany, Ca3SI!_jay-n RdI., ;;i1=irngtc, I.C.(b) C ent~ral Electric Compan7, San Jose, Callfornf-a (N.EZG)(2(o-mq L-d dd-, Cpý,-A PMb WLtW fto..Wt Vwci..2. WQ I~t~I~ti'~ H~d~tI s~tiai 1\5122 ~ N.__________(a) Cz-awcract-Ar-L--c~ii t* D~a-n No 7S53 4GWCOm nS ~pxi 7 D. L. Fatarson 0b) Cantrol Roa1 Dri~'e, llxdia #7?.fDB144DrC001 'W Cid: acio W L V ;'75 L361-Z (c) Aqq1I-cxblc &E oiiriU. dill. C mo______11.XAMMAMSumxLrd part for t=Q vi~tl Raaccor. Uydroitatlca217 cm~ctsd at 1820 pal.m__*Total -m;~rber o-f sheets -2 fc ~ to Ch [bsacaaci=o

e A.Ea4Ez:" S-eIo. MU.kn*a kloWtr f~or m' mp~2 nromu~, frcr wmiihio a see-u-zi DkrV2 Sp-=ffir-3nM Sunn Rc~o-z U' L. ttv m2~~fC mot 1flzfudzd LIn [hbs~ Dt-slz spectccztti Cnd iSL-uRPM 2/22~ 83 r.Z I j77F -pa 1 ~ .JT ~-U C-EH91FIGATION OF DE5IGN FOR APURTENA0NCE

ýwin ppIjcmbl)Dt0 p **mf*L=c 450a GENERAL-ELECT-RIC. CO. .SAN JOSE, C-ALtFORNI-A 22A556,~v. ~ flRA~ELEC-TRIC CO., SAN JOSE, CALIFORNIA 22A4912, Rn-v. 2 u;~Jy~* r-pet 1ff~J B. N4. Srid]zr PO ct ~i 34 CtEIMflCkTE OF. 910P HMSPEC71ON

1. Cho c 'cZ a BJi 'm<tio iz40tz bY LLI ý40CO7221 BO.gId Of BOi!Cr ..n PfeS7-'XU

' -1743" aD/VOf th'W State n c Of lorth Caro!+/-nLa and L7DeDonra---nt of Labor of St~a~e c!-r-rth r3rcyum ?imv' ivitd &, ps" -a a pr-su- rV2S4 desrib-cd ýu ch-i$ball ". litbla. in wy ceacawt fo-r any paremio- lacux-y or pro2-rm dammctgv or a toas of ory kitnd A-.AIQZ tzc= cc CýMat:cz" widxch Chi jot sp-con 2/22 93 Dat 19 G. 723JA.WC17Th6, OHIO C.Z= DZ on** (fl71 ~~Thi form (ELCGd0)mirVt4~ .ob~n,frcd ttflnfl O, Cror De-zr- ASNI.\1 3-.46 E. 4701 St.. Nt... York..N.Y. 012U1 74 Itankg 4-4 i EZd "'C dc9p~v'rc-l I4ct *!M,!I* ?ieA) Vt TSs. jsc-ýe~ 62. jjbjCC:d yea"S-el CW ShQiljJ Of 11412 W1Ch=WrS.4. sel: ~.~d _ ,S,_____Thne~~.Alloa cw..ia. Dim.ft.-.sn. k1,~hzttja Sa. o?'_______ IL T. ________ f.' oE ecy.. _______.Hcaamr (a) 4MwJ _______ .3 -a * (bj ~4zýaiiJ_____ T.S.______ C?09. ud.v~) ThL~k.~e E-e" aa.ý at.Cj Apox A~jtr usd1.. DtA=Vt*V (Cýw.(a__ __ _ ____ ___ _ _ ___ __ __(6) _______ _______ _____ ________ _________________ 8- pa ta~ 575__________________C~ axgienin.* I.re~r!2 9 r-nd 103 t~ ýN C'ZPt, ý !oW %Z!t, =CiO a 9. Tmb-a ta-ht~vý SUa--j' ' .I Ol._______T hoo..mga in. Atzmchni-10. .0. ...s iz. Thicknoss -.- Ty-bi ________Irte=3 11-14 inCf. TO bý CCPc tl~d f~fi n--rr Cftýý~ Gi .&ZrC~rd mae~- chdamn-217 a! hcec c-cfi p .ý-----. ---qciao~* ~ ~ ~ ~ ~ ~ ~ l- c l r.~lI Dir-6 _____ -TS i a-o-ac L e-3... 05...o ft L 2_ Soýo Losx _ _ _ _ _ _ .T _ _ _ _ _ _ R.T. __ _ _ _ _ _Elfjcioc-,.

r._____FLT________

RT.______ No. 01 Cavrs 0). Hwod .~ Vct-fjil b__ _ __ _ _ _ 1S (b &Z i __ __ _ __ _ .-S..L_ I. Thu. koo 044..i- oi o. Av.. A~mL. .d1jo DL.ý cc ' r ý(ts) Top.* --~ _____ ___ ___ ______If rZC~'C SbQdC.V EIko()_________d (C) ________ lhnr 11izCqilt ChZ 3rpy IrnpsCI it,1b 14. Dc-g p .r<ZA__________________ wat U___________ _ OF c ceup, O hesbe-1oý to b~e comaplec,-' foi, all vziscls wF~cta spplIcable.

15. S-iery Vail'r Oujticts Numbj,nr_______

_________ __________________________ t6. Nozzles: O~tI.. 0:_~I~oo, Oo.o a Typ i~.t4 Tl~ooUaaiH o 17. laspvcrici'Ln hI-s NO._ ___- -______L.co ___Optcn~in : H .'o-_____ ~ _ _ _ __Lo~ oicn _____Z.Sr49paoro( oi Lc';s 0!her_ Alc d REPORT NO. P0059-011 Sheet 2 of 2 27oU FR PTCERT!FICATE ?1OLDERS' DATA REPORT FOR NUCLFAR PART AND APURTNAs'CL17O 3 A5 rcuired by thc Provision of the ASNME Clc~Sco i.Dv.(a)Wnftedb General Electric Compnny, Castle Bayrne Rd., Wilaington, N.C.(6) 14anfacufStlMd ta Careral Eliectric Company, Ssn Jone, Clfri FG-4 & 4dg, ý14 NC.,Oflc t. HL4 ar t-. I,'o~- ~~2.Idenan.tUon-CertIflc~te Htdcet' Sefrida No. o( 'airt A5 12 2 a t'I Bd. N o.____________(a) Ccanstructtd Aco-Ia to D:auiog No. E52D1by. D.'L.S Prpaied b Mb Dscrption of Pan~c~w Control1 R~od Drive. Model #7PDB1.44DGO01 N 207 (c) Applicable AW~E Codc: Sectk-j 111, Edto -ý- AddcodadAze. -Case No.161Cla1

1. Cao 166B9274P1 (167A2343)

SA182 -F316 3/8 thick x 1 1/16 OD 2. IndIcator Pipe 166B93i3P] SA312-TP316 3/4 sch 40..-seamless pipe 0.113 tall 1.065 max. dia.3. Pluq 159Ail176NP SAI82-F304 1/4 thick x 0.812 00 4. Flange 9190610P1 (719E474)..SA182-F03ot 3.37 thick x 9 .5/) 00.neck I 1/16 thick x 5.0 0D 2.875 ID III 5, -5 Base 137C5311P1 XM-i 9 AS.IE SA479: 3.0 0D x .884 I1 6. Ring Flange 11495122P2 SAj82-F304 1" thick x 5.0 0D x 1.75 ID 7. Cap Screw 117C-516P2 , SAl93-36: 6 ea. 1/2 dia. on 4 1/8 bolt circle 8. Plug 175A7S61P1 SA182-F304 .0.38 thick x 1.307 dia.CON~TROL ROD DRIVE MIG -7613E534 9. N~ut 137CS934P1I*.~ X%,-19 SA479 1. 30 thtcL x 2 .62 dla.-75 REPORT NO. P0059-011-- 2 29OF3 FOAM 4N-Z NfPT CF-RT-fCATE rIOLDERs' DATA REPORT FOR NUCLEAR PART AND APPURTFNANCES' A:; required by' the Provision of thc ASNIE Code Rules. Section 111, Div-1. (a) N--cw. Ibq General E-lectric Comrpany, Castle Rlayne Rd., Wilm-ltgton, N.C.(b)Maraac~td orC6EZteal neectrlc Cowpafiy, Sea Jose, Califor-nia (NEBG)2-dnictja-e-fe~ Holders serial r~.o a A4 531 -Noe Bd_ No.____________ 768E534C-001D.L Q raa (b) Decip-o of Pu npc Control Rod Drive, Model l#7RDBl44DG00l (c7 974 w75 C.N 1361-21 ()Applicab.2A-SME CodierSection III,Edition -..,, Add ndadi-ee____ _____ _________~. ~Standard part for use with Reactor. Hydrostatlca117 tested at 1320 pui.STotal number of sheets -2 Vecertfy that the scaseewuts mo~de in this repr1,t arer cororer and this 'essaeI pant oc app tensoacc as defined in the Code cor-iThe applicable DtOeatg Spevljlentuon and Stres Report 2re not the re~ponislbity o4 tse N4VT Certifcate Holder for part. An NF1 CerTi-it:2s Holder for appunciwicra is rezpomabls for Aurnish 123 a itptimste Design Specillcsuno and Stress Report if the appurterane u not Included lIn the comtorionct Deslx Specificattort and Stress tegoem)* 't'fc!!, ~ ~June 16, 1981 -.P N- 7~ 7 ___________ CERTI1FICATIN OF DESIGN FOR APPURTENANCE (whien applicable) DeosgitGE, NEPD-1 TaiD-QA, Castle Hay-ne Rd. , W4ilmington, N.C.22A-5556, Rev. 1 Stress afysia reor on file ý GE, ý D-W'ThD--QA, Caarle Hay-ne Rd. , Wilminggton, N.C.22A4912, Rav. 2 De.ign spe-cificauons. ,,rified by. B. N. Sridhar pm.EgsseCalif Reg. No~k8 3 4.5 Streas ana~lysis mport cerified b a .N. Srid~har z a~~ Cal-if Rc CERTIFICATE OF SHIOP INSPECTON 1. the L=!:!.nI;-z---------ý e b~y Lhe Niziar abidd~ 61 Guit a'd pressoxit Vessel anPeCIoes*aod/or the Scare of provin~ce of North CaroliLna arid etnploye-d b.Department of Labor of State of North Carolina have inokpecced the part of a pre.aore aesrel described in this iu 0-Oal Datas P.poti on 5/1 194 and.state that to the best o lrflkowled"t anhellef, the NPT Certijiate Holder has constructed this panrtoI accordance with the ASfAE Code Section 111.4y signing this certificate,. neither the inspectro oor his etnployer makes my warrantry. expressed or implie-d. concern..log the Dart described In this Partial Data Report. Furthermare. nithller the !rzrector nor hit -rmro'rzr shall he liable in any manner for *my petsonna injury or property damage or a loss of any kind arising from~ or connected W.ith this inspection. Dare -~ 19N-i. 723,PA.W1766, OHIO i~~( 5W II" t1007) Thit formr (EO0O401 maybeocbmined from the Ordear Camo.. ASME. 345 E. 47th Sa,.Now York. N.rY. 10017 76 ~. ~II ~ ___ TS _______ hi~o~. in All.--nc 1n. Di- -f. -i Lc gth -ft. -____ n.~.Seam- Loti________ H.T.'________ R.T. Effic~iecy GithRT. __ _ _ _ _ _No. of Cottir" I _ _ _ _ __ _ _ _6. He-.4.z (a) Maceri..i __________ -T.S. -(b) 4tr. _______ TS.&________ C.-o. C K..kj. KIlipt&.h4 CoodC.J -"I : 9*,.. 1 f. tSid t. P,-..____________-_.)_ R_ 1._ A_ A-~Cl _________(C

7. Jske _______ *tc.foW...oce6

-kl ý n. D i-nb .. &Itch? o. L n ~ j n B.Dein fes.u" 120 ti 4 7 o, Chaspy fnmpsct -ft-lb Ites ad 0 ottt u~pLeted for offoe~cI *hrccc ppcss 9.TN amber it:_____ Size__________ Dirio _______ __________________________(r~d & S -14..)RSbqMt VrImnt Flain- Mt erial. Di- o L. ..s~ Thickano..o n At4.s ht.J o ttoh Handhole, No. __________ Lorrotio. _____________________ 12.o Lca-, Othrir _________ AtoRd ___________ it! P,.t-oid Hoo-Teossd. Li1st othwf intto-J "r 1-0 een s- -111o. r coincid-r '*w.rt ho.~n .{,ollclblo. REPORT NO. P0059-011 I i O -4 N-1 ý,T CF-R&1rJCATr-i;OLDERS' DATA REPjORT FOE NUCLEAR PA-0T AN)D 2-7 0,_As rc-quir-d by the Provision of Lhe SkME Codc Rules. Sccuon Ill. Div. I I- A(,tJU,,,r b5, General Electric Company, Castle Hayna Rd., Wilmington, N.C.(b) &, ,.,d tot General Elactric Company, San Jose, California (NEBG)2. !em"Ctim-ce.lcat*., Holdtr.w me$o. o0 pa A4531 B.,4 !. No.(B) Ac.ording to DuejAg No.ý 768FP514CO01 Dr-ini Pr"&rd by D. L. Petersoi, (4 Dcri, o o Control Rod Drive, .!odel #7RiB!44DG001 N207 (c) ,Aplicb,,. sM ECo4-l~ U.Ei c --1974- .A,,,a,,.d .W4'75 C-..No.. 1361-2 ci,.. 1 1. Cap 166B9274P1 (167A2343) SA182 -F316 3/8 thick x 1 1/15 00 2. Indicator Pipe 166B9313PI SA312-TP316 3/4 sch 4 G-seamless pipe 0.113 wall thickness 1.065 max. dia.3. Plug 159A1176P1 L SA182-F304 .1/4 thick x 0.812 OD 4. Flange 9!gD610PI (719E474)* 3SA182-F304 3.37 thick x 9 5/800 neck 1 1/16 thick x 5.000 2.875 ID 5. Base 137C5311P1

XM-19 ASME SA479 3.0 00 x .884 ID 6. Ring Flange I14B5122P2 SA182-F304 I" thick x 5.0 00 x 1.75 ID 7. Cap Screw 117C4516P2 SA193-B6 6 ea. 1/2 dia. on 4 1/8 bolt circle 8. Plug 175A7961P1 SA182-F30q 0.38 thick x 1.307 dia.I ~P5OYP! 02 CONTROL ROD DRIVE DWG -768E534 9. Nut 137C5934P1 XM-19 SA479 1.30 thick x 2.62 dna.Rungs=77 REPORT NO. P0059-011 I jug 'I FOR.~ '-%Vq-PT CERT1F1CATE HOLDE2S' DATA RE?'ORT FOR. NCLEAR PV-qT A'D A-P1URTEYANCES, As i-c-qui.-Ld by the ?rt~iuon of the ASM.E Code Rulc-3. Scc tion [I. Dt'ý. I 3 t231 L- c*-. by General. Klectrtc Comoany, Ca-9~ fye~L ~L~goNC (6) %taaleeacnami t~oe Gau&ra-1 Ele.Ctrii Connan7. Saa Jose, Califormi-a

(?IFEBG)tM-aw. oad add7- G4 A4 C.,lft~ca 14t. lw f to JMI~~ Dut Coa-M--lGeRia i4obd*r I SrMs ';0- of Pan A-1054 -.4-ei a,-, m.-(4 Camtwctw Accoediall ca Drwwing ý1_763E534GOO1 Dra-ing Prepared bn D. L. Contro-L Rod DriLve, Mfodal 4I7RDl31'44DGO1 -.... .1974 W'75 1261-2 (cli AqPLi.v6wA4E F-Code% 5*cion "Edintom -.Addesdadate

CseNo. Cl&Asm____

R&m~=Standard part for us. with aaactor. ElydrostaticaLly caured at 1320 pa:L.3-(21tall d--4MIaaO -ta- I- -ftt-lf -" ""C-d)*' Tocal mi~ber of shean: -2 Iv~ Cmffify' Cheharzb 'Cta~tagaza*i t his. jo rrct am. cariicit xnd this rossci part f. Ppp~wi--nce as df-ineA in che code Cop-tocwx to ite. rtlaeS at c,=.eayico* oi dim AS1A Codw Swctioo [II.,rbr appiltabie Vesgun SpecAi~llczon and SUress Report are riot the rr3 nsfbiHUY of th r e~latHie trOrl l P etf-~e Ho~der for sopurtetraacs is rriortsible for humunrih a sepsru.e Dmgis Spccxijcanou 2Dd Stre" Report 1f the 21pvoufen-ICO rIsotýMe~dad U L~ he cm:1vonewnt DeIMM Srpectefrzilon and SUTrr R~rtioL)'2/30 j930 Sie TMP-;4M1-OQA______________ 0!Cuivwi uh-io Expir-es cetrtifiksrw o1 Auhorizatiao \I. ; ________CRIMFICATION OF DE.EIGN FOR APPURTENANCE (-I,hcn amplicable) W1. sas Walyrsis mý Ofrt o*File G (ý. Nz7 ;L-D-r7'LA, CastIe Ravie- Rd. I LW~zingon, N. C LI~ ~ -C'24r2,aa. Pro. Fx. g ae SL-1 3g. 43~1!.CERTIFICATE OF SHOP INSPECTION

h r. d e.~drsifnird.

holdug a valid coazaison tiszued btr the 4.jotiai Board olfBoiler ---d P~-eivrw Ves,,ei [~er a~'a te taw P a.,c of Norrth CarolUna ~d ~ 5 Deoa~r~nc or Labor Sý1 -tare oi Jorth Carollaa have iaape-ce the ~rx p of a pressure Wesset descsibed Inthis PartWa Data Rxv(U*t 08 12/30 it9j 9 and stage tivt to the beAt ry know,,dx,-4btqef. Ute N"T Ccrtifieaie Holder has cons~ucted this tort in acerndate wsithl the ASME Code Section lit.By 3 igi*4 this certifiecax. taeicher the (eantiocroi nor hi,3 c~rxLayet ruakes aoy warra~nry, ezprcsa-td or imp~lied, ccaer-n'-Lif the :Ynrt described La this Partial Dama Report. Fuztlterm~ore. nelther the intspector nor Nis ernplioyer-all b. liaol*in an y ruanfwe ior any personal intQ*7 or pt-operty damag~e or a loss at wny kind w~rising trtam oir connccted rtjb this :aupection.. .. NG 779,PA.WCI-GO, OHIO&* /1 ate-sS-1. 3t.... 7'o--c- -.d 4t...1 1,11115MS N: //r*77) Thn ýrm , EOGO -10)rrwv w,.aaota'-u tram -w~a~i E 1 .~7n Y2' !0., 'rr 31 ~~ 7 78 4r FORMI N-2 (b~acýJ lit-ni 4-13 1.,. 1., be complee I ic r -K 1, 'l Ie,l. ;acfc'.s .,l C " ,a e ed a Isc or 'h' lls ui he.1 -tCh..nie". Nominal Corrosion'Itll. Nftmerl _ __ ___T.Si. -____ Thicknt s -in. All.-..cce 3 .ia. ft._... in. Length -. ft- in.___fK"n & SP- 3. .) (Ml-i -( R-... 5t,..ei-li. ' 7 .Ssý Long ________ H.r.______ _ R. T. _________Elfficincy ________ .Girth -H.____ _ HT.'_______ R. T. N______ 'o. of C e,~6. He-eds~z (-) *'srct.J ______- T.& _________(b) Mmite-ial _________Ti. __________ Lie.it C -~.s lKmaeitl EMlP11.1 C-6-9a 314.ct.eO~ plt .toP.,...Cr0O. liostit. *dl The. -doi, RIdtial. Rain. Ap.x AnýI Roia Dlii.,.,O lCC~. O Cot.j It cesnorable, bolts useid ____________________Othser Iiasiening l t...... SQ.-.NS... T.3.. St... HinbaDlosrlbib o -.u h *sketch)ackee (D scribe a, qc~e a.. *td. bur. sic. Et b- citt- dtmes,-esss. ibottod. ds-eeb, of ii-t h)~~~~~Csp i-sgs ~ 15055 0 ltp.ct It-l b lcc,., 9 a-rid 10 ca be- completed for etabi sections 0rbe, Shice's SCa'iio.... Y. M.Criiij________ Di.._________ Fnicknies... in. Aerrohrnenc (Kid ft SP-. ya.- (Subi.ctC ..u" (add ot8 F7 Io.iing. i4m-ieeial_______ Dia. _________Tikes.... Attachrmetne 0- Tob-s M.aersi __________ O.D. ___in. flsickne-s _______o -Type.(3'ir. U Il!ct-m3 11-14 Anct. :a 5,completed roe inner cnhaiber of ;.cleted vsel.or channels of he., eschangcr3. Nominal1 Corrosion e.S'lI: 'aeral______T .___ __rsiCk.esS ...i. Alloua'CC ..n. Dia...... it- in. Lcng~h- f.J n S-n,: Lon g H________I .________ R. T. _______-Elficiency -_ 1_________ q__ _____.___ R.r. _________No. Of CO.',:c ______________ C-ot X-nA.ci Elliptic i C--c~ Ho-t-h.r-c& Pt., Sid.tiP*.L~crios T~uciun.'. Ro.di. Rod~o Ca.". Ac. A* .R.dl.. 0~t.~r (o..i Cocci I-) Top. b.t.it, 7rid.5___________ ___ _____Die etglst ((saiPy Impact _ li-lb 14. Desig ,reisc'_______________ psi a ____________ Fm atemp. of__________" Items Oeio- to be completed for all -esslse 1 oserc applicable. Sm,,y V.1c, Outlets: 4umber -_______itte-_______ Locatio maos. ni't. tnsemn Out~. l.in N_-nie Di.. Stat t'V. 14inrit -rhies... S tti i4a.-~tCI t .:ospcct- A -.Csnols. 'co. _______ ie_______Li -ion.__________________________ It P,.-1-i H1a-7--dI i e .ncL. ...--e. it.- ,t ~ teitt'W '5o5 ~ ~i~ irn REPORT NO. P0059-011 FORM 1 "CPT CEr-FMiCATE HOLDERS' DATA REP'ORT EOR RUCLEAR P.AJTSn APO DPURTENANCES.As require~d by Lhe ?mv.iion of the ASME Code Rulc3. Sciuon 111. Div-L .' General Electric Comoan7, Ca3trle Ravne Rd. , Wilmingraon. N.C.(b ~.~~ M.~ lt General Electric Company, San Jose, California (mG)Q4 4 .6. It C.Uný4 H0ý o-oI-.40oA. i.:. ii cm ,'o. CC P~rt _____________________. Ar C.. 5 o. ____________ (04 Coou"Mcred Accoodiog to Drwwg N.76F-514C,Ol1 Ppd by D. L. Perer3ori (b) 0-D-ripu on i. ps. Ipod. Control Rod Drive, Model 47RDBI44DG001 N20 7 (c¢) aL F46o. 19T4 .Ad^4dad.n c__ W'75 C_ 1361-2 7C1.33.r. Cap 166B9274PT (167A2343) SA182 -F316 3/8 thick x 1/16 00 Z-. Indicator Pipe 166R9313?1 SA312-TP315 3/4 sch 40-seamless pipe 0.113 w:all thickness 1.065 max. dia.3. Pluc 159AI176P1 SAl82-F304 1/4 thick x 0.812 OD 4. Flange 915061OPT (719E474)-SAl 84204 3.37 thick x 9 5/a OD neck 1 1/16 t~hick x 5.0 o0 2.875 E0 5. Base 137C531 1 P1 M4-19 ASIlE SA479 3.0 00 x .884 ED 6. Ring Flange 11485122P2 SA182-F3C4 1" thick x 5.0 00 x 1.75 ED 7. C3p Screw- 117C4516PZ SA193-86 6 ea. 1/2 dia. on 4 1/8 bolt circle 8. Plug 175A7961Pl SA0 82-3x0 .* 0.33 x 1.3107 die.P5OYPIOI0 CCI!TRPL ROD DRIVE OWG -76SEz34 9. ;ur 137C5924PI

i-L9 SA479.. i 3Qlr_.ic :x L2_A5_I ..... --79 REPORT NO. P0059-011 QI0a1 -36 e 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.10 Center Road, Perry, Ohio 44081 2. Plant: Perry Nuclear Power Plant (PNPP)10 Center Road, Perry, Ohio 44081 Date 5-8-07 Sheet 1 of 1 Unit 1 200259287 (Repair Org. P.O. No., etc.)Type Code Symbol Stamp NR Authorization No. 33 Expiration Date 9-28-08 3. Work Performed By: FIRSTENERGY Nuclear Operating Company PNPP 10 Center Road, Perry, Ohio 44081 4. Identification of System: 18B21 Nuclear Boiler System 5. (a) Applicable Construction Code: ASME Section III -Class 1 NF NAMEISECTION/DIVISiON/CLASS Winter 19 75 Addenda Code Case(s) 1644-4, 1728, N-272.1974 Edition (b) Construction Code used for repairs, modifications, or replacements:

1974 W/75 Edition Addenda (c ) ASME Code Section XI applicable for Inservice Inspection: 1989 N/A Edition Addenda (d) Applicable Edition of Section XI Utilized for Repairs, Modification, or Replacements: 198 N/A 19 N/A Addenda N/A Code Case(s)(e) Design Responsibilities FENOC 6. Identification of Components Repaired, Modified, or Replacement Components N/A Code Case(s)N/A Code Case(s)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 Electric 1B21 64084 1B21 1985 Replacement YES System G7091 7. Description of Work: Replace snubber SN 275 (existing) w/new snubber SN 043 8. Test Conducted: Hydrostatic-Li Pneumatic-L] Nominal Operating Pressure-E] Other- LI Pressure NA psi Test Temperature NA degrees F Code Case(s) NA 80 NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back)PNPP No. 9308 Rev. 9/11/00 NOQ-1741 9. Remarks: Functional Location number 1B2 1G7091 was originally installed as a General Electric hanqer numrber 1 B21-G006-S 107C as shown on drawinq 92-0605-05033 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 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 XA of the ASME Code and to the National Board Inspection Code "NR" rules.National Board Certificate of Authorization No. 33 to use the "NR slamp expires 28 SEPT 2008 Date 5-8-2007 Signed FENOC-PNPP G/f OE (name of repair organization) represeftative) (title)CERTIFICATE OF INSPECTION/INSERVICE INSPECTION I, Thomas 0. 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 HARTFORD STEAM BOILER CT. of HARTFORD, CT have inspected the repair, modification or replacement described in this report on V`i&A A. 20 0l 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 01T Signed ,MTlA Commissions NB 9330 "N"I"A" Ohio Comm (inspector) (National Board (include endorsements), and jurisdiction, and no.) REPORT NO. P0059-011) I Q 1 -uý ,7 Pý I j -ýNIS-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 NQI-1741 1. Owner: FIRSTENERGY CORP.10 Center Road, Perry, Ohio 44081 2. Plant: Perry Nuclear Power Plant (PNPP)10 Center Road. Perry. Ohio 44081 Date 5-2-07 Sheet 1 of 3 Unit 1 200168163 & 200168164 (Repair Org. P.O. No., etc.)Type Code Symbol Stamp NR Authorization No. 33 Expiration Date 9-28-08 3. Work Performed By: FIRSTENERGY Nuclear Operafing Company PNPP 10 Center Road, Perry, Ohio 44081 4. Identification of System: 1 B21 Nuclear Boiler System 5. (a) Applicable Construction Code: ASME Section III -Class 1 NB NAMF/SECTION/DIVISION/CLASS Winter 19 75 Addenda Code Case(s) None 1974 Edition (b) Construction Code used for repairs, modifications, or replacements: 1974 W/75 Edition Addenda (c ) ASME Code Section XI applicable for Inservice Inspection: 1989 N/A Edition Addenda (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 FENOC 6. Identification of Components Repaired, Modified, or Replacement Components N/A Code Case(s)N/A Code Case(s)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 QA-26 665 1B21 1981 Replacement YES International F0032A Order 200168163 Corp Valve Rockwell OC-51 670 1B21 1982 Replacement YES International F0032B Order 200168164 Corp 7.8.Description of Work: Remove test connection from valves for inspection and replace Ht # K5632 Test Conducted: Hydrostatic-E] Pneumatic-E] Nominal Operating Pressure-El Other- E]Pressure 1035 psi Test Temperature 78 degrees F Code Case(s) N416-2 81 NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back)PNPP No 9308 Rev 9/11/00 NOI-1741 9. Remarks: NONE 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, Russ Matthys 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 "NP-,stamp expires 28 SEPT , 2008 Date 5-2-2007 Signed FENOC-PNPP "b f'\ ý" QC Supervisor (name of repair organization) (auth.orized represe ative) (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 HARTFORD STEAM BOILER CT. of HARTFORD, CT have inspected the repair, modification or replacement described in this report on MAI4-, 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 5_, 20 o0l Signed 16,.A Commissions NB 9330 "N"rA" Ohio Comm.(inspector) l (National Board (include endorsements), and jurisdiction, and no.) REPORT NO. P0059-011 A -q-dLy Clc ov -7c-'s C the SECd:*C~ltE0

-tr1 o" 1 t tinlCor .1900 S nundcra S~t., T~~ih N 27603 CHCefll Elecirl Hower)~y p.O ox.500. CleveIOa2d.

Ohio 4,4101 2.. .--d.1',dF~ Aid .Ill ) .W rt erY~~~~~~ 3r t~~' ,~~~" ?Ey TjC r por laflt. llS 162lrh pry'~ ~ 1.ýu osvi._______________ onni1 1 20 Oult~ 20 MdoNo (b) N Cvnllficatt HOlderS dCndNl*Sn.5 No.~ginol d P orlypoNo* ~~~~-I (1 jZ~C A 6 NA D8 44017-15 1665: 1981 (4)O_51 4z53z 57 Co nrold Closur Ch22Vle .50.6 40 Neat ~ ~ o.ma No.4143S2.... kv.. .. ..t .. .. .y. ..4810453 s"k 216 Cr (JCC..(b) F-19-02 S .SA : .6 3 .36996 sA:638.C 6T SA.N *o *. o p.... V 1 ." : ." (Metal ..t L K C-Charles E. Larson. cover: Calan & Saul. Steel Di~k Co~mpanpyý Chirles. E..Larson C'ket RetaIn3fer tCharlesx E?.-A L carso .Drain Cap:2):C .ar em cj£:E Larson.: Test Fittinlg* Sp 0!~e Ltshetsusfor,' of Foss. sketChte or dr_ -be sdi pov~dtd (1)(size is 8-1(2.55. r.~ee'~ .7~od on t~'Dt. Pepornis. includemd on cach. I~t:.nd (),c seti-d 5 .6 r; tE C O .7 ) '. 1) -b .~ .~ ~ ... O '. 0 0 5 A. ~F 3 .5 E .S r , S ..-. Y , .N Y ID017 ASME. 3-.5 E. 17ý, 5'.. N'- Y'ho/i)211 82 (c) D05 N /A P~rinur4!-" .t I- .(ni) Othii, Palls L2jt%9 SA16 Gr. B Equalizer-05 .-,; --6ýca ital. pipe. &,*~steel. IFroducts.

m. (Q)d 335 .... r 13; D ... ...... .........

250 d..CHITIFRCATE OF.COMPLIANCE W., iy at neh.- -coette and that thit WPe~tj..vaa.,of.n ot. 'Ia WeC-t-lio th.t the ttttettI-ae f N.flethi ro-Pi F-- Cw .-.5ý"L-Ei~ 1914 ,d Winter .1975 c 0 caeFj / as13-1 _utt ssuranc CERTIFICATION OF OE-SIGN .-Dt ; nmfol,-ori-nn ,,c I PcselInterniati onal Corp. Role[$ b.NC. 27603 S-,I.~ ~~~~~t atxi rPnk' I IdI'l 1Rcell luter-natiofla Corp~. .Ralciph, 27603ýA ..~ o078303-F. SiE xi *ritYS4. eartifisid he b (1) PR. Clzipper.. PE .C -.. Q .No. I0057.7 .K.(1 * .. toe o .s ...m ..i ia. 0..sif~.t. the oie~id odi~.~~-nd the stalco, F' -;,,ce of UGotE.1 la , tord. CT r-oca .h Pnp. oar -ft-e in -siod.CERTlFICATE Of SHc.0 tn~spEcnON ,sinxni, ,aed b~y the N.tion.l B-ad of loile, -nd ao.V..a ---ttoI h CarolIA and ernPiptY-1 b ELSBI & I Cu.h-.: oi-P-ocl the .-p. o Ir .v.1- .de-tbad ten th,~s Data. ftetd on ladslt tetthe bet- of my kno.d-ide anrd bliet the N C~rificatc Hold-"h.a~o nce 0.mth thi ALSME Codt. Sx;o.- SIl-ipxctorr nrio h~i emtployer aiats .ny w-~ranty. captetted Ot nmtpfe& mnclnoeng teprt oitettto~. tthet the tItpediaa cine Kai tpfo'y- ~hall 15e I;.bt i. any if dam%2%ot, C'.o-s of any iEnd .o..s~ng from wa co-necied watt this Znstpý-,ttiot IfB8363 VC919 I Ely.~si th;. c-iifk~te. sienlhsthe I tit- ea.;-ctm.pli dsctuitmd

i. IN;. Gala-nr- F., any P-i.n.t .rijýmy Osprps I.-~4~i'~~--22~r REPORT NO. P0059-011 fI.a .oe N. ..I .C i 1ll, le older $ (C) C.nadian 3."rlal N.R-f (b) N Cc "" (r) Na 1 (g) Yer.* *Typ. No* No" No * (e) Clss, -d Nt. Brait.-*..C'5.."A DBI 24401-15 1 *670 ..1982 7) 59v AWc Q-,,I;IF)(91.Co n o-i.. .e ..O..ureo Check Vlve k .a v....:. : * ..... : ..*... ..S ein onicnS 1)10. f$ -_426 ,VIV". " "____. .__.."- _ ' " " ' " "; .. ' :; ." .: -: : ..! g 3 3 -z !., .-: .-.:: .: .':'--.i. .i...:. !.,.;.., , .: ::.: : .: ' ._ 0i .. ..:-'.C .. : I-." : I .;, ..: .'. P-o,.. pi ..'. :. ..W " A, Reqcieesd by Itle -,v,,,nsn CAl the A M oe elo l c fl~ I~icid P0~ 1 1 t i'o' al -rp-, 1900 S.aunders Sr.. Raleigh. N 70 cse~~Clevland ElohioCnafY cicronof ~ ert" ~ cISC Poh~e lan Unit 1 -2 1(rth ?cerrýY Ohio eo-i .leNiia Itlrc 0 O tlSa 20 l, -dAd- 0r)jicsie

.B.SA 38 r 60T2Chrles E. Lron Caoketr et e charlesi E Lasn Drin .'C h ae:: .h E .. L a r s on. .e.. .i.t. G et-i n SAha 105 11 For Y p ..o:tve ."." ..- * :.."..l.ca -.. p er r n al ~ t ;n toreu ; , 0s t li 0 ,*,'-.. e o" : .. rng- ..:..... .... .;.." :- I ..:. " "*' "...!. 0,.N ..M.""... ', f Spec No- nof ..tt'f.,.. .... l .irk :.4 8C,, 33 s, 216. Cr WCC 1t a ti I """Body. : "~~~r .... 1. :...* : ..; ......, .. ......;. ... ." .' ....q'hcel. in 1., (sc~ejnd3) cit .hcct ;sjcica c d ~~b9 f h e-,1: 2 soil 5;onthis 0el. Reporis jmnclohd an raeh heect.d ucae o hel.. .2ie i iop of thil Inct. ..........LW 4jdý k4,,,y6,k. N.Y. ICIC o.. .7)______ :i 2 83 1; /A .'ml 4 ~ hJ ot-t ee) .......,. .f -._ _ _" _ _ " _ 4-.* ._l,:_.capital. Fipe.&v:LquaLizer Y--..-..StL~ I<TtOCrJCES2 .Y .. : .-.. ..'7 .1!'.': t I<" ts':..).4. .>-' ~'. -...... .4 05505 ....4.... _106 cr. B alia Pipe.:...Se1FrbdutIst Drztin.Plippe (2)1. klydr _ýi 33 5 > c0k O~t,-l,;r .1.t prlar-? ..-ii.t ; .* , = A *,, ,,, , , * , , ., , .... ...., .....CIERTIFICATE (if- COMPLIANCE. Wecet tatte 10enerrs ,a de in this eport Ir c ed It r ta t thr r.nr P err. a Ive. 'orrlto m to Ih N ue n.. of O e

tr."r."o Of the AS .. E Code tot, N" : c.e.. PoC er mat C -o -ertro n Set.a .-.". .111 ."e 4 1974.. *' -. ,: :" j:dn lUenter. 975 CodCc,.. o N/A Date , .0 -.gre ROckv, Int Zl t iontal Co O ,r ASME Cc,. cate of ;rao. No N-1 562 -.. ..'e the: Nep*,e 11/26/82 CERflECATION OF DESIGN :~ ~...De~g ;S?;r-ton on Lie .1 pockje II ntrtc j-nlajoral ICdrp 2 3.Ral eigh11~.C 27603.: I~er aor r~oetCtsr oeryloref R *Rcj nil. nfernjationil Corp., Ralei gh. NC 27603 Ce ~ e~tcrror Crirredtry4))

ljtoti C -Caplotlis P riae i A ." ., No 028303-E S rs. t,...l'- rn r.ed by .".1 R ':. ..Clap e' .(1 s,,e 11C "r, No 10057-1 , r rrteor.rrd. tl naryr orrly.(-a ,:..... , .":. ..:. .' 0 .* -*..* I --, m CERTW4CAFE.OF SHDP INSPECTION I. the rrrdrrgret )odarr. -1ald co,rrerrrio orissure -dIty thre Nalotonl Dado dof 13orlee aenti~~nVrsttr~el

err the .Stlte 6, P.oý;.e~ of u -orth bI Caol .((SB G- I Co.of h.,U;.i .-~od IS9 .rr e ; 1t. Daa eVo sterrcred ttrr. Poerri or 1.1e, in carape rr the ASKAE C~de, Seit.on III-~S ej s;,gnsr this Cerirr6eale -ither1h tlrlrptctor of his errrployet -sere *ny ocrat~epee

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oersr the eq 1 p Iermeer drrsc;b ed int-.,a ReotFirIrr~oc nther the lrrP-dov inor hit, .P~ t t-all bý laIi cn -ny-r -I.,e -r a 1-1 iyr natrjury or property damrage ea Io %s of any kerd artrgtoe ncrroelrr hitir -rpc. n B~ 3- NC.919 IN.tI d. S-r..~. F- d .-S .3/..--------------- 211 REPORT NO. P0059-011 I 4ý 1~'- I(. ?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 10 Center Road Perry. Ohio 44081 2. Plant: Perry Nuclear Power Plant (PNPP)10 Center Road, Perry, Ohio 44081 Date 5-4-07 Sheet 1 of 1 Unit 1 200261585 (Repair Org. P.O. No., etc.)Type Code Symbol Stamp NR Authorization No. 33 Expiration Date 9-28-08 3. Work Performed By: FIRSTENERGY Nuclear Operating Company PNPP 10 Center Road, Perry, Ohio 44081 4. Identification of System: 18B21 Nuctear Boiter System 5. (a) Applicable Construction Code: ASME Section III -Class 2 NF 1974 Edition NIvAME/SECTION/DIVISION/CLASS Winter 19 75 Addenda Code Case(s) N-224-1, N-225, N-249, N-272, N-3, N-413, N-71-6, N-71-9, N-71-11, 1728 (b) Construction Code used for repairs, modifications, or replacements: 1974 W/75 N/A Edition Addenda Code Case((c) ASME Code Section XI applicable for Inservice Inspection: 1989 N/A N/A Edition Addenda Code Case((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 FENOC 6. Identification of Components Repaired, Modified, or Replacement Components (s)(s)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 001 1H22H27 1985 Replacement YES System Controls 44 7. Description of Work: Replace mechanical snubber Lisega (existing SN 00614803-006) w/new Lisega snubber.-3 ,k 5,&/- , SN 2"0400002/09

8. Test Conducted:

Hydrostatic- [I Pneumatic-D Pressure N/A psi Test Temperature N/A Nominal Operating Pressure-E] Other- E)degrees F Code Case(s) N/A 84 NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back)Pi'PP No. 9308 Rev. 9/11/00 N01-1741 9. Remarks: Fuinctional location number 1 H22H2744 was originally installed by Johnson Controls hanger number 1 H22-P027-H 1122 as identified on isometric8l4-0605-00901. Ref: JCI final N-5 data report 1 B21-0070-F 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 8 112 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, Puss Matthys 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 , 2008 Date 5-4-2007 Signed FENOC-PNPP (L. \rrý OC Supervisor (name of repair organization) (authorized represk alive) (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 HARTFORD STEAM BOILER CT. of HARTFORD. CT have inspected the repair, modification or replacement described in this report on 20Ak4- 20 01 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 i t Signed Commissions NB 9330 "N"l"A' Ohio Comm (ins (National Board (include endorsements), and jurisdiction, and no.) REPORT NO. P0059-011 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: 2. Plant: FIRSTENERGY CORP.10 Center Road, Perry, Ohio 44081 Perry Nuclear Power Plant (PNPP)10 Center Road, Perry, Ohio 44081 Date 5-5-07 Sheet 1 of 1 Unit 1 200063004 (Repair Org. P.O. No., etc.)Type Code Symbol Stamp NR Authorization No. 33 Expiration Date 9-28-08 3. Work Performed By: FIRSTENERGY Nuclear Operating Company PNPP 10 Center Road, Perry, Ohio 44081 4. Identification of System: 1 B21 Nuclear Boiler System 5. (a) Applicable Construction Code: ASME Section III -Class I NF-1974 Edition NAME/SE CTION/DIV ISION/CLASS Winter 19 75 Addenda Code Case(s) 1644-5, 1728, N-32-4, N-241, N-242, N-272, N-282, N-413 (b) Construction Code used for repairs, modifications, or replacements: 1974 W/75 N/A Edition Addenda Code Case(s (c) ASME Code Section XI applicable for Inservice Inspection: 1989 N/A N/A Edition Addenda Code Case(s (d) Applicable Edition of Section XI Utilized for Repairs, Modification, or Replacerments: 1989 ý N/A 19 N/A Addenda N/A Code Case(s)(e) Design Responsibilities FENOC 6. Identification of Components Repaired, Modified, or Replacement Components s1 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 1B21 109 1B21 1985 Replacement YES System H0445 7.8.Description of Work: Replace snubber SN 614001/96 (existing) w/new snubber SN 04616533/010 Test Conducted: Hydrostatic-0I Pneumatic-D Nominal Operating Pressure-111 Other- El Pressure NA psi Test Temperature NA degrees F Code Case(s) _J 85 NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back)PtNPP No. 9308 Rev. 9/11/00 NOQI-1741 9. Remarks: NONE 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, Russ Matthys 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 Xt 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 2008 Date 5-5-2007 Signed FENOC-PNPP -C Supervisor (name of repair organization) (authorized (title)CERTIFICATE OF INSPECTION/INSERVICE INSPECTION I, fVo, &-- Lpeý 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 HARTFORD STEAM BOILER CT. of HARTFORD CT have inspected the repair, modification or replacement described in this report on F 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 ill , 20 o-T Signed -VlM4 Commissions -,ABI, 33 " iA T -_A" C61.u (inspector) (National Board (include endorsements, and uris diction, and no.) REPORT NO. P0059-011 I I -) o *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.10 Center Road, Perry, Ohio 44081 2. Plant: Perry Nuclear Power Plant (PNPP)10 Center Road, Perry, Ohio 44081 Date 5-5-07 Sheet I of 1 Unit 1 200063005 (Repair Org. P.O. No., etc.)Type Code Symbol Stamp NR Authorization No. 33 Expiration Date 9-28-08 3. Work Performed By: FIRSTENERGY Nuclear Operating Company PNPP 10 Center Road, Perry, Ohio 44081 4. Identification of System: 1B21 Nuclear Boiler System 5. (a) Applicable Construction Code: ASME Section III -Class 1 NF ,1974 Edition NAME/SECTION/DIVISION/CLASS Winter 19 75 Addenda Code Case(s) 1644-5, 1728, N-32-4, N-241, N-242, N-272, N-282, N-413 (b) Construction Code used for repairs, modifications, or replacements: 1974 W/75 N/A Edition Addenda Code Case(s (c ) ASME Code Section XI applicable for Inservice Inspection: 1989 N/A 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 FENOC 6. Identification of Components Repaired, Modified, or Replacement Components s)s)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 1B21 109 1821 1985 Replacement YES System H0449 7. Description of Work: Replace snubber SN 614001/97 (existing) w/new snubber SN 04616533/017

8. Test Conducted:

Hydrostatic-E] Pneumatic-E] Nominal Operating Pressure-El Other- E]Pressure NA psi Test Temperature NA degrees F Code Case(s) NA 86 NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back)PNPP No. 9308 Rev. 9/11/00 N01-1741 9. Remarks: NONE 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, Russ Mattihys 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 , 2008 Date 5-5-2007 Signed FENOC-PNPP QC Supervisor (name of repair organization) (authorized representve) (title)CERTIFICATE OF INSPECTION/INSERVICE INSPECTION 1, -LAQS 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 HARTFORD STEAM BOILER CT. of HARTFORD, CT have inspected the repair, modification or replacement described in this report on V\Aof11_ 200-1 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 01 Signed Otd Commissions oP O (inspector) k( lNational Board (include endorsements), and jurisdiction, and no.) REPORT NO. P0059-011 I I -3"r7I 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 10 Center Road, Perry, Ohio 44081 Perry Nuclear Power Plant (PNPP)10 Center Road, Perry, Ohio 44081 Date 5-5-07 Sheet 1 of 1 Unit 1 200063003 (Repair Org. P.O. No. etc.)2. Plant: 3. Work Performed By: FIRSTENERGY Nuclear Operating Company PNPP 10 Center Road, Perry, Ohio 44081 Type Code Symbol Stamp NR Authorization No. 33 Expiration Date 9-28-08 4. Identification of. System: 1B21 Nuclear Boiler System 5. (a) Applicable Construction Code: ASME Section III -Class 1 NF 1974 Edition NAMEISECTION/DIVISION/CLASS Winter 19 75 Addenda Code Case(s) 1644-5, 1728, N-32-4, N-241, N-242, N-272, N-282, N-413 (b) Construction Code used for repairs, modifications, or replacements: 1974 "W/75 N/A Edition .Addenda Code Case(.(c ) ASME Code Section XI applicable for Inservice Inspection: 1989 N/A N/A Edition Addenda Code Case(.(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 FENOC 6. Identification of Components Repaired, Modified, or Replacement Components s)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 1B21 109 1B21 1985 Replacement YES System H0450.7. Description of Work: Replace snubber SN 61403/24 (existing) w/new snubber SN 03615883/020

8. Test Conducted:

Hydrostatic-E] Pneumatic- [I Nominal Operating Pressure-EL Other- EL Pressure NA psi Test Temperature NA degrees F Code Case(s) NA 87 NIS-2fNR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back)PNPP No. 9308 Rev. 9/11/00 401-1741 9. Remarks: NONE 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, Russ Matthys 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 2008 Date 5-5-2007 Signed FENOC-PNPP (L- OC Supervisor (name of repair organization) (authorized represer tive) (title)CERTIFICATE OF INSPECTION/INSERVICE INSPECTION 1, Cr. L4&P. ,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 HARTFORD STEAM BOILER cr_ of HARTFORD, CT have inspected the repair, modification or replacement described in this report on , 20 6JL 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. -'- -" 80ic Date j , 20I l Signed Commissions tA V9.330 t -1 PA C () t..(inspector) (National Board (include endorsements), and jurisdiction, and no.) REPORT NO. P0059-011 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 NIQ-1741 1. Owner: FIRSTENERGY CORP.10 Center Road. Perrv. Ohio 44081 2. Plant: Perry Nuclear Power Plant (PNPP)10 Center Road. Perry, Ohio 44081 Date 5-5-07 Sheet 1 of 1 Unit 1 200174739 (Repair Org. P.O. No., etc.)Type Code Symbol Stamp NR Authorization No. 33 Expiration Date 9-28-08 3. Work Performed By: FIRSTENERGY Nuclear Operating Company PNPP 10 Center Road. Perry. Ohio 44081 4. Identification of System: 1B21 Nuclear Boiler System 5. (a) Applicable Construction Code: ASME Section III -Class 1 NF.A 974 Edition NAME/SECTION/DIVISION/CLASS Winter 19 75 Addenda Code Case(s) 1644-5, 1728, N-32-4, N-241, N-242, N-272, N-282, N-413 (b) Construction Code used for repairs, modifications, or replacements: 1974 W/75 N/A Edition Addenda Code Casecs (c) ASME Code Section XI applicable for Inservice Inspection: 1989 N/A N/A Edition Addenda Code Case(s (d) Applicable Edition of Section XI Utilized for Repairs, Modification, or Replacements: 19Qj 4 N/A 19 N/A Addenda N/A Code Caae(0)(e) Design Responsibilities FENOC 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 1B21 109 1B21 1985 Replacement YES System H0471 7. Description of Work: Replace snubber SN 614323/1 (existing) w/new snubber SN 30400009/17

8. Test Conducted:

Hydrostatic-E] Pneumatic-E] Nominal Operating Pressure-E] Other- E]Pressure NA psi Test Temperature NA degrees F Code Case(s) NA 88 NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back)PNPP No. 9308 Rev. 9/11/00 N01-1741 9. Remarks: NONE 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, Russ Matthys 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 ro. 33 to use the "NR stamp expires 28 SEPT , 2008 Date 5-5-2007 Signed FENOC-PNPP ,----O' 0 Supervisor (name of repair organization) (authorized representa\) (title)CERTIFICATE OF INSPECTION/INSERVICE INSPECTION I. J-" hA 2- L&, S -.holding a valid comrnission issued by The National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HARTFORD STEAM BOILER CT. of HARTFORD, CT have inspected the repair, modification or replacement described in this report on 0 " 11 , 20 0"7 and state that to the best of my knowledge and belief, this repair, modification or replacemnent 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 lL, 20 07 Signed-rlt,,fb ' Commissions

_.5___6 "o_. _ C ()___L.(inspector) (National Board (include endorsements), and jurisdiction, and no.)

REPORT NO. P0059-011/, 2/- -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 NQI-1741 1. Owner: FIRSTENERGY CORP.10 Center Road, Perry. Ohio 44081 Date 5/9/07 Sheet 1 of 2 Unit 1 200073616 & 200081977 (Repair Org. P.O. No., etc.)2. Plant: Perry Nuclear Power Plant (PNPP)10 Center Road, Perry, Ohio 44081 3. Work Performed By: FIRSTENERGY Nuclear Operatinq Company PNPP 10 Center Road, Perry, Ohio 44081 Type Code Symbol Stamp NR Authorization No. 33 Expiration Date 9/28/08 4. Identification of System: 1B21 Nuclear Boiler 5. (a) Applicable Construction Code: ASME SECTION III CLASS I NAMEISECTION/DIVISION/CLASS WINTER 19 75 Addenda Code Case(s) 1728, 1644-4, 272 1974 Edition (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 Case(s (d) Applicable Edition of Section XI Utilized for Repairs, Modification, or Replacements: 1989 __ 19 N/A Addenda N/A Code Casels)(e) Design Responsibilities First Energy Corp 6. Identification of Components Repaired, Modified, or Replacement Components s)s)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 1B21F41D 1985 REPLACEMENT YES SYSTEM ELECTRIC 7. Description of Work: Removed valve S/N 160886 and installed valve S/N 160851. Used 12 new inlet studs 1-5/8" HT # K745 and 12 new 1-5/8" hydra nuts HT# 623A. Continued in remarks.8. Test Conducted: Pressure 1032 Hydrostatic- [] Pneumatic-E]psi Test Temperature 142 Nominal Operating Pressure-0 Other- []degrees F Code Case(s) N/A 89 NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back)PNPP No. 9303 Re.'. 9/11i00 NQI-1741 9. Remarks: Used 16 new 1" hydra nuts HT# 591A. Used 16 new Y" studs HT# OG81 NO NAM1EPLATE/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 Sept. , 20 08 Date 11 May 20 07 Signed FENOC-PNPP ,O'->"7 DC Tech.(name of repair organization) (authori 6d representative) (title)CERTIFICATE OF INSPECTION/INSERVICE INSPECTION I, -(. 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 Mhl 20 01 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 UL Signed ____ Commissions I7inspecbr)W (National Board (include endorsements), and jurisdiction, and no.) REPORT NO. P0059-011 FO IWI NV-1 M ANI -I-At. UA IA trlUHI -U-L ý,Arl- ;IV. .FI'U DArrly ncLir- r VA kLVC r -/(As Required by the Provisions of the ASME Code, Section III, Div. 1)/ 2 0 9 M l 1 .-..ii' d by 1. l.)ikkrs Lt ci. N.V. HleigeIeo (0) The Netherlands IN -ne a'nd Adiress of Manulechtrer) 2 M ....., or ( .iucr l E lectr-i. San Jo0 _Ca!if.IN-,.u a-d of Puchasar or Owne,..)3 Luc Iuoi, Of IrslfalaiOu, Noro h lr ' I y (1.6 O P1rry ) .IN-me nd Addressl-. --......... GC471-6/125.v4.

2) _ ..ICHNi (Drwing No.1 IN.l. Bid. No.) (Vler 8 le2/4-Lf-3 1978 8ut I 5. VL.Ivt, Type 0orlic.e Size Gil I I Identifying Nos.. 6-085, 1 I ~odii No Snirs N. ) .

SIiio N..safet:/u1je.otei-ly. ily H-1t1 .il'd Po -Acl ttled 4.- 34" Nominal Inlet Size .......-............... Outlet Size .0 Irch inch inch 6 Set Pressure (PSIG) 1 16I .1 Slairiped Capacify 905732 Sol. Hydrostalic Test (PSIG) Inlet .2350 7. Pressure Retaining Pieces.. .Rated Temperature -......... F IbsJhr @ Overpressure Blowdown (PSIG) .39.7..-.Outle .9 .-p to v -lve for closed systems onlyl Serial No. or Identification Materiel Specification cIn. Type or Grade Body Bonnet or Yoke Support Rods Nozzle Disc Spring Wa,;heis Adjustinig Screw Spindle Spring Boluoij (Qihe, FIeces C.ov e r vur pipn e Fl anlge ;U3.05.6. s/n 2 11- 12.8 e/n 2.AEU 049 ..59 .04.8 s// 311 263(J95 s;/n 43 AFU 112 +, U66 iýEW 033.',. A.JR, AKA, ALJY, AMR, AJM 66.07.6 s/n 1s/n 3 AFW 015 AFV 0119 124... .......... .S.A._ 3 52_LC3L ..... .....--SA--352. -LCB-...S. -U....... ............. ........... ............ SA_ .35.1._LF.2A........................ ........ ... .. 5 C r. _ +L __t .V i t ... ..... ... ...... .... ... S _182--F31 ..------- .......... 564. 2 ty pe_ _AL30. -c and ...1i0.J.0 AJJ , ALR,.....SAI.9.3=.T/SA .194-7/SA. 19-4-7211..SA_351..CE3Al ............- SA... 51... ... ....--SA. _.L05..-..-SA.15 M'lix, ourstile di,:tiii.

jjlve body: i-l-x. ,rurside j ,i l ,igrh valve 475 ,nm (18.70 inch)1643 olin (b4.b9 inch)Supplveniertal sheets in form of lists, sketches or drawings may be used provided (1) size is 8.112" x I 1", (2) information in tic-ns 1 2 On this data report is included on each sheet. and (3) each sheet is numbered and number of sheets is recorded at tup ol this form.(1/76) This form (EO0042) may be obtained from the Order Dept.. ASME. 345 E. 47 St.. New York. N.Y. 10017 90 I/..FORM NV-I (Back)CERTIFICATE OF COMPLIANCE 5,Jr cerlify that the staltmonts Made in this report awe correct and that this vaive conforms to the rules of cnnstruction of the ASME Code hfr Nluclear Power Plant Components, Section 1t1, Div. 1., 7 Edition, Addenda set. 7 Code Case No. ......Date 1l0-1 1-7d .Signed .C. -. L kkjrs. .._ .V. by W.1`.. Wi IeITS Otir ASME Certificate of Authorization No 1 611 .to use the NV{NV)symbfol expires steL JuLY,.._98t---------------

INV IDate)CERTIFICATION OF DESIGN Design information on file at ..... L. ,e_. nc .andPer ry Stress analysis report lClass 1 only) on file at -_Gene-raL ric and. .erry[e5iqjn specifications certified by t .... Roy. P-... rooks............... PE Slate Ca.irnL-.... ...... e Reg No. 1...........13655 otress report celifiud by' ..... .-Robe r L-.. We i s,.s&.. .PE Sfate CaI L .fornia/I.Li inn is..... ..... Reg. No. .W1492.1/62-25749 Signature not req-ired--hrt name only.CERTIFICATE OF SHOP INSPECTION the undersigrned. holding a valid commission issued by the Nalional Board of Boiler and Pressure Vessel Inspectors and the Slate or Province of ... o ._ r.. ............. ......- and employed by ..._K empir Ins.of Lo ..have inspected the pump, or valve, described in this Data Report on S( ..........

19. a ... r ad state that to the best of my knowledge ard belief, the Manufacturer has con-sitructed this pump, or valve, in accordance with the ASME Code for Nuclear Power Ptant Components.

By signing this certificatr. neither the Inspector nor his employer makes any warranf, expressed or implied, concerning the equipment described In this 0Dat Report. Furthermore, neither the inspector nor his employer shall bo liable in any manner for any pereonal injury or property damage or a loss of any kind arising from or connected with this inspection. Drate 11)1 1 -8 Signed -- -.,z ....Commissions .. ..... 4_ ,5 _ ......i......Oin.pee 1or .N 8d.. Store Pro,. O nd No.) REPORT NO. P0059-011 i2/1- 377/NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As required by the Provisions of the ASME Code Section XI PNtPP No. 9308 Rev. 9/11/00 NC1-1741 1. Owner: FIRSTENERGY CORP.10 Center Road, Perry, Ohio 44081 Date 5/14/07 Sheet 1 of 2 Unit 1 200073622 & 200081984 (Repair Org. P.O. No., etc.)2. Plant: Perry Nuclear Power Plant (PNPP)10 Center Road. Perry. Ohio 44081 3. Work Performed By: FIRSTENERGY Nuclear Operating Company PNPP 10 Center Road. Perry. Ohio 44081 Type Code Symbol Stamp NR Authorization No. 33 Expiration Date 9/28/08 4. Identification of System: 1B21 Nuclear Boiler 5. (a) Applicable Construction Code: ASME SECTION III CLASS 1 NAME/SECT ION/DIVIS1ION/CLASS WINTER 19 75 Addenda Code Case(s) 1728, 1644-4, 272 1974 Edition (b) Construction Code used for repairs, modifications, or replacements: 1974 W75 Edition Addenda (c ) ASME Code Section XI applicable for Inservice Inspection: 1989 NONE Edition Addenda (d) Applicable Edition of Section XI Utilized for Repairs, Modification, or Replacements: 19 ____8 19 N/A Addenda N/A Code Case(s)(e) Design Responsibilities First Energy Corp 6. Identification of Components Repaired, Modified, or Replacement Components Code Case(s)N/A Code Case(s)Name of Name of Manufactuier Nat. Other Year Repair. ASME Component Manufacturer Serial No. Board ID. Built Replacement, Code_No. or Modification Stamped PIPING GENERAL 1B21 64084 1B21F47H 1985 REPLACEMENT YES SYSTEM ELECTRIC 7. Description of Work: Removed valve S/N 160870 and installed valve SIN 160894. Used 12 new inlet studs 1-5/8" HT # OG84 and 12 new 1-5/8" hydra nuts HT# 590A. Continued in remarks.8.Test Conducted: Pressure 1032 Hydrostatic-E] Pneumatic- [I Nominal Operating Pressure-El Other- El psi Test Temperature 142 degrees F Code Case(s) N/A 91 NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back)PrtPP No. 9308 Rev. 9,11100 PJQI-1741 9. Remarks: Used 16 new 1" hydra nuts HT# 591A. Used 16 new 1" studs HT# OG81 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 TC psick , 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 "HR stamp expires 28 Sept.. 20 08 Date 14 tvlay 20 07 Signed FENOC-PNPP ,--- 7/ -"- CC Tech.(name of repair organization) (authorized representative) (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 O1ItO and employed by HSB CT. ot Hartford, Conn. have inspected the repair, modification or replacement described in this report on ..I41 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 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 1_ 20 0-_ Signed-. Commissions NB 9330 "N" "I" "A" Ohio Comm.(inspector) (National Board (include endorsements), and jurisdiction, and no.) REPORT NO. P0059-011 As Required by the Provisions of the ASME Code, Section tit. Div. I / ./ 13/ Z e Z -1. Manufactured by G. flikkerA .Co.-1V -.- le ng eJ o () _Ibe-.._eLhe r]ands -IName and Address of N Certificale Holder)2. Manufactured for .. enel... E I el tric, Sq n Jo9se, Cal I forni a Nanee land Address of Pu-clhr0. or " "n -1 3. .:aio n of Installelion _. Perry I + l p:ares Nortfl -erry N d Addreoss9 4. G 471-6/125. 0T._ rev. 6 ._ 152

1979 l CRNv NDF.,la ing No I iNet'l. Brd. No.) (Yesr Built)5. Valve G471_ ..

Nos. -J16_0814 (Model No., Seriea No.) IN Certlllcat Holder'j Serial No.)Typo Safety/Relief ...._..So.sey. Safety ýoilef: Pilot: Po-w Actuated Orifice Sie 4,84 __ Nominal Inlet Size 8 (Flaqý Outlet Sizp inch Inch .. .ich S. Set Pressure. (PSIG) LL&Stamped Cepacity, Sat. Steam 7.ydrostatic Test (P;ig) Inete 7. Pressure Retploing Piteces 9- ..ated Temperoture .'F-_iIlbshr @ Overpressure Blowdown (PSIG) 2 .50 2350 " " 975 Outlet ?Serial No. or Identification S.Appliralwts to v&rve Ipr cIose. systims Materieal Spe cific.tion I IncL Type Or Grade Body Bonnet or Yoke Support Rods Nozzle Disc Spring Washers Adjurling Screw Spindle Spring;olhing O t t isr "-lCTv e --V IhTTP-Pfe-F] anglejs-AJWJ-9 .-._-AMELGaA5B3 020 SA 352 ?LB________ SA 352 L.CP SA '350 ' F2 SA 351 C F3A ,. 45 Cr Mo V67.SA 182 F 316 A 564--j type 630 cond. HI-00 ANY/ANZ/CAM/AJS/APA/APB/ANZ CAL/AL R/AWZ 51.36.8 s/n 2 63.38.8 s/n 2 AW- 005~ASA10ASA 221-5A-35T-CT8MW-.SA-IU5-Max. outside diarn. valve body Max. outside length valve 480 mm (18.90)1647 mm (64.84)* Supplemental sheets in form of lists, sketches or drawings may be used provided (1) size is 8-12' 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 i.recorded at top of this form.(10/77) This form JE000421 rr)ay be obtained from the Order Dept.. ASME, 345 E. 47th St., New York, N.Y. 10017* I 1 I ~ k M"~2~92 CERTIFICATE OF COMPLIANCE We cerlify that the ýtatemenls made in this report are correct and that this valve conforms to the rules of construction ol the ASME Code for Nuclear Power Plant Components. Section III. Div. I 1974 Edition. Addenda sum. ' 76 Code Case No. ID .&I.).e i cl."-o)I 'Signed G. Dikkers & Co NV by O r SMIN Cerlifica2e Holder1 Our ASME Certificalp of Authorization No. 1806 to use_._the NV INV)symbol expires 1st. July 1980 y (Date)CERTIFICATION OF DESIGN Design information.n file at General Electric and Perry I + I I spares Stress analysis report (Class I only) on file at GeneraI El ectric and Perry I + I I spares Deslgn specificaio ceriiedy Boyd P. Broks PE State .Ca ii forni a R 13655 Stress report c /ri_C artifdhl ASCa~frn-- a/ 11 In01s Reg. No. N1916-54 Signature not requIred-list name only.CERTIFICATE Of SHOP INSPECTION I. the undersigned, holding a valid, commiss r, Issued by he National Board of Boiler and Pressure Vessel Inspectort; and the State or Province of 0-v,' [A-Vt V L.1,L-"Q-, and employed by Royal I ndemn I ty Co.of N4eLcLL .. ...have inspected the pump. or valve. described in this Data Report on IL__ajJx-obe r____... 19 19 and state that to the best of my knowledge and belief, the N Certificate Holder has"onstructed this pufp. or valve, in accordance with the ASME Code for Nuclear Power Plant Components. .'r signing this cerlificale, neither the Inspector nor his employer makes any warrant. expressed or implied, concerning. the equipment described in this Data Reporl. Furthermore. neither the Inspector nor his employer shall be liable in any manner lor anksr .Ioral in iJry or flropety damage or a loss of any kind arising from or connected with this inspection. Date -C' 1 9iN6 Signed T11_____ .A -1k _1 mrnssions N__________________&__S___-a,__ 11tieclotl (NMt 1. W.. Stare Prow.~ and No.).. .............. .....- .*: %1" REPORT NO. P0059-011 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.10 Center Road, Perry, Ohio 44081 Date 5/15/07 Sheet 1 of 2 Unit 1 200073621 & 200081983 (Repair Org. P.O. No., etc.)2. Plant: Perry Nuclear Power Plant (PNPP)10 Center Road, Perry, Ohio 44081 3. Work Performed By: FIRSTENERGY Nuclear Operatinq Company PNPP 10 Center Road, Perry, Ohio 44081 Type Code Symbol Stamp NR Authorization No. 33 Expiration Date 9/28/08 4. Identification of System: 1B21 Nuclear Boiler 5. (a) Applicable Construction Code: ASME SECTION III CLASS 1 -1974 NAME/SECTIONI/DIVISION/C LASS WINTER 19 75 Addenda Code Case(s) 1728, 1644-4, 272 Edition (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 Case(s)(d) Applicable Edition of Section XI Utilized for Repairs, Modification, or Replacements: 1989 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. OGher Year Repair, ASME Component Manufacturer Serial No. Board ID. Built Replacement, Code No. or Modification Stamped PIPING GENERAL 1821 64084 1B21F47F 1985 REPLACEMENT YES SYSTEM ELECTRIC 7. Description of Work: Removed valve S/N 160873 and installed valve S/N 160875. Used 12 new inlet studs 1-5/8" (8) HT # K745 (4) HT# OG84 and 12 new 1-5/8" hydra nuts HT# 590A. Continued in remarks.8. Test Conducted: Hydrostatic-F] Pneumatic-E]Pressure 1032 psi Test Temperature 142 Nominal Operating Pressure-ZJ Other- E]degrees F Code Case(s) N/A 93 NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back)PNPP No. 9308 Rev. 9/11/00 N01.1741 9. Remarks: Used 16 new 1" hydra nuts HT# 591A and 2 new 5/8" nuts HT# 407C Used 16 new 1" studs HT# OG8B 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 Inspeclion Code "NR" rules.National Board Certificate of Authorization No. 33 to use the "NR stamp expires 28 Sept. , 20 08 Date 14 May 20 07 Signed FENOC-PNPP 7" "C Tech.(name of repair organization) (authorizod rep:esentative) (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 H-artford Conn. have inspected the repair, modification or replacement described in this report on rA., 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 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 I~,20 CQ1 Signed tO-' -Commissions NB 9330 "N".T'"A" Ohio Comni.(inspector) (National Board (include endorsements), and jurisdiction, and no.) REPORT NO. P0059-011 As Required by the Provisions of the ASME Code, S&ction III, Div. I //3 2/ 3 _>S;1. Manufacured by ....... JLkers...Qo. _VJhengei o LQLJThg Nethe r and S 0N4-e ar4d Addr-s ft N Certiflcale Holderl 2. Manufactured for __ Genel Electri , San Jose Cal iforni asn( Address of Purctlaser or Owner)3. Location of Installation Per ry 1I V orth Perry Ohl _o.(Name and Address)4. G 471-6/125.04.03 rev. 6 80 1979 ICRN) (Drawing No) (Nat'l. Brd. N IYear Built)5. Valve G471 .. Identifying Nos. 168-75 SMo aol No. , Soria a No.) IN C-r11tfcaet Holder'3 SerIal NO.)Type~ _ _ Safety/Relief S,,vty. P/tot: Power Actuar&rd Orifice Size --_ _-- _ Nominal Inlet Size Outlet Size inch inch inch 6. Set Pressure (PSIG) I LBO gated Temperature -F Stamped Capacity 9172.5 lbs/hr @ _% Overpressure Blowdown (PSIG) __ _ .__Sol. tasm 2350 .975 Hydrostatic Test IPSIG) Inlet Outlet 1. Pres ure Reta~ining Pieces : (Applicable to vslves for closed sys emu only)Serial No. or Identification Material Specification Incl. Type or Grade Body 0_7i2£8s n__Bonnet or Yoke 0_L0_7_8SfL _Support Rods Nozzle J.V_03_-Disac _5A1_3 0. 511 _ B Spring Washers 2 0_ Sn 76 __-3T Adjusting Screw AME 028 AMF 010 Spindle AJE 039 Spring 1ý Boufing ArNY AJJJ/_A YAVS/AJK_AWYZ/A1J S AFA/AJL ____L Liner c;6.17.8-2 C o-ver --52 -5 ..... ..--Vent.T_-Ppe __ AKE 008-Fi-anges AFV 128 AKF 0 ..... .A 352 LCB SA 352 LCB SA 350 LF2 SA 351 CF3A 45 Cr Mo V 67 SA 182 F 316 A 564-74 type 630 cond. H1100 SA 193-B7/SA 194-7/SA 194-2H-$75 FUTFA -5A icr~d Max. outside diam. valve body 178 tnlf (18,82)" Max. outside length valve 164~1 mmn ( 4, 0 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.(10/77)This form IE00042) may be obtained from the Order Dept., ASME, 345 E. 47th St., New York, N.Y. 10017 SIN1 94 CERTIFICATE OF COMPLIANCE We certlify 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 III. Div. I.. 4.9-7___ Edition. Addenda -SLLiL6.'7 Code Case No. U. A. (--. oate)Date R1 -0 Q -2 £ Signed ____G-_il -LeCrs_&_JLDUV-l- -by IN Cerlificatr Holder)Our ASME Certificale of Authorization No. 1806 to use the N1L INV)symbol expires i St. duly 1980 IDate)CERTIFICATION OF DESIGN Dpsign.information on file at, Generar I I Y Stress analysis report (Class 1 only) on file at -enexaLe t n Per-y I design specifications certified by' 1ronks_PE State .a-iLflEfli a Reg. No. 1365-9 Stress report certified by' Rohert.L -ai-e..si.)E State C Ca- i f o n tja£13JLijA1 s Reg. NO ..M 14 2/6 -257 _49 Signature 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 Inspectors and the State or Province of -j0o- PA and employed by-----Kefflpei-i ns.of 4 1 have inspected the pump. or valve, described in this Data Report on.23 March , 19 79.. and state that to the best of my knowledge and belief, the N Certificate Holder has constructed 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 equipment described in this Data Report. Furthermore. neither the Inspector nor his errployer shall be liable in any manner for any personal injur, or property damage or a loss of any kind arising from or connected with this inspection. D ate -.Signed _____. __. Con..imissions N B 4305 ru ecOF) iN81rI. 8d. State Proy. ard No.)3.,', ' ... ""r'. " .C .. "i', .." ' ..,' ., , ..." :. .! . REPORT NO. P0059-011 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 10 Center Road, Perry. Ohio 44081 Date 5/14/07 Sheet 1 of 2 Unit 1 200073619 & 200081981 (Repair Org. P.O. No., etc.)2. Plant: Perry Nuclear Power Plant (PNPP)10 Center Road. Perry. Ohio 44081 3. Work Performed By: FIRSTENERGY Nuclear Operating Company PNPP 10 Center Road, Perry, Ohio 44081 Type Code Symbol Stamp NR Authorization No. 33 Expiration Date 9/28/08 4. Identification of System: 18B21 Nuclear Boiter 5. (a) Applicable Construction Code: ASME SECTION III CLASS 1 NAME/SECTIOrI/DIVIS!ON/CLASS WINTER 19 75 Addenda Code Case(s) 1728, 1644-4, 272 1974 Edition (b) Construction Code used for repairs, modifications, or replacements: 1974 W75 Edition Addenda (c) ASME Code Section XI applicable for Inservice Inspection: 1989 NONE Edition Addenda (d) Applicable Edition of Section XI Utilized for Repairs, Modification, or Replacements: 198 __9 19 N/A Addenda NI/A Code Case(s)(e) Design Responsibilities First Energy Corp 6. Identification of Components Repaired, Modified, or Replacement Components Code Case(s)N/A Code Case(s)Name of Name of Manufacturer

hrt. Other Year Repair, ASME Component Manufacturer Serial No. Board ID. Built Replacement, Code_,_No. or Modification Stamped PIPING GENERAL 1821 64084 1B21F47B 1985 REPLACEMENT YES SYSTEM ELECTRIC 7. Description of Work: Removed valve S/N 160891 and installed valve S/N 160855. Used 12 new inlet studs 1-5/8" HT 4 K745 and 12 new 1-5/8" hydra nuts HT# 623A. Continued in remarks.8.Test Conducted:

Hydrostatic-E] Pneumatic-D Norninal Operating Pressure-NJ Other- El Pressure 1032 psi Test Temperature 142 degrees F Code Case(s) N/A 95 NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back)PNPP No. 9308 Rev. 9/11/00 N01-1741 9. Remarks: Used 16 new 1" hvdra nuts HT# 591A. Used 16 new 1" studs HT# OG81 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 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 ceodify 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 '"RP rules.National Board Certificate of Authorization No. 33 to use the "NR stamp expires 28 Sel!_ 20 08 Date 14 May , 20 07 Signed FENOC-PNPP ,2 --W OC Tech.(name of repair organization) (authoirized representative) (title)CERTIFICATE OF INSPECTION/INSERVICE INSPECTION I. Thomas G Laps 'holding a valid commission issued by Tihe 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 01 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 "IR'" 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. Dale S ,20 6 Signed Commissions NB 9330 " "I" "A" Ohio Comm.(mispec-or (National Board (include endorsements), and jurisdiction, and no.) REPORT NO. P0059-011 flqmuvy m~e rrov,,lons 0f in. R,,-mt uojde, ziection mI. urv. I//3 2. -326 1. Manufc-tured by 2. Manulactured for 3. Location of Installation G. Di kkers Co. WV. Hengelo (0) Ihe Nether'lands Cu nej li~ e~'rh 0 7~Ali Nj C aYWri IN-m. and Add-e. of PurCh~s.r 0, 0-1tt-1)Pr-I 1y I North Rurr-' Ohic C '71-6/1jt. (4. L3)("1-71 l~ssreNo IIN.sIi Bid No I 4.ICAN)5. Valve lysar B.110t tI-i Idrentifving Nos.-16J8ff5 1N Cerltificte Holder's Seraljs No.Type Po.. .... ... ... ..Saetya. Safetty Relief: Pilot, Power Actuats~j Orifice Size 1, ..Nominal Inlet Size 8"3 Inch Outlet Size 1Q0-nh inch 6. Sol Pressure (PSIG) .1180 SIomped Capacity 917-..25.. Sol. Slaam Hydrostatic Test (PSIG) Inlet 7. Pressure Retaining Pieces Rated Tem perature .. .. -- .. -585 .... .....lbs/hr C 3 .... % Overpressure Blowdown (PSIG) 1 0. 4 2.. .3 510 ....975-p 3l 0 __ Outlet _________o__________ ___ (Applicable to valtv, for closed systemse only)Serial No. or Identification Materiel Specification Incl. Type or Grade Body Bonnet or Yoke Support Rods Noule Diac Spring Washers Adjusting Screw Spindle Spring BoilingPi-eces L i n[r.Cov er Vent. Pipe Fl anges 10.44. 7 nr 6 Q4 .I .Z4 R 2 AEUJ 057 s3. 03. 8 /4zA 211653 1 1 AFU 102 AFU 091 AEWA- 01/4 AJR, AJJ, AUP, AKA, ALR, AuY, AMR, AJM, AJL.61. 15. 8 Snl 55. 50. 7 sn7 AFW 0.3)AFV 033 AF\, 064 SA 352 LCB SA-35-2 TUf SA I350 LrZF--SA -351 C F3A ~~ __----15 Cr Mo V6~.- __SA 1-82 F A -5fi414 type 630ftvond-. "I}(j-SA I93-B.7/SAK194-7/SA 194-2H SA SA SA SA 351 C.F3A 351 C FM 105 105 lax. outside diarm. valve body)rNax. outlside le ngth valve 478mrn ( 18. 74 ')I6/0.3rirm (64 .68 )S Supplemental sheets in form of lists, sketches or drawings may be used provided (1) size is 8-112' x W1. (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 reacorded at top of this form.(10/77)Thi sors (fE000421 may be obtained from the Order Dept., ASME. 345 E. 47th St., New York, N.Y. 10017 96 FORM NV-i1 Back)CERTIFICATE OF COMPLIANCE WVv certify Ihat I.he statelentie s made in Ithis report are correct and that this valve conformrs to the rules of construction if tho ASMC t-le Nu.lear Power Plant Components. Srction Ill. Div. I .'9 ]4 Edition. AddendaSum .1 7(b C eale'.Cud,, Ca~.e .. .D,, ~ ~ ~ ~ L Il-I1/i St- .L)ik k e r 14C .'V.0u', ASN'll. Crurtific:..te cr Arrtlhorrzation No i irlrii~by W.M. Wi Ilelts 1806 to use the MVI Symbol r .)lfrr-N Is( J ly. 961 CERTIFICATION OF DESIGN Desigrn information on fite at Genoerai El ec.-r jc and Perry Stress arralysrs'report (Class 1 only) on life at .General El ec r ic and Perry Jesiqn specifications certihred by' UOyd F. trooiks.PE State CaI i I. r,) ir i i Reg. No.Stress report certified by' Robt2 t L. We i ss PE Sctae t.:;j iirtt(I l oi n .O.s Reg. No Si(tralture not required -list name only 13655 F CERTIFICATE OF SHOEP INSPECTION 1.[ie undersigned. holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors

-nd the Stare or Province of (.)It i 0 and enmployed by K,-irt pe r I n s .of 1.o ru r (-iv " I I [ have inspected the pump. or valve, described in this Data Report on I0- .1978 and state that to the best of my knowledge and belief, the Manufacturer has con%tructed this pump. or valve, in accordance with the ASME Code for Nuclear Power Plant Components.

Dy signing this certificale. neither the Inspector nor his employer makes any warrant. expressed or implied, concerning Ith equipment described in this Data Report Furthermore, neither the Inspector nor his employer shall be liable in any rinanner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection. Date I U A1 19 IJI".igrred c' -. , , -'. * -L. .' ..Commissions Nti 4456 It Ic ryrect e 'IIN.,r I ed.. SI.Ir Pr,-v. .nd N,,I REPORT NO. P0059-011/22/- 37 NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As required by the Provisions of the ASME Code Section X)PNPP No. 9308 Rev. 9111/00 N01-1741 1. Owner: FIRSTENERGY CORP.10 Center Road. Perrv. Ohio 44081 Date 5/14107 Sheet 1 of 2 Unit 1 200073620 & 200081 982 (Repair Org. P.O. No., etc.)2. Plant: Perry Nuclear Power Plant (PNPP)10 Center Road. Perry, Ohio 44081 3. Work Performed By: FIRSTENERGY Nuclear Operating Company PNPP 10 Center Road. Perry. Ohio 44081 Type Code Symbol Stamp NR Authorization No. 33 Expiration Date 9/28/08 4. Identification of System: 121 Nuclear Boiler 5. (a) Applicable Construction Code: ASME SECTION III CLASS 1 ,1974 Edition NAME/SECTION/DIVISION/CLASS 19 75 Addenda Code Case(s) 1728, 1644-4, 272 WINTER (b) Construction Code used for repairs, modifications, or replacements: 1974 VV75 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 Xl Utilized for Repairs, Modification, or Replacements: 1989 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 1821 64084 1B21F47D 1985 REPLACEMENT YES SYSTEM ELECTRIC 7. Description of Work: Removed valve S/N 160890 and installed valve S/N 160856. Used 12 new inlet studs 1-5/8" HT # K745 and 12 new 1-5/8" hydra nuts (6)HT# 590Aand (6)HT#623A. Continued in remarks.8. Test Conducted: Pressure 1032 Hydrostatic- [] Pneumatic-E] Nominal Operating Pressure-ZJ Other- LI psi Test Temperature 142 degrees F Code Case(s) N/A 97 NIS-2INR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back)PNPP No. 9308 Rev. 9/11/00 NOl-1 741 9. Remarks: Used 16 new 1" hvdra nuts HT# 591A. Used 16 new 1" studs HT# OG81 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 Seot. 20 08 Date 15 May , 20 07 Signed FENOC-PNPP OC Tech.(name of repair organization) (authorized reptese tative) (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 bftA/A. 20 01 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" "I" "A" Ohio Comm.(National Board (include endorsements), and jurisdiction. and no.) REPORT NO. P0059-011 As Required by the Provisions of the ASME Code, Settion III. Div. I //P S / -3 7.2 5//>14/2 I.2.3.4.5.Manufatured by ..... ,.....0k.:s.L_ . andS (Name and Address of N Cetlllc.lt Holder)Manufacured fo .........GeneralElc.tric_ _Sai. .Jo-s.,_Ca-C fD-fo-A a IName and Address of Purchaser or Owner)Location of Inallation I orth Perry Ohio Narme and Address)G 471-61ý25.04.03 rev. 6 30 _ __1 (CRN) 10rowong No.) INal'l. 8rd. No.) IYear Buil Valve G471 ]Identifying Nos. N 160856 Model No.. Series No.1 IN CertilAtete Holdr"% Serl.TypeS Safety/Re] ief Saety S rtstt felief; Pilot; Power Actuated 81, r0d Orifice Size 4,8_ " Nominal Inlet Size Outlet Size inch inch I Hal inch 6. Set Pressure (PSIG) --4 80 l~ated Temperature °F Stamped Captacity 9725 3 lbs/hr @ j % Overpressure Blowdown (PSIG) 63L6,7 _Set. Steam 2350 .975 Hvdrostatic Test IPSIG) Inlet Outlet 7. Pressure Retaining Pieces Serial No. or Identification JApplicable to valves for closed systems only)Material Specification Incl. Type or Grade Body Bonnet,or Yoke Support Rods Nozzle Disc Spring Washers Adjusting Screw Spindle Spring Bolting Liner Cover-V-en t--. T-h pe Fl -Ing ..-100.Ok...&.sn 1--AEU 063 53. 3A 26.30.59-50 AFU 038 AFU 074 AEW 015 AUP/AJR/AKA/AJJ/ALR/ AUY/AMR/AJM/AJL

53. 1 sn-S __3_52_LL.-

SA 350 LF2CF3A 45 Cr Mo V 67 SA 182 F 316 A 564-74 type 630 cond. H1100 SA 193-BF7/SA 194-7/SA 194-2H SA 351 CF3A 55.46.7 sn 2 SA 357--IFW 033 .SA 1ob.....V. 0_ [ o .00, TAN Max. outside diam. valve body 479 mm (18.86)"*) Max. outside length valve 1647 nim (611.811)" 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 (3) each sheet is numbered and number of sheets is recorded at top of this form..(10/77) This form [EOOO42) may be obtained ftrm the Order Dept., ASME. 345 E. 47th St., New York, N.Y. 10017?I a::4 98 CERTIFICATE OF COMPLIANCE We certify that the statements made in this reporl are correct and that this valve conforms to the rules of construction of the ASME Code for Nuclear Power Plant Components. Section Ill. Div. t., 1974 Edition. Addenda (Date)Code Case No. N A.*Date 9I- OU2 Signed G. Dikkers & Co NV by (N Cerlltic.te Holder)Our ASME Certificate of Authorization No.~ymbol expires Ist. July 1980 (Date)lout) to use the NV (NVI CERTIFICATION OF DESIGN Design information on file at General Electric and Perry II Stress analysis report (Class 1 only) on file at General El ectri c and Per- I I Boyd P. Brooks Design specificartioncerlified by'C 4 I 'ýr_ F, L, PE State a Uc1 atUtttt Req. No.ceifdhtRobert L. 1.Jeiss Stress report ce ifi~dM -e r L es Stesrpr a/]f~rnri a/ I) linoi s M 14921/62-25749 PE State Reg. 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 and Pressure Vessel Inspectors and the State or Province of Ohio0, P8 and employed by KellriPr I ns-of Long Grove have inspected the pump, or valve, described in this Data Report on.--1 1. 19 -.8 and state that to the best of my knowledge and belief, the N Certificate Holder has constructed this pump, or valve, in accordance with the ASME Code for Nuclear Power-Plant Components By srgning this cerlificate. neither the Inspector nor his employer makes any warrant, expressed or implied, concerning the equipment described in this Data Report. Furthermore. neither the Inspector nor his employer shall be liable in any manner tot any/ersonal injury or property damage or a loss of any kind arising from or connected with this inspection. Date -_____Signed Commissions NB 48o5 llrrpe e~r)(Nart1. ftt.. State Ptoy, and No.)ýr*J REPORT NO. P0059-011/ 132- 13 77 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.10 Center Road. Perrv, Ohio 44081 Date 5/12/07 Sheet 1 of 2 2. Plant: Perry Nuclear Power Plant (PNPP)10 Center Road. Perry. Ohio 44081 Unit 1 200073623 & 200081985 (Repair Org. P.O. No., etc.)3. Work Performed By: FIRSTENERGY Nuclear Operating Company PNPP 10 Center Road. Perry, Ohio 44081 Type Code Symbol Stamp NR Authorization No. 33 Expiration Date 9/28/08 4. Identification of System: 1 B21 Nuclear Boiler 5. (a) Applicable Construction Code: ASME SECTION III CLASS 1 NAMEISECTIONIDIVISION/CLASS WINTER 19 75 Addenda Code Case(s) 1728, 1644-4, 272 1974 Edition (b) Construction Code used for repairs, modifications, or replacements: 1974 W75 Edition Addenda (c) ASME Code Section XI applicable for Inservice Inspection: 1989 NONE Edition Addenda (d) Applicable Edition of Section Xl 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 Code Case(s)N/A Code Case(s)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 1B21F51B 1985 REPLACEMENT YES SYSTEM ELECTRIC 7. Description of Work: Removed valve S/N 160860 and installed valve SIN 160862. Used 12 new inlet studs 1-5/8" HT # OG84 and 12 new 1-5/8" hydra nuts HT# 590A. Continued in remarks.8. Test Conducted: Pressure 1032 Hydrostatic-E] Pneumatic-E] Nominal Operating Pressure-M] Other- El psi Test Temperature 142 degrees F Code Case(s) N/A 99 NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back)PNPP No. 9308 Rev. 9/11/00 NOI-1741 9. Remarks: Used 16 new 1" hydra nuts HT# 591A. Used 16 new 1" studs HT# OG81 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 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 lhe 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 expire 28 Sept. 20 08 Date 12 May , 20 07 Signed FENOC-PNPP OC Tech.(name of repair organization) (authorLn-d 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 K 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 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 o 20 6- Signed Commissions NB 9330 "N" "IA" Ohio Comm.(inspector) U (National Board (include endorsements). and jurisdiction, and no.) REPORT NO. P0059-011 As nequireo Dy me rrovisions of the ASME Code, Section III, Div. I 1//3 2 / -7 3 2-/1. G... Dikkers & Co. NV. Hengelo (0) The Netherlands I?1m dnr f N Crltct a ~ fade 2. Manufaturedfor Genera lec tri'G an Jose, 1lorni (N&an, and Address of Purchs-er or CO ne,)3. Location of Installation -PerF r-y-I--Nf&hF-Pe-rF X- &i 0, 4. G 471-6/125.0U'3 rdev. o 39 1978 WCRN) ID,r ,nng No.) INat'l Brd. No) (Year Buihl 5. valve 47 ___ Identifying Nos. 160862 T p (Model No.. Se s n Ro ) i f IN CetrlffIcle Holder' .S e rlsf No.)s .. ..j,, &.i. f; P ilot, Po we A ctuated V" 10 " Orifice Sir. 0 Nominal Inlet Size outlet Size inch inch inch 6. Set Presaure (PSIG) I L90 Htaled Tempera Stamped Capacitýy 934q3 lbs/hr @ % Overp Sot. Steam 2350 Hydrostatic Test (PSIG) Inlet Outlet 7. Pressure Retaining Pieces .Serial No. or Identification ~585.ilure -F ressure Blowdown (PSIG) _4._2_975 lApplicable to "elves for closed systems only)Material Specification , Incl.:Type or Grade Body Bonneltor Yoke Support Rods Nozle Di sc Spring Washers Adjusting Screw Spindle Spring Bohing 13.46:7 s/n 2 13.24.8 s/n 3 SA 352 LCB SA 352 LCB AEU 053 6103.8 s/ln 3B 26.30.95 s/n36.AFU 099/AFU 028_AEW 010 Aq/a/AJR4&/AJJ LA --R-SV35V(AJA 415 Cr rio yb!6 X-564--7-4-ty-pe -1.30-ynM -.NT-0-tr-T[5A-t94-77SA-1-94-2N- -A-35-1 CHfA-&A 105¶1 (08.77)-I--- t- e ._AFV 028/AFV 086 fax. outside diain. valve body : 477 mm Max. outside length valve:(614. 56)* 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 (3) 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.A-S"2'a 100 CERTIFICATE OF COMPLIANCE We certify that the statements made in this feporl are correct and that this valve conforms to the rules of const uclion 1974 Sl______of the ASME Code tor Nuclear Power Plant Components. Section III, Div. 1., 2974 Edition, Addenda SUfl.i7 Code Case No. ..(Date)Date o9 1 -07T-(3-igned G. Dikkers & Co NV by (N Ce tt....e Hotder) 1806 NV Our ASME Certificate of Authorization No. to use the -.Ist. July 1980 INV)symbol e (paes (Date)CERTIFICATION OF DESIGN Design information on fileat General Electric and Perry I Stress analysis report (Class I only) on file a1 Genera I El ectri c and Perry f Design specifica ioos rertified by' " b ,o,.PE State me.t No. s 3655 Stress report ce ft ili M mdmlrc, nol. !s M4 i4921/.62-25749 PE State Reg. No.Signature not reqitred-list 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 Ohio and employed by Kemper Ins.of Lotly Grove I1I1 have inspected the pump. or valve, described in this Data Report on 28- 1 1 19 .8 and state that to the best of my knowledge and belief, the N Certificate Holder has constructed this pump. or valve, in accordance with the ASME Code for Nuclear Power Plant Components. By signing this certilrcate. neither the Inspector nor his employer makes any warrant, expressed or implied, concerning the equipment described in this Data Report. Furihermore. neither the Inspector nor his employer shall be liable in any manner for any personal injury nr o tropelly damage or a loss of any kind arising from or connected with this inspection. Date _ __1 Signed ,i " 2.Commissions-r)P or) INrot i ad. Stare Prov and NoI)I ;(T ~ REPORT NO. P0059-011 5-2/1- 3 7)'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 NOt-1741 1. Owner: FIRSTENERGY CORP.10 Center Road, Perry, Ohio 44081 2. Plant: Perry Nuclear Power Plant (PNPP)10 Center Road. Perry, Ohio 44081 Date 5/14/07 Sheet 1 of 2 Unit 1 200073617 &200081980 (Repair Org. P.O. No., etc.)Type Code Symbol Stamp NR Authorization No. 33 Expiration Date 9/28/08 3. Work Performed By: FIRSTENERGY Nuclear Operating Company PNPP 10 Center Road, Perry, Ohio 44081 4. Identification of System: 1B21 Nuclear Boiler 5. (a) Applicable Construction Code: ASME SECTION III CLASS 1 1974 Edition NANIE/SECTION/OIVtSION/CLASS 19 75 Addenda Code Case(s) 1728, 1644-4, 272 WINTER (b) Construction Code used for repairs, modifications, or replacements: 1974 W75 Edition Addenda (c ) ASME Code Section XI applicable for Inservice Inspection: 1989 NONE Edition Addenda (d) Applicable Edition of Section XI Utilized for Repairs, Modification, or Replacements: 198 __ 19 N/A Addenda N/A Code Case(s)(e) Design Responsibilities First Energy Corp 6. Identification of Components Repaired, Modified, or Replacement Components Code Case(s)N/A Code Case(s)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 1B21F41F 1985 REPLACEMENT YES SYSTEM ELECTRIC 7. Description of Work: Removed valve SIN 160869 and installed valve S/N 160871. Used 12 new inlet studs 1-5/8" HT # K745 and 12 new 1-5/8" hvdra nuts HT# 623A. Continued in remarks.8. Test Conducted: Hydrostatic-D Pneumatic-E] Nominal Operating Pressure-Z Other- El Pressure 1032 psi Test Temperature 142 degrees F Code Case(s) N/A 101 NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back)PNPP No. 9308 Rev. 9/11/00 NOI-1741 9. Remarks; Used 16 new 1" hydra nuts HT# 591A. Used 16 new 1" studs HT# OG81 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 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, Michael J i , 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.Nationat Board Cerlificate of Authorization No. 33 to use the "HR stamp ex ires 28 Sept. , 20 08 Date 14 May ,2007 Signed FENOC-PNPP / -Z" QCTech.(name of repair organization) (authodzed 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 cerliticale 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 14IN .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 , 20 0-7 Signed Commissions NB 9330 "N" "I" "A" Ohio Comm.(inspector) (National Board (include endorsements), and jurisdiction, and no.) REPORT NO. P0059-011 As Required by the Provisions of the ASME Code. Section III, Div. I 13 3 , 2/4 , 1. Manufactured by G-D -ik-kers_&_Co._..NV ienge1a _ ý Pe-thi s,_d iName and Address of N Certilfcate Holderl 2. Manufacured for .Ge.neraiLELec-tric ,_-San- dose, -Cal]fornta Il~rgmt anPddress of Putchaser or Owner)3. Location of Instllation .Pe-rry I I NOrth erry O0 ne_ _IName and Address)4- _ _ _ __ G_47L-d6LL2_0_,_3.A _ey_6 6- _71 1979 ICRN) (Drawing No.) INail. Brd, No.) (Year Built)5. Va.ve .G4..71 Identifying Nos. IbU__/t IModel No.. Series No.) IN Certificate Holder's Serial No.)Type Safety/Relief

Safety, Pilot; Power Actuated Orifice Size 4,84 Nominal Inlet Size 8 Outlet Size 10 inch inch inch 6. Set Preszsure )PSIG) 1I6% .I ... Rated Temperature 4o,5 -F Stamped Capacity 905732 lbs/hr @ -% Overpressure Blow~1own (PSIG) 'l0 .Sot. Steam Hydrostatic Test IPSIG) Inlet 2350 Outlet .975 7. Pressure Retaining Pieces Serial No. or Identification Vpplrculre to vWrve. For closed systems only)Material Specification Incl. Type or Grade Body* Bonnet or Yoke Support Rods Nozzle Disc ,S Spring Washers Adjusting Screw Spindle sn_6 __5_8_sn I

_AJ_W,_0 Z 3-5-L. B I 26. 30. ..-3 AFU 062 AFU 001 AJE 006 SA_352 I FR SA_3.52_LCB S/_K35Q_LE2 SA 351 CF3A 45 Cr Mo V 67 SA 182 F 316 A 564-74 tVwe 630 cond. H1100 Spring Bolting ANY/AYE/AVS/ ALR/ AWZ/AMR...) .e iai,:03ý AJM/AJL/AJJ Liner 67.17.8 sn 2 Cover --3.--- 8T n-6 Vent. Pipe AKE 050 Flanges AKF 013 AF-V -01 SA 193-B7/SA 194-7/SA 194-211 SA 351 CF3A SA 351 CF8M SA 105-SA7[--T Max. outside diarn. valve body 478 rnm (18,82)'Max. outside length valve 1644i mm (64.72)'* Supplemental sheets in form of lists, sketches or drawings may be used provided (1) size is a-112" 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.(10/77) This form WE00042) may be obtained from the Order Dept., ASME, 345 E. 47th St., New York, N.Y. 10017* .: ' .. 1... .: .-........ '- i ...L 0: ." ii .Q 102 CERTIFICATE OF COMPLIANCE We certify that the statements inade 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 III, Div. 1., 19Z4 Edition. Addenda SUm. ' 76 Code Case No. N. A. IDatel Date SSigned G. Di kkers & Co NV by M Certtt1icl& e Holder)Our ASMF C ertificr of Authorizaton No I 1806 to uset tr V t symbol expires 1st. July 1980 (Date)(NV)CERTIFICATION OF DESIGN Design irformation on file at ]j'c and Perry I I Stress analysis report (Class I only) on file at General El ec tri ndaoPde,-y I I Desipr. specifications certified by' Boyd P. Bro0ks PE State Cal ifornia Reg. No. 13655 Stress report certified by' Robert L. Weiss ,pE State Cal ifornia/II lnois Reg. No. M 14921/62-25749 I Signature not required-list name only.CERTIFICATE OF SHOP INSPECTION I. the undersrgned. holding a valid commission issued by the National Board of Boiler and Pressuore Vessel Inspectors and the State or Province of ____-f O jiO P! -and employed by-- KeZ ..e14l._of mong.GnGOAV]_eL.P[ I have inspected the pump, or valve, described in, this .Data Report on 3 -1/ 19 and state that to the best of my knowledge.ard belief, the N Certificate Holder has constructed 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 equipment described in this Data Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury orproperry damage or a loss of any kind arising from or connected with this inspectron. Date Signred __Commissions .m 480'5*os eclor) INart. 8d. State Prov. and No.).. :...g .- ~ ,,.' j ... : .-. , r t I... ... : I :. ,÷. ..I :,~ ,, . REPORT NO. P0059-011 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.10 Center Road, Perry, Ohio 44081 Perry Nuclear Power Plant (PNPP)10 Center Road. Perry, Ohio 44081 Date 5/14/07 Sheet 1 of 2 2. Plant: Unit 1 200073624 & 200081986 (Repair Org. P.O. No., etc.)3. Work Performed By: FIRSTENERGY Nuclear Operating Company PNPP 10 Center Road, Perry, Ohio 44081 Type Code Symbol Stamp N R Authorization No. 33 Expiration Date 9/28/08 4. Identification of System: 1B21 Nuclear Boiler 5. (a) Applicable Construction Code: ASME SECTION III CLASS 1 L1974 Edition NAME/SECTION/DIVISION/CLASS 19 75 Addenda Code Case(s) 1728, 1644-4, 272 WINTER (b) Construction Code used for repairs, modifications, or replacements: 1974 W75 Edition Addenda (c ) ASME Code Section X1 applicable for Inservice Inspection: 1989 NONE Edition Addenda (d) Applicable Edition of Section Xl Utilized for Repairs, Modification, or Replacements: 1989__ 19 N/A Addenda N/A Code Case(s)(e) Design Responsibilities First Energy Corp 6. Identification of Components Repaired, Modified, or Replacement Components Code Case(s)N/A Code Case(s)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 1B21F51D 1985 REPLACEMENT YES SYSTEM ELECTRIC 7. Description of Work: Removed valve S/N 160857 and installed valve S/N 160896. Used 12 new inlet studs 1-5/8" HT # OG84 and 12 new 1-5/8" hvdra nuts HT# 590A. Continued in remarks.8. Test Conducted: Hydrostatic-E] Pneumatic-LI Nominal Operating Pressure-M Other- LI Pressure 1032 psi Test Temperature 142 degrees F Code Case(s) N/A 103 NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back)PNPP No. 9308 Rev. 9/11/00 .101-1741 9. Remarks: Used 16 new " h,/dra nuts HT# 591A. Used 16 new 1" studs HT# OG81 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 Tesick certify that to the best ot 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 14 May, 20 07 Signed FENOC-PNPP D 'C Tech.(name of repair organization) (authorized representative) (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 fA,! I -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 -loss of any kind arising from or connected with this inspection. Date 20 0-L Signed Commissions NB 9330 "N "I" "A" Ohio Comm.(inspector) (National Board (include endorsements), and jurisdiction, and no.) REPORT NO. P0059-011 As Required by the Provisions of the.ASME Code, Section I1l, Div... 1 a": 2 I. Manufoclured by -. f* n le&io t1~fngeto_(f1)beNet he-rIJ& W__s (Name and Addie$, of N Ce ItfIc.t, 1 Holder) .2 Mahufactured for C.ge ral Electric, San Jose, _Cal iforni a (N~mlrrnd Address o~puFchrpaF Ownrel.Location of ln,,alion Per rýy I + II spa_rdes_ .rth_ P_erry 0ho telme end Add,..s.,.. -N/A_ G 471-6_/125.04.03 rev. 6 154 1979 ICRN) TDraing No.) )N 5 t'I. Brd. No.) (Year Oul"t)5. Volvo W__-__ I._G? .denlit!ying Nos..__________ IModal No., Series No.) IN Crrtlifl.te Holdtr's Serial No.)Type Safety/Relief Sft.a- Oq;Pio;Poww A'Iuai18 Flne. wet ___________ Orifice Size "1,"_ Nominal Inlet Size _ 8" (Flange)________ 1' _.." '..inPch *' inch":".. .. inch*6. Set Prft.sure (P5IG) I.. 90 Ji ated Temperature ..... .Stampetur .apaci-y 9293 m 66 SLamp~d ~ b r Overpros'ure Blowdovin (PSIG) 111,66 drbstatic Test (PSIG) Inet 2350 0 1". 1I 975 SI.AppliFbi)ble I va, oifor Flo.d'yterps 6nly'...7. PressuJre lR~taining] Places.' .". ....Serial No; or 4 "' .Material Specili tion.Identification ' incl. Type orGra .de Body --13.2hALSLLi Bonnet or Yoke o3-LAI_5LtLL .. ._.Support Rods -Nozzle AJW 129 Disc ___5_.__.09_. __s__n 2B SpringWashers 26.30.95 S/n 156 Adjusting Screw CBA 057 CBA 008 Spindle CAD 0011 Spring Bolling ANY ANZ/CAML~AJ/APA/!APB/AN Z CAL/ALR/AWZ _ __Co-ve L,- Psn -52.37.8_s_/n_2. v-in--t. vpe .AWB o44 Fl-1diges ASA 076 ASA 226 ..flax. outside diam. valve body 479 mm (18.8.6)_5A 35ý L1_0 SA 350 F _ _F2: _"_" SA.351 ,F3A 45 Cr Mo 1- 67 5.S 182 F 316 "._.A 564-74 type 630 cond. H1100-SAT3-7SAT-4-TSAT -Zf-5ýA :Jb I U FJA fax. outside lengthi valve 16'47 inm (64.84t)* Supplemental sheets in form of lists, sketches or drawings may be used provided tI) size is.8-I12' x 1", (2) information In items .-2 on this Data Report is included on each sheet.- and (3) each sheet is numbered and number of sheets is.recorded pt top Of this form. ,...'.:1 0/77) Thig form IE00042) may be obramned from the Order Dept., ASME,.345 E. 47th St., New York, N.Y. 10017 N.104 CERTIFICATE Of COMPLIANCE We certlfy that the statements made in this report are correct and that this valve conforms to the rules of construction of the ASME Code Iqr Nuclear Power Plant Components, Section III Div- 1. 1974 Edition, Addends sum. '76 Code Case No. N.e Ap l ntSivlDatl-Date Signed G. Dikkers & Co' NV b ON Certltlcate Holdert NV Our ,laCeriiqate. of Authorization N 18o. to use the NV ASME st. July 1980 " ( (NV)symbol expires St .J -980 CERTIFICATION OF DESIGN Design, information pn file ai GeneraI El ectric and Perry : 4- I spares Stress analysis repor tCiass I only) on tile at General El ectric and Perry II spares , Design specificatiorn certified by' Boyd P. Brooks PE State Ca iforni a .3.".5:5 Stress reporl cear it R obe r" L492 /e-s s :7 4',State Ca ~l f rni a/I linols beg- No:.' M.: 14"92 6 2.4.! ..., : .Signature not required-list name only.CERTIFICATE OF SHOP INSPECTION I. the undersigned. 'holding-a ýlid rorm-i itn. issued the National Board of Boiler -and Pressure Vessel Inspectors and the State or Pro t ,'ince of. I"sVV"O -- and employed by Royal Indemnity Co of -___ have inspected the pump, or valve, described

.n this.. I Data Report on r' .19 -79 and state that to the best of ny knowledge and belief, 'the N Certificate Holder has constructed this pump, or valve, in accordance with the ASME Code for Nuclear Power Pla.nl Crnponcnts.

)3y signing this ceiljficale, neither the Inspector nor his employer makes any warrant, or implied, concerning the equipment described in this Data Report. Furthermore. neither the Inspector nor his frnployeor shall .be liable in any manner for * 'tj),ar °nal in ry or perty damage or a loss of any kind arising from or connecled with this inspection: Dare .19 4 Signed .1__ ____ urrirrss~ions b Inspectoi INat I. Bd., Srate Prv. and No.)I T.. .-7* .. , ..... REPORT NO. P0059-011 113 Z/ 3,&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. 9308 Rev. 9/11/00 N'0-1741 1. Owner: FIRSTENERGY CORP.10 Center Rnad Perry. Ohio 44081 Date 5/14/07 Sheet 1 of 2 2. Plant: Perry Nuclear Power Plant (PNPP)10 Center Road, Perry, Ohio 44081 Unit 1 200073615 & 200081975 (Repair Org. P.O. No., etc.)3. Work Performed By: FIRSTENERGY Nuclear Operating Company PNPP 10 Center Road. Perry. Ohio 44081 Type Code Symbol Stamp NR Authorization No. 33 Expiration Date 9/28/08 4. Identification of System: 1B21 Nuclear Boiler 5. (a) Applicable Construction Code: ASME SECTION III CLASS 1 1974 Edition NAME/SECTIO t/DIVISION/CLASS 19 75 Addenda Code Case(s) 1728, 1644-4, 272 WINTER (b) Construction Code used for repairs, modifications, or replacements: 1974 W75 Edition Addenda (c) ASME Code Section XI applicable for Inservice Inspection: 1989 NONE Edition Addenda (d) Applicable Edition of Section XI Utilized for Repairs, Modification, or Replacements: 1989 19 N/A Addenda N/A Code Case(s)(e) Design Responsibilities First Energy Corp 6. Identification of Components Repaired, Modified, or Replacement Components Code Case(s)N/A Code Case(s)Name ot Name ot Manufacturer Nlat. Other Year Repair, ASME Component Manufacturer Serial No. Board ID. Built Replacement, Code No. or Modification Stamped PIPING GENERAL 1121 64084 1B21F41B 1985 REPLACEMENT YES SYSTEM ELECTRIC 7. Description of Work: Removed valve S/N 160848 and installed valve S/N .160849. Used 12 new inlet studs 1-5/8" HT # K745 and 12 new 1-5/8" hydra nuts HT# 623A. Continued in remarks.8. Test Conducted: Pressure 1032 Hydrostatic-LI Pneumatic-Li-psi Test Temperature 142 Nominal Operating Pressure-E] Other- E]degrees F Code Case(s) N/A 105 NIS-2INR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back)PNPP No. 9308 Rev. 9/11/00 NQ1-1741 9. Remarks: Used 16 new 1" hydra nuts HT# 591A. Used 16 new 1" studs HT# OG81 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 Sept. , 20 08 Date 14 May .20 07 Signed FENOC-PNPP ,--'/ .-OC Tech.(name of repair organization) (authorized representative) (title)CERTIFICATE OF INSPECTION/INSERVICE INSPECTION I, I lnKoc, &C. , -holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors and cedificate of competency issued by the jurisdiction of OHIO and employed by HSB CT. at 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 l , 20 -1" Signed Commissions ________"_'_"_______ ,,__(inspector) (National Board (include endorsements), and jurisdiction, and no.) REPORT NO. P0059-011 ncrji rrtil or-r.l!, AP'U Z1Ai--IY HELIEF VALVES' ' .j -%(As Required by the Provisions of the ASME Code, Section III. Div. I / -_/1. Mro....facluied by (. Dikkfrb ý Co. N.V. lleligelo (0) The tlecherlands IN-n. -rid Address of Marucarl 2. or -Guere'al .Electric Sar Jose .CAlif.(Name ar,.(J Adre8s fI Purchaser or Owr 0-)3. Location ol histallatioi dor ih Perry, Ohio Perryl.(Narrio -rd Adareiss)4. ---------------------- -4II-.b/125. U4.U4. 24 (C:RN) (OraD -mrg No.) Brd. No.) (.e,, BOuO 5.Valve Type Ofitic" Size-4 7 1 ...Identifying (Mortl No.. Series No.)Saetly. Satety Relief; I'rot. Power A uaealed....... .84 Norminal Inlet Size inch Nos. .LU 49 Serial No I.......... Outlet Size inch inch 6. Set Pressure (PSIG) 1_1b5 Slamped Capacity. 9 57.7))2. -Sal Steam Hydrostatic Test (PSIG) Inlet _. 2350.I7. Pressure Retaining Pieces... .. .. Rated Temperature

... ...lbs/hr @ / 1.'. ,' % Overpressure Slowdown (PSIG) .96., 2 S Oute .........

o 975.(Applicable to valves for closed systems only)Serial No. or Identification Material Specification Incl. Type or Grade Body Bonnet or Yoke Support Rods Nozzle Disc Spring Washers Adjusting Screw Spindle Spring Boiling Other Pieces Liner-Cov e r Veir. pi pe-, 1, 1anger; ..0..S Ln. L..AEU. D31 5iJ.U3_8 Z11b53 /I3.. -A1EW 00 1. .....AUP., AiR., AKA,_AJJL.,.AUY a AItW* AJH--b4_04.83 s/ni 2 5 d.4f3. 7 yn 7. .-AI'W 030 Al?), 022/AFV) U91 SA 352 1Glb--. ..-63IE 2 _...ld i IU.ALR, ..SA.AJ i'lix. ,uUt:;tL! diam. valve body: Utax. out side leng[h valve 47b ,rat (18.74 inch)1645 nun (64.76 inch)* Supplenentlal sheets in form of lists, sketches or drawings may be used provided (1) size is 8. 112" x I1". (2) information in items 1.2 (in 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.11/76)This form (E000421 may be obtained from the Order Dept-, ASME, 345 F. 47 St., New York, N.Y. 10017 106 ,,V /" A FORM NV-i (Back) &l I CERTIFICATE 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 IIf, Div 1 9 7 4 Ed;rion. Addenda iii'. 76 Code Case No.................... Date 1U0T:71 ..... Signed G.. Dikkerts h. .N.V. _ by W.IHt. Willenis Our ASME Certificate of Authorization No...............I83 to use the NV symbol expires.. s Juy._ 9INV)arte) -CERTIFICATION OF DESIGN Design information on file at ...... _Generat _ ect r ic and -erry Stress analysis report lClass I only) on file at Gene ra I E1eC t r ic. and Ie rry.Design specifications certified by' --_ioyd P_ ...-PE State ...Cali f.o.r.ni a................... Reg. No.. .. -I35 Stress report certified byr .. Robet- L. We is.s .. .... .PE State _.._..CaLi.forcida/IL I ino is R..... ..... Peg. No. P14921 Signature not required-list name only./62-25749 CERTIFICATE OF SHOP INSPECTION I. the Undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Ve:ssel inspectors and the State or Province of _ _. Sh IDO .. and employed by ...Kernpe r I n s p.of .L,___ cQ( ..,[.L .............. have inspected the pump. or valve, described in this Data Report on[... LL.- --__ -- i97. and state that to the best of my knowledge and belief, the Manufacturer has cor-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 equipment described in this Data Report. Furlherriore, neither the Inspector nor h-is employer shall be liable in any manner for any personal injury or property damage of a loss of any kind arising from or connected with this inspection. Date 1AJ1J .. ..-19_78. .)Signed L__'- i d._---2........... .. Commissions ....NB 4456 (Inspocrorl I(N it'. Ew.. Stale Pro,. .nd No.l REPORT NO. P0059-011 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.10 Center Road, Perr,, Ohio 44081 2. Plant: Perry Nuclear Power Plant (PNPP)10 Center Road. Perry, Ohio 44081 Date 5/14/07 Sheet 1 of 2 Unit 1 200174507 & 200247881 (Repair Org. P.O. No., etc.)Type Code Symbol Stamp NR Authorization No. 33 Expiration Date 9/28/08 3. Work Performed By: FIRSTENERGY Nuclear Operating Company PNPP 10 Center Road, Perry, Ohio 44081 4. Identification of System: 1 B21 Nuclear Boiler 5. (a) Applicable Construction Code: ASME SECTION III CLASS 1 NAME/SECTION/BIVISIONI0/CLAS S WINTER 19 75 Addenda Code Case(s) 1728, 1644-4, 272 1974 Edition (b) Construction Code used for repairs, modifications, or replacements: 1974 W75 Edition Addenda (c) ASME Code Section XI applicable for Inservice Inspection: 1989 NONE Edition Addenda (d) Applicable Edition of Section XI Utilized for Repairs, Modification, or Replacements: 1989 , _19 N/A Addenda N/A Code Case(s)(e) Design Responsibilities First Energy Corp 6. Identification of Components Repaired, Modified, or Replacement Components Code Case(s)N/A Code Case(s)Name of Nbame of Manufacturer Nat. Other Year Repair, ASME Component Manufacturer Serial No. Board ID. Built Replacement, Code No. or Modification Stamped PIPING GENERAL 1821 64084 1B21F41K 1985 REPLACEMENT YES SYSTEM ELECTRIC 7. Description of Work: Removed valve S/N 160888 and installed valve S/N 160883. Used 12 new inlet studs 1-5/8" HT # K745 and 12 new 1-5/8" hvdra nuts HT# 590A. Continued in remarks.8. Test Conducted: Hydrostatic-L] Pneumatic-LI Nominal Operating Pressure-Z Other- El Pressure 1032 psi Test Temperature 142 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 N0I-1741 9. Remarks: Used 16 new 1" hydra nuts HT# 591A. Used 16 new 1" studs HTf OG81 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 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 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 14 May., 20 07 Signed FENOC-PNPP /2-' -- OC Tech.(name of repair organization) (authorized representative) (title)CERTIFICATE OF INSPECTION/INSERVICE INSPECTION I, G- LA.M ,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 N)A I 20 02 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 "P.R" 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 0-1 Signed ,-,-yAOA Commissions 9B (inspector) (National Board (include endorsements). and jurisdiction, and no.) REPORT NO. P0059-011 AS Mequtred by the Provisions of the ASME Code, Section III, Div. I // 2 / -2 '2 1. Manufctured by _. G. Dikkers & Co. NV. Hengelo (0) The Netherlands leNda"0'ecn and 8s, oý A c N eg~st lc'e. Mo r n ..2 Manufactured for General Electric, ban Jose, Vlornl a INmrns and Addles, ofPu.ch..tor Owne." 3. Location of instellation _er[ I + II spares -Perry Uito G 4.71-6/125. .'- .143 *1979 iCiNi G4171 iDrwirng No I I N- ,.stt If J 3 IY, r puitl)5. Valve ......... identifying Nos.No, No. ýiVAf R/Rel ief (N C,_,,__ c,, .od*Vs No.)Typq I Reli.f; Pilo; Power Kaz.ed 8" (Flange). .10" Orlikce Size Nominal Inlet' Size Ou-let Size a' LC Inch inch inch 6. Set Pressure (PIIG) 11 65 " 5ated Temperature. ., Stme aaiy 905732. .b/h (P.Stampe) Cacit, 90 2 I r. % Overprqs4re El0owdpwn (P$IG)sat..Steam Y50 ,975 Hydroetatic Test (MP1() Inlet -Qutllt 7. *y~vir ti (Applcable to IWesl for ciosed yvt.ems. only)7. RertaIning P "' ,.e, Serial No. or Materiel a Identification .! pjcI. Typo or Greo: s ody Bonnet or Yoke Support RodS Nozzle Disc Spring Washe, a Adjutling' SFre, Spindle Spring Boating--f-I ang-es-05.19.8 s/n 4 01.12.8 s/n 0 SA 352 LCB AJW 085.55.08.9 s/n IB 26.30.95 s/n 1-22 ASB 103 AS6 018 APG Oil ANY/ANZ/AJS/AJM/APB/ANZ

53. 0. 1s/n-1 53.23.&f-f

ý 9 A- 06 -SA 1~1.. ..l SA 350 LF2 SA 351 CF3A_S1Cr Mo Vý 67 A--56W"-74 type 63 c ond. H1100-A35TTTUrI~SWIO5-SAi08~Max. outside diam. Valve body Max. outside length valve 4 7 8 mm (18.82)1645 mm (64.77)S sheets in form of lists, sketches or drawings may be used provided (i) size is 8-lIT x 11". (2) information In Items .1-2 on this Data Reporl is included on each sheet, and J3) each sheet is numbered end number of sheets is recorded at top of this fprm.110/771 This form (EOOO42) rnry be obtained from the Order Dept., ASME, 345 E. 47th St.; New York, N.Y. 10017?'* ;!!; ii' ', 108 CERTIFICATE OF COMPLIANCE We cerlify that the statements made in this report are correct and th4l this valve conforms to the rules, of construction of the ASME Code tor Nuclear Power Plant Components. Section 111, Div. 1.. 1974 Edition, Addenda sum. ' 76 Code Case No N.A. lDatel Dare 0l') &-- Signed G. Dikkers & Co NV b_______-__ _ _Mr i Cerlrlcatne Holder).. .... .. ... .. .. ... .... ..1806 .. .. ..rqv UUFr Aom I)[v Leirn ilic~l o or /Authro riztiorn No1.symbol expires 1st. July 1980 eDole)_Su5e rhe INV)CERTIFICATION OF DESIGN Design information on file at General Electric 'and Perry I + I spares Stress analysis report fCI ss I Onlyi on file at General Electric and Perry.÷ II spares Design specifications certified by' Boyd P. Brooks PEState California .L.ei. No. 13655 .-,aess report certitdv, Robert L."State Cat na/fl olnol sg,. No. N 14921/62-25749 Signature not required-list name only.CERTIFICATE OF SHOP INSPECTION. I. the undersigned, holding a valid commi n issued the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of a__ -V"l -and employed by Roya I Indemn i ty Co.of Ae,3YoQ1 have inspected the pump, or valve, described in this Data Report on 26 September --. i 7 and stale that to the best of my knowledge and belief, the N Certificate Holder has constructed 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 anywarrant, 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 a inliry Orproperty damage or a loss of any kind arising from or connected with this Inspection. Date 1Y 1 t Signed 141 -mmni ssions -______Al ________S______3__ ln spea , Iur (Notl 1. a .Store Prey anld NoI'I,..T '.". REPORT NO. P0059-011 1B21-383 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: 2. Plant: FIRSTENERGY CORP 10 Center Road, Perry, Ohio 4,1081 Perry Nuclear Power Plant (PNPP)10 Center Road, Perry, Ohio 44081 (Repair Org P.O. No., etc.)Date 5/16/07 Sheet 1 of 3 Unit ONE ORDER 200170106 Type Code Symbol Stamp NR Authorization No. 33 Expiration Date 9-28-08 3. Work Performed By: FIRSTENERGY Nuclear Operating Company PNPP 10 Center Road. Perrv Ohio 44081 4. Identification of System 1B21 NIJCLEAR BOILER SYSTEM (1B21)5 (a) Applicable Construction Code: ASME SECTION III NB 1974 Edition rJAME/SECTIONIDIVISION/CLASS 19 75 Addenda Code Case(s) 1728, 272 1644-4 WINTER (b) Construction Code used for repairs, modifications, or replacements: 1974 WINTER 75 Edition Addenda (c) ASME Code Section XI applicable for Inservice Inspection: 1989 N/A Edition Addenda (d) Applicable Edition of Section XI Utilized for Repairs, Modification, or Replacements. 19 89 EDITION 19 N/A Addenda N/A Code Case(s)(e) Design Responsibilities FIRSTENERGY NUCLEAR OPERATING COMPANY PNPP 6 Identification of Cornponents Repaired, Modified, or Replacement Components Code Case(s)N/A Code Case(s)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 7-560 N/A 1B21 1976 REPLACEMENT YES MORILL F028C 7. Description of Work: Replaced poppet with new poppet S/N 5, HT# 215143 using (18 )-DOUBLE ENDED STUDS HT TRACE # M23553 and (1 8)-HEAVY HEX NUTS (6) HT.TRACE # J206,.AND 12)HT TRACE # OL53.8. Test Conducted: Hydrostatic-E]Pressure 1032 psi Test Temperature Pneumatic-E] Nominal Operating Pressure-N Other- D 142 degrees F Code Case(s) N/A 109 NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back)PrJIP 1,,o. 9308 Rev. 9/11/00 NQ1-1741 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 VW. 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 Xt 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 Sept 28 , 20 08 Date 5/16/ 2007_Signed FENOC-PNPP Q__ _ _ _ OE (name of repair organization) L authonzed repres~Stative) (tile)CERTIFICATE OF INSPECTION/INSERVICE INSPECTION I, 1Pc\ .D M, -L-Ký 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 A C(-. iof tAARY&rzo¶' , Ck. have inspected the repair, modification or replacement described in this report on W 20 U7 and state that to the best of my knowledge arid belief, this repair, modification or replacement has been completed in accordance with Section XI of tie 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 emptoyer 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 b-7 Signed "- K.l tA. 'U '134 Commissions R0, q3z!l tL& Co.uk-.(inspector) "J (National Bo rd (include endorsements), and jurisdiction. and no) REPORT NO. P0059-011 FOIEM NIPV.I MANUFACTUIEERS' DI'A REPOIT 1OR NUCL(E.. PUMPS OR VALVES*A-s Reqruired by tie Provisions of the Code HIales 1. Manufactured bAtvwood & Morrill Co.Inc.,Salern, Mass .01_970 Order No.1 1559-0](fiaoe , Address of S anufa-xurer)

2. Manufactured for OGr.erI if__r_ (O_ Ch Order No. ZF771i_(NSe and Addre-,).3. Ow-ner M] I .. "l " riev[Ilumi Llnc 4" Location of P]1.trs-c4-}r Przsy~rsy 1-cr lan[ ~vtrr 7_ .-...5, Pump or Valve Ide .nrfication NAIhL&S /NI~ 7-560 2~'57~54~

NaiiiSf~arn Tholal-ion Vislvr'~2r," q7c;iý Main Stjaýýýýve For Service in Main Steam Piping.System (Brief dencription of service for -hich equiproent as deslined)(a) Drawing No. 135rQ I L Prepared by----ROhLeb tJKflCL (b) National Board No. N /A 6. Design Co.diri'ors 1 3 7 5 psi F- -(T on 0~ rat c~)/-. !7.. The material, design, construction, and workmanship complies wirh ASME Code Section 111. Class Editicon 1974 Addenda Date N/A , Case No. L622 Nisri No.. " -Nl-rrrl Spec, No.Manuf actrern Remarks (a) Castingrs ady- -SA~C21&MCB- -u ak er:- l-lo-y SA .5D 8 F 4 F --in- +(b) Forgings Ponnet q A~ C -4r 0 (.r-_ .T, --(-nnI n ,r_ *q- ', 1.q/M 8-f60 Cover -SA10-5(QT) C-nn r-5.rnil S/N 7-5%0 k../'Supplementa1 sbheets in far- of list,, sketchre or drawings may be used provided (1) size is 8,'%' 11", (2) inforrntion in items, 1, 2, 5 and 5b on this data report is included on each sheet, end (3) each sheet is numbered and nuraber of sheets is recorded nt top of this fom.110 FOtmI NiP-I (back).... M-1, No.taterial $Cpt. No.Manufact-re! R-earks (c) Dlting__CoLrS~n d s__(i1L___ !AG4r_9_T _Bh2_3_-_C-La__JQw3'1s0x1&aon$j Heat*~ 1111188 J__ __c'e ic_ i-u Lt___ L8_-I~A~1O CriR 2~JToy~Dvson&Sons Heat4*134951

ý -, -, -__ __ __ 1_____1 --___ ---I C1a~ss5__i4_____________________________

4 ~ __________________ 6 _____________________(d) Other Poats* Msi n r- (21ýzmng~ ~r R Ty q qf-snr-l I I*Nof t-mbh sea-_J Jb.viifbhahs a c a dr Msr g ncti S* -x-* anans~mllsip JlL__t f .a design is nfllor n dp _ _ _ _ _ _ _ _BJody Poppet 1. iiydrostatic tot 2L75. 14_0_ psi.CERTIFICATION OF DESIGN Design infortmationt on file at31 .Geit_ ja _iP I ' e Stress analoysis reorot on file at i-fn.I .c.Tose fly3liforniy, Design spacilications certified by----Ranji t-Raenj an-.ho s h (1) Prof. Eng. State CaIif egg. No.I 6f_'3+/-71 Stress analysis tcpot cetified by IQOt O (1) Prof. Eng. State _aLS-S Reg. No..-O-9..(I) Signature not r-q, ired. List name only.We Certify that the statements made in this report are correct.Date__ -24 i9 _igond A3\t"."Morr, 11 -(~aoJt ast orert Certificate of Ataiotizatiof No. _ N -] expires a----_____219_7-7 -V' /CERTIFICATE OF SHOP INSPECTION I, the uncdersrignetd, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and/or the State of Province of MaStS. .bL. Eý_tts and employed by S] r' " "tS oLf axrtfoDrrt._Co have inspected the equipment -e scr{ld-ir, %s Data Report on 3 -? 19-36-, and stare that to the best of my knowledge and belief, the Manufacturer has consrtrrcted this equipment in accordance with the applicable Subsections of ASME Code, Section Ill. .By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concern-ing the eqiipmeat described in this Data Report. Furthermore, neit-ter the Inspector nor his employer shall be liable in any manner for any personal injuoy or property damage or a loss of any kind arising from or connected with this inspection. Date 3-24. 1976 Commissions Ma s s -1(264 nhion rnmrnirzrinn (tnseertor) a '.t Gerard Cocuzzo (Nationat Board. Stare, Pro-ione and N-.)Printed in Uq.S.A. (6/72)rThin form (E37) in obtainobte trom tht ASME. 345 E. 47th St.. N-, York, N.Y. 10017 REPORT NO. P0059-011 FORM N 2 CERTIFICATE HOLDERS DATA 0REPRT FOR .IDENTrCAL NUCILEAR PARTSADAPUTNNE A","s: R q9 us red.' by the:' P,,y vta6, ASMEtCode Sqct Ii"r. III.Not To Exceed.One.ay:s Production ...:. -.2alcz, ý6%-C Ce'eland. Electric IDCne odNrhPryOhlo .4O081..IQ 21/6 7 -626-D, R'ev 0 SA:16:, 76NQ s /A: 190.. ." 5- : ." .. ... .. AS ECoe S r'- it j7. -.'..'.. : -.-'NO ...' ......., ..-.-.I :':-" !" i~i,. ......0 10....._*',

A .....'* .. ...or- " " "" ".ed Dv A e on. Ass'em ...-'y6c1 'i. Re I Th i s cerificationo m hýee the rterrements

'o, ASME Sect onEllh:ornii. lnirrrtsS

,, 8 1. /, Sr ia N O" r I" T 11~r T5& ýA N NA enirn iii -. -~161 121 met liSt'I lOL liii'tat 1151 1161.'-201-I -12cr -I..--ill 0FRMN24b back) HT. 215143* ..: .: .: :~~ ~~~. :*:...*: ................

.CEB IJFICATY0ON OFmi 6EI: : ..... : " .. .. " : ~ ~ .. E S .G.::i:.:

N. -.:-[OO~g'ta cI C.yot, ih.Id by Clyde Tý Hj.h lp steCAIBo 158s n .-% .Herber* C k .. S CE~RIFICA fE OF SHOP COMPUIANCý,E:

tAe~nly tha In.e sta-me6f mcei Dereon atZorc n ht hsIhSI Pp con--r 1_ýo oi mh Sd aeScinII oa / 5 Tý At tod &t or Il C1 co-nc.CERT HIFrICAT O SOPtPETIOPl.ad 1vod -; by , Co N-,-1 rlI~ REPORT NO. P0059-011 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.10 Center Road. Perry, Ohio 44081 Date 4-27-07 Sheet 1 of 2 Unit 1 200063010 (Repair Otg. P 0. No., etc.)2. Plant: Perry Nuclear Power Plant (PNPP)10 Center Road. Perry, Ohio 44081 3. Work Performed By: FIRSTENERGY Nuclear Operating Company PNPP 10 Center Road, Perry, Ohio 44081 Type Code Symbol Stamp NR Authorization No. 33 Expiration Date 9-28-08 4. Identification of System: Reactor Recirculation System 1 B33 5. (a) Applicable Construction Code: ASME Section III Class 1 -NF 1974 Edition NAME/S ECTION/DIVlSION/CLASS Winter 1975 Addenda Code Case(s) 1728, 1644-4, 272 (b) Construction Code used for repairs, modifications, or replacements: 1974 W75 Edition Addenda (c) ASME Code Section Xl applicable for Inservice Inspection: 1989 N/A Edition Addenda (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 FENOC 6. Identification of Components Repaired, Modified, or Replacement Components N/A Code Case(s)N/A Code Case(s)Name of NFame of Manufacturer Nlat. Other Year Repair, ASME Component Manufacturer Serial No. Board ID. Built Replacement, Code No. or Modification Stamped Piping General Electric IB33 64076 1B33G70 1985 Replacement YES System 64B (see -remarks)7. Description of Work: Replace 100 KIP, E-Systems snubber serial number 60 (existing) with replacement serial nzimher 57 (new'l serial number 57 (new)8.Test Conducted: Hydrostatic-El Pneumatic-E] Nominal Operating Pressure-EI Other- E]Pressure ,)A psi Test Temperature ^) A degrees F Code Case(s) N/A 112 NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back)PNPP No. 9308 Rev.' 9/1 1/00 NQI- 1741 9. Remarks: Functional Location number 1B33G7064B was oriqinally installed as a General Electric hanoer nurnber 1B33-G006-S369B as identified on isometric 34-0021-00001 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, Russ Matthys , certify that to Ihe best of my knowledge and belief the statements made in this report are correct and the repair, modification or replacement of the iterns 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 9-28-2008 Date 4-28-2007 Signed FENOC-PNPP OC Supervisor (name of repair organization) (authorized r ,epre5` tative) (title)CERTIFICATE OF INSPECTION/INSERVICE INSPECTION I, Thomas G. Laps holding a valid corm-nlssion issued by The National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHI)and employed by HSB CT. ol Hartford, CT. have inspected the repair, modification or replacement described in this report on 200-7 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 0- Signed ommissions NB 9330 "N"I"A" Ohio Comm (inspector) dy (National Board (include endorsements), and jurisdiction, and no.) REPORT NO. P0059-011 11 ? 127P6 i 113

REPORT NO. P0059-011 NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As required by the Provisions of the ASME Code Section XI PPPP Ho. 9308 Fe,. 9/11/00 NOQ-1741 1. Owner: FiRsTrENERGY CORP.10 Center Road, Perry, Ohio 441081 Date .V- 7 a- ro Sheet 1 of 2 Unit 1 200063012 (Repair Org. P.O. No., etc.)2. Plant: Perry Nuclear Power Plant (PNPP)10 Center Road, Perry, Ohio 44081 3. Work Performed By: FIRSTENERGY Nuclear Operating Company PNPP 10 Center Road. Perry. Ohio 44081 Type Code Symbol Stamp NR Authorization No. 33 Expiration Date 9-28-08 4. Identification of System: Reactor Recirculation Svstem 1B33 5. (a) Applicable Construction Code: ASME Section III Class 1 -NF ,1974 Edition NAME/SECTION/DIVISION/CLASS Winter 1975 Addenda Code Case(s) 1728, 1644-4, 272 (b) Construction Code used for repairs, modifications, or replacements: 1974 W75 N/A Edition Addenda Code Case(-(c) ASME Code Section X1 applicable for Inservice Inspection: 1989 N/A 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 FENOC 6. Identification of Components Repaired, Modified, or Replacement Components s)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 Electric 1 B33 64076 1B33G70 1985 Replacement YES System 66B (see remarks)7. Description of Work: Replace 100 KIP, E-Systems snubber serial number 59 (existing) with replacement serial nrumher 26 (newt 8.Test Conducted: Hydrostatic-E] Pneumatic-LI Nominal Operating Pressure-L] Other- LI Pressure PR psi Test Temperature N M degrees F Code Case(s) N/A 114 NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back)NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back)PNPP No. 9308 Rev. 9/11,00 ý 1741 9. Remarks: Functional Location number 1 B33G7066B was originally installed as a General Electric hanger number 1B33-G006-S371B as identified on isometric 34-0021-00001 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 sheel is numbered and the number of sheets is recorded on the front of Ihis form CERTIFICATE OF COMPLIANCE I, Russ Matthys , 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 sa expires 9-28-2008 Date 4-27-2007 Signed FENOC-PNPP Qj. ;::a Q-C SLlpervisor (name of repair organization) (authorized representaN e) (tithe)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. ot Hartford, CT. have inspected the repair, modification or replacement described in this report on 2 20 0- and state that to the best of my knowledge and belief, this repair, modification or replacement has been cornpleted 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 Q,:_ Signed Commissions NB 9330 "N"I"A" Ohio Comm I(inspector) _)(National Board (include endorsements), and jurisdiction, and no.) REPORT NO. P0059-Oil.... ~ FS¶T1 t1fl1 Ynt~tP F1I'vidtlf zdt IV fty, I IT~ ~ ~ Blac Fox R STulsa Ck~hom~74102 .--£ poi P.g ~r.1.. D~-4p. ,4g -,- .L o..d C. C'oeT'tN¶ o 2.. N6:. tl N Y S I-, I"~2 a o'(60)ci)Tn r^;";:* ýo Ad* I II Y'--d ~ ~ ~ ~ O .F"FCT1: COF COK.V'IlA NIC c-. c-N-JA f4 A 6BZ1fi .1 706ý,NZ42,1

-- -C, ASM K' ,tk, IE A, 'IN ,,do., W __________

CIATMflýa11O O DESIGN:, E Systemns, 1). , otkDvision, Salt Lak'e City, uT I" F4.o,- Lo-d C.....dY D.,. I,-..0 FP ESytm Y n Mote Diiso Salt fT.riy DIg5.f_[",o. C.H 'f;.db y 11) M, D P t~ ____________ P- 1_Rob'.e-mdcr t Lee Warren IlIl Utah ~34))1 1114. f1.. 24 9 1p*I~ 1 T.... ...115 W-1. Mak.4. .~ro Nd "' i 4d 6---d I by t. e 3o..14 j d 04. I'mu~ ~Is n .t.o Isbe In "Nw Y rk. a .w X..tf_*4 -- ý-~ s 44 YA- f 0't b I.".4' ~ ý 0. -fl I-~ 4 S .. ir -.44444 4-4 4.4 --4 4 REPORT NO. P0059-011 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 5-2-2007 10 Center Road, Perry, Ohio 44081 Sheet 1 of 2 2. Plant: Perry Nuclear Power Plant (PNPP) Unit I 10 Center Road, Perry, Ohio 44081 200063011 (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 9-28-08 4. Identification of System: Reactor Recirculation System 1B33 5. (a) Applicable Construction Code: ASME Section III Class 1 -NF 1974 Edition NAME/SECTION/DIVISION/CLASS Winter 1975 Addenda Code Case(s) 1728, 1644-4, 272 (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 N/A Ni/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 FENOC 6. Identification of Components Repaired, Modified, or Replacement Components Name of Name of Manufacturer Nat. Other Year Repair; ASIVME Component Manufacturer Serial No. Board ID. Built Replacement, Code No. or Modification Stamped Piping General Electric 1B33 64076 1B33G70 1985 Replacement YES System 65B (see remarks)7. Description of Work: Replace 100 KIP, E-Systems snubber serial number 61 (existing) with replacement serial number 63 (new)8. Test Conducted: Hydrostatic-E] Pneumatic-LI Nominal Operating Pressure-El Other- El Pressure , A psi Test Temperature ,,, A degrees F Code Case(s) N/A 116 NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back)PNPP No. 9308 Rev. 9/11/00 t101-1741 9. Remarks: Functional Location number 1 B33G7065B was originally installed as a General Electric hanqer number 1B33-G006-S370B as identified on isometric 34-0021-00001 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. Russ Matthys , 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 9-28-2008 Date 5-2-2007 Signed FENOC-PNPP (L, r"\ O OC Supervisor (name of repair organization) (authorized represkntative) (title)CERTIFICATE OF INSPECTION/INSERVICE INSPECTION J, 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, CT. have inspected the repair, modification or replacement described In this report on I ,- 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 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 Irossf any kind arising from or connected with this inspection. Date _ 20 01 Signed _Y VYY'V-4 -Commissions NB 9330 "N"I"A" Ohio Comm (inspector) k (National Board (include endorsements), and jurisdiction, and no.) REPORT NO. P0059-011-P IF C-IP4S DaT4j gpA__________C (cl nsMCt rN&~rTJ (zjb.X)F TitC ,i- --- c, -1 " -17 Il C~ ,r tee4~ Yr-, IlltkOosi or s- I____711 10F El ~ m El :1!'Ii IW Li~ -E OHM44C~Ij Sack)r* I .!: .:i-ýj. Yzr Sý, ON.. ....... .... REPORT NO. P0059-011 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.10 Center Road, Perry, Ohio 44081 Date 4/16/07 Sheet 1 of I Unit 1 Order 200257554 (Repair Org. P.O. No., etc.)2. Plant: Perry Nuclear Power Plant (PNPP)10 Center Road, Perry, Ohio 44081 3. Work Performed By: FIRSTENERGY Nuclear Operating Company PNPP 10 Center Road, Perry, Ohio 44081 Type Code Symbol Stamp NR Authorization No. 33 Expiration Date 9/28/08 4. Identification of System: C41STANDBY LIQUID CONTROLS NC 5. (a) Applicable Construction Code: ASME SECTION III CLASS 3 1974 Edition NAME/SE CT IOP/DIVIS ION/CLASS WINTER 19 75 Addenda Code Case(s) *N242,N272,N413, N240, 1644-5,1644-8 (b) Construction Code used for repairs, modifications, or replacements: 1974 .W75 Edition Addenda (c ) ASME Code Section XI applicable for Inservice Inspection: 1989 NONE Edition Addenda (d) Applicable Edition of Sectiorn XI Utilized for Repairs, Modification, or Replacements: 1989 __ 19 N/A Addenda N/A Code Case(s)(e) Design Responsibilities First Energy Corp 6. Identification of Components Repaired, Modified, or Replacement Components Code Case(s)N/A Code Case(s)(_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 C-41 108 1C41- 1985 REPLACEMENT YES SYSTEM POWER D0003 7. Description of Work: REPLACED (6) 3/4"X10 SA 193 HT TRACE# 1IG5257 CAP SCREWS, AND (8)` X10.HEAVY HEX NUTS UNC-2B. HEAT TRACE # K534..8. Test Conducted: Hydrostatic- [i Pneumatic-E] Nominal Operating Pressure-E] Other- El Pressure N/A psi Test Temperature N/A degrees F Code Case(s) N/A 118 NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back)PNPP No. 9308 Rev. 9/11/00 NQI-1741 9. Remarks: VT-2 NOT REQUIRED. ONLY BOLTING WAS REPLACED ONE BOLT AT A TIME..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 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, John messenger,cedify 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 expir s 28 Sept.. 20 08 Date 15 April .20 07 Signed FENOC-PNPP ,-. 0C (name of repair organization) L 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 0-HIO and employed by HSB CT. of Hartford, Conn. have inspected the repair, modification or replacement described in this report on k 20 -_ and stale 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 Joss of any kind arising from or connected with this inspection. Date 41 -L. 20 0- Signed OAs w = Commissions NB 9330 "N" "I" "A" Ohio Comm.(inspector'\J (National Board (include endorsements), and jurisdiction, and no.) REPORT NO. P0059-011 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.10 Center Road. Perry. Ohio 44081 2. Plant: Perry Nuclear Power Plant (PNPP)10 Center Road, Perry, Ohio 44081 Date 5/1107 Sheet 1 of 4 Unit 1 200166846 (Repair Org. P.O. No., etc.)Type Code Symbol Stamp NR Authorization No. 33 Expiration Date 9-28-08 3. Work Performed By: FIRSTENERGY Nuclear Operating Company PNPP 10 Center Road, Perry, Ohio 44081 4. Identification of System: 1C41 Standby Liquid Control 5. (a) Applicable Construction Code: ASME Section III NB.1971 Edition NAME/SECTION/DIVISON/CLASS 19 72 Addenda Code Case(s) N/A Winter (b) Construction Code used for repairs, modifications, or replacements: 1971 Winter 72 Edition Addenda (c ) ASME Code Section XI applicable for Inservice Inspection: 1989 N/A Edition Addenda (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 FIRSTENERGY Nuclear Oprerating Company PNPP 6. Identification of Components Repaired, Modified, or Replacement Components N/A Code Case(s)N/A Code Case(s)Name of Name of Manufacturer Nat. Other Year Repair, ASME Component Manufacturer Serial Nto. Board ID. Built Replacement, Code No. or Modification Stamped Valve Conax Corp. N/A 113 N/A 1975 Replacement Yes Description of Work: Replaced primer/trigger assembly with Kit S/N 752EQ using trigger subassembly S/N 5541 and inlet fitting S/N 5516. The squib valve asset is 1C41-F004B. 7 8. Test Conducted: Hydrostatic-Li Pneumatic-E] Nominal Operating Pressure-Li Other- E]Pressure N/A psi Test Temperature N/A degrees F Code Case(s) N/A 119 NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back)PtPP 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 1.1 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 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 08 Date1 May 20 07 Signed FENOC-PNPP "/// O CC Tech (name of repair organization) (autflorized 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 , CT have inspected the repair, modificalion or replacement described in this report on IAfL. 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 01-" Signed eo) Commissions NB 9330 "N' "I" "A" Ohio Comm.(inspector) (National Board (include endorsements), and jurisdiction, and no.) REPORT NO. P0059-011 FORM N-2 CERTIFICATE HOLDERS' DATA REPORT FOR IDENTICAL NUCLEAR PARTS AND APPURTENANCES* As Required by the Provisions of the ASME Code, Section III Not to Exceed One Day's Production 3 7 'Of 2 S00?P 9.1 -of2-. Manufactured and cetified by IST Conax Nuclear, Inc. .402 Sonwil Drive, Cheeklowaqa, NY 14225) f 2. Manufactjred for (name ,and addr-, of NI: Cerfi-ctr Holder)GE Ni c -lear Eergy L Siervice (name and add-ess of Pu-chasei) Unknown 3. Lohtio"n of installation (name and addrs,)75 KS1 WA 4. Type: N200O1. Rev. G SA47313,4ST N/A 2006 (dr-i4ng o )(matl sec. no.)(tnsile (CRtj)(ye.r toit):5. ASME Code. Section III, Division 1: 7" Surie r 77 1 NIA (edition) (addenda datn) -(cla ) (Code C.-. -o)6. Fabricated in accordance with Const. Spec. (Dc. 2 only) -- Revision .D 7. Remarks: Trigger Body Subassembly for explosive actuated valve replacernemt kit for standby Liquid Control6Sy'elem Para. NB-2121 (b) is applicable to ram. Press riotseal on .328 & .4375 diameters. Overall subassembly lenqtth is.2.5ý%Pressure Test at 2900 psi for 10 minutes.8. Nom- thickness Cin.) See remarks Min. design thickness (in.) See remarks Dia. ID (fl & in.) See remarks Length overall (ft a in.) r-75. jemark.9. When applicable, Certificate Holders' Data Reports are.attached for each item of this report:... ...* .. _ _. a ...Part or Appurtenance Serial Number National Board No-in Nurnerical Order Part or Appurtenance Serial Number National Board No.in Numerical Order)(1)(2)(3)(4)(5)(6)(7)(1)(9)(10)(11)(12)(13)(14)(15)(16)(17)(18)(19)(20)(21)(22)(23)(24)(25)7300 7300* 7301..3.-.. ".7302 7302 7303 7303 7304 7304 7305 7305 7306 7306 7307 7307 (26)(27)(28)(G29)(30)(31)(32)(33)(3,1)(35)(36)(37)(38)(J9)(40)(41)(42)(43)(44)(45)(46)(47)(48)(49)(50)________________________________________________ Ii __________________________________________________ ++_________________________ Ii _____________________________ ____________________________________ I__________________________________________

0. Design pressure 1500 psi. Temp- 150 'F. Hydro. test pressure* See Remarks at temp. 'F (when appira hi)e'Supplemental information in the form of lists, sketches, or drawings may be used provided (1) size is 8, x 11i. (2) itormation in items 2 and 3 on this Data Report is included on each sheet, (3) each sheet is numbered and the number of cehetes i lrecorde'd at the top of this forrm A.S.M.E. 1 091 37 Code Item 120 FORM N-2 (Back -Pg. 2 of 2 )Cerlificate Holder's Serial Nos.7300 lhough 7307 Design specifications cerlirted by Design report certified by CERTIFICATION OF DESIGN George 1. Skoda tfi-n aPephlabJe P.E. Stale CA Reg. no. 15347 Francis J_ Domino P.E. State NY Reg. no 36132 rcn *pph-ebie)

CERTIFICATE OF COMPLIANCE We certify that the stalements made in this report are correct and that this (these) Tringer Body Subassembly conforms to the rules of construction of the ASME Code, Section i11, Division 1.NP T Certiticate of Aulhoriz'ation No.Date C /9 6.Name N-1350 Expires September 3, 2007 IST-Conax Nuclear Signed INJNT caslltae Iwide'I .'a4t.O1ded lepe rlf, eI CERTIFICATE OF INSPECTION I. th- undersigned. holdlig a -rid commission issued by te, Nalional Board of ioile, and Pressure Vessel Inspeclors and the Sthte or Province of New YarI and employed by HSB CT of Hartford. CT have inspected these items described in this Data Report on 2 7 , -,, and -state that to tie besl of my knowledge and belief, ttre Certrficate Holder has. fabricated these parts or appurtenances in accordance with the ASME Code.Section III. DivIsion 1. Each part listed has bwen authoriZel for stamping on the date shovm above.By signing this cerfificote. neither the irspector nor his employer makes any vrarnanty. expressed or implied, concerning the equipment described in this Datl Report. Furthermore, neither the inrspector nor his employer shall be liable in any manner for any personal injury or property damage or loss of any kirnd arising from or connected with thisinspection. Date 0,2,c -Signed C'Cmmissions Date .p.ero NI3 1096AAN NY 5057 Ir4on ad. iicI. -ros deno o 5Stopý or -res'o Yv.,t 77.:P.y nfli LO0z/[O/£O REPORT NO. P0059-011/ UfV) "-o3)FORM N-2 CERTIFICATE HOLDERS"'DATA REPORT FOR IDENTICAL NUCLEAR PARTS AND APPURTENANCES* As Required by the Provisions of the ASME Code, Section III Not to Exceed One Day's Production 51111117T3

7/-- Yr 00g Pg. 1 of 2-1., Manufactured and ceiired by Manufactured for]ST Conax Nuclear, Inc. 402 Sonwil Drive, Cheektowaga.

NY 14225 (nan-e and addrens of NPT CerGcýrdie Hoide0)GE Nuclear Energy 3. Location of installation (nm nd add-en el P-rh-se)Unknown (-as .nd eddr-n)4 Tvre: N380117 Rev_ F 75 (SI PItA NIA 2DO5 ,.

SA479rAMSST 75 KSI N/A (dmra-ng no.)(norl spne no.)(1-k sil arnnqh)SurnrnerT77 (1RN)5. ASME Code, Section III, Division 1: 77 N/A 6. Fabricated in accordance with Const. Spec. (Div. 2 only)(addenda datel Revision (no)(ctd ) (Ce,, Came no.)Dale 7. Remarks: Inlet Fifting for explosive actuated valve replacernent kit for Standby Liquid Control System Pressure Test at 2800 psi for 10 rninutes 8. Nom. thickness (in.) .w4i" Mi. design thickness (in.)9. When applicable, Cerlif"-ate Ilolders' Data Repoits are attached.031- [a. ID (ft & in.) .815- Leigthvoer-aill (ft & i)for each item of this report 2 ZW5.J National Part or Appurtenance Board No.Serial NumberBorN.

in Numerical Order (1) 7230 7230 (2) 7231 723i (3) 723.2 7232 (4) 7233 7233 (5) 7234 7234 (6) 7235 7235 (7) 7236 7236 (B) 7237 7237 (9) 7238 7238 (10) 7239 7239 (11) 7240 7240 (12) 7241 7241 (13) 7242 7242 (14) 7243 7243 (15) 7244 7244 (16) 7245 7245 (17) 7246 7246 (18) 7247 7247 (19) 7248 7248 (20) 7249 7249 (21) 7250 7260 (22) 7251 7251 (23) 7252 7252 (24) 7253 7253 (25) 7254 7254"-, r :,-.4a"e.N National Part or Appurtenance 'ý.' Board No-Seral Number n. Nurpencat Order (26) ,,_-_______- ,-(27) >'.(28) "" (2-)(30)(31)(32.)(33)(34)(3-5)(36)(37)(38)(39)(40)(41)(42)(43)(44)(45)(46)(48) __,_____-,_____ (49) 7__________- (50)__ _ _ _ _ _6.Design pressure 158 D p. Temp. 150 'F. Hydro. test pressure

See Remarks at temp. 'F I/ (wea n applicable)

Supplementat information in the form of lists, sketches, or dr-awngs may be used pcovided (1) si-e in W11 x 11. (2) information in items 2 and 3 on this Data Report is included o n each sheet, (3) each sheet is numbered and the number of sheets is recorded at the lop of this torm. A. S. EI. E 1 0 9 137 Code 1tez 121 FORM N-2 (Back -Pg. 2 of 2 )Certificate Holder's Serial Nos.7230 through 7254 Design SPoecitications cefrtirld b'y CERTIFICATIONJ OF DESIGN George 1. Skoda I reeiit01-b,0 P E. State CA Reg. no. 15847 Deý; ign report' ceirt_-d b)Francis J. Domino P E, State NY Reg. no 36832 t(,ice aroicabir CERTIFICATE OF COMPLIANCE We certify that the stalernenis made in this reporl are correct and that this (these)conforms to the rulels at constructionL ot thtr ASME Code. Section ill. Division 1.Inlet Fittings NPT Certificate ot Authorization No.Date i- ( , tlam, 1,-1850 Expires September

3. 2007 IST-Conax Nuclear Signed -2'X "./A. .;Z-17.1.rPt Cem wfi" -. Holdeaa t lauv'or'e pers tket CERTIFICATE OF INSPECTION

.the underincd, hotding a -,vrtd commo.sn insm,ed hy iths rstlonal t ,rd of Boiter and Pressure Vesfel Inspectors and the State or Province of Now Yorlr and e'mptoycrd by HSB CT ob! lilartlford, CT .,hove insioerted these denas rdkscnbed in this Data Report en .*L .' and state that to the best of my kno'vtedge and beiet, the Certiticate Holdet has tabtic.ated these parts or appurtenances in accotdancevith the ASME Code..'rctior, ttt. Division 1. Each poart IL.t.d has been authorized for stamping on the date shown above.By signingthis certificate, neither the insFpclor nor his employer makes any wrarranty, expressed or implied, concerning the equipment clescribed in this Data Report. Furthermore. neither the inspfctor nor his employer shatl be liable in any manner for any personal injury or pxopert-/ damage or lrms of any kind arising from or connecteo w-ith this inspection. Date 1/-'~-~~jSigned(T Kr'2§ ommissions, NB 1098-4AN NY 605T rilarIi Sd (-Le -dvcr~~s era r ýt r p-e r nd~--"a )flL./r~L- .LL~i(L'z4~f~ ~~14I~,~7~ ---r~~r,~< &~-c'I.-' REPORT NO. P0059-011 conax nuclear Ic q1I- o 37 s -/ I/Tabulation Of Materials 012 VALVE REPLACEMENT KIT P/N N27006-03 7 Trigger Body.PIN: N38018-01 Ramn Primer Chamber Inlet Fitting*1 -i 4-P/N: N-39012-01 PIN: N38062-01 P/N: N38017-01 B Vendor: Dubose Natl. Vendor: Carpenter Tech Vendor: Dubose Natl. Vendor: Dubose Natl.P.0. :_P93-S-574N P.O.: N91896 P.O.: P93-S-574N P.O. : P93-S-377N Heat No.: 151107 Heat No.: 53891 Heat No.: 151107 Heat No.: 12764 Control No.: 25075 Control No.: 24901 Control No.: 25020 Control No.: 24825 Trigger Subassembly N.B.S/N: 7300 J SEP SIN: 1738 N.B. SIN: 7247 Customer: Customer P.O.: IST Conax S.O.: Item No.: MPL NO.: G.E. S/N: General Electric Nuclear Energy 431002142 7TZ800 008 C41-F004 G.E.-752-EQ 1ST Conax Nuclear Quality:2_Q Date: /6 C3-,C A. S. .E. 1 09 17 C,., Item 122 REPORT NO. P0059-011)Qq1- QVýý I" I C) ý D, U 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 N01-174 I 1. Owner: FIRSTENERGY CORP.10 Center Road, Perry, Ohio 44081 Date 4-26-07 Sheet 1 of 2 2. Plant: Perry Nuclear Power Plant (PNPP)10 Center Road, Perry, Ohio 44081 Unit 1 200174471 (Repair Org. P.O. No., etc.)Type Code Symbol Stamp NR Authorization No. 33 Expiration Date 9-28-08 3. Work Performed By: FIRSTENERGY Nuclear Operatinq Company PNPP 10 Center Road, Perry, Ohio 44081 4. Identification of System: Standby Liquid Control C41 5. (a) Applicable Construction Code: ASME Section III Class 2 NC 1974 Edition PJAMEISECTION/DIVISION/CLASS Winter 1975 Addenda Code Case(s) 1644-8, N-242, N-272, N-240, N413, 1644-3 (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 N/A 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 FENOC 6. Identification of Components Repaired, Modified, or Replacement Components s)Name of Name of Manufacturer Nat. Other Year Repair, ASME Component Manufacuhrer Serial No. Board ID. Built Replacement, Code No. or Modification Stamped Piping Pullman Power C41 108 1 C4 IFOG 1985 Replacement Yes System 29B 7. Description of Work: Install reolacement relief valve serial number 4. Serial number 6 was removed.8. Test Conducted: Hydrostatic-nj Pneumatic- [] Nominal Operating Pressure- [Pressure 1225 psi Test Temperature 83 degrees F Code Case(s)Other- E]N/A 123 NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back)PNPP No. 9308 Rev 9/11/00 NQ1--1741 9. Remarks: none Note: Attach all applicable Manufacturer's Data Repods. 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, Russ Matthys , 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 Xt 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 September, 28,2008 Date 4-26 2007 Signed FENOC-PNPP v.Q OC Supervisor (name of repair organization) (authorized -eprevntative) (title)CERTIFICATE OF INSPECTION/INSERVtCE INSPECTION I, l-4 (w. _ ,. 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 \kAc CA. of ,,k -bF-6)-, CT have inspected the repair, modification or replacement described in his report on '20 O0- 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 "N1" 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. omo Date 4 .7, 20 0-1 Signed- N--W, Commissions k I P, C rk L'.i (inspectorJ (National Board (include endorsements), and jurisdiction, and no.) REPORT NO. P0059-011.2. FORM NV-1 MANUFACTURERS' DATA REPORT FOR SAFETY AND SAFMTY REUEF VALVES, (As. Required. by the Provisions of the ASME Code. Section Ill. Div. I)l. Manuacuredby. TARGET ROCK CORP., 1966E.. Broadhollow Rd. E.Farmingdale, N1Ynd AA:Wres riMnutactu,),. 2 Manufacruredfor Cleveland Ll~c'tr ic / uminating Co.,. Cleveland, Ohio Perry 'r PerOhio 3. Location of Installation

4. 1 1/2 x .REH-S--ICJON 4 Dra-ing No.). (Narl. Brd-N. No) 'ea Built)5. Valve 6 H-0 2 Identifying Nos.(Modl No.. S-" N" I (ManUISCere Serial No.)Type Relief Valve Sifery. Sait"y fli~t Pilo:c Pow-r Actuated Orfice Size' 500 Nominal Inlet Size 1 12 Outlet Size ir,-h inr" inc& Set Prer (PSIG) 1275 Rated. Temperati'u-120 Stamped Capaciy IbsIhr @ % Overpressure Blowdown (PSIG)Sax. Stearn Hydrostatic Test (PSIG) Inlet 3250 outlet 3250 7. Pressure Retaining Pieces (Applicatx.

to valvs far ., loseo s5yst , onty)Serial No. or Material Specification Identification IncL.Ty;:re-or Grade Body Bonnet or Yoke Support Rods Nozre Disc Spring. Washers Adjusting Screw Spindle Spring Bolting Other Pfecoei 300424 inQ3.97 LSMlE-SA479--316L ASME-SA4 79-3 16 ASME-SA479-316L ASIIE-SA564, GR.63 r 202075_209989 N'ut Hfex 3/8-16 UNC2"B ASME-SAI94-2H202074 ASME-SA479-316L Screw Sock. Hd. 318-16 x 1 1/2 ASME-SAI93-B7 Screw Sock. Hd. 102609 ... ASME-SA193-B7

Supplemental sheets in form of list. 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 induded on each sheet. and (3) each sheet is numbered and number of sheets is recorded at top of this form.0 I1/l6)This form (EO0042) may be obtained from the Orde"Cepti-ASME, 345 E. 47 St., New York. N.Y. 10017 124 FORM NV-1 (Back)CEFrFI:CATE OF COMPUANCE'Ne certify that the statements made in this report are correct andt that this valve conforms to the rules of cons5t§l-ft, of the ASME Code for Nuclear Power Plant Components.

Section Ill. Div. 1., 197 Edition. Addenda Sum_.Code Case No. -D ate)Dais /0. / 72 Signed Ta rget Rock Corp. -by -'/" " ' (Man ,w9 / i4'" Abruzzo, Mqr. Quality Our ASME Cartificate of Authorization No. 949 to use the symbol expires 12/9/83{Datol CSRiMF1CA11ON OF DESIGN Design information on file at Target Rock Corporation Stress analysis report (C1a= 1 only) on file at --Design specifications cerdtfied by Jan Pau I Socke I PState .P. Reg. No. 20130E Stress report certified by' -- -PE State Reg. No. -_-_-' Signature not required-4iss name only.CHfFICATE OF SHOP INSPECTION I, the undersigned, holding a valid commiseion issued by the National Board of Boiler and Prewsure Ves.el Insectort and the State or Province of New York and employed bý orne rc i a I Uni on ins.of Bost n , Mass have inspected the pump, or valve. descrbed in this Data Report on Z 2 1q-- .A and state that to the best of my knowledge and belief, the Manufacturer has con-structed tUhs 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 eqtuipment described in this Data Report. Furthermore. neither the Inspector nor his employer shall be liable in any manner for any nal or connected wjtp this inopectfcion. D= / NWY K P COMMIVSION. NO. 2/,,.-,. p 4-,.-J/1 Cxr\i o , -* .,~fl~l O... n ALSO CONIMlSSIONED IN Penn.. Ohio & Conn.(InsDe.orl tNr1trL 8-. Slate PrO,. arn Na.)-9 QZ4 REPORT NO. P0059-011/F,2 -.2 ?3?9Hlý / 'a/=: &!_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 NQ[-1741 1. Owner.FIRSTENERGY CORP.10 Center Road. Perry. Ohio 44081 Date 11/10/06 Sheet 1 of 2 2. Plant: Perry Nuclear Power Plant (PNPP)10 Center Road, Perry, Ohio 44081 Unit 1 200192906 (Repair Org. P.O. No., etc.)Type Code Symbol Stamp NR Authorization No. 33 Expiration Date 9/28/08 3. Work Performed By: FIRSTENERGY Nuclear Operating Company PNPP 10 Center Road. Perry Ohio 44081 4. Identification of System: RESIDUAL HEAT REMOVAL 1E12 5. (a) Applicable Construction Code: ASME Section III class 2 1974 Edition NAME/SECTION/DIVISION/CLASS 19 76 Addenda Code Case(s) N/A Winter (b) Construction Code used for repairs, modifications, or replacements: 1974 W76 Edition Addenda (c) ASME Code Section Xl applicable for Inservice Inspection: 1989 N/A Edition Addenda (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 FirstEnergy Corp 6. Identification of Components Repaired, Modified, or Replacement Components N/A Code Case(s)N/A Code Case(s)Name of Name of Manufacturer Nat. Other Year Repair, ASME Component Manufacturer Serial No. Board ID. Built Replacement, Code I_ I _:;, No. or Modification Stamped Pump Bingham IA015 795 N/A 1980 Replacement Yes Willamette

7. Description of Work: Removed rotating element S/N 1A015 and installed rotating element S/N 1A018 (including stuffing box and seal gland) Note the pump casing was not changed.Installed 1/2" plug HT XGB.8.Test Conducted:

Hydrostatic-LI Pneumatic-E] Nominal Operating Pressure-0 Other- E]Pressure 45 psi Test Temperature 78 degrees F Code Case(s) N/A 125 NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back)PNPP No. 9308 Rev. 9/11/00 NOI-1741 9. Remarks: .72 .. /5 /15 , C (J 0 3 1./7 10 l qjo7 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 8 112 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 !hat 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 tam expir s 28 Sept. , 20 08 Dale 10 Nov. 20 06 Signed FENOC-PNPP OC Tech.(name of repair organization) (auth6rized represenlttive) (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 AiAb. 1-3 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.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 oI oss of any kind arising from or connected with this inspection. Date_- 20 Q Signed u insp ecr 4 Commissions NB 9330 "N""1" A' Ohio Comm.A Uinspector)J (National Board (include endorsementso )and jtinsdiction, and no.) REPORT NO. P0059-011 I.I FORM NPV-1 A..UEACTUREAS. DATA SýP.99 NlR._L 4AA Pumps -OR VALVES 1A Fr ork ts.o the ASWVE Ctode. Svctiotv 11f. Div. 11 (Au fj ýil---RA~~~~ Pedi'ýi ýoPr Thd UnJItS 1 &.2 aN r -ew2.4 .P., .n-ý*-4,.Wr p~ Nominnal, Into Si 2 Outlet Sue ____-(Abarv fP6, (bi 100t4fatU~rerif (ci Canadian 34kiei AsTSe9 -- -gistreton, (dl DrýwiNg (fl Natir. (U) Year oriType 14.6,e No. le) ClI1 Sd. No. Built 4111 Water Leg Pvmpý1 0 61 "rid ,4y, kw4- ýp if- rg;d (ZSCS____ 140T50 ýjo ValveP .Ce-L-a.ip ;~r r-v.ý.un Pwfa-Mw~r. No- Meial.-Spec"No. Monuf~actrre R.maIW3 a) Cast~ng At47-'771-2 SAý-3&V- CF& 0 atv6ast- aS1-TPiA. o 11 tIU 1. -Iý'- , 7a 11) For manrually operatad Value, onlY.SupplespertLal shteets in form of Iist-. sk~ethes or daig may~ be us~ provi~o 11 ino i~i~. i items 1, 2 and 5 cn this dala fcpoil is incLuded on each shout. and 13) each-ýioet is rynub-ered ..ancf rtn61bdr mtsi l-ia recorded at tc13 of zhis form-t (12771 Th;3 formn lEIOOO27l ,Qy t;Orin rmtr.OdrO~. S~ 2 ~ ~ IY Ot 126

.y" srr 3amareier* 1 1c) Bacitilg I .I *Sltud',. Case-8:7181.4 ISA- i93i~i i 2W"4_..___________

1~SI~3 B~ ._______J___ 818:1 ~ ~ ~ ~ ~ ~ M~fý .. VTAcf________ _______A.i 4A.S;4 -, aEeI# 8ýO Sacket, M6o-t A SA-3?'i Tnt. 1

fnn P 0. 1-48565b SA 92 .304r 6 A-1Tri bozr Drye.VI.0 wlaz 2S 8~04 ________063T- .¶M8.34Met -rix 0Fr1 VD0.,.VFA--j-VK0Y .S 9 W".304. .a i n .Rr d , 0 ..a eriy.t,at.

the ýsia niets mae m; hin. r~ot creradta~te n5~~~n~~~d~~fl1 , the 14Sx; -d o ula o~a ln oioe at________ Qur AME Criifate i ofA~,tno Rzztian No ...1. L ale'b p Z/88 CR1IAT)OWfOF DSGN Sties 1anslysi2 repolrctb (Cls I only ort Ri~ Iaivti- LA ASO-gre.9pe 011a on RUhidy 1 ~ lTfr iOIt. -.~ Penn Rag- 28Ea -t~ utdr.2 n~,holding a ald anr.ion ,e-odrb. h n ed ~B ered e, cei i~,~nd We Star c~ Proqjn.. of= r~ned.~ryd~~0at~rt alrcjcted lhis ptme. or VAI.ve;:l i cn rinp ih-i- S1 da$etnIt-Bf5ij j deerrlre i this Offfatolte. ihoIjeino Fr: ranm ;, iih h -np~oo~i~m ty.6. r a bf --otonr r any~p-monel in;.ry-P Or poreydr trsleecav idasn-rr~o onipe :bl~n Op Ycxna.Ji rbr.F-..' ..;: .".; REPORT NO. P0059-011/1/Z -2 , y 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.10 Center Road, Perry, Ohio 44081 Perry Nuclear Power Plant (PNPP)10 Center Road, Perry, Ohio 44081 Date 4/6/07 Sheet 1 of 1 2. Plant: Unit 1 200187255 (Repair Org. P.O. No., etc.)3. Work Performed By: FIRSTENERGY Nuclear Operatingt Company PNPP 10 Center Road, Perry, Ohio 44081 Type Code Symbol Stamp N R Authorization No. 33 Expiration Date 9/28/08 4. Identification of System: RESIDUAL HEAT REMOVAL IEl 2 5. (a) Applicable Construction Code: ASMOE SECTION III CLASS 2 11974 Edition IAME/SECTtONt/IVISION./CLASS WINTER 19 75 Addenda Code Case(s) *",N224,N242,N272,N275,N282,N4 13,1728, 1644-5 (b) Construction Code used for repairs, modifications, or replacements: 1971 W75 Edition Addenida (c ) ASME Code Section XI applicable for Inservice Inspection: 1989 NONE Edition AddendJa (d) Applicable Edition of Section XI Utilized for Repairs, Modification, or Replacemenls: 198c__ 19 N/A Addenda N/A Code Case(s)(e) Design Responsibilities First Energy Corp 6. Identification of Components Repaired, Modified, or Replacement Components Code Case(s)N/A Code Case(s)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 tE12H06 1985 REPLACEMENT YES SYSTEM POWER 66 7. Description of Work: INSTALLED NEW LOAD STUD HEAT CODE MSS.8. Test Conducted: Hydrostatic-L] Pneumatic-E] Nominal Operating Pressure-D] Other- LI Pressure N/A psi Test Temperature N/A degrees F Code Case(s) N/A 127 NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back)PNPP No. 9308 Rev. 9111/00 NQ1-1 741 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 Tersick , certify that to the best of my knowledge arid belief the statements made in this report are correct and the repair, modificatiun 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 Authorication to. 33 to use the "HR stamp expires 28 Sept. , 20 08 Date 6 APRIL., 20 07 Signed FENOC-PNPP .z._-"' DC Tech.(name of repair organization) (author ~ed 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 o1 competency issued by the jurisdiction of O-HI1 and employed by HSB CT. of Hartford, Conn. have inspected the repair, modification or replacement described in this report on ____i______ 20 A 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 loeý of any kind arising from or connected with this inspection. Date4 , 20 0_-_ Signed Commissions NB 9330 "N" "IA" Ohio Comm.(inspetor l (National Board (include endorsements), and jurisdiction, and no.) REPORT NO. P0059-011 NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As required by the Provisions of the ASIVIE Code Section XI PNPP No. 9308 Rev.,. 9/11/00 H01-1741 1. Owner FIRSTENERGY CORP.10 Center Road Perry. Ohio 44081 Date ,1/7/07 Sheet 1 of I 2. Plant: Perry Nuclear Power Plant (PNPP)10 Center Road, Perry. Ohio 44081 Unit 1 200175667 (Repair Org. P. O. No., etc.)Type Code Symbol Stamp NR Authorization No. 33 Expiration Date 9/28/08 3. Work Performed By: FIRSTENERGY Nuclear Operating Company PNPP 10 Center Road Perry Ohio 44081 4. Identification of System: RESIDUAL HEAT REMOVAL IE 12 5. (a) Applicable Construction Code: ASME SECTION III CLASS 2.1974 Edition NAME/SECTION/DIVISION/CLASS WINTER 19 75 Addenda Code Case(s) *N224,N242,N272,N275,N282,N413.1728, 1644-5 (b) Construction Code used for repairs, modifications, or replacements: 1971 W75 Edition Addenda (c) ASME Code Section XI applicable for Inservice Inspection: 1989 NONE Edition Addenda (d) Applicable Edition of Section XI Utilized for Repairs, Modification, or Replacements: 1989, __ 19 N/A Addenda N/A Code Case(s)(e) Design Responsibilities First Energy Corp 6. Identification of Components Repaired, Modified, or Replacement Components Code Case(s)N/A Code Case(s)Narne 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 1E12H50 1985 REPLACEMENT YES SYSTEM POWER 02 7. Description of Work: INSTALLED NEW PSA-10 snubber S/N 42858.8. Test Conducted: Pressure N/A Hydrostatic-Li Pneumatic-El psi Test Temperature N/A Nominal Operating Pressure-Li Other- El degrees F Code Case(s) N/A 128 NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back)PNPP No. 9308 Rev. 9/11/00 1`10-1741 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 Sept. , 20 08 Date 7 APRIL. 20 07 Signed FENOC-PNPP .QC Tech.(name of repair organization) (autthorihze 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 20 UJ 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 , 2007 Signed Commissions NB 9330 "N" "I" "A" Ohio Comm.(inspectom (National Board (include endorsements), and jurisdiction, and no.) REPORT NO. P0059-011 I cGt9- -U Rvb 1 ýNIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As required by the Provisions of the ASME Code Section XI PNPP Ho. 9308 Rev. 9/11/00 N01-1741 1. Owner: FIRSTENERGY CORP.10 Center Road. Perry Ohio 44081 Date 4-26-07 Sheet 1 of 2 Unit 1 200175647 (Repair Org. P.O. No., etc.)2. Plant: Perry Nuclear Power Plant (PNPP)10 Center Road. Perry. Ohio 4,1081 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: 1E12 Residual Heat Removal 5. (a) Applicable Construction Code: ASME Section III -Cis NF.1974 Edition NAME/S ECTION/DIVISION/C LASS Winter 1975 Addenda Code Case(s) N-38, N-71-6, N-71-9, N-224-1, N-225, N-249, N-272, N-413, 1728 (b) Construction Code used for repairs, modifications, or replacements: 1974 W75 NA Edition Addenda Code Case(s (c ) ASME Code Section XI applicable for Inservice Inspection: 1989 HA NA Edition Addenda Code Case(s (d) Applicable Edition of Section Xl Utilized for Repairs, Modification, or Replacements: 1989 NA 19 NA Addenda NA Code Case(s)(e) Design Responsibilities FENOC 6. Identification of Components Repaired, Modified, or Replacement Components ))Narne of Component Name of Manufacturer Manufacturer Serial No.Nat.Bowd No.Other ID.Year Built Repair, Replacement, or Modification ASME Code Stamped Piping Johnson IE12 010 1H22H02 1985 Replacement Yes System Controls 09 (see remarks)Description of Work: Replace PSA ',/ mechanical snubber serial number (existing 34309) with new snubber serial number 28142 7.8. Test Conducted: Hydrostatic-E] Pneumatic-El Nominal Operating Pressure-0 Other- LI Pressure N/A psi Test Temperature N/A degrees F Code Case(s) N/A 129 NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back)PNPP No. 9308 Rev. 9/11/00 NOI- 1741 9. Remarks: Functional locatinn number 1H22H0209 was orioinallv installed as Johnson Controls hanoer number 1H22-P0004-H1043 as identified on isometric 814-0608-00906. Ref: JCI final N-5 data report 1E 12-0066-F 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, Russ Matthys , 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 toAse the "NR stamp expires September 28, 2008 Date 4-26,2007 Signed FENOC-PNPP K -CC Supervisor (name of repair organization) (authorized repres,1 aive) (title)CERTIFICATE OF INSPECTIONPINSERVICE INSPECTION I, i--ViotAA _ s-. L6 ,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 kASV, .To of A,-Fe-o rF?-0RL CT-- have inspected the repair, modification or replacement described in this report on Cd, 2., 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 , 200 Signed Commissions -3c3.o fYA U D (inspector) (National Board (include endorsements), and jurisdiction, and no.) REPORT NO. P0059-0il Az Roquired bry firProwitioro c4 tth: ASM Co-da Fuits. sckti N I. Dl)IriFl)ýn ~.c~i-b aifi5ý% cientfi 11346 -.: State ()ll eqe Bv. AntemC 92803.Power .PprCo:ý 62 Br,- crA Pi tsbh ýPA' 1233.~.-vo O'o...ngt .rti o Ltctad CC-Gorio r-T N.1 I BoCidC'I0Ný a w. Rv-v D.19.- C'rv Dsti. Shý4 -1o' 1 ~ ~ N o..B I j S30 1i 8 180104- 05-J D 1348 PvB:Lnr 1 tlE 18 (6)CFEHllFYCAiF OF. CO(-'vAPLtANCE .-\Cft C.1Ici.HlNv O~~nASMEC U98:tP A!)g 4 98s C I. CrTIF I CA F1 0N Of DESIGN D~.ri nrorril~n o Fi.

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ýCLRTIFCATIE OFSHOP INSýPECT)ON _jt .1-cie 1t- ,nort.n ft. itt dýlte Inc ths lt-thet A SkiE Co-i. lo icet r -EtatC o et By *g~nQ cs car car.r n~t T.. thr pc no, f)i, "tep Ioy.i mI e It ~ k e raiy*i IýuppýoiI described in thus Data Repiort Furhthemore-neither th~e Inipeýclot no( hits empl0v P, u-a Pn I injury Pt propery damage; or a tots of any kird autoing ftam or con'ec~ted -it Sa. Vi Ej LI Ons S ~ ~ ~ ~ ~ ~ ~ ~ ~ ( IeaL~.A <~.1 <Cnmrtn~.ue v~0 eln~cr " ad If"' SLat. o-j in-,G hf,-yret I -x se sh all Le loiabl in any marnner for an~y Ithit inhpe V ti, n If.stavtý Pt 0 , and No..to..'! , CERIICATON f FIELD INSPECTION I heudtr,-rd ht.Jdlng a vafid com'rsToitn 111-1 by the Natio n ol o t cl ot b~I air and P(eiiutt Vectcl In eit nd th? ,reo 0~*of_______________ niploýYtd by _______________of______________ ha- ieCompared the stl ient n 0 4ItiC at Reporl with the de~scroted Compý_onen euprt nd Cott a.c,:rrt.....4 AS... Cod. foe %..1. P- latC...... ............ .........13,y .I cii , f tt vth- t 'e 'eo t s mY. .sks any .erranty .a rpicted ,ii the1 cc .n .I-tl-o499., /.....' t':..":

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.... M, -.g NXH REPORT NO. P0059-011 I .I .E / a,._- , -- I ...... ..NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As required by the Provisions of the ASME Code Section XI ENFP No. 9.308 Rev. 9/11/00 NQ1-1741 1. Owner: FIRSTENERGY CORP. Date 4-28-07 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 200168098 (Repair Org. P.O. No., etc.)3. Work Performed By: FIRSTENERGY Nuclear Operatin, 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: 1E12 RESIDUAL HEAT REMOVAL 5. (a) Applicable Construction Code: ASME Section III -Class 2 NC .1974 Edition NAME/SECTIOr/DIVt1 ISIO5 /CLASS Winter 1975 Addenda Code Case(s) 1644-5J,128 N-224, N-272, N-275, N-282, NA413,N-242 (b) Construction Code used for repairs, modifications, or replacements:

1974 WV/75 N/A Edition Addenda Code Case(s)(c ) ASME Code Section XI applicable for Inservice Inspection: 1989 N/A N/A Edilion 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 FENOC 6. Identification of Cornponents Repaired, Modified, or Replacement Components Name of Name of Manufacturer Nat. Other Year Repair. ASME Component Manufacturer Serial No. Board ID- Built Replacement, Code Nto. or Modification Stamped PIPING PULLIvIAN E12 83 1E12F00 1985 REPLACEMENT YES SYSTEM POWER 63C 7. Description of Work: Replace check SN 1-51906-A with SN 1-52969-B 8. Test Conducted: Hydrostatic- -Pneumatic-El Nominal Ope Pressure 125 psi Test Temperature N/A degrees F rating Pressure-N Other- El Code Case(s) N/A 131 NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back)PNPP No 9308 Rev. 9/11100 NQ1-1741 9. Remarks: NONE 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 forrn CERTIFICATE OF COMPLIANCE 1, Russ MaHhhys 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 tNationat Board Inspection Code "NR" rules.National Board Certificate of Authorization No. 33 to use the "NR stamp expires 28 SEPT , 2008 Date 4-28-2007 Signed FENOC-PNPP (name of repair organization) (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 HARTFORD STEAM BOILER CT. of HARTFORD, CT have inspected the repair, modification or replacement described in this report on & 200"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 loss of any kind arising from or connected with this inspection. Date 20 07 Signed Commissions NB 9330"NA"A" Ohio Comm (inspector) -ý (National Board (include endorsements). and jurisdiction, and no.) REPORT NO. P0059-011 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 Certificate Holder)2. Manufactured for First Energy Corporation, 10 Center Rd.. P.O. Box 97, North Perry, OH 44081 (name and address of Purchaser)

3. Location of installation Perry Nuclear Power Plant 10 Center Road, Dock No. 1. North Perry OH 44081 (name and address)4. Model No., Series No., or Type Dual Plate Check Valve Drawing 50079-A Rev. 06 CRN N/A N/A cGode Ca-e no.1 5. ASME Code, Section III, Division 1: 1974 (edition)Winter 1975 (addenda date)2 (dass)6. Pump or Valve Valve Nominal inlet size 8 (in.)Outlet size 8 (in.)7. Material:

Body SA216-WCB Bonnet N/A Disk SA487-CA6NM Boiting N/A (a)Cert.Holder's Serial No.l 1-52969-B ( b)Nat'l Board No.NIA (c )Body Serial No.HT. 11:87633 RT#: 75249 ( d)Bonnet Serial No.NIA (e )Disk Serial No.HT. /1: 7506 RT#: 75238 &75240* Supplemental information in form of lists, sketches, or drawings may be used provided (1) size 8 Y2 x 11, (2) information in items I through 4 on this Data Report is included on each sheet, (3) each sheet is numbered and the number of sheets is recorded at the top of this form (12188) This form (E00037) may be obtained from the Order Dept., ASME, 22 Law Drive. Box 2300, Fairfield, NJ 07007-2300. 132 FORM NPV-1 (Back -Pg. 2 of22 )Certificate Holder's Serial No. 1-52969-8 8. Design conditions 740 psi 100 'F or valve pressure class 300 (1)(pressure) (temperature)

9. Cold working pressure 740 psi at 100'F 10. Hydrostatic test 1125 psi. Disk differential test pressure 825 psi 11. Remarks: Pin Retainers SA 479-410 HT# 504.120 TR# 1510 CERTIFICATION OF DESIGN Design specification certified by Hiram R Reppert P.E. Slate PA Reg. no. 24928-E (,,hen applicable)

Design report certified by N/A P.E. State N/A Reg. no. N/A (wheo applicable) CERTIFICATE OF COMPLIANCE We ceitify that the staternents mode in this report are correct and that pump or valve conforms to the rules for construction of the ASME Code, Section III, Division 1.1`4 Certificate of Authorization No. N-2606 Expires 6-13-07 Date lName WEIR VALVES & CONTROLS USA INC.. S IN Crt,frcare Holder) (authorizerrepresentativeo CERTIFICATE OF INSPECTION I, the undersigned, holding a valid conomriss )n is.uerd by the tNational Board of Boiler and Pressure Vessel Inspectors and the State or Province of Massachusetts an/Vmployed by HSBCT of Hartford CT have inspected the pump, or valve, described in this Data Report on ____, and slate that to the best of my knowledge and belief, the Certificate Holder has constructed this pump, or valve, iraccordance with the ASME Code, Section III, Division 1.By signing this Certificate, neither the inspector iror his employer makes any warranty, expressed or implied, concerning the equipment described in this Data Report. Furthermore. neither Mire inspector nor his employer shall be liable in any manner for any personal injury or property dama ý- or ss of any kind ar, or, nne -d with this inspection. Dale Signed Commission /A (A hor1oized rnSpecrort ( Nai'l. Bd. lind. endorsernee s) and state or pro. and rno.)(1) For manually operated valves only. REPORT NO. P0059-011 NIS-21NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As required by the Provisions of the ASME Code Section XI PtNPP No. 9308 Rev- 9/11/00 NO1-1741 1. Owner: FIRSTENERGY CORP.10 Center Road, Perry,Ohio 44081 Date 5-2-07 Sheet 1 of 2 Unit 1 200148638 (Repair Org. P.O. No., etc.)2. Plant: Perry Nuclear Power Plant (PNPP)10 Center Road, Perry, Ohio 44081 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: 1E12 RESIDUAL HEAT REMOVAL 5. (a) Applicable Construction Code: ASME Section III -Class 2 NC ,1974 Edition NAME/SECTION/DIVISION/CLASS Winter 1975 Addenda Code Case(s) 1644-5, 1728, N-224, N-272, N-275, N-282, N-413,N-242 (b) Construction Code used for repairs, modifications, or replacements: 1974 W/75 N/A Edition Addenda Code Case(s)(c ) ASME Code Section XI applicable for Inservice Inspection: 1989 N/A 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 FENOC Identification of Components Repaired, Modified, or Replacement Components 6.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 E12 83 1E12 1985 REPLACEMENT YES SYSTEM POWER F086 7. Description of Work: Replace check SN 1-52154-A with SN 1-52969A 8. Test Conducted: Hydrostatic-E] Pneumatic-ED Nominal Operating Pressure-El Other- ED Pressure 145 psi Test Temperature 71 degrees F Code Case(s) N/A 133 NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back)PNPP No. 9308 Rev. 9/11/00 NOQ-1741 9. Remarks: NONE NO NAMEPLATE/STAMPING PERFORMFD 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, Russ Matthys 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 st expires 28 SEPT , 2008 Date 5-2-2007 Signed FENOC-PNPP Q('. '(A OC Supervisor (name of repair organization) (authorized represen\3tive) (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 HARTFORD STEAM BOILER CT. of HARTFORD. CT have inspected the repair, modification or replacement described in this report on M'"-A -2, 20 C1 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 oss of any kind arising from or connected with this inspection. Date , 200 Q7. Signed e d Commissions NB 9330 "N"I'A" Ohio Comm (inspector)- (National Board (include endorsements), and JurisdtctlQn, and na.) REPORT NO. P0059-011 j E o- Ci ý V) 0 clý D'.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 Certificate Holder)2. Manufactured for First Energy Corporation, 10 Center Rd., P.O. Box 97, North Perry, OH 44081 (name and address of Purchaser)

3. Location of installation Perry Nuclear Power Plant 10 Center Road Dock No. 1 North Perry OH 44081 (name and address)4. Model No., Series No., or Type Dual Plate Check Valve Drawing 11949-01 Rev. 04 CRN N/A 5. ASME Code, Section tIl, Division 1: 1974 (edition)Winter 1975 (addenda date)2 (class)N/A (Code Case no )6. Pump or Valve Valve Nominal inlet size 6 Outlet size (in.)7. Material:

Body SA216-WCB (a)Ce rt.Holder's Serial No.1-52969-A Bonnet N/A (b)Nat'l Board No.NIA (c)Body Serial No.HT. #:87643 RT#: 75242 6 (in.)Disk SA487-CA6NM Bolting N/A (d) (e)Bonnet Disk Serial Serial No. No.N/A HT. #:87506 RT#: 75217 &75218 Supplemental information in form of lists, sketches. or drawings may be used provided (1) size 8 '/" x 11, (2) information in items 1 through 4 on this Data Report is included on each sheet, (3) each sheet is numbered and the number of sheets is recorded at the top of this form (12/88) This form (E-10037) may be obtained from the Order Dept., ASME, 22 Law Drive, Box 2300, Fairfield, NJ 07007-2300. 134 FORM NPV-t (Back --Pg. 2 of 2 )Certificate Holder' s Serial No. 1-52969-A 8. Design conditions 740 psi 100 'F or valve p (pressure) (temperature)

9. Cold working pressure 740 psi at 100'F i0. Hydrostatic test 1125 psi. Disk differential test pressure 11, Remarks: Pin Retainers SA 479-410 HT4: 504420 TR# 151D ressure class 825 300 (1)psi CERTIFICATION OF DESIGN Design specification certified by Hiram R. Reppert P.E. State PA (when applicable)

Design report certified by N/A P.E. Slate i'l/A (when apphcIble) Reg no. 2492 Reg. no.8- E N/A CERTIFICATE OF COMPLIANCE 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 I11, Division 1.INl Certificate of Authorization No. N-2606 Expires 6-13-07 Date 7 ~ ~ Nm WEIR VALVES -S CONTROLS lISA INC-.._7 CePCýct Name lusrze peeniie (althGr'Zed fepr-entatiye)(N' Certii~cite Holder)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 Massachusetts an,-;erployed by HSBCT of Hartford, CT have inspected the pump, or valve, described in this Data Report on .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 I11. Division I-By signing this Certificate, 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 liable in any manner for any personal injury or property damoe or ss of any kind arising from or connected with this inspection-Dale SignoJ A Commissio~n ý ~ '- ' '(Authorized Inspector)( lail. Bd. (inol. endorsement,,) and state or pray. and no.)(1) For manually operated valves only. REPORT NO. P0059-011 I E 13- 3-Oý A Pý 14 3-NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As required by the Provisions of the ASIVME Code Section Xl PNPP Nlo. 9308 Rev. 9/11/00 NOI-1741 1. Owner: FIRSTENERGY CORP.10 Center Road. Perry. Ohio 44081 Date 5-2-07 Sheet 1 of 2 Unit 1 200168096 (Repair Org. P.O. No.. etc.)2. Plant: Perry Nuclear Power Plant (PNPP)10 Center Road. Perry. Ohio 44081 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: 1 E12 RESIDUAL HEAT REMOVAL 5. (a) Applicable Construction Code: ASME Section III -Class 2 NC 1974 Edition 1 NAME/SECTION/DIVISIONI/CLASS Winter 1975 Addenda Code Case(s) 1644-5, 1728, N-224, N-272. N-275, N-282, N-413,N-242 (b) Construction Code used for repairs, modifications, or replacements: 1974 W/75 N/A Edition Addenda Code Case-s (c) ASME Code Section X1 applicable for Inservice Inspection: 1989 N/A 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 FENOC 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 E12 83 1E12 1985 REPLACEMENT YES SYSTEM POWER F063A 7. Description of Work: Replace check SN 3-51001-A with SN 1-52183-A 8. Test Conducted: Pressure 150 Hydrostatic-D Pneumatic-LI psi Test Temperature NOT Nominal Operating Pressure-N Other- El degrees F Code Case(s) N/A 135 NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back)PNPP No. 9308 Rev. 9/11/00 NQI-1741 9. Remarks: NONE 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, Russ Matthys , 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 2008 Date 5-2-2007 Signed FENOC-PNPP OC Supervisor (name of repair organization) (authorized repres tative) (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 HARTFORD STEAM BOILER CT. of HARTFORD, CT have inspected the repair, modification or replacement described in this report on MJ 1.- 20 01 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?a.,20 0~1 Signed Commissions NB 9330 "N"I"A" Ohio Comm (inspector) U (National Board (include endorsements), and jurisdiction, and no.) REPORT NO. P0059-011 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: 2. Manufactured for First Enercjl Weir Va3lves and Controls USA Inc. 285 Canal St. Salem MA 01970 (name and address of N4 Certificate Holder)onned.O. o 7 Nodh a ress of 4Prh 1e (name and address of Purchaser) U-yOcpo 3. Location of installation Perrty (ucleas Posrer Plant, 10 Center Road D No 1 No Ot t 4081 (name and address)4. Model No, Series No., or Type Dual Plate Chech Valve 5. ASME Code, Section Itt. Division 1- 1974 edjlior)Drawing 5r07q-A Rev. 05 CRN NIA W]inter 1975 (aOde-d dale)2 (d.n)NIA (Code cas no)6. Pump or Valve Valve Nominal inlrt -,ze B1 Outlet size B (in.) (in.)7. Material: Body SA2-6-WCB (a)Cert.Holders Serial No.1-52 183-A Bonnel NlIA Disk 3A4J3,-C7OlIMl. Boiling NIA:( b )Hlat'l Board NIo.N'/A (c)Body Serial t,/o HT. #.04200 S/I: V6lt (d) (e)Bonnet Disk Serial Serial No. No.Il/A HT. 0:04204 SIN:V615 & V616 4 72 F* Supplemental information in foire of lists, sketches, or draings may be used provided (1) size 8 ' ax I1, (2) information in items I through 4 on Ihis Data Report is included on each sheet. (3) each shect is numbered 3nd the number of sheets is recorded at the top of this form (12188) This form (E000371) may be obtaioed trom the (,der Dept.. ASt.IE, 72 La, Drive, Bo. 2300, Fairfield. NJ 07007-2300. 136 FORM NPV-1 (nack -Pg..2 of .2)Cerfiflt:le Hoder' s Serial No. 1-5,J83-A R. Design crnditicns 500 psi 4.90 F or valve pressure class to (1)(pressure) (temperature)

9. Cold working pressure 740 psi at 100-F 10. Hyd-ostatic test 1125 psi. Disk ditferential test pressure 825 psi 11. Remarks: Pin Retainer-SA 479-410 HT# G7190 TR# 127D CERTIFICATION OF DESIGN De_.ign specification certified by Hiram R. Reppert P.E. State PA Reg. no. 142.48U-(I-n aeplcbie)Design repod certified by N/A P.E. State N/A Reg. no. 11A (.,hrn CERTIFICATE OF COMPLIANCE We certify that the statements made irl this repert are correct and that pump or valve conforms to the rules for construction of the ASrNE Code.Section III. Division 1.N Certificate of Authorization Ito N-2606 Expires 6-13-07 Date N ame WPJEIR VALVES & CONTROLS USA INC..l CerSca3te Hodert) Or L-t 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_t-saslch-ý!Jý and employed by HSBCT of Hartford CT have inspected the pump, or valve. described inrthis Data Report an -V /7 ý and state that to the best of my knowledge arid belie.f the Certificate Holder has constructed this pump. or valve.in accordarce eith the ASME Core. Section II. Division 1.By signing this Certificate, 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 shad be liable in any manner for any personal injury or property damage or loss of any kind ar9si gf om or connected with this inspection.

Date 'z7- 5Orged Ill /Z,1 CoMmri-oro / / 7 ..A' 2 (Althrooed I-opecor) ( Naon. Ird (imr. endorsemer nod srare or p-or aod n0 (1) For manually operated valves only. REPORT NO. P0059-011 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: FtRSTENERGY CORP.10 Center Road, Perrv, Ohio 44081 Perry Nuclear Power Plant (PNPP)10 Center Road, Perry, Ohio 44081 Date 5-2-07 Sheet 1 of 2 Unit 1 200168097 (Repair Or,. P.O. No., etc.)2. Plant: 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' 1E12 RESIDUAL HEAT REMOVAL 5. (a) Applicable Construction Code: ASME Section III -Class 2 NC.1974 Edition NAME/SE CTION/DIVISION/CLASS Winter1975 Addenda Code Case(s) 1644-5, 1728, N-224, N-272, N-275, N-282, N-413,N-242 (b) Construction Code used for repairs, modifications, or replacements: 1974 W/75 N/A Edition Addenda Code Case(s (c) ASME Code Section XI applicable for InservIce Inspection: 1989 N/A 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 FENOC 6. Identification of Components Repaired, Modified, or Replacement Components3)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 E12 83 1E12 1985 REPLACEMENT YES SYSTEM POWER F063B 7. Description of Work: Replace check valve SN SN 2-51906-A with 2-52969- B 8. Test Conducted: Hydrostatic-E] Pneumatic-LI Nominal Operating Pressure-Z Other- []Pressure 150 psi Test Temperature NOT degrees F Code Case(s) N/A 137 NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back)PNPP No. 9308 Rev. 9/11/00 N01-1741 9. Remarks: NONE 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 8 112 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, Russ Matthys 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 , 2008 Date 5-2-2007 Signed FENOC-PNPP Q A ! OC Supervisor (name of repair organization) (authorized reprtentative) (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 HARTFORD STEAM BOILER CT. of HARTFORD. CT have inspected the repair, modification or replacement described in this report on t 20 0-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. Dale 20 01 Signed jTý AA Commissions NB 9330 "N","A Ohio Comm (inspector) I (National Board (include endorsements), and lurisdictfon. and no.) REPORT NO. P0059-011 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 Certificate Holder)2. Manufactured for First Energy Corporation, 10 Center Rd., P.O. Box 97, North Perry OH 44081 (name and address of Purchaser)

3. Location of installation Perry Nuclear Power Plant, 10 Center Road, Dock No. 1. North Perry OH 44081 (name and address)4. Model No., Series No., or Type Dual Plate Check Valve Drawing 50079-A Rev. 06 CRN N/A N/A (Code Case nor)5. ASME Code, Section III, Division 1: 1974 (edition)6. Pump or Valve Valve Nominal inete size Winter 1975 (addenda date)Outlet size 8 (in.)2 ( dCa )8 (in.)7. Material:

Body SA216-WCB Bonnet N/A Disk SA487-CA6NM Bolting N/A (a)Cert.Holder's Serial No.2-52969-B ( b)Natll Board No.N/A (c)Body Serial No.FIT. #:87633 RT#: 75248 ( d)Bonnet Serial No.N/A (e )Disk Serial No.IT-IT 9: 87506 RT//: 75239 &7 524 1" Supplemental information in form of lists, sketches, or drawings may be used provided (1) size 8 %,£ x 11. (2) information in items 1 through 4 on this Data Report is included on each sheet, (3) each sheet is numbered and the number of sheets is recorded at the top of this form (12188) This form (E00037) may be obtained from the Order Dept., ASME, 22 Law Drive, Box 2300, Fairfield, NJ 07007-2300. 138 FORM NPV-t (Back -Pg. 2 of 2 )Certificate Holder' s Serial No. 2-52969-B 8. Design conditions 740 psi 100 (pressure) (temperature) 'F or valve pressure class 300 (1)9. Cold working pressure 740 psi at 100'F 10. Hydrostatic test 1125 psi. Disk differential test pressure 825 psi 11. Remarks: Pin Retainers SA 479410 HT# :504420 TR9 1510 CERTIFICATION OF DESIGN Design specification certified by Hiram R. Reppert P.E. Stale PA Reg. no. 24928-E (w.hen applicablel Design report certified by N/A P.E. State N/A Reg. no. N/A (when .rrpplicrable) CERTIFICATE OF COMPLIANCE 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 11. Division 1.N Cerlificate of Authorization No.-Date / -" Name N-2606 WEIR VALVES & CONTROLS USA INC..IN Certificate HolderI Expires 6-13-07 CERTIFICATE OF INSPECTION I. the undersigned, holding a valid comrnrssinn issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Massachusetts /and nployed by HSBCT 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 Certificate Holder has constructed this pump, or valve, in ccordance with the ASME Code, Section Ill. Division 1.By signing Ihis Certificate, neither the inspector nor his employer makes any warranty, expressed or implied, concerning the equipment described in this Data Report. FurthermrEior-. ither the inspector nor his employer shall be liable in any manner for any personal injury or property dam /,e or ss of any kind. ing em or co z'ted with this inspection. Date S,0neSigne Commission /,/W / A A4 -(Authorized Inspecor) ( Nai'l. Ed. (incl. endorsements) and staie or prov. and no.)(1) For manually operated valves only. REPORT NO. P0059-011 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 N141-1741 1. Owner: FIRSTENERGY CORP.10 Center Road, Perry, Ohio 44081 Date 5-5-07 Sheet 1 of 2 Unit 1 200157306 (Repair Org. P.O. No., etc.)2. Plant: Perry Nuclear Power Plant (PNPP)10 Center Road. Perry. Ohio 44081 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: 1E12 RESIDUAL HEAT REMOVAL 5. (a) Applicable Construction Code: ASME Section III -Class 1 NB 1974 Edition NAME/SECTION/DIVISION/CLASS Winter 1975 Addenda Code Case(s) 1644-5, 1728, N-224, N-272, N-275, N-282, N-413,N-242 (b) Construction Code used for repairs, modifications, or replacements: 1974 W/75 N/A Edition Addenda Code Case(s (c) ASME Code Section XI applicable for Inservice Inspection: 1989 N/A 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 C ase(s)(e) Design Responsibilities FENOC 6. Identification of Components Repaired, Modified, or Replacement ComponentsName of Name of Manufacturer Nat. Other Year Repair, ASME Component Manufacturer Serial No. Board ID. Built Replacement, Code No. or Modification Stamped PIPING PULLMAN E12 83 1E12 1985 REPLACEMENT YES SYSTEM POWER* FQ41A 7. Description of Work: Reworked valve and replace disk -SN 87709-3 8. Test Conducted: Hydrostatic-LI Pneumatic-El Nominal Operating.Pressure-M< Other- []Pressure NOP psi Test Temperature NOT degrees F Code Case(s) N/A 139 NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back)PNPP No. 9308 Rev. 9/11/00 N0I- 1741 9. Remarks: NONE 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, Russ Matlhys 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 ASIVME 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 2008 Date 5-5-2007 Signed FENOC-PNPP O " DC Supervisor (name of repair organization) (authorized repr intative) (title)CERTIFICATE OF INSPECTION/INSERVICE INSPECTION I, 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 HARTFORD STEAM BOILER CT. of HARTFORD. CT have inspected the repair, modification or replacement described in this report on ON 20 01 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, properly damage or loss of any kind arising from or connected with this inspection. -A -ýr ý V .... ...' .0 O .k ; -0 Date 20 Q-1 Signed nM&I Commissions V -_3 V I A CD-S(inspector) \1 (National Board (include endorsements), and jurisdiction, and no.) REPORT NO. P0059-011 I C-)D--SGj e ) 4 1 D, FORM N-2 CERTIFICATE HOLDERS' DATA REPORT FOR IDENTICAL NUCLEAR PARTS AND APPURTENANCES-As Required by the Provisions of the ASME Code, Section III Not to Exceed One Day's Production Pg. 1 of 2 1. Manufactured and certified by Flowserve Corporation, 1900 S. Saunders St., Raleigh, NC 27603.u rna-n, ad dd, NP" W --- 1-1o.d.0 2. Manufactured for First Energy Corporation, P. 0. Box 6100, Johnstown, PA 15907 l o n a m .a n d a d d m s o t -p -r---r--r-r--rr a s e 3. Location of installation First Energy Corp., Perry Nuclear Plant, 10 Center Rd, Perry, OH 44081 4. Type D82-24401-18, R/J SA105 N/A N/A 2006 (d -irg no.) OWrna 1P..se no-) 11 -j IRN l -uit tr~e o1N-"- f~~ eetleRN) 'year huihl5. ASME Code, Section III, Division 1: 1974 Winter 1975 1 N/A tn~~rltded ae da,) (Code tis no.)6. Fabricated in accordance with Const. Spec. (Div. 2 only) N/A Revision N/A Date N/A 7. Remarks: Disk for 12" 4094(WCC)JNQTY Valve_S. 0. 37287 B. Norm. thickness (in.) N/A Min design thickness (in.) Per #t Dia. Io (f & in.) N/A Length overal (ft & in.) N/A 9. When applicable, Certificate Holders' Data Reports are attached for each item of this report K Natioral Part or A ppurlerranc. Board No.Seial Num ber in Nur reri ral O rder i1) 87709-1 N/A (2) 87709-2 N/A (3) 87709-3 N/A ('1) 97709-4 N/A (5) 87709-5 N/A (6)17)(8)(9)10)(12)(13)(14)(15)(16)(17)(18)(20)(21)(22)(23)(24)(25)Part or Appurtenance serial Number (26)(27)(28)(29)(30)(32)(33) -(34)(35)(36)(37)(39)(40) -----(41)(42)(43)(44)(45)(46)(47)(48)(49)(50)National Board No.in Numerical Order 10. Design pressure 1421 psi. Temp. 573 'F. Hydro. test pressure N/A _ at temp. °F 1when apph-cble) Supplemental information in the form of lists., sketches. or drarings may be used provided It e sie is 8 r/ 0 11, 12) information in items 2 and 3 on this Data Report is included on each sheet (3) each sheet is numbered and the number of sheets is recorded at the top of this form.(7/193( This form (EO00401 may be obtai-ed fom the Order 1- -.-........140 .7 I., FORM N-2 (Back -Pg 2 of 2 )Certificate Holder's Serial Nos. 87709-1 through 87709-5 CERTIFICATION OF DESIGN Design specifications certified by P.E. State Reg. no.Design report* certified by 1-h- FP.E. State Reg. no.CERTIFICATE OF COMPUANCE We certify that the statements made in this report are correct and that this (these) Part(s)conforms to the rules of construction of the ASME Code, Section III, Division 1.NPT Certificate of Authorization No. N- 1563 Expires November 26, 2006 Date Name Flowserve Corporation Signed 6 ,A -L k Dae NPT Caerlt 1,t Holder} J-uhorin-r 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 N-- and employed by H-S. f_of Hartford. CT have inspected these items described in this Data Report on -" t2. 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 III, Division 1. Each part listed has been authorized for stamping on the date shown above.By signing this certificate, 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 liable in any manner for any personal injury or property damage or loss of any kind arising from or connected with this inspection. Daote No7 rSigned ~ "commissions JC. n n.lAodo,rix,d Nuclo-, n;4,,, IN.O. Bd. ,C-. -d oeu -1. u ,o r p-.o. ..d n. REPORT NO. P0059-011 I15 IX- -ý0D 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 5-10-07 10 Center Road, Perry, Ohio 44081 Sheet 1 of 1 2. Plant: Perry Nuclear Power Plant (PNPP) Unit I 10 Center Road, Perry, Ohio 44081 200153520 (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 9-28-08 4. Identification of System: 1E12 RESIDUAL HEAT REMOVAL 5. (a) Applicable Construction Code: ASME Section III -Class 2 NC .1974 Edition NAMEiSECTION/DIVISIONI/CLASS Winter 1975 Addenda Code Case(s) 1644-5, 1728, N-224,-N-272, N-275, N-282, N-413,N-242 (b) Construction Code used for repairs, modifications, or replacements: 1974 W/75 N/A Edition Addenda Code Case(s)(c) ASME Code Section XI applicable for Inservice Inspection: 1989 N/A 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 FENOC 6. Identification of Components Repaired, Modified, or Replacement Components Name of Naame ot Manufacturer Nat. Other Year Repair, ASME Component Manufacturer Serial No. Board ID. Built Replacement, Code No. or Modification Stamped PIPING PULLMAN E12 83 lE12FOO 1985 REPLACEMENT YES SYSTEM POWER 18B 7. Description of Work: Replace pipe and tee as a result of flow accelerated corrosion (new pipe HT S20419 New tee HT M377J)8. Test Conducted: Hydrostatic-E] Pneumatic-E] Nominal Operating Pressure-Ej Other- LI Pressure 315 psi Test Temperature 79 degrees F Code Case(s) N416-2 141 NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back)PNPP No. 9308 Rev. 9/11/00 NQI-1741 9. Remarks: NONE NO NAMEPLATE/STAMPING PERFORMED DUE TO THE INTERFACE CONTROLS GF 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, Russ Matthys , 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 , 2008 Date 5-10-2007 Signed FENOC-PNPP R '"' OC Supervisor (name of repair organization) (authorized representA ve) (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 HARTFORD STEAM BOILER CT. of HARTFORD, CT have inspected the repair, modification or replacement described in this report on YJAY JA: 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 o loss of any kind arising from or connected with this inspection. Date /14- , 20 b-7 Signed I', -h O -Commissions NB 9330 "N'A"A" Ohio Comm (inspector) U (National Board (include endorsements), and jurisdiction, and no.) REPORT NO. P0059-011 1E12-303 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 NOI- 1741 1. Owner 2. Plant: FIRSTENERGY CORP.10 Center Road. Perry. Ohio 44081 Perry Nuclear Power Plant (PNPP)10 Center Road. Perni. Ohio 44081 Date 05-31-07 Sheet 1OF 2 Unit ONE ORDER 200174615 (Repair Org P 0. No. etc.)Type Code Symbol Stamp NR Authorization No. 33 Expiration Date 09-28-2008

3. Work Performed By: FIRSTENERGY Nuclear Operating Company PNPP 10 Center Road. Perry. Ohio 44081 4. Identification of System: 1E12 Residual Heat Removal 5. (a) Applicable Construction Code: ASME SECTION III NC 1974 Edition NAMEISECTION/DIVISION/CLASS WINTER 19 75 Addenda Code Case(s) 1644-5, 1728, N-224, N-242, N-272, N-275, N-282, (b) Construction Code used for repairs, modifications, or replacements:

1974 WINTER 75 see above Edition Addenda (c) ASME Code Section XI applicable for Inservice Inspection: 1989 no Edition Addenda (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 FIRSTENERGY NUCLEAR OPERATING COMPANY PNPP 6. Identification of Components Repaired, Modified, or Replacement Components Code Case(s)n/a Code Case(s)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 tE12 83 N/A 1985 replacernent yes System 7. Description of Work: Replaced 4X6 FLANGED RELIEF VALVE S/N-4 WITH NEW RELIEF VALVE S/N-5.(0 1 E12-F0055B.USiNG NEW 2" DIA PIPE HEAT # 99035, PIPE FLANGE HEAT TRACE # 4M38343, AND WELD ROD HEAT # F5512. AND 901213.8. Test Conducti Pressure 315 ed Hydrostatic- [] Pneumatic-D__ psi Test Temperature 79.8 Nominal Operating Pressure-N] Other- D " degrees F Code Case(s)--HiA- /-t.// --XZ 6"" 53/- 0 142 I 9. Remarks: NONE 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, 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 _ 20 __Date zl-i 20 07 Signed FEI'IC-PNPP DE (nfame of repair organization) C-"-- (authorized representitive) (title)CERTIFICATE OF INSPECTION/INSERVICE INSPECTION I. THOMAS G LAP'S holdiig a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors and coelificate of corrpetency issued by the jurisdiction of OHIO and employed by HARTFORD STEAM BOILER CT of HARTFORD CT have inspected the repair, modification or replacement described in this report on .JU,. C 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 clfoss of any kind arising from or connected with this inspection. Date (,L. 20 Signed Commissions NB9330"'N""I"A" OHIO COMM.I 7ispect.l X (National Board (include endorsements). and jurisdiction. and no0.) REPORT NO. P0059-011 FORM NV-i CERTIFICATE HOLDERS' DATA REPORT FOR PRESSURE OR VACUUM RELIEF VALVES'As Required by the Provisions of the ASME Code, Section III, Division 1 Pg. 1 of 2 I. Manufactured and certified by Target Rock; 1966E Broadhollow Rd.; E. Farmingdale, NY 11735 (name and address of NV Certificate Holder)2. Manufactured for FirstEnergy Corporation: 10 Center Rd.; Perry, OH (name and address of Purchaser)

3. Location of installation Perry Nuclear Power Plant: 10 Center Rd.; Perry, OH (name and address)4. Valve 76H-013 Orifice size 2.94 Nom. Inlet size 4 Outlet size 6 (Model no., series no.) (in.) (in.) (in.)5. ASME Code, Section III, Division 1: 1974 Summer 1975 2 None (edition) (addenda date) (class) (Code Case no.)6. Type Spring 485 N/A 450'F 1100 at Ambient 'F (spring, pilot or power operated)(set pressure, psig) (blowdown, psi) (rated temp) (hydro,test,pig,inlet)

7. Identification 5 N/A 76H-013 Rev. D N/A 2007 (Cert. Holder's serial no.) (CRN) (drawing no.) (Natrl. Bd. no.) (year built)8. Control ring settings Not Applicable

9. Pressure retaining items: Serial No. Or Identification Mat'l. Spec.Including Type or Grade Tensile Strength Body S/N 1 SA105 Bonnet or Yoke Support Rods Nozzle Seat S/N 7 SA479 316L Disk S/N 11 SA564 630 Spring Washers Adjusting Screws Spindle Spring Bolting Heat # 7244720 SAt193 B7 Other Items 10. Relieving capacity 3,442gnm@10%

overpressure as certified 70 ksi 70 ksi Hl100 140 ksi 125 ksi by the National Board N/A (date)11. Remarks: Outlet Flange S/N 1 SA105 70 ksi Cap S/N 2 SA216 WCB 70 -95 ksi CERTIFICATION OF DESIGN Design Specification certified by John S. Holton P.E. State PA Reg. No. 027024 E Design Report certified by Not applicable P.E. 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-1949 Expires 12/12/2007 Date ./ -7 Name Target Rock (NV Certificate Holder)Signed " R. E. Glaz r,OA Maager (authorized representative)

Supplemental information in form of lists, sketches, or drawings may be used provided (1) size is 8/2 x 11, (2)information in items 1 through 4 on this Data Report is included on each sheet, (3) each sheet is numbered and the number of sheets is recorded at the top of this form.(12/18) This lform (EIX)O37')

i.-y be obtained from the Order Dept.. AS ,IE. 22 Law Drive. Bnx 2300, Fairfield. NJ 07007-2300 REPR INT 61/3 143 FORM NV-1 (BACK -Pg. 2 of 2 )Certificate Holder's Serial No. 5 CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State of Province of New York and employed by OneBeacon America Insurance Company of Boston, NL\ have inspected the pump. or valve, described in this Data Report on cL 0 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 certificate, neither the inspector nor his employer makes any warranty, expressed or implied, concerning the component describ is Data Repo. Furthermore, neither the inspector nor his employer shall be liable in any manner for any personanury or'opert daage or a loss of any kind arising from or connected with this inspection. Da Signed ommissions " ,i Inspector) (Nat'l. Bd.(incl. endorsements) and state or prov. and no.) REPORT NO. P0059-011 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 1/00 NOI-1741-/ 0/-4 1. Owner: FIRSTENERGY CORP.10 Center Road, Perry. Ohio 44081 2. Plant: Perry Nuclear Power Plant (PNPP)10 Center Road. Perry, Ohio 44081 Date 11/2/06 Sheet 1 of 2 Unit 1 200192905 (Repair Org. P.O. No., etc.)Type Code Symbol Stamp NR Authorization No. 33 Expiration Date 9/28/08 3. Work Performed By: FIRSTENERGY Nuclear Operating Company PNPP 10 Center Road. Perry. Ohio 44081 4. Identification of System: Low Pressure Core Spray 1E21 5. (a) Applicable Construction Code: ASME Section III class 2 1974 Edition NAMEJSECTION/DIVISION/CLASS 19 76 Addenda Code Case(s) N/A Winter (b) Construction Code used for repairs, modifications, or replacements: 1974 W76 N/A Edition Addenda Code Case(s)(c) ASME Code Section Xl applicable for Inservice Inspection: 1989 N/A. 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 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 Pump Bingham 1A017 797 N/A 1980 Replacement Yes Willamette Description of Work: Removed rotating element S/N 1A022 and installed rotatinq element S/N 1A017.Note the pump casing was not changed.7 8.Test Conducted: Hydrostatic-E] Pneumatic-E] Nominal Operating Pressure-El Other- EL Pressure 50 psi Test Temperature 77 degrees F Code Case(s) N/A 144 NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back)PNPP No. 9308 Rev. 91i 1100 NOI-1741 9. Remarks: , 7-- ,, // C __2,Z 2. 7/9/o?-t6A\ -71 q 107 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 8 112 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 Sept. .20 08 Dale 2 Nov , 20 06 Signed FENOC-PNPP QC Tech.(name of repair organization) (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 1 20 0(6 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 ..IY.20 0 (a Signed -t7- Commissions NB 9330"N""1""A" Ohio Comm.(inspectorf- (National Board (include endorsements), and jurisdiction, and.no.) REPORT NO. P0059-011/,c 2 J -,0 3 7 5 '~"/9/2-FORiM NPV4 -JNJFACTUIREAV BATA-:11EPORT FOR NiL EAa PUJMPS 6f VALVJES-~~ffi P ovisionvof theAM Cod S4ctiottF.Div. 1)Ai-niffam-40VfiTt C6., ý2,800il ?'- Fr-jn~t. Ave -.. Port, 11d', Oregon 972i()f ta2 fctý. 4oinrEecrc. Triain 2 2-ýeitrt3obv (d) lf~9(if Nerf. -9) Year mrrvTpo Na.?~. Nm. (eVt0s= gd! No. Bul fk 'CAR' -Wl A FD1OS2 I.,jý~ 93 (4).5$: Ocn~~n ~r'dh~on 10 p*~j 140T c,~ Vof'~e. Pr,-Suaý Cl _________ 1 N I~3~i.Kirk No= 'm~ei~se o M~gnufadtjr, Re,1mkl I1 29.,:J7;3 'SAI-5 cF8 &:ý-- fi.a -Cast S.' Ultf i nqc;B-I1T-78 iSAm-351 CF8. 0. bAT. CWst S. il Gl.asnd,.... .... ...-I__________[PAG I~~~or~~ rna. P n~ty.SL-pleme'zi i o~fl o-r s oetchýe -ma-n.'ay be us~ pro.d~8t1).d -? 6,~~ 2.n6o1n 4,: 1,n~ 2 .,. 5 -on thit datz ;ýopn. ic k;okded --h = hcet c.8ý(3) ezd, is:e (-',nobcredv-n zn.cf e m 1 V is a-c~,d ato cf this form (37JThin' form1 IC000371 ( t-0Yc3,7bt1r~ed'frcm t?04 CidwT0Det_ .SAG M.3 5 F 7 S,..~~Y~N 01 145 FORM NFV.T1 Moa~M Mark No. Mattriil ScO.C. No. Man--I --i 81784 ISA-193 87 M'otriv Stud- Case G12- A-9381 erxJ Stud, Gland 818 S-14 3M1'. xerix I Mut, Gland A SA- 4. 9- CT 2 Metri.X Capscrew Bracket, Motr A!SA-325 Tp I Ke'tr Bolt. Pumo 0610 ________ SA19 87 Mtr Tager Pin V-67 T-5 56-S SA-1,92 304 Fami~lfan Plug. Orain _l1{405.1 .SP.A3i] 104 Tbe I .ec; Pf4I VITO S A'ý18? Wo4 *~~ia o ViG7 -: A-l8Z 304 Familiar, Elbo VHV 1SAAi 82 3,04 _Fdniilian Pu 0631 ) SA- 182 30 UerxOrfc VDQý,VA ýVKO ] tSA- 182 304 _____O__an _ 1nion%. Hydvositie-lc.tst -22/900j psi.CE~RflCATE OF COMPLIANCE We- ee'tify-.that tht .staternents: made: intT his.-,eport ate corinR and- that lhii pump. or valve; conform& .o the. ruie,% of ccpinstr-ucion of. the. ASME Code. for. Nuclear, Powmer Rianrý Componentm .Section 11f, iDivý L, orit97 A~ldenda..~IL~i~ -.Code. Cie& No._________ Our A-ME Car-srficatd of Authorization No. N.165.4 TN_5.T~ H symnbol e.*pirre 22 IN INVI Dx.CERIFIiCATIONP OF DES !GN Doeaign Informazion on fila~t 8.1nghzim-Wil lamette Cominany SZrez nshyr;s report iC1tasi oniv). on r..ef a, Nil Design pecrficlons cnified by 1),-. H-iram R- Reapert_PCstate Venn .eNo. 24928E* Sires natysi, eq re (1) Pul) 01i iver -Va -Gu i k: Assoc-.-~ 0:egon Req. No. 626.1 I11 S&0*tura not rertuireld. List name onody.1,teuntiqrsiqned. holding a valid ori!ini~e CST C try OF e Natona INSPECIoN-:Bie and Pjresesure Vessel Itnpectorx adiaState or Pro~ o Ort-gan and 5-ploYetd by eaten of _____________________ -'ave inspected the pomp, or valve, described in To,, (Data, Rapot dor 19 Xf2. and Ittt'i that-to the. best Of MoY krnOwledgean belief. the- Ma ,fact..,rer h~asccK-.3tsTIt 106i3 PUMP,. or valve. int acc dar-a -ith tise ASME Code. Section Mi.BY signin~g this cotifpczte. neihf-er The- IntPectOr norf his employer rnka3 any WA!1znrty. ex-sprefte Or Implied. concernirn." if-.e equipment dasczibed in 21is. Data Rroper-- Fu~lhermo.-e, neither Thea InsPeCtor nor his emnploy.r ahlalf be liý!~~:.r' ransnrer for any persolnal injury or property damnage or a loss of anyt kind a'ising.ftrcr or monected wVith This. intspectibo. Dat,~ -* .~va-a~ar$,.Commission, Tti d.Ssa. t-r a o jtspsetort REPORT NO. P0059-011/ /-Z 2 -o 6 ý2-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.10 Center Road, Perry, Ohio 44081 Date 10/10/05 Sheet 1 of 2 Unit 1 200170404 (Repair Org. P.O. No., etc.)2. Plant: Perry Nuclear Power Plant (PNPP)10 Center Road, Perry, Ohio 44081 3. Work Performed By: FIRSTENERGY Nuclear Operating Company PNPP 10 Center Road. Perrv. Ohio 44081 Type Code Symbol Stamp NR Authorization No. 33 Expiration Date 9/28/08 4. Identification of System- 1E22 Hiqh Pressure Core Spray 5. (a) Applicable Construction Code: ASME Section III Class 2 ,1974 Edition NAME/SECTIrON/DIVISIONICLASS 19 76 Addenda Code Case(s) n/a Winter (b) Construction Code used for repairs, modifications, or replacements: 74 w 76 Edition Addenda (c ) ASME Code Section XI applicable for Inservice Inspection: 1989 none Edition Addenda (d) Applicable Edition of Section XI Utilized for Repairs, Modification, or Replacements: 19 89, none 19 none Addenda n/a Code Case(s)(e) Design Responsibilities FIRSTENERGY Corp.6 Identification of Components Repaired, Modified. or Replacement Components n/a Code Case(s)n/a Code Case(s)Name of Name of Manufaclurer Nal. Other Year Repair, ASME Component Manutacturer Serial No. Board ID. Built Replacement, Code No. or Modification Stamped PUMP Bingham 1A018 798 1E22- 1980 Replacement Yes Willamette C003 7. Description of Work: Worked the pump using replacement stuffing box and seal gland fron pump s/n 1A017.8. Test Conducted: Hydrostatic-E] Pneumatic-E]Pressure 51 psi Test Temperature 110 Nominal Operating Pressure-Z Other- E]degrees F Code Case(s) n/a 146 NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back)PP)PP No. 9308 Rev. 9/11/00 NOf-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 Tesick 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 10 Oct. 20 05 Signed FEOC-PNPP i " C Tech.(namne of repair organization)t (author~ized reprexenilaive) (title)CERTIFICATE OF INSPECTION/INSERVICE INSPECTION I. Thornas C 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 OHtO and employed by HSB CT. of Hartford, Conn. have inspected the repair, modification or replacement described in this report on CXT 10 20 OS- 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 dama e loss of any kind arising from or connected with this inspection. Date 20, 0 Signed 1I+et W/J140_7 Commissions NB 9330 "N" .I" "A" Ohio Comm.(inspector)U (National Board (include endorsemenls). and jurisdiclion, and no.) REPORT NO. P0059-011'9 I.FORM Ilf'-1 -NUFACTUREAS DATA REPORT FOR 1`41 FAA PUMPS OR VALVES-jA!; Aquirad by U~e Pzovisior.s of the ASME Code. Sacition, Ill. Div. 1)1. Bio Clloh jgh an.-Wi IIamfet.te Co. 2800 tvi1 Front Aie. , Portland, Oregon 97210 2. r Gilrt- nli~ieath/C eveland Electric Illuminatin I Lo.ziion ot`I.%tjIlfarcn -P e rryp N u c ra 'r"rw~e'r 'Pf 3 t Un t s 1 & 2 4. Pump qr 'Jr(;w Purna NamJoni,m. Inle Size 0 001e Sit 2li;-hl Serie No:.-cr "vpI (b)~ Manfisowes' S.*rfiI --, NO.1c) Can.dl.n,-Ragisvti~on No.(d, OoD.;g --C ) o.No. (e) Cfe." Bd. No.(q) Buiit ill CA?IA017 ,A FO IA015/22TI7 iN8 -79 7 I ' t 12)---- r .....IC5. ______Rif ______1-9)101 __5. ____!-a ter. 1-eq Pump Ihrint drnrrrtnr 0t -mc~O .lh -,p,,r- -, d-vij-cei 6.7.3.Cold W., zing Pressura -~Praeuptr Ifetaiing PieteS Markr Ne.11,79-77-3 SA-I1 B7 -7 7-3 140-IT~~on~ur. 'F or 'fiePresure Class-psi a: tOOF.M.ate~ri. SpieC No. --ttnfcue I[11)35 1 CF-3 SCFS 351 CF8 oua H -cast Cuja~li-cast -n I iR I i -(',I-Stuffing Box Sea] Gland I_____________ I .~1 __________________ 7c~lAMO~.>x ________ I _____________ ___________ _________(if For rr~nuallv opera'Ed ',.1-e ofli-.-.0*1'I--.1.S /;dI / j 4 ----------- ITE~h_____________________________ ___________ --i _______SuFpl-ervrrrnl sh fo ci listi. fsh-c hias or driing, I.ay he used provided I0) sit. is S-lIT a 11'i $2) inforr ation in rins 1. 2 ard 5 .n thi data r;bpt is included cr ezch rhect. and M3! each sheet is numbered and number of sheem is rcrO-d at Zop of this -'Yr ,k.(217 J I Thhe- r-r- IE'20371 2,l I.e ,bt.r.ird remr. Order Ctp. ..-SSIE. 345 P. 47 S:. i4e ork. N.Y. 100 17 147 1,1,k No- " Masrr.i Spc. No. Mar uIzr po rn,".87:84 ISA-193 87 __etrx Stud, Case----_____ JSA-1. 4 H -____ lietri x 0M IOA-:9 3 8M etrix Stdln-_7__7 _ _ SA-194 BER Metrix Nut.. Gland A SA-4 CI 2 I eKtrix Capscrew Bracket, Mot A _SA-325 Tp 1 Metrix a6 t., Pump-IOT- _ SA-193% B7 Metrix Taper Pin'7-T-45565 SA-192 304 FamilIi an P _uq, (al Other p rt, S ,~urcui" " [ti Piina TH4051 1_JA_304 .J Ti I Ps -_ -ipp--VHL SA-_ 18 304. Familian ___ _ __HV _ _ IA-182 304 Farai I ian Plug w' ~0637 _j_,4182 304 tMetrix -0iie___FAVK0 IA_8 2_ 304 ___F CERTIFICATE OF COMPLIANCE¢erfy that the in this 'epori are csrfdo and that this pump, or va,,f. conforms :o the rsles of ntruIctrsson of !Ne ASME Code for Nuclear Power Piant Components. Section M$I. Div. I.. -Edilon. 1_974__,'=.ddma 76-.... __ Code Cas- No. __Date_ .Ce.a ___.Binghan-Willarrette Comnany -.."'0o, AýýNE Cslia oG Acri A rion No. r- -1654 to t she N Symbol .2I2L CER1IFICATION OF DESfON:'foss.t:. or on f-il B i ngham-Wi 1 lamette Companynnryi one srsnd b~ICI --1 o ty) on ft f a N'PE Penn S ,N, 24928E Sress a cart-ifiwd byjN Paul Oliver -Van Gulik. Assoc-.S Ore gor Ra No. 6261 I1I Sinoz-urn not eaq-.rnd. Liý-. ne r>n t f.S.. .. CERFICATE OF SHOP IPJSPECTnOrJ 1d sI, u uNdelsignod, hGldinqg a vAlid issued by the NatiohaI Bord of Boiler and Pressure Vessel ispe..or$--ad sire State 0r P-om~cc of Irgn. and 0mpfoyed by Departiment of Commerce han~s inspe.ted the psrnp. or valon, d.scribed in this Oata Report on-tIS .ansrd $fart that to the beos of ny kno-edge and baliuf. the MansfacLurer, h sIta'-uctd thi- bump. or val-'e. in accordans-a sith le ASME Code. Section Ill.9%, rignfng :IMS crtif...=a,, nether If-, inspector nor his employer makes any warrZnry, or implied. co-,ce-rsing rie c-j.uio.nesn fn.si bed in this Oata Mnpost. Furthermnore. neither the Inspector nor his emnloyr shi.ftbe lisble in any n rnn- fot any prsnotal inaurr oc property demage or l 0oss of any kind arising hoe or0 .onnected with th;s inspec:icn. L7i-"* o,. ...'--si-bd _s N P'*... -d n. REPORT NO. P0059-011 I E22-063 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 Hl(t 17711 1. Owner: FIRSTENERGY CORP.10 Center Road, Perry, Ohio 44081 Date 1-24-06 Sheet 1 of 2 2. Plant: Perry Nuclear Power Plant (PNPP)10 Center Road, Perry, Ohio 44081 Unit one order 200192276 RIO (Repair Org. P.O. No., etc.)Type Code Symbol Stamp NR Authorization No. 33 Expiration Date 09-28-2008

3. Work Performed By: FIRSTENERGY Nuclear Operating Company PNPP 10 Center Road. Perrv. Ohio 44081 4. Identification of System: 1 E22 High Pressure Core Spray 5. (a) Applicable Construction Code: ASME SECTION III NC NAMEISECTION/DIV SION/CLASS Addenda Code~1974 Edition Case 1644-5, 1683-1, N224-1. N240, N242. N272. N275. N413.winter 19 75 (b) Construction Code used for repairs, modifications, or replacements:

1974 w__ winter 75 Edition Addenda (c ) ASME Code Section XI applicable for Inservice Inspection: 1889 no Edition Addenda (d) Applicable Edition of Section XI Utilized for Repairs, Modification, or Replacernerts: 19 89 n/a 19 n/a Addenda n/a Code Case(s)(e) Design Responsibilities First Energy Nuclear Operating Company PNPP see abov Code Case(s)n/a Code Case(s)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 1E22 86 NA 1985 RPL YES SYSTEM POWER 7. Description of Work: Replaced horizontal waterleg pump S/N 1A017 at 1 E22-C0003 with new waterleg pump S/N 1A018..8. Test Conducted: Pressure 55 Hydrostatic- [] Pneumatic-D]psi Test Temperature 111 Nominal Operating Pressure-X degrees F Code Case(s) NA Other- E]148 NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back)P PP r i,: 930 Rev' 9/11/00 N IO-i1741 9 Rermarks: 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 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 forn.CERTIFICATE OF COMPLIANCE I, John VV. 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 "PtR" rules.National Board Certificate of Authorization to. 33 to use the -NR stamp expires 9-28 20 08 Date 1/23 20 06 Signed FENOC-PNPP D OE (name of repair organizalion) aLth-7 e ronzt (title)CERTIFICATE OF JNSPECTION/INSERVICE INSPECTION I, Thoin-, La ps holding a valid commission issued by The atinal 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 0 (o and state that to the best of roy 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. Dale --, 20 Signed Commissions NB 9330 "N" "I" "A" OHIO COMM.(n c( (National Board (include endorsements), and jurisdiction, and no.) REPORT NO. P0059-011 IF22-Sheec 2 of 2 FORM NPV-1 .PJUFACTURERS' DATA REPORT FOR NU , AR PUMPS OR VALVES'(As Required by the Provisions of the ASME Code. Section III, Div. 1)I -Manufactured by Bingham-Willamette Co., 2800 NM Front Ave., Portland, Oregon 97210 (Name and Address of M rr)2. M,-anuatured tor Gilbert-Commonwealth/Cleveland Electric Illuminating (lame and Addrss of Purchaser or O-nerl 3. Location of Installation Perry Nuclear Power Plant Units 1 & 2 -1r4a,-ne -d Address)4. Pump or Valve Pump Nominal Inlet Size 2 Outlet Size 2 (-nch) (inch)(a) Model No7,- (b) Manufacturers" (c) Canadian Series No. -Seial -. -.-Registration or Type No. No.(d) Dra wving -' (0j Natl. (g) Year No. (e) Class Bd. No. Built (21 (3)14)(51 CAP]AOI18 NA -FD-1A015/22 11 NB -798 T-IA018 171 181 101 5.Water Leg Pump (Briel description of service for which equipment was designed)6. Design Conditions 150 psi 140 F or Valve Pressure Clars. I _ 1)(Pr- -surl) (Temperaturel

7. Cold Working Pressure 150 psi at I0WF.8. Pressure Retaining Pieces I Mark No- Material Spec. No. Manulacturer Remarks a) Castings 1147-77-4 SA-351 CF8 Quail-Cast Case 1147-77-4 SA-351CF8 UPQai-as Slffino B __1147-77-2 SA-351 CF8 Quali-Cast Seal Gland b) Forgings_izz. _iiprzz,,-

ITFM ,'a -, 4- H N Fr Iti-tuc It j__ _ __ _ +/- _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _(1) For manually operated valves only.Supplemental sheets in form of lists, sketches or drawings may be used provided (1) size is 8-1/2- x 11]. f2) information in items 1. 2 and 5 on this data report is included on each sheet, and (3) each sheet is numbered and number of sheets 149 FORtM"t NI'.- 1 Mar. No. t.taleteal Spec. No (c) Bolting 8784 S SA-193 B7 8285_ SA-194 2H 0124 SA-193 B t,1=7 SA-194 B 8'M A SA-449 Cl 2 A I SA-325 Tp 1 J Mannu. rer Stud, Case --i e i JIekidl le tri x Nlt( r('Stud, Gland Me tr ix Me tri x Nut, Gland Capscrew Bracket, Mo Metrix 0610 SA-193 B7 P.O. 1-45565 SA-192 304-Me tr ix FamiI i an Bol.t, Pump Taper Pin Plua. Drain--1 (dl Other Parts Seaf] Ci rcu a- tioon- jpipjlfZ_SA~fl2 qn Tiihp S~lp Pino TH405 1 Lsndaxu Ii'm1~V10 .SA-182 304 VHV SA-182 304 0637 ISA-182 304 VDOVFAVKO SA-182 304 9. Hydrostatic test 225/900 :0:0 I Familian Flhnw IFarnilian P1 uo Metri x Familian n r-i fi r-P Union-I-CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and that this pump, or valve, conforms to the rules of construction of the ASNIE Code for Nuclear Power Plant Components-Section III. Div. I., EdiLion 1974 Addenda W'76 Code Ca .no. 1A .Da:te,,J- _Signed 8ingham4-I 1 ame tte Company by Our A.SME Certificate of Authorization No,- N1- 654 to use the N symbol expires 238_83 (NI (N F1) (oDate, CERTIFICATION OF DESIGN Design information on file at Sinqham-Wi 1 lamette Company Stress analysis report (Class I only) on file at NA Design specifications certified by (1) H i ram PJ Re-peJt PE State Penn Reg. No. 24928E Stress analysis certified by (1) Paul Oliver -Van. Guli k Assoc.PE State Oregon Reg- No. 6261 (1) Signature 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 Inspectors and the State or Province of Oregon and employed by Department -of Commerce -have inspected the pump, or valve, described in this Data Report on:ý/ -9, !- and state 'hat to the best of my knowledge and belief, the Manufacturer has con-stnjcted this pump. or valve, in accordance with the ASME Code. Section III.By signing this denificate. 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 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

tg9 k.C ,~<Co sor2 fi'0 Bd.. Sl-te. Pre. andomsin (Ir pero Ntlr't 8d.. State. Prov. anrd No-I REPORT NO. P0059-011 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.10 Center Road. Perry. Ohio 44081 Date 11/6/06 Sheet 1 of 2 Unit 1 200233328 (Repair Org. P.O. No., etc.)2. Plant: Perry Nuclear Power Plant (PNPP)10 Center Road. Perry, Ohio 44081 3. Work Performed By: FIRSTENERGY Nuclear Operating Company PNPP 10 Center Road, Perry, Ohio 44081 Type Code Symbol Stamp NR Authorization No. 33 Expiration Date 9/28/08 4. Identification of System: HIGH PRESSURE CORE SPRAY 1E22 5. (a) Applicable Construction Code: ASME Section III class 2 ,1974 Edition NAMEISECTION/DIVISION/CLASS 19 76 Addenda Code Case(s) N/A Winter (b) Construction Code used for repairs, modifications, or replacements:

1974 W76 Edition Addenda (c ) ASME Code Section XI applicable for Inservice Inspection: 1989 NIA Edition Addenda (d) Applicable Edition of Section XI Utilized for Repairs, Modification, or Replacements: 19 89_9 N/A 19 N/A Addenda N/A Code Case(s)(e) Design Responsibilities FirstEnerqy Corp 6. Identification of Components Repaired, Modified, or Replacement Components N/A Code Case(s)N/A Code Case(s)Name of Name of Manufacturer Nat. Other Year Repair, ASME Component Manufacturer Serial No. Board ID. Built Replacement, Code No. or Modification Stamped Pump Bingham 1A019 799 N/A 1980 Replacement Yes Willamette Description of Work: Removed rotating element SIN 1A018 and installed rotating element S/N 1A022 (including stuffing box and seal gland) Note the pump casing was not changed.7.8.Test Conducted: Hydrostatic- [] Pneumatic-LI Nominal Operating Pressure-M Other- Li Pressure 51 psi Test Temperature 112 degrees F Code Case(s) N/A 150 NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back)PNPP No. 9308 Rev. 9/I 1/00 NQI-7741 9. Remarks: X/,7.- --, /-5 //- Z Z. COQ00 3-' .;-7 7- Z-o07.VGA. ___1 tC.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 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 stainexpires 28 Sept.. 20 08 Date 6 Nov. 20 06 Signed FENOC-PNPP OC Tech.(name of repair organization) (auth rized 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 I14\1. V-o 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 to s of any kind arising from or connected with this inspection. Date AIE, 20 Signed 4__Commissions NB 9330 "N" "1" "A" Ohio Comm.(inspector) (National Board (include endorsements), and jurisdiction, and no.) REPORT NO. P0059-011/ ýC_2 ? -04f L: 17 FORlM NPV-1 %NUFACTURERS* DATA -IEP.ORFT FOR PN EAR ?UPAPS OR~ VA~LVES'(A-vRoquirvd ..y tha Provislonw of: 1110. JSMS Code. Section 111, Div. 1)i.Mom; fkfi rncd& nirh arni.Wil et.Le- Co. ' 80G 11W~ roflt- Ave-., PcrtTland, Ore.gon 97210 2~ ~~o G~~~u~~4.iib'ert Lor= m; .a .e nt- EI-ectri' 1 I Iumi na ti ng X C-~ mt~o er, RNud ýe&r Power I antf. Lnimits: 1 2 4: Purrpý. or, Vx!Va.- Pm ora e.ss 2 Oet 2* (a)M dAN: orTypre (b) M~nufkira'!r No,.10) Capodizn flRugisiraiorv: (d 1O0r a'.%;, rib. No: 1.9'Not NI. .g) Year 10) Classa B& No. auill CAP- JA022? N FD NAI522 I 80YT2 O (3'Wai( eg-Pm 15 F or av P es r .ln -1'3)n'a Ti p -u )751s % ,F (.(,rN-. t1.1 erial Sbec_ No. Pju3T!rR m rs (:r. W 2.in' 7:3 (b):V.df-P a te -Oua-I i Cast.Case.I7S A'.;-3 i7F8.ý nurli-ca,t

~:t.rr-~f.i~rrrT.

R~*ry__ __ __ __ __ f--.- I.ffi .f I. I ....1--1 .' +e al l.Ganrid.VC_____________ 3.16L }.stfern..anls I: F +U < A: r, 1.__ ___4_ --4-()For rn-o~fly operated -:orry.Su pF lert.o en a I I sin r. f or n af istt. x orlc ca dr am ioj7 mnay be us,3r1.p ojoc6td. 11.) 3ia3dis, 8;.1r i7. W. :((.rfIrm#5ib .or3 itrramrs -1. 2 a d 5 on, t h;s. d ata re port i s. ir ' luct-d' r r eo ch s h "L, and& 13) %ea ch- hee?. i Snurrumbe red an d..numeofh is eco~dcd at icp of thiz form.12177) This form E00Cr3?1 t. b Obaiej hlor tsO~dgr Oepi.. ASE3,5E N3t icoii~. 00ý151 'CRM rNpv..lSec

mark _14. 34rlcriz;JSpo-No: ,i(a, Remarks I -~(ci f~4 SA-1:938 Me 1tri x Stud., Case___________

S A49-1 .2H- ____i x~L as 012 41 SA.-19188 Mi._____ ?ltrix. Stud., Gland~~7~~.7a KA14~ ~ ri* x ut, Glano A SSA,-4i4.g C]2x Caonsrrw Rfrark p tMn c_________ ________________ TO________ I Msolx ,ct' pump, 061q0 }SA-1932V -M.etr.i x lacer Pin T-.1 ý.-4 5565' SA-19 310.4' Fainjilian f~ g Dr I d){O~ 01a at r S Ae -c312 3 (- a, ri-I- I-DA{ n 11111) cýA_7A7 -ýn4 V'.ii i A n... .... .._. .. .. .,_V1:0! SA-.182. 304.I 304 FainI-i ia n Fami I fan rt r i <O-ri f4 riý053T 5 A--182. 304 063T I SA-132 'A14 v. DO V.F VK(O ISA-.12 304 I F,:T J:1 i ,) n~~1 -- ____________ ___________ ______________________ ii.-_________________ __________________________________ ___________________________ -I______________________ I ____________________________________ ______________________

9. H,'d:o~taic lv~ 225/900 5 CER0TIM1AXE OF COMIPLIA(NC-,A~..CIIt

,",A ho Slzternýisr made -in -zhis-revert.

ar--corr~cct and- that. Thi4 0.rnpi 0r lve, con~forms

o'Tir ru:05 of cos-hj in.t t~no-ASMECode.

for- NUclevr Powar.'Plant Corn potnTnM S~ct~o, W. D., , Edtih ~ 1974 Addeida. -WU'76 Code Case No. NA .c&I_________ Slnd B-i nqhani-i I 8he Co)mpa ny ~__ _____0.r ASME cemficar,, of -.Mrho~iza.i~ 164 t~~er ~ ~ ,ricaie 28 .813 CEffTIFICAT1O0J OF. rCESIGN De egwinormnazion onfl it 6i ngharn-'4i-ll~anette-Comcany Su"anaoy-jig:!port IC14a 1 only) -on fiie.at NA Ocjg pecin-oaliona cilfe byO) Hram .R ar PESau penn Regi No. 24.92SE5*Slr'm.Inal~ysiz etienfed byv (1) Paul Oli ver -Van Guli.ik Ps.-Gsc..not req.;red. UU riant orilv.C~FltF;CATE'.OF SHOP *IASPE-TIO

1. the undersigned.

hoiodsr.g a valid cornmissicn issund b-,. the.- Notional. 9oard o-f Boiler and:Pres.rosVesnl art __e_.0r .andermployed by Da rtren .tof " "e ' r Prori.rc f- ----~o h_____'__"_"___"_"'_"_" _ "_"_"_"_:- --../' ~er .hahe. inspected the. pump; or a'vfi. decubod, i, thi: Data" Report c.._ -i3 ..j and-stare thtt:to eNhe:a-rl of try rro's-Ie'-gq artd beli has con-, stect=d this .pump. of vanle. in 3c.ordance wNith the ASNME Code. Section III.By .signing thia ce lifite. neither the 'nspeceo, nor. hi: -ernploar-mak.s: any'waarrnrry. erp!._sed. or implid, co'izctrni'ng:." to. soiprrenr dz.cibsd iin this.clar Fleportý Furtnetnoori. neilher the Inspector.or hi .eMploy-.t ihal! -'.,bl.:nv-rr-.anner for an.y personal inury Or property damtgor.o a I-s, of ay kynd.vris~ng. os.or.,connactd..wirh..hig.inspocto. ... .. ---7. .A] rti ml scion, rLCr.ns~cd~,~j<&e- '~ ¶3 4. -it tsr: ~rar, a-~Ad;Notr REPORT NO. P0059-011/,e52 L -0a-1 NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section X1 PNPP No. 10282 Rev. 7/22105 Pane 1 of 2 NQ1-1741 1. Owner.FIRSTENERGY CORP.Name 10 Center Road, Perry, Ohio 44081 Address Perry Nuclear Power Plant (PNPP)Name 10 Center Road, Perry, Ohio 44081 Address Date 1/26/07 Sheet 1 of 1 2. Plant: Unit 1 200203387 (Repair Organization P.O. No., Job No., etc.)Type Code Symbol Stamp NR Authorization No. 33 Expiration Date 9/28/08 3. Work Performed By: FIRSTENERGY CORP.Name 10 Center Road, Perry, Ohio 44081 Address 4. Identification of Syslem: HIGH PRESSURE CORE SPRAY 1E22~. A lA~hi~ C-~ ~ ia~ia' N/A 10 N",JA Iditinn N'./A Addenda, N/A Code Case (b)Applicable Edition of Section X1 Utilized for Repairs or Replacements 19 89 6. Identification of Components Repaired or Replaced and Replacement Components Name of Name of Manufacturer National Other Year Repaired, ASME Component Manufacfurer Serial No. Board Identification Built Replaced, Code No. or Stamped Replacement (Yes or No)PIPING N/A N/A N/A 1E22F541B N/A replacement No 7. Description of Work: Replaced 2 way air start valve with new valve. (This item is not built to.ASME Code but is in the ASME Section XI boundary)8.Test Conducted: Hydrostatic-E]Pneumatic- [_ Norninal Operating Pressure-E Other- LI Pressure 230 psi Test Temperature 86 NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 81/2 in. x 11 in., (20 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.152 NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back)PNPP Ho 10282 Rev 7/22/05 Page2of2 NOI-i741 9. Remarks: None Applicable Manufacturer's Data Reports to be attached CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and this replacement conforms to the rutes of the ASME Code, Section Xl. repair or replacement Type Code Symbol Slamp CertIficate of Authorization No.NR 33 Expiralion Date 9128/08 Date 14 FEBRUARY Signed z-'* ./X ( " ", C 7-?/"c//Owner or Owner's Designee, Title 20 07 CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of boiler and Pressure Vessel Inspecturs and the State or Province of Ohio and employed by HSBCT of HARTFORD. CT. have inspected the components described in this Owner's report during the period tMA. 0o "t". and slate that to the best of my knowledge and belief, the Owner has pprformed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code. Section XI.By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in the Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or properly damage or a loss of any kind arising from or connected with this inspection. -71F Commisions N`B 9330 "N" "1" "A" OHIO COMM Inspe r Signature National Board, State, Province, and Endorsernents Date (4- o0-"T REPORT NO. P0059-011/I32a -o7D NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASIVIE Code Section Xl PNPP No. 10282 Rev. 7/22/05 Page I of 2 NQI-1741 1. Owner FIRSTENERGY CORP.Date 1/26/07 Name 10 Center Road Perr; Ohio 44081 Address 2. Plant: Perry Nuclear Power Plant (PNPP)Sheet 1 Unit 1 200203386 of 1 Name 10 Center Road. Perry, Ohio 44081 Address 3. Work Performed By: FIRSTENERGY CORP.(Repair Organization P. O. No., Job No., etc.)Type Code Symbol Stamp NR Authorization No. 33 Expiration Date 9/28/08 Name 10 Center Road, Perry. Ohio 44081 Address 4. Identification of System: HIGH PRESSURE CORE SPRAY 1E22 5 (a) Applicable Construction Code. N/A 19 N/A Edition, N/A Addenda, N/A Code Case (b)Applicable Edition of Section XI Utilized for Repairs or Replacements 19 89 6. Identification of Components Repaired or Replaced and Replacement Components Name of Name of Mvlanufacturer National Other Year Repaired, ASME Component Manufacturer Serial No. Board Identification Built Replaced, Code No. or Stamped Replacement (Yes or No)PIPING N/A N/A N/A 1E22F541A N/A replacement No 7. Description of Work: Replaced 2 way air start valve with new valve. (This item is not built to.ASME Code but is in the ASME Section X1 boundary).

8. Test Conducted:

Hydrostatic-E]Pneumatic- [L Nominal Operating Pressure-f]Other- L]Pressure 230 psi Test Temperature 86 °F NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 81/2 in. x 11 in., (20 information in Items 1 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.153 NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back),PNPP No 10282 Rev. 7/22105 Page 2of 2 NQI-1741 9. Remarks: Slight air leak at mechanical joint was evaluated on CR 07-12502 and it was determined that Applicable Manufaclurer's Data Reports to be attached the leak will have no detrimental effect on the system performance The leak will be corrected in a future outage.CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and this replacement conforms to the rules of the ASME Code, Section XI. repair or replacement Type Code Symbol Stamp NR Certificale of AulhoIzalion No 33 Expiration Date 9/28/08 Signed Q".,i----". S/? 6_C 7--(:C' Date 14 FEBRUARY 20 07 Owner or Owner's Designee, Title CERTIFICATE 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 HSBCT of HARTFORD, CT. have inspected the components described in this Ovwner's report during the period _____,_L___ to 'E_1. ;to-'/7 .and state that to the best of rny knowledge and belief, the Owner has pe/lorrned examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code. Section Xl.By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied.concerning the examinationis and corrective measures described in the Owner's Report. Furthermore, neither the Inspector nor his employer shalt be liable in any manner for any personal injury or property damage or a loss of any kind arising from cr connected with this inspection.)~Commisions NB 9330 "N ""'"A" OHIO COMM Inspectc National Board. State, Province, and Endorsements Date _____ Il- 20 90L REPORT NO. P0059-011 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.10 Center Road. Perry. Ohio 44081 Date 5-10-07 Sheet I of 2 Unit 1 200208363 (Repair Org. P.O. No., etc.)2. Plant: Perry Nuclear Power Plant (PNPP)10 Center Road. Perry. Ohio 44081 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: 1 E22 High Pressure Core Spray 5. (a) Applicable Construction Code: ASME Section III -Class II NC ,1974 Edition NAME/SECTION/DIVISION/CLASS Winter1975 Addenda Code Case(s) 1644-5, 1683-1, N-272, N-240, N-224-1, N-242,N-275, N-413 (b) Construction Code used for repairs, modifications, or replacements: 1974 W/75 N/A Edition Addenda Code Case(s (c) ASME Code Section Xl applicable for Inservice Inspection: 1989 N/A 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 FENOC 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 E22 86 1E22F00 1985 REPLACEMENT YES SYSTEM POWER 34 Description of Work: Replace old with new valve SN E-295P-1-2 and connecting piping with new pipe (HT 99035) and elbow (HIT 75187)7 8. Test Conducted: Hydrostatic- [I Pneumatic-LI Pressure 33.4 psi Test Temperature 72.1 Nominal Operating Pressure-El Other- L]degrees F Code Case(s) N-416-2 154 NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back)PNPP No. 9308 Rev. 9/11/00 N01-1741 9. Remarks: NONE 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 8 112 in. x t1 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, Russ Matthys , 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 2008 Date 5-10-07 Signed FENOC-PNPP R" M OQC Supervisor (name of repair organization) (authorized repreentative) (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 HARTFORD STEAM BOILER CT. of HARTFORD. CT have inspected the repair, modification or replacement described in this report on ftA II 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 ot4oss of any kind arising from or connected with this inspection. Date (e20 tSigned vt Commissions NB 9330 "N"("A" Ohio Comm.(inspector) 1,1(National Board (include endorsements), and jurisdiction, and no.) REPORT NO. P0059-011 I F ýD-Q 0 ýFORM NPV-1 N CER1I1F) CATE HOLDERS'. DATA:. REPORT. FOR NUCLEAR.PUMPS OR VALVES'S .Requ.iredby d; ProvIton5 of the ASME Code Section Il:II Div; 1ý1. by .l e .. , ."p. .7 ...First treet ..S'l "iam ncrrt .I1 : .* N a m ~e O .A: dc 0 so f .N ..C e r tif i a t e H o t de r )2 .ahacrdo.Thn. Tl.luminatig~fg Coopan;"" pf O.. Box".946OR ..C~peve.fnd" .:O. 4, lID) -4h~~I ..-....... ......... .. ........o: .- ..-r.J. Lo ,n "f Intalýati err,' PP 0 'enter oed bock #1 North .rr y OH k '1l,-,71' " " Nerouo of ~ Ads~t adI 1 Pum p .r Valve.: -.... N Inlet .re O U.let S. ._finch):ortypNe, (b N Certificate. H. "cer .c SerII .Rleistratio-f,6:: (a) .Cia ss.V I N a J ilT..Y -.? 1lo6be .(4)i5)(17 (9).SOb0.0:I215', R/A> t 11/A 199-? .... .... .--.-....110).w/1-4" fipl-c c, 1_. * .. .... .. -.. .....6: 7: 8: b?'~nConda-0,in 29_____ _____ F or Valy Rct!~ r Ciz ss rI Pi-slJre. Retaining P'iece.',- --------------- lbII .n -.S,'No 10:Y ! .....:,.... , .... .... :: : ¢::::: YUokde H-T- ýT# S:l, p I lit Ir ne c IT 7.; For --.-ly O:erated --Ie.o , .0-S pp. li- artol. sth irs form, o TF , l,-fs ketches or. drasrng- -nay.be use prodd IS-s-12 e ')n natnin SR :.tni5:te M-%1 aind 5. oan this ( Reort! Is.include on. recri hoýet And (3). each-,neet. i~s:numbered jnd numbepr: ci l is. rk&6rded'jt too of this 1m b.u.:.* 1.-(10/77) Tlnit foirm 1(E()0037 maya be bta'reo 1.-.r ric Oro bmo b.t 34 E r~t j.'~ 91 155 M~r~.No.M aterial'So .No.M uflulO u~drt C ~ ~fl ~IC) Bdltmng _________________ 1j/ A__________ __7_ _ _ _ _ _ _ __. _ _ _ _ _ _ _ _ ___ __ __ __ __ W -m. __ _ _ _ _ ___________________ -____________4_~_________ 9: Ylydiot..66ýt-f 1ý -., I I -; , ,- " 1)7 -ý -, II l,,z pi- -C:ON CERTIFICATE OF COMIPLANCL .e c i h h t n mad"e In ht "-ipor r correct and that th's pm onf t rle, oDf o0"t- '1 f the A S-M Codef~ t r Nuclear PowerI Ptant1 C'Omo nt Sectio5 ý,-6n jII 1,vI ý, EDr-a Wio I. 1 7 Addlenda Wice 99 Code. Case N .t /A.Sind 5lweceCr hy.....

tl i .. ... I-- .Our .....rtihcate on t. :." o e r,. 4.-:h/.1 5/0"'HI ;.:}I fl ! aral CERTIFICATJON-Ot- UES16N ...... '?':frmaio on....f.....e.

.: F :o,- r.-' 701 , i rstr* .tIi a m s or P ..cs 7 1 ...n.. D b! th und r hi ne ho di g ial i Co mi si n sud by the Naio a Bhr f B ie r ss r e s l I s e t r Bys igený ang this certificat et he the Iset r or hIs Im l yr m ks ay w rat x rse ri pid C nenn manner.. fo personalinur, o , mage or.a: lo of any k ind arisin hgtram or corrnected' with tis at) e.19 ;- n 6 L Only CETFCT CommiSsion ISETO~NnSiV S29 JOt~g e {OITI,,oung lnuei ry thd SIfi'i ii REPORT NO. P0059-011 IE51-139 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.10 Center Road. Perry, Ohio 44081 Date 12-20-05 Sheet 1 of 2 2. Plant: Perry Nuclear Power Plant (PNPP)10 Center Road. Perry. Ohio 44081 Unit one ORDER 200095847 R/O (Repair Org. P.O. No., etc.)Type Code Symbol Stamp NR Authorization No. 33 Expiration Date 09-26-2008

3. Work Performed By: FIRSTENERGY Nuclear Operating Company PNPP 10 Center Road. Perry. Ohio 44081 I 4. Identification of System: 1E51 RX ISOLATION COOLING SYSTEM 5. (a) Applicable Construction Code: ASME SECTION III CLASS NC ,19 74 Edition NAME/SECTION/DIVISION/CLASS 19 75 Addenda Code Case(s) 1644-5, 1728. N-224, N-241, N-242, N-272, N-275, WINTER N-413 (b) Construction Code used for repairs, modifications, or replacements:

1974 winter 75 Edition Addenda (c ) ASME Code Section XI applicable for Inservice Inspection: 1889 NA Edition Addenda (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 Ntuclear Operating Company PNPP NA Code Case(s)NA Code Case(s)6. Identification of Components Repaired, Modified, or Replacement Components Nbame ot Name of Manufacturer Nat- Other Year Repair, ASME Component Manufacturer Serial No. Board ID. Built Replacement, Code No. or Modification Stamped PIPING PULLMAN 1E51 84 N/A 1985 REPLACEMENT YES POWER Description of Work: REPLACED 6" DIA. DUO CHECK VALVE WITH NEW VALVE S/N 2-11683-01 (IE51FOO11) 7 8. Test Conducted: Hydrostatic-E] Pneumatic-Li Nominal Operating Pressure-Z] Other- El Pressure 69 psi Test Temperature 115 degrees F Code Case(s) N/A 156 NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back)PNPP No 9308 Rev. 9/11/00 Nat-1741 9. Remarks: H/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. Messenmer , 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 9-26 20 08 Date/1 ' 20-ZI5 Signed FENOC-PNPP GE (name of repair organization) ( .. (authorized representative) (title)CERTIFICATE OF INSPECTION/INSERVICE INSPECTION I. Thomas Laps ,holding a valid commission issued by The Nalional Board oi Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HSB I&l CT. of HARTFORD -have inspected the repair, modification or replacement described in this report on DEC_ 3-.. 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 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 ot any kind arising from or connected with this inspection. Date 3- ., 20E 19 Signed I- tr- " Commissions NB 9330 "N" "'" "A" OHIO COWM.(inspector) (National Board (include endorsements), and jurisdicrion. and no.) REPORT NO. P0059-011 FORM NPV-1 CERTIFICATE HOLDERS' DATA REPORT FOR NUCLEAR PUMPS OR VALVES-As Required by the Provsions of the ASME Code. Section I11. Division 1 Pg, 1 of I 1. MNrnofactud andcr.ilmedb, Atwood & Morrill Co.t Inc. 285 Canal St., Salem, MA 0197(Inoar,.-. d -ddd.. o N C-of1..o-i HNod-2 M AacreiIo, First Energy Corp., P.O. Box 3611, Akron, OH 44309-3611 in-a,, r dd'rl of '.r 'ldz, 3. Perry Nuclear Plant, 10 Center PLd., North Perry, OH 44081 i -... od .dd '...4. r'ideI No.. S11- No., o Typ Dal Plate a 11683-01 -0 CRN N/A 5 ASE Co~d. Se,,oo M. 0.,i,.on 7: 1974 Winter 1975 2 N/A i.d.aooi dd~end, oaTt. cia,! tCod. Cat. no.!6 Pu-, O Valv'e 4oloal roel ¶,, 6 6 7 maTe,,.1. P-j, -A216 ;-'B Bonnet N/A Dik -,A487 Boltin N/A (.1 Ce2.Holder Sn-r,ab N'o 2 -11683--01 (hi Na.C BoaN.No.U/qA (cl (dl Body Bonne!5Serial Serial NO N o.HT#: 9994 N/A_5_L~t1,I__ ______(e)Disk No.SIN: 99105.SIN: L167 & L168* Supcleomtn:a4 .U 0 ejtoo ,n 00- ob, s.eche or oa#ohqi mao be , .0.noed II re , 8 -I,. b2r ,o~otmlon ,-0 ,0-r-d ( m1ou'A 4 on lb., Da Ott, ,s iecruo~e on each thee! Ii tatIh sh- .-, nubelred -nC Ishe -t.mt- ot iS ecOded a! Che top of rirs 1-, 11, a8, 1h.0 oI 'I-C'U007, i3", be obdnor' I-on h, Ort D-, ASMAE. 22 La. 0,, -o. 2200 -a,,-lJ. 07007.2300 157 OR: le FORM NPV-1 (Back -Pg. 2 of 2_ )Certificate Holder's Serial No.8. Design conditions 285 psi 100 tF or else pressur,. class 150 for.. 28. f I,. mP, 10 .f 9. Cold wsorfking prsut 285 ps t0 *~ Foo 10. H-ydrostatic tes 45 psi- Dis differential test presr.rr.325 11. R.emarlks: Pin Fetainrar SA479, 410 HT.G3617 TR: 76D CERTIFICATION OF DESIGN Oes1rqr S faohcaton certfhed by H. R. PeprLt P. E.5 Desrgn Repror ceMfhed by N/Ar P E.late PA p,,. no. 2492SE leate _NZ A Pg no. N/A CERTIFICATE OF COMPUJANCE We certI, Th.t the sta:ements made rn this rport are Caeeýct and that thls pump o. valve conforms to the rules 1o n ot he ASME Coe. Sectror Ill. 7.C-ri-te. of Arirho.rr>n No. 66E.P;e Care ~ j r>4~ At-r-cxA & rbirill Co., Inc. Signed roc-y/( <" i'fN C.rrtic.r. Holder0 Ii *11-rrtd --oe I-CERTIFICATE OF INSPECTION I. the unde-s.gned. hnld;ng a -alid conrmission issued by the National Board of Boiler and Pressure Vesse Inspectors and ,he Srare or Province of MaSSachus-ettS and employed by H-.S.. B .& I. Co.f Ha7r1ford, (-rf h-6e inspected (he pr,-np. or valce. described -n thiS Data Report on A- A .and state that to the best of my knowledge and belief, the Certificate Holder has con-Slrrcred this o.ump. O vale. in accordance the ASME Code. Section Ili. Onivsion 1.ay Srgrrng rhrs Certhfrcate. nerthte the inspector nor his employer makes any warranty. expressed or irmplied. concernig the Component descrbed in thrs Data Report- Furthermore. neither the inspector no. hs employer shall be liable in any manner tor any personal injury or proper-ty damage ow a loss of any kind arising from or connected with this ins ziion.Da--/ 7/ e / * -" -. .,-iAunh.orrzd rn -crorl INat'l. Bd. linel. .nootlrrrnrl and Itrar or tro, .-nd no.1 II For raruall- operated valves only REPORT NO. P0059-011 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 5-2-2007 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 200188157 (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 9-28-08 4. Identification of System: Reactor Core Isolation Cooling System E51 5. (a) Applicable Construction Code: ASME Section III Class 2 -NC 1974 Edition NAME/SECTION/DIVISION/CLASS Winter 1975 Addenda Code Case(s) 1728, 1644-5, N-224, N-241, N-242, N-272, N-275, N-413 (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 N/A 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 FENOC 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 IE51 84 1E51D00 1985 Replacement YES System 02 7. Description of Work: Replace rupture disc SN 9909003-1 with new rupture disc SN A10900001 8. Test Conducted: Hydrostatic-E] Pneumatic-E] Nominal Operating Pressure-LI Other- El Pressure NA psi Test Temperature NA degrees F Code Case(s) N/A 158 NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back)P-IPP No. 9308 Rev. 9/11/00 NQI-1741 9. Remarks: 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, Russ Matlhys , 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 9-28-2008 Date 5-2-2007 Signed FENOC-PNPP fLx z\QC Supervisor (name of repair organization) (authorized represent ive) (title)CERTIFICATE OF INSPECTION/INSERVICE INSPECTION I, Thoma:; G. L;-ps 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, CT. have inspected the repair, modification or replacement described in this report on fA4.., 20 -J... 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 2007 Signed n pectr 9 Commissions NB(9330 N"I"A' Ohio Commu (inspector)t (Nationat Board (include endorsements), andjuhýuiution, and no.) REPORT NO. P0059-011 I E S1L-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. 9308 Rev. 9/11/00 NOI-1741 1. Owner: FIRSTENERGY CORP. Date 5-5-2007 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 200062949 (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 9-28-08 4. Identification of System: Reactor Core Isolation Cooling System E51 5. (a) Applicable Construction Code: ASME Section III Class 1 -NF .1974 Edition NAME/SECTION/DIVISION/CLASS Winter 1975 Addenda Code Case(s) 1728, 1644-5, N-224, N-241, N-242, N-272, N-275, N-413 (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 N/A 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 FENOC 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 Pullman Power 1E51 84 1E51H00 1985 Replacement YES System 73 7. Description of Work: Replace snubber SN 614001-94 (existing) w/new snubber SN 04616533/011

8. Test Conducted:

Hydrostatic- [] Pneumatic- [] Nominal Operating Pressure-E] Other- []Pressure NA psi Test Temperature NA degrees F Code Case(s) N/A 159 NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back)PNPP No. 9308 Rev. 9111/00 NQI-1741 9. Remarks: Note: Attach all applicable Manufaclurer'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. Russ Matlhys , 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 9-28-2008 Date 5-5-2007 Signed FENOC-PNPP Oý', :^ -- OC Supervisor (name of repair organization) (authorized representatV) (title)CERTIFICATE OF INSPECTION/INSERVICE INSPECTION 1, "TOIPAAS 6. k-, holding a valid con/mission 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 onV\h'1 , 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 r loss of any kind arising from or connected with this inspection. Date £ , 20 _bL Signed -_ Commissions ". !T-.", C, (inspector) (Nlational Board (include endorsements), and jurisdiction, and no.) REPORT NO. P0059-011 NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As required by the Provisions of the ASME Code Section Xl PRPFR No. 9308 Rev. 9/11/00 N01-1741 1. Owner: FIRSTENERGY CORP.10 Center Road. Perrv. Ohio 44081 Date 5-5-2007 Sheet 1 of 1 2. Plant: Perrn Ntuclear Pnwer Plant (PNPP4 10 Center Road, Perry, Ohio 44081 Unit 1 200062950 (Repair Org. P.O. No., etc)3. Work Performed By: FIRSTENERGY Nuclear Operating Company PNPP 10 Center Road. Perry. Ohio 44081 Type Code Symbol Stamp NR Authorization No. 33 Expiration Date 9-28-08 4. Identification of System: Reactor Core Isolation Coolinq System E51 5. (a) Applicable Construction Code: ASMF Section III Class I -NF 1974 Edition NAME/SECTION/DIVISION/CLASS Winter 1975 Addenda Code Case(s) 1728, 1644-5, N-224, N-241, N-242, N-272, N-275, N-413 (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 N/A 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 FENOC 6. Identification of Components Repaired, Modified, or Replacement Components Name of Name of Manufacturer Nat. Other Year Repair, ASME Component Manufacturer Serial I'lo. Board ID. Built Replacement, Coide No. or Modification Stamped Piping Pullman Power 1E51 84 1E51HOO 1985 Replacement YES System 74+ 4 4 4 4- 4+ 4 4 4 4 4- 4 7- Description of Work: Replace snubber SN 614001/95 (existing) w/new snubber SN 04616533/001

8. Test Conducted:

Hydrostatic-L] Pneumatic-LI Nominal Operating Pressure-Ej Other- Li Pressure NA psi Test Temperature NA degrees F Code Case(s) N/A 160 NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back)PNPP No. 9308 Rev. 9/11/00 NQI-1741 9. Remarks: 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 numnbered and the number of sheets is recorded on the front of this form.CERTIFICATE OF COMPLIANCE 1, Russ Matthys , 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 "IR stamp expires 9-28-2008 Date 5-5-2007 Signed FENOC-PNPP (,-"-- _ OC Supervisor (name of repair organization) (auth/r zed represen 1 ,e) (title)CERTIFICATE OF INSPECTION/INSERVICE INSPECTION 1 ,, A tL S -bhohling a valid f.roimrnission issued by The National Board of Boiler and Pressure Vessel Inspectors and certificate of competoncy 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 .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 "NIR" 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, properly damage or toss of any kind arising from or connected with this inspection. Date ,--0 20 0-7 Signed Commissions 0 Rio (inspector) (National Board (include endorsements), and jurisdiction, and no.) REPORT NO. P0059-011 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 5-5-2007 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 200062951 (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 9-28-08 4. Identification of System: Reactor Core Isolation Cooling System E51 5. (a) Applicable Construction Code: ASME Section III Class 2 -NF J1974 Edition NAMEISECTIONIDIVISIONICLASS Winter 1975 Addenda Code Case(s) 1728, 1644-5, N-224, N-241, N-242, N-272, N-275, N-413 (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 N/A 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 FENOC 6. Identification of Components Repaired, Modified, or Replacement Components Name of Name of Manufacturer Nat. Other Year Repair, ASIVME Component Manufacturer Serial No. Board ID. Built Replacement, Code No. or Modification Stamped Piping Pullman Power 1E51 84 1E51H20 1985 Replacement YES System 78 7. Description of Work: Replace snubber SN 61319-102 (existingq) w/new snubber SN 04616353/013

8. Test Conducted:

Hydrostatic- [] Pneumatic-El Nominal Operating Pressure- [] Other- E]Pressure NA psi Test Temperature NA degrees F Code Case(s) N/A 161 NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back)PNPP No. 9308 Rev. 9111/00 NQI-1741 9. Remarks: 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, Russ Matthys 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 9-28-2008 Date 5-5-2007 Signed FENOC-PNPP Prso Supervisor (name of repair organization) (authorized A reentative) (title)CERTIFICATE OF INSPECTION/INSERVICE INSPECTION 1, TAocNAS - holding a valid commission issued by The Nulional Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHI-o and employed by HSB CT. of Hartford, CT. have inspected the repair, modification or replacement described in this report on fAlf ID. 20 b-7 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 o°toss of any kind arising from or connected with this inspection. Date 0, 20 -1 Signed _trt \ Rt Commissions K\13 (j?,) A'"OiK (inspector) J" (National Boar/r (include endorsements), andjurisdiclion, and no.) REPORT NO. P0059-011 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 2. Plant: FIRSTENERGY CORP.10 Center Roadf Perry Ohio 44081 Date 5/9/07 Sheet 1 of 2 Unit 1 200168010 (Repair Org. P.O. No., etc.)Perry Nuclear Power Plant (PNPP)10 Center Road Perry, Ohio 44081 3. Work Performed By: FIRSTENERGY Nuclear Operating Company PNPP 10 Center Road. Perry. Ohio 44081 Type Code Symbol Stamp N R Authorization No. 33 Expiration Date 9/28/08 4. Identification of System: Reactor Core Isolation Cooling 1 E51 5. (a) Applicable Construction Code: ASME SECTION III CLASS 1 NAME/SECTION/DIVISION/CLASS WINTER 19 75 Addenda Code Case(s) N/A ,1974 Edition (b) Construction Code used for repairs, modifications, or replacements: 1974 W75 Edition Addenda (c ) ASME Code Section XI applicable for Inservice Inspection: 1989 NONE Edition Addenda (d) Applicable Edition of Section XI Utilized for Repairs, Modification, or Replacements: 1989 __19 N/A Addenda N/A Code Case(s)(e) Design Responsibilities First Energy Corp 6. Identification of Cormponents Repaired, Modified, or Replacement Components Code Case(s)N/A Code Case(s)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 RA-53 824 1E51F066 1982 REPLACEMENT YES Description of Work: Installed new disc retainer insert assembly s/n 71996-2.7 8. Test Conducted: Pressure 1032 Hydrostatic-E] Pneumatic-ED psi Test Temperature 142 Nominal Operating Pressure-ZJ Other- []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 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, Michael J Tepsick , certify thaI 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 9 may 20 07 Signed FENOC-PNPP / .C Tech.(name of repair organization) (authorized replesenrative) (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 C+1HI0O and employed by HSB CT. of Hartford, Conn. have inspected the repair, modification or replacement described in this report on .!k,.A, 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 Xl of the ASME Code and the National Board Inspection Code TIR" 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. Dale .,20 0 ._ Signed- / Commissions NB 9330 "N"' 'I "A" Ohio Comm.(inspector) -I (National Board (include endorsements), and jurisdiction, and no.) REPORT NO. P0059-011 FORM NPV-1 N CERTIFICATE HOLDERS' DATA REPORT FOR NUCLEAR PUMPS OR VALVES'As Required by the Provisions of the ASME Code, Section III, Div. 1 1. Manufacturedby Rockwell International Corp., 1900 S. Saunders St., Raleigh, NC, 27603 (Name and Address of N Certificate Holder)2. Manufacturedfor Cleveland Electric ll]uminainP C(o,. P0 Box 500. Cleveland Oh. 44101 IName and Address of Purchaser or t -ner)3. Location of Inslallation ,Ee.F- yi1uc-ljaJar 2 hcAe.L_.Irayihi L-iQ 4 2 Nort P r Ohio Name and Address)4. Pump or Valve Valve Nominal Inlet Size Outlet Size 6 (inch) (inch)1a) Model No.. (b) N Certificate Holder's (c) Canadian Series No Serial Regstraton (d) Drawing if) NatCf. ig) Year or Type No. No. No le) Class Bd. No. Built 4094(WCC)J0TY RA-53 (1)N/A D82-24401-17 1 824 1982 Rev. B (2)(3)(4)(5)(6)(7)(8)(9)(10)S. Butt Weld End Testable Check Valve (Lht6, descriptron of servce 1o, whch equipment -as der,gned)Heat No. F4743-1 Sales Order 36-24401 6.8.Design Conditions 1 4-(, IPr essure)Cold Working Pressure 1535 Pressure Retaining Pieces psi 574 (l mfemeralut e)ps, at t100F.'F or Valve Pressure Class S_1. Int .613 (1)Mark No.(a) Castings F4743 Material Srpec. No.Manufacturer Remarks SA-2jC__Cr.~j~CC 11 E. skA- 1.o csdy i i f-+/- F + -#-~~trv nf --/,N +rgA'7l (b) Forgings T- 5980 Co P or 5~-1p5 trh;zrrlpo F Ioronn T-5980 I SA-105 [Charles E. Larson Test Fittin R i I Charles E. Larson Disk 10502 SA-IO5 I -39796 SA-638 Cr. 660T2 Charles E. Larson I Gasket Retainer Charles E. Larson Indicator Housing IG3766 I SA-182 Cr F316L_______ F _______ F __________________________________________ (1) For manually operated valves only.Supplemental sheets in form of lists, sketches or drawings may be used provqided (1) size is 8-1r2' x 11, (2) information in items 1, 2 and 5 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.3 1/0177)This frrm IE'OY1371 may he obtained from the Order Dept.. ASME. 345 E. 471h St.. New York, N.Y. 10017 163 FC C P.v- i F "N'.- (E ck](c) Boltnq,,, 1 J Material Spec No. NManufacturer R na:ks 1d) Other Parts KA77 62 SA-106 Gr. B Capitol PiDe Equalizer 9. Hydrostatic rers _2 U _ psi. Disk Differential test pressure 1550 psi CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and that this pump, or valve, conforms to the rules of construction of the ASME Code for Nuclear Power Plant Components. Section Ill. Div. I., Edition 1974 Addenda Winter 1975 , Code Case No. N/A Date MDte) Code C .t 2 Signed Rockwell International Corp. ey" x -z IN Cerlificate Holdr)Our ASME Certificate of Authorization No. 1562 to use the N symbol espires I 1 26 135_.1.(N) Wt.I.)CERTIFICATION OF DESIGN Design information on tle at Rockwell International Corp. .Raleiyh _NC Stress analysis report lClass I only) on file at Rockwell International Corp._ Ralei h NC Design specifications certified by (1) Francis C. Rosch, Jr.PE State Pa. Reg. No. 002855E Stress analysis certified by (1) T. F. Kunkle PE State Pa. Reg. No. 016818E (1) Signature not required. List name only.CERTIFICATE OF SHOP 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 North Carol ina and employed by HSBI&I Co.of r d Ct .have inspected the pump, or valve, described in this Data Report on f ) 79 L .and stale that tothe bestof my knowledge and belief, the NCertificate Holder has con-structed this pump, or valve, in accordance with the ASME Code, Section Ill.By signing this certificate, 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 liable in any manner for any personal in-ury or property damage or a loss of any kind arising from or connected with this inspection. Date 4,x /6 1 9 fa/ I Commissions? AC /9---Natl Bd. State. Pro .8rand No.I REPORT NO. P0059-011 I dI S 1- ILi S 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: 2. Plant: FIRSTENERGY CORP.10 Center Road, Perry, Ohio 44081 Perry Nuclear Power Plant tPNPP)Date 5-14-2007 Sheet 1 of 1 Unit 1 200167798 (Repair Org. P.O. No., etc.)10 Center Road Perry Ohio 44081 3. Work Performed By: FIRSTENERGY Nuclear Operating Company PNPP 10 Center Road, Perry, Ohio 44081 Type Code Symbol Stamp NR Authorization No. 33 Expiration Date 9-28-08 4. Identification of System: RE 5. (a) Applicable Construction Code: eactor Core Isolation Coolinq System E51 ASME Section Il Class 2 -NC 1974 Edition NAMEISECTION/DIVISIONICLASS Winter 1975 Addenda Code Case(s) 1728, 1644-5, N-224, N-24t1, N-242, N-272, N-275. N-413 (b) Construction Code used for repairs, modifications, or replacements: 1974 VW75 N/A Edition Addenda Code Case(.(c) ASME Code Section XI applicable for Inservice Inspection: 1989 N/A N/A Edition Addenda Code Casecs (d) Applicable Edition of Section XI Utilized for Repairs, Modification, or Replacements: 1989, N/A 19 N/A Addenda N/A Code Casels)(e) Design Responsibilities FENOC 6. Identification of Components Repaired, Modified, or Replacement Components s)Name of Component Name of Manufacturer Manufacturer Serial No.I"Int.Board Nn Other ID.Year Built F',epair, Replacement, or Modification-A- S Iv -1E Code Stamped Piping Pullman Power 1E51 84 1E51 DOO 1985 Replacement YES System 01 7. Description of Work: Replace rupture disc SN 9909003-1 with new rupture disc SN A10900001 8. Test Conducted: Hydrostatic-LI Pneumatic-EI Nominal Operating Pressure-H Other- FI Pressure 1150 psi Test Temperature 73.4 degrees F Code Case(s) N/A 164 NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back)PNPP No. 9308 Rev. 9111V00 NOI-1741 9. Remarks: 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, Russ Matthys , 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 9-28-2008 Date 5-14-2007 Signed FENOC-PNPP " '-N- OC Supervisor (name of repair organization) (authorized rpresentatip (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, CT. have inspected the repair, modification or replacement described in this report on J/3K\.A 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 .~j __. 20 1 Signed .IO3(A4 -S 1 6i Commissions NB 9330 "N"I"A" Ohio Comm (inspector) (National Board (include endorsements), and jurisdiction, and no.) REPORT NO. P0059-011 IE 'S -146 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 NQt- 1741 1. Owner: FIRSTENERGY CORP. Date 5-14-2007 10 Center Road, Perry, Ohio 44081 Sheet 1 of 1 2. Plant: Perry Nuclear Power Plant (PNPP) Unit I 10 Center Road, Perry, Ohio 44081 200173141 (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: Reactor Core Isolation Cooling System E51 5. (a) Applicable Construction Code: ASME Section III Class2 -NC .1974 Edition NAME/SECTION/DIVISION/CLASS Winter 1975 Addenda Code Case(s) 1728, 1644-5, N-224, N-241, N-242, N-272, N-275, NA413 (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 N/A 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 FENOC 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 IE51 84 1ESICO 1985 Replacement YES System 03 7. Description of Work: Replace water leg pump SN Q1A021 (existing) with rebuilt pump SN 1A015 8. Test Conducted: Hydrostatic-0] Pneumatic- [] Nominal Operating Pressure-M Other- El Pressure 63.8 psi Test Temperature 103.6 degrees F Code Case(s) N/A 165 NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back)PNPP No. 9308 Rev. 9/11/00 NOI-1741 9. Remarks: 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, Russ Matthys 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 slamp expires 9-28-2008 Date 5-14-2007 Signed FENOC-PNPP Y;7.ý _.' ., OC Supervisor (name of repair organization) (authorized reprosentalve) (title)CERTIFICATE OF INSPECTION/INSERVICE INSPECTION I, Jacob C. Scholl 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, CT. have inspected the repair, modification or replacement described in this report on 5-14 20 07 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 5-14 20 07 Signed Commissions NB 7920 "N"I"A"B" Ohio Comm 432 (inspector) (National Board (include endorsements), and jurisdiction, and no.) REPORT NO. P0059-011 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 1/00 NQ- 1741 1. Owner: FIRSTENERGY CORP.10 Center Road, Perry, Ohio44081 Date 5-8-07 Sheet 1 of 1 2. Plant: Perry Nuclear Power Plant (PNPP)10 Center Road. Perry. Ohio 44081 Unit 1 200153518 (Repair Org. P.O. No., etc.)Type Code Symbol Stamp NR Authorization No. 33 Expiration Date 9-28-08 3. Work Performed By: FIRSTENERGY Nuclear Operating Company PNPP 10 Center Road. Perry, Ohio 44081 4. Identification of System: Combustible Gas Mixing System I M51 5. (a) Applicable Construction Code: ASME Section III Class II NC 1974 Edition NAME/SECTIONIDIVISION/CLASS Winter 1975 Addenda Code Case(s) N272, N-242, N-275, 1644-5, 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 N/A N/A Edition Addenda Code Case(s (d) Applicable Edition of Section XI Utilized for Repairs, Modification, or Replacements: 19 1989 N/A 19 N/A AddendaN/A Code Case(s)(e) Design Responsibilities FENOC 6. Identification of Components Repaired, Modified, or Replacement Components s)Name of Name of Manufacturer Nat. Other Year Repair, ASME Component Manutacturer Serial No. Board ID. Built Replacement, Code No. or Modification Stamped Piping Pullman Power 1M51 106 1M51F00 1985 Replacement Yes System 10B 7. Description of Work: Replaced 36 bonnet nuts heat trace 506C size 5/8-11 S. Test Conducted: Pressure N/A Hydrostatic-E] Pneumatic-E] Nominal Operating Pressure-El Other- E]psi Test Temperature N/A degrees F Code Case(s) N/A 166 NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back)PNPP No. 9308 Rev. 9/11/00 N0I-1 741 9. Remarks: VT-2 not recuired Interoretation XI-1-95-52 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, Russ Matthys , 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 XA 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 9-28-2008 Date 5-8-2007 Signed FENOC-PNPP g Yýý OC Supervisor (nfame of repair organization) (authorized represet. live) (title)CERTIFICATE OF INSPECTION/INSERVICE INSPECTION I, .Jacob C. Scholl ,-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 CT. have inspected the repair, modification or replacement described in this report on 5-14 20 07 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. Ohio Comm "432" Date 5-14 20 07 Signed Commissions NB 7920 "N1I"A""B" V (inspector) (National Board (inc ude endorsements), andjunsdoction, and no.) REPORT NO. P0059-011 1 NJj~- D C5 Vý I ýNIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As required by the Provisions of the ASME Code Section XI PNPP No. 9308 Re,. 9/11/00 NQI-1741 1. Owner: FIRSTENERGY CORP.10 Center Road, Perry, Ohio 44081 Date 5-7-07 Sheet 1 of 2 2. Plant: Perry Nuclear Power Plant (PNPP)10 Center Road. Perry, Ohio 44081 Unit 1 200173855 (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 9-28-2008 4. Identification of System: Main Steam Line and Miscellaneous Drain Lines 1N22 5.(a) Applicable Construction Code: ASME Sectinn III Class 1 NB 1974 Edition NAME/SECTION/DIVIS ION/CLASS Winter 1975 Addenda Code Case(s) N-272 &.1644-5 (b) Construction Code used for repairs, modifications, or replacements: 1974 W/75 Edition Addenda (c) ASME Code Section XI applicable for Inservice Inspection: 1989 N/A Edition Addenda (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 FENOC 6. Identification of Components Repaired, Modified, or Replacement Components N/A Code Case(s)N/A Code Case(s)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 1N22 112 1821F00 1985 Replacement YES System 16 7. Description of Work:.replaced gate w/new (SN07X216-2)

8. Test Conducted:

Hydrostatic- [] Pneumatic-ED Nominal Operating Pressure-H' Other- El Pressure 1032 psi Test Temperature 147 degrees F Code Case(s) N/A 167 NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back)PNPP No. 9308 Rev. 9/11/00 NOI-1741 9. Remarks: Valve installed bv Pullman Power and documented on the N-5 for the N22 system PMT comoleted oer order 200172372. No nameplate/slampinq performed due to the interface controls of RA-2370 being in effect and jurisdictional Authoritv concurrence havina 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, Russ Matthys , 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 star expires 28 September, 2008 Date 5-7-2007 Signed FENOC-PNPP 00 ! QC Supervisor (name of repair organization) (authorized represen tive) (title)CERTIFICATE OF INSPECTION/INSERVICE INSPECTION t, 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 _ -A!> (-V. of IA-A,- F0 C-D (CT-. have inspected the repair, modification or replacement described in this report on _01\-l 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 ASMIE 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 S 20 _ Signed Commissions NB 9330 'NA" Ohio Comm (inspector) (National Board (include endorsements), and jurisdiction, and no.) REPORT NO. P0059-011 FORM N-2 CERTIFICATE HOLDERS' DATA REPORT FOR IDENTICAL NUCLEAR PARTS AND APPURTENANCES* As Required by the Provisions of the ASME Code, Section III Not to Exceed One Day's Production Pg. 1 of 2 Flowserve Corporation 1900 S. Saunders St. Raleigh, NC 1. Manufactured and crt)2. Manufactured for ified by name and address of NOP Ceritirare Holder)First Energy Corp/Accounts Payable/P.O. Box 6100 Johnstown, PA 15907-6100 name and address of purchaser) Perry Main Warehouse/Perry Nuclear Power Plant/ 10 Center Road, Perry OH 4,081 3. Location of installation tnoree and st 81180 R/L ASME SA216, GR. WCC N/A N/A 2007 4. Type td, aaan9 no.t (r-1 spec. no.) (tlesite ot engrthd CRNt (ya. bhalt 1974 Winter, 1975 1 N/A 5. ASME Code, Section 111. Division 1: (edition) (addenda date) (taasl (Code Case noa N/A N/A N/A 6. Fabricated in accordance with Const. Spec. (Div. 2 only) Revision Date 0no.)7. Remarks: GATE FOR 3" 1500# FW Gate Valve The material meets ASME Section I], 1974 Edition, Winter 1975 Addenda throuqh (983 Edition, Summer 1985 Addenda 8. Norn. thickness (in.) N/A Min. design thickness (in.) Per #4 Dia. ID (ft & in.) N/A Length overall (ft & in.) N/A 9. When applicable, Certificate Holders' Data Reports are antached for each item of this report: Part or Appurtenarie Serial Number Nalional Board No.in Numerical Order (1) 07X216-1 (2) 07X216-2 (3) 0TX216-3 ii (5)(6)N/A N/A/A (7)(8)(t0)0l1)112)(13)1111X National Part or Appurtenanc~e Board No.Serial Number in Numerical Order (261 (27)(28) _______________ _________________ (29)1301)_______________ 1311)____________ (32) ______________ (3A)(3S)(37) _______________ 139)141)(42)(43)1441)_______________ (45) ______________ 1461)_____________ (48) _ _ _ _ _ _ _(50) ___1iot (16)(171 (t8)(19) _____________ 120)(21) _______________ (22)(23) ______________ _______________ (24) _______________ ________________ (25) _____________ ______________

10. Design pressure psi. Temp. 'F Hydro. test pressure at temp. *F (.hen applicable) 6 Supplemental information in the form of lists, sketches.

or drawings may be used provided (1) size is 8/12 x 11. (21 information in items 2 and 3 on this Doata Report is included on each sheet, (3) each sheet is numbered and the number of sheets is recorded at the top of this form.(1 t,105)168 2 FORM N-2 (Back -Pg. 2 of __07X.216-1 07X216-3 Certificate Holder's Serial Nos. through CERTIFICATION OF DESIGN Desigr, specifications certified by N/A F.E. State N/A Reg. no. N/A.h-en applicable) Design reporl* certified by N/A P.E. State N/A Reg. no. N/A[when applicable) CERTIFICATE OF COMPLIANCE Parts We certify that the statements made in this report are correct and that this (these)conforms to the rules of construction of the ASME Code, Section 111, Division 1.1, the indersigned. holdingt a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of NC and employed by INC of eartfird CT have inspected these items described in this Data Report on o7_han and state that to the best of my knowledge and belief. the Certificate Holder has fabricated these parts or appurtenances in accordance with the ASiE Code, Section (if, Diision 1. Each part listed has been authorized for stamping on the date shown above.By signing this certificate, neither the inspector nor his employer makes any warranty, expressed or implied, concerning the equipment described in this Data IReport. Furhermore, neither the inspector nor his employer shall be liable in any mariner for any personal injury or property damage or loss of any kind arising from or connected with this inspection. Dale -Signed Commissions __ ________q___,iztAu5h ed Nuciea,t rssr rodt tNail. 8d. fincl -ndo-e n. t and r ,e or p n. Io 7 REPORT NO. P0059-011 NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As required by the Provisions of [he ASME Code Section XI FPNPP No. 9308 Rev. 9/11/00 NOQ-1741 1. Owner: 2. Plant: FIRSTENERGY CORP.10 Center Road. Perry, Ohio 44081 Perry NuclearPowerPlant LPNPP) __Date 5-7-07 Sheet 1 of 2 Unit 1 200011552 (Repair Org. P.O. No., etc.)10 Center Road, Perry, Ohio 44081 3. Work Performed By: FIRSTENERGY Nuclear Operating Company PNPP 10 Center Road. Perry, Ohio 44081 Type Code Symbol Stamp NR Authorization No. 33 Expiration Date 9-28-2008 4. Identification of System: Main Steam Line and Miscellaneous Drain Lines. 1N22 5. (a) Applicable Construction Code: ASME Section III Class 1 NB 1974 Edition NAME]SECT)ONIDIVISION/CLASS Winter 1975 Addenda Code Case(s) N-272 & 1644-5 (b) Construction Code used for repairs, modifications, or replacements: 1974 W/75 N/A Edition Addenda Code Case(s (c ) ASME Code Section XI applicable for Inservice Inspection: 1989 N/A N/A Edition Addenda Code Case(s (d) Applicable Edition of Section XI Utilized for Repairs, Modification, or Replacements: 1989 ý N/A 19 N/A Addenda N/A Code Case(s)(e) Design Responsibilities FENOC 6. Identification of Components Repaired, Modified, or Replacement Components .1 Name of N.lame of Manufacturer Nat. Other Year Repair, ASIvIE Component Manufacturer Serial No. Board ID. Built Replacement, Code No. or Modification Stamped Piping Pullman Power 1N22 112 1B21F00 1985 Replacement YES System 19 Description of Work: replaced gate w/new (SN07X216-3)

8. Test Conducted:

Hydrostatic- [] Pneumatic-E]Pressure 1032 psi Test Temperature 142 Nominal Operating Pressure- [] Other- E]degrees F Code Case(s) N/A 169 NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back)PNPP No. 9308 Rev 9/11/00 NQI-1741 9. Remarks: Valve installed by Pullman Power and documented on the N-5 for the N22 system PMT completed per order 200168008. 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, Russ Matlhys 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 September, 2008 Date 5-7-2007 Signed FENOC-PNPP " QYWýN Q (-' S U V .o (name of repair organization) (authorized represeiative) (tit e)CERTIFICATE OF INSPECTION/INSERVICE INSPECTION I, Thomas G. Laos ,holding a valid comrriission issued by The National Board of Boiler and Pressure Vessel Inspectors and certiticate ot competency issued by the jurisdiction of OHIO and employed by _ A S-6 (-T.-- of R* A -T -. .CT. have inspected the repair, modification or replacement described in this report on J_ý 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 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 I ss of any kind arising from or connected with this inspection. Date 20 01 Signed M Commissions NB 9330 N"A" Ohio Comm (inspector) W (National Board (include endorsements), and jurisdiction, and no.) REPORT NO. P0059-011 FORM N-2 CERTIFICATE HOLDERS' DATA REPORT FOR IDENTICAL NUCLEAR PARTS AND APPURTENANCES* As Required by the Provisions of the ASME Code, Section III Not to Exceed One Day's Production Pg. 1 of 2 Flowserve Corporation 1900 S. Saunders St. Raleigh, NC 1. Manufactured and certi 2. Manufactured for fied by Iraer ard dd-ess of IPT Crmf.te Hloldr First Energy Corp/Accounts Payable/P.O. Box 6100 Johnstown, PA 15907-6100 (nam, and addres, of purchase-) Perry Main Warehouse/Perry Nuclear Power Plant/ 10 Center Road, Perry OH1 "14081 3. Location of installation " (name and addess)81180 R/L ASME 5A216, GR. WCC N/A N/A 2007 4. Type rdrnawen no.) In-a0. apes, no.) Itensile JEAenpihl ICINI lyea built)1974 Winter, 1975 1 N/A 5. ASME Code, Section III, Division 1: leditionl (addenda dare) class) (Code C-ne no.)N/A N/A N/A 6. Fabricated in accordance with Const. Spec. (Div. 2 only) Revision Date 7En.t 7. emaks: GATE FOR 3" 1S00# FW Gate Valve The material meets ASME Section ][, 1974 Edition, Winter 1975 Addenda through 1983 Edition, Summer 1985 Addenda B. Nom. thickness tin.) N/A Min. design thickness (in.) Per #f4 Dia. IO (fl & in.) N/A 9. When applicable, Certificate Holders' Data Reports nre attached for each item of this meport: Length overall lth & in.) N/A Part or Appurtenance Serial Number (t) 07X216-1 11V 07X216-2 Nlational Board N4o.in Numerical Order Part or Appurtenance Serial Number National Board No.in N.um rical Order N/A N/A 13) )7X216-3 N/A 161 (7)(9) _______________ (10)(12)(13)(171 (20)(22)(23) _____________ ______________ (241 (251 (26)(27)i2n)(29)(30)(31)(32)(33)(14)(35)t35)(37)(38)(39)(40)(41)1(42)(43)(44)(45)(46)(47)(48)(49)(50)10. Design pressure psi. Temp. -F. Hydro. test pressure at temp. 'F Iwbhen applicable)

Supplemenral information in the form of lists, sketches, or drawings may be used provided (1) sihe is 81/, x 11. (2) information in items 2 and 3 on this Data Report is irrcluded on each sheet, (3( each sheet is numbered and the number of sheets is recorded at the top of this form.0 Was)1 170 2 FORM N-2 JBack -Pg. 2 of __-__07X216-1 07X216-3 Certificate Holder's Serial Nos. through CERTIFICATION OF DESIGN N/A Design specifications certified by Design report' certified by iwhen epplic-bfl N/A RE. State N/A Reg. no. N/A P.E. State N/A Reg. no. N/A (whe- Ppklc blý)CERTIFICATE OF COMPLIANCE Parts We certify that the statements made in this report are correct and that this ithese)conforms to the rules of construction of the ASME Code, Section III, Division 1.NPT Certificate

ýoAuth rization No.Date 5 Name N-163Expires 11-26-09 Flowserve Corporation Signed -MiPs Ce fitiare )h/CERTIFICATE OF INSPECTION 1, the undersigned. holding a valid comrmission issued by the Nlational Board of Boiler and Pressure Vessel Inspectors and the State or Province of NC and employed by cL____-of Hartford. CT 7rave inspected these items described in this Data Report on _-_,___-__.__"__:__7 _, and state that to the best of my knowledge and belief, thc Certificate Hold-e has fabricated these parls or appurtenances in accordance with the ASME Code, Section Ill, Division 1. Each part listed has been authorized for stamping on the date shown above.By signing this certificate, neither the inspector nor his employer makes any warranty, expressed or implied, concerning the equipment described in this Data Report- Funhermore, neirher the inspector nor his employer shall be liable in any mariner for any personal injury or property damage or loss of any kind arising from or connected with this inspectior,. Date Signd ../T__ 0ed iAutho.red urea, r etri Commissions kk3t. '/9'-/Nat'l. 1d. (inc-. ndor-mr-enW~ and naiee ca proc. and no.1 REPORT NO. P0059-011 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.10 Center Road, Perry, Ohio 44081 Date 5-8-07 Sheet 1 of 2 Unit 1 200168166 (Repair Org. P.O. No., etc.)2. Plant: Perry Nuclear Power Plant (PNPP)10 Center Road. Perry, Ohio 44081 3. Work Performed By: FIRSTENERGY Nuclear Operating Company PNPP 10 Center Road, Perry, Ohio 44081 Type Code Symbol Stamp NR Authorization No. 33 Expiration Date 9-28-08 4. Identification of System: 1N27 Feedwater and Feedwater Leakage Control System 5. (a) Applicable Construction Code: ASME Section III -Class 1 NB 1974 Edition NAME/S ECT ION/B IVISION/CLASS 19 75 Addenda Code Case(s) None Winter (b) Construction Code used for repairs, modifications, or replacements: 1974 W/75 N/A Edition Addenda Code Case(s)(c ) ASME Code Section Xl applicable for Inservice Inspection: 1989 N/A N/A Edition Addenda Code Case(s)(d) Applicable Edition of Section X1 Utilized for Repairs, Modification, or Replacements: 19 8 N/A 19 N/A Addenda N/A Code Case(s)(e) Design Responsibilities FENOC 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 PZ42 663 !N27 1981 Replacement YES International F559B Corp.7. Description of Work: Remove tect connection from valve for inspection and reinstall using filler material HT 47758 8. Test Conducted: Hydrostatic- [I Pneumatic-E] Nominal Operating Pressure-Ej Other- EL Pressure 1041 psi Test Temperature 156 degrees F Code Case(s) N416-2 171 NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back)PNPP No. 9308 Rev. 9/11/00 P1O-10741 9. Remarks: NONE 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 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, Russ Matthys 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 ASMAE 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 , 2008 Date 5-8-2007 Signed FENOC-PNPP ,,1 " OC Supervisor (name of repair organization) (authorized represe ative) (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 HARTFORD STEAM BOILER CT. of HARTFORD CT have inspected the repair, modification or replacement described in this report on _,h 20 0J 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 Boaid 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 S117- , 20 0 Signed X Commissions NB 933 o "N"l"A" Ohio Comm.(inspector)- (N ~ (National Board (include endorsements), and jurisdiction, and no.) REPORT NO. P0059-011 FONM NPV-1 N CERTIOCA7E HOLDERS' DATA FIEFORT FOR NUCLEA.R PUMPS OR VALVES '"',;..~d by y of i,, ,5'.E cod. S;0*n Di.. ; /4;4, -3 1 .d a¢,ck.~e11 In terontf ,:.1 Cor p.. 1900 S_ Sa rders. St.. Raleigh, NC 27603 3NdmO d.n Addtt.% of', Co~t,3~cb ,OI~t 34 d 2- M. f..I. ,rd I-, .N -I.? io L R1n 1 f)C1 1 In' 4 O ......_ _ __ _ Nonl m0 S;,* 2 Owlot Si4.4. 5r- " ;cý-.f.) ModO N.o lbi N Ce-lilflc.3. NoJ8¢,I le C d-,," ...S~d*- tR,. Seria. itgd $04r.1toi ' [d) D, nig -If) NH t.l Ig) Y.., -.-oT, No- Nix No, le) Chs " Bd. No. B ..257(rC j11.2 -112 ------------ O ? -----8 101 1 "..L 1 .l"1510._ 12 -F V g .1- P--- ?.'.-/'53}7 C., j_1__p,__2__5_____________ 333-s. f10,15-11Iolll SO 6-&0& gn; Co-nr,o,, 1510 'l 20 -3: o, Vain P,..,.,e al.,. N/A D 7.~ F'1 " P .o.nr g Prm r.. 2 50-, nI,'r-I' .-,-, 220528 SA 105 C.nn& Soul Steel Disk 32076 SA 105 Char es E. Lzrson Draln Cap 133,792 jSA 3115 Zharles E' "rson Test 51iti--V') F-. .-no.P p--'d '0 Only." S..Ant -.wil .h. n f-,. oF 1;. -Lcd,,, o d'.,.,'-o. ' .-y, d p-ov4d.d ()3 ;i:t 4I 8vlIT- .71. 3[2 h-form,4Ot L.,eo- I. 1 , .2-d S -. D-.) ;3. '-T,,dd4 --LhN -d 3 1-h V- ;. n.boad -iod ---b' of n'.O"tI I.n Codod A p .1 LK40.,ý;. f- tEZOW71 ý ý I~ 0-d-, ýý ýMIE.145, F_ 41,)- '51- ýý Y-,&ý ý-Y- loo" 172 M.,L No..A.r, !;pe No. P-4.,.C.C REPORT NO. P0059-011 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 NQI-1741 1. Owner: FIRSTENERGYCORP. Date 5-12-07 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 200168165 (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 9-28-08 4. Identification of System: 1 N27 Feedwater and Feedwater Leakage Control System 5. (a) Applicable Construction Code: ASMIE Section IIl -Class 1 NB .1974 Edition NAME/SECTION'JIDIVISIONICLASS Winter 19 75 Addenda Code Case(s) None (b) Construction Code used for repairs, modifications, or replacements: 1974 W/75 N/A Edition Addenda Code Case(s)(c ) ASME Code Section XI applicable for Inservice Inspection: 1989 N/A N/A Edition Addenda Code Case(s)(d) Applicable Edition of Section XI Utilized for Repairs, Modification, or Replacements: 1989 ý N/A 19 N/A Addenda N/A Code Case(s)(e) Design Responsibilities FENOC 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 PZ83 662 !N27 1981 Replacement YES International F559A Corp.7. Description of Work: Remove tect connection from valve for inspection and reinstall using 1 1/4 inch round Stock HT 14512 8. Test Conducted: Hydrostatic- [i Pneumatic-LI Nominal Operating Pressure-MI Other- El Pressure 1041 psi Test Temperature 156 degrees F Code Case(s) N416-2 173 NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back)PNPP No. 9308 Rev. 9/11100 HUl-1741 9. Remarks: NONE 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, Russ Matthys 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 2008 Date 5-12-2007 Signed FENOC-PNPP (YA 11 (\OC Supervisor (name of repair organization) (authorized representatiu-) (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 OHIC)and employed by HARTFORD STEAM BOILER CT. of HARTFORD CT have inspected the repair, modification or replacement described in this report on I'll" 20 01 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 54 1 L. 20 Signed Commissions NB 9330 "N"A" Ohio Comm.(inspector) (National Board (include endorsements), and jurisdiction, and no.) REPORT NO. P0059-011 I P -oO- 0 ý P I J4 a-NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As required by the Piovisions of the ASME Code Section XI PNPP No. 9308 Rev. 9/11/00 NQI-1741 1. Owner: FIRSTENERGY CORP.10 Center Road, Perry, Ohio 44081 Date 5-2-2007 Sheet 1 of 2 Unit 1 200173853 (Repair Org. P.O. No., etc.)2. Plant: Perry Nuclear Power Plant (PNPP)10 Center Road, Perry, Ohio 44081 3. Work Performed By: FIRSTENERGY Nuclear Operating Company PNPP 10 Center Road, Perry, Ohio 44081 Type Code Symbol Stamp NR Authorization No. 33 Expiration Date 9-28-08 4. Identification of System: Condensate Transfer and Storaoe Svstem P11 5. (a) Applicable Construction Code: ASME Section III Class 2 -NC 1974 Edition NAME/SECTION/DIVISIONICLASS Winter 1975 Addenda Code Case(s) 1644-5, N-272, N-275, N-413 (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 Inser/ice Inspection: 1989 N/A N/A Edition Addenda Code Case(s (d) Applicable Edition of Section XI Utilized for Repairs, Modification, or Replacements: 1989ý N/A 19 N/A Addenda N/A Code Case(s)(e) Design Responsibilities FENOC 6. Identification of Components Repaired, Modified, or Replacement ComponentsName of Name of Manufacturer Htat. Other Year Repair, ASME Component Manufacturer Serial No. Board ID. Built Replacement, Code No or Modification Stamped Piping Pullman Power. 1P1l 107 1Pi 100 1985 Replacement YES System 60 7. Description of Work: Replace valve SN 1-53236-A and install w/new studs HT 7806 and nuts HT Z214 8. Test Conducted: Hydrostatic-LI Pneumatic-El Nominal Operating Pressure-Z1 Other- EL Pressure 157 psi Test Temperature NOT degrees F Code Case(s) N/A 174 NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back)PNPP No. 9308 Rev 9/11/00 NQI-1741 9. Remarks: Retest fVT-2) nerformed bv Order 200173853 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, Russ Matthys , 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 st ip expires 9-28-2008 Date 5-2-2007 Signed FENOC-PNPP " .OC Supervisor (name of repair organization) (authorized repre ntative) (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, CT. have inspected the repair, modification or replacement described in this report on i.h4.3, 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 ss of any kind arising from or connected with this inspection. Date 42. 20 Dj Signed a -A -. Commissions NB 9330 "N"I"A" Ohio Comm (inspector) (National Board (include endorsements), and jurisdiction, and no.) REPORT NO. P0059-011 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 LISA Inc. 285 Canal St. Salem MA 01970 (name and address of N Certificate Holder)2. Manufactured for First Energy Corporation, 10 Center Rd., P.O. Bo" 97, North Perr'l, OH 44081 (name and address of Purchaser)

3. Location of installation Perry Nuclear Power Plant. 10 Center Road Dock No. 1, Norlh Perry OH 44081 (name and address)4. Model No., Series No., or Type TCBV 5. ASME Code, Section tIn, Division 1: 1974 (edition)Drawing 53236-A Rev. 02 CRN N/A Winter 1975 (addrenda date)2 (lcass)1635-1 (Code Case m r.)6. Pump or Valve Valve Nominal inlet size 12 Outlet size 12 (in.) (in.)7. Material:

Body SA351-CF8M (a) (b)Cerl. Nat'l Holder's Board Serial No. No.1-53236-A N/A Bonnet SA2tO-316 ( c Body Serial No.H-T. '1:06262 S/N. fi: Y578 Disk SA351-CF&A~(d )Don net Serial No.HT. #:OAD7 S N. #I: I Bolting see remarks e )Disk Serial No, HT. #: 06251 S/NI. #: Y579* Supplemental information rn form of lists, sketches, or drawings may be used provided (1) size 8 A x 11, (2) information in items 1 through 4 on this Data Report is included on each sheet, (3) each sheet is numbered and the number of sheets is recorded at the lop of this form (12/88) This form (E00037) may be obtained from the Order Dept.. ASME. 22 Law Orve, Box 2300, Fairfield, NJ 07007-2300. 175 FORM NPV-I (Back -- Pg. 2 of 2 )Certificate Holder' s Serial No. 1-53236-A 8. Design conditions Body 275 psi 100 'F or valve pressure class 150 (1)Disc 160 psi 220 (pressure) (temperalure)

9. Cold working pressure 275 psi at 100°F 10. Hydrostatic test 425 psi. Disk differential test pressure 180 psi 11. Remarks: HEX CAP SCREWS SA193 GR B8M CLI. HT#: 151788 TR#: 136C CERTIFICATION OF DESIGN Design specification certified by Richard D. Stadel P.E. Slate Michigan Reg. Ho. 6201027244

(.hen applicable) Design report certified by N/A P.E. State N/IA Reg. no. N/A (.her applicable) CERTIFICATE OF COMPLIANCE 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 II. Division 1.N Certificate of Authorization No. N-2606 Expires 6-13-07 Date lName WEIR VALVES & CONTROLS USA INC.. Siped /. -/IN Ctic(eauhored Heprese lie)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 Massachusetts nd erployed by HSBCT of Hartford, CT have inspected the pump. or valve, described in this Data Report on ..and state that to the best of my knowledge and belief, the Certificate Holder has constructed this pump, or valve, in a cordd nce with the ASME Code. Secfion Ill. Division 1.By signing this Certificale, 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 liable in any manner for any personal inlury o0 property o loss of any kindan ,,on ec -dewith this inspection. Dale "e _443/?-, Commi ,si7 (Authorized Inspector) ( Nat'l. Bd. find. endorsements) ard state or prey. and no I (1) For manually operated valves only. REPORT NO. P0059-011 I P I I- C) (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: FIRSTENERGYCORP. Date 5-11-2007 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 200259739 (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 9-28-08 4. Identification of System: Condensate Transfer and Storage System P11 5. (a) Applicable Construction Code: ASME Section III Class 2 -NC 1974 Edition NAMlE/SECTION/lDIVISIOIN/CLASS Winter 1975 Addenda Code Case(s) 1644-5, N-272, N-275. N-413 (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 N/A 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 FENOC 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 IPll 107 1P11F05 1985 Replacement YES System 45 7. Description of Work: Install new valve wafer disk/pin HT # D4844/15079 -also installed new mounting studs HT 52852-DE and nuts HT 714684 8. Test Conducted: Hydrostatic-E] Pneumatic-El Nominal Operating Pressure-U Other- El Pressure 152 psi Test Temperature 104 degrees F Code Case(s) N/A 176 NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back)PNPP No. 9308 Rev. 9/11/00 NOI-1741 9. Remarks: 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, Russ Matthys , 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 9-28-2008 Date 5-11-2007 Signed FENOC-PNPP (L. ýý\ 0C Supervisor (name of repair organization) (authorized represen tive) (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, CT. have.inspected the repair, modification or replacement described in this report on I 20 M 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 loss of any kind arising from or connected with this inspection. Date &_L. 20 9 Signed 1 Commissions NB 9330 "N"I"A" Ohio Comm I (inspector) U (National Board (include endorsements), and jurisdiction, and no.) REPORT NO. P0059-011 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. Owneri FIRSTENERGY CORP.10 Center Road. Perrv Ohio 44081 2. Plant: Perry Nuclear Power Plant (PNPP)10 Center Road, Perry, Ohio 44081 Date 8/3/05 Sheet 1 of 2 Unit one 01-12834-000 (Repair Org. P.O. No., etc.)Type Code Symbol Stamp NR Authorization No. 33 Expiration Date 9/26/2005 3. Work Performed By: FIRSTENERGY Nuclear Operating Company PNPP 10 Center Road Perry. Ohio 44081 4. Identification of System: 1P43 Nuclear Closed Cooling 5. (a) Applicable Construction Code: ASME Section III NC 1974 Edition NAMEISECTION/DIVISION/CLASS 19 75 Addenda Code Case(s) N/A Winter (b) Construction Code used for repairs, modifications, or replacements: 1974 Winter 75 Edition Addenda (c ) ASME Code Section XI applicable for Inservice Inspection: 1989 N/A Edition Addenda (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 FIRSTENERGY Nuclear Oprerating Company PNPP 6. Identification of Components Repaired, Modified, or Replacement Components n/a Code Case(s)n/a Code Case(s)Name of Name of Manufacturer Nat. Other Year Repair, ASME Component Manufacturer Serial No. Board ID. Built Replacement, Code No. or Modification Stamped Valve Contromatics 84509-26-3 N/A 1 P43 1977 Replacement Yes F355 7 7 Description of Work: Rebuilt valve using (8) 1/4-20 cap screws HT#726438, shaftldisc assembly HT#TSI, studs 7/8-9 four of HT code 81. two of heat code 2. and three of heat # 8991565 continued in remarks.8. Test Conducted: Hydrostatic- [] Pneumatic-E] Nominal Operating Pressure-E] Other- D Pressure N/A psi Test Temperature N/A degrees F Code Case(s) N/A 177 NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS (Back)PNPP No. 9308 Rev. 9/11/00 N01-1741 9. Remarks: Reference CR 03-06248 and CR 03-06252 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 ot 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 26 Sept. , 20 05 Date A 20 05 Signed FENOC-PNPP y"'Z/ I-9 CC Tech.(name of repair organization) (authdrized 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 cerditicate 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 S..'T. I, 20 JS 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 q 20 t.. Signed o. Commissions NB 9330"N""I""A" Ohio Comm.(inspector,3 (National Board (include endorsements), and jurisdiction, and no.) REPORT NO. P0059-011/,P q-3) -- 6 / &2_c--"CORRECTED REPORT" S.D. NP84509, Item #2E, P.O. P-1191-K, Item #RNN -12 FORM NPV-1 MANUFACTURERS" DATA REPORT FOR NUCLEAR PUMPS OR VALVES'(As Required by the Provisions of the ASMlE Code, Section it1, Div. 1)1. Manufactured by Contromatics Div., 222 Roberts St., E. Hartford, Ct. 06108 2- Manufactured for Cleveland Elec. ILiUra. Co , Illumninat-ing Bid. Pu bli Sq., (Name and Address of Purchaser or Ow.nedl CI7ve an , Ohio 44-dl 3. Location of nsrallationPerUr y NUC. Pwr. Pits., Units 1&2, Near PainesviL _e Q0hio (Name and Addressl 4. Pump or Valve Butterfly Valve. Nominal Inlet Size 10 Outlet Size linch)(a) Model No., (b) Manufacturers' (c) Canadian-Series No- Serial Registration .(d) Drawing or Type No. ..No. No. (e) C (1) CW-2566-BB 84509-26-3 N/_A 2498-Io-26A 2 (f) Nat'l. (g) Year lass Bd. No. Built N/A 1977 (3)(4)J5)(6)(7)(8)(9)(10)5. Demineralized Water (Active)(Brief descriprion of service for which equipment was designed)6- Design Conditions 150 -psi 150 or Valve Pressure Class NIA ()(PressureI (Temperature) 7- Cold Working Pressure 275 psi at 100tF_8. Pressure Retaining Pieces (1) For manually operated valves only-Supplemental sheets in form of lists. sketches or draw-ings may be used provided (1) size is S-1I2" x 1V. (2) information in items 1, 2 and 5 on (his data report is included on each sheet, and (31 each sheet is numbered and number of sheets is recorded at top of this form-(1/76)Th,is form (E100371 may be obtained lrom the Order Ceor.. ASIE. 3-,5 E. 47 St., tie-, York. N.Y. 1001 7 178 /FORM., rZ'ZV-1 (Back)Mark No.Material Spec. No.Manufacturer Remarks (c) Boilting I Studs ASMIE-SA-193 IBA Co. arnd Uni ersal-Cyclops Hft #G_89 83 jGr. B8 C r Bolts ASME-SA-193 IBA Co. and Jon s & Laughlin Htff#08238 jGr. B8I Nuts ASPIE-SA-194 IBA Co. and Allegheny-Ludlam fft- 8`//870 47 Gr. 8 _ _ _ _ _ _(d) Other Parts LU'Wi &teAS- -"n K\r)Hr. r~q G-r. 7(]J Fraciiinma Worksm Disc(Plate) ASME-SA ser Steel jt #5-2o(D4 2-1 Gr. .0 U .7_Z Retainer Stahlwerke Peint -Salzgitter AG Ht e,+/-21 I Gr. 70 ROIJ #7226-4 9- Hydrostatic test -25 psi CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and that this pump, or valve, conforms to the rule, of constriction of the ASME Code for Nuclear Pow.,er Plant Components. Section III, Div. I., Edition -_1974 Addenda Winter 1974 .Code Case No. N/A Date _ "_/_-___Signed Contromatics Division __,_,,_,__._ Our ASME Certificate of Authorization No. £-8,5 to use the 14 " symbol expires 9.(NI IN ) (t4FV)el CERTIFICATION OF DESIGN Design information on file at Controuiatics Division Stress analysis report (Class I only) on file at Design specifications certified by (11 Hiram R. Reppert PE State Pa. Reg- N-o 24298-E Stress analysis certified by (1)PE State Reg. No.(1) Signature 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 Inspectors and the State or Province of Corr-necticut and employed by Lumbermens Mutual Co.of _UOrthQiaL._n , Maas. have inspected the pump. or valve, described in this Data Report on 1/- 19 2i. and state that to the best of my know.'ledge and belief, the Manufacturer has con-structed this pump. or valve, in accordance with the ASME Code, Section Ill.By signing this certificate, neither the Inspector nor his employer makies 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 propert/ damage or a loss of an/ kind arising from or connected with this inspection. Date ',/- t-,cf'" I (1lnspecrorl /Commissions -- RJI'I .St i .Pro,. and No.) REPORT NO. P0059-011 1 P54-009 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.-10 Center Road, Perry, Ohio 44081 Date 5/19/07 Sheet 1 of 2 2. Plant: Perry Nuclear Power Plant (PNPP)10 Center Road. Perry, Ohio 44081 (Repair Org. P.O. No., etc.)Unit ONE ORDER 200173873 Type Code Symbol Stamp NR Authorization No. 33 Expiration Date 9-28-08 3. Work Performed By: FIRSTENERGY Nuclear Operatinq Company PNPP 10 Center Road, Perry, Ohio 44081 4. Identification of System: 1P54 FIRE PROTECTION

5. (a) Applicable Construction Code: ASME SECTION III NC 1974 Edition NAME/SECTION/DIVISIONICLASS WINTER 19 75 Addenda Code Case(s) N-242-1,N-272.N-224.N-413,1644-5 (b) Construction Code used for repairs, modifications, or replacements:

1974 WINTER 75 Edition Addenda (c ) ASME Code Section Xl applicable for Inservice Inspection: 1989 N/A Edition Addenda (d) Applicable Edition of Section XI Utilized for Repairs, Modification, or Replacements: 19 89 , EDITION 19 N/A Addenda N/A Code Case(s)(e) Design Responsibilities FIRSTENERGY NUCLEAR OPERATING COMPANY PNPP 6. Identification of Components Repaired, Modified, or Replacement Components Code Case(s)N/A Code Case(s)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 1P-54 76 NA 1985 REPLACEMENT YES SYSTEM POWER 7. Description of Work: REPLACED CHECK VALVE CVIB-0430 WITH NEW CHECK VALVE SN- N99934-00-0001. -, 7-, -,- / 5 /," S _/ /ý_A ý8 ýVl 7/ý../,,/#,7 '7t- _ 71c( 167--8. Test Conducted: Hydrostatic-11 Pressure 8.2 psi Test Temperature Pneumatic-jj Nominal Operating Pressure-E] Other- El 72.5 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 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 Sept 28 , 20 08 Date 5/19/ 2007__Signed FENOC-PNPP JL QE (name of repair organization) (authorized mpres lative) (title)CERTIFICATE OF INSPECTIONIINSERVICE INSPECTION I, C , £'_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 A/'/ý C of 9,z,-- -Fc /gp C 7- have inspected the repair, modification or replacement described in this report on .---/ , 20 LL 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, pro rty damage or loss of any kind arising from or connected with this inspection. Date 7 017 ige Commissions I}6 7f 4Z 419 1 -0/. / 113 z-(inspector) (National Board (include endorsements), and jurisdiction, and no.) REPORT NO. P0059-011 Q.C.-398, Rev. B Form N`PV-FOR'I NPV-l CERTIFICATE HOLDERS' DATA REPORT FOR NUCLEAR PUNII'S OR VALYE,,S*As Required by the Provisions of l'th ASME Code, Section II, Division i Pg. 1 of 2 1. Manufactured and certified by Anderson Grecowood Crosby. 43 Kendrick St., Wrenwham, MA 02093 (nafne and address of N Certificate Holder)2. Manufactured for FIRST ENERGY CORP.(name and address of Purchaser)

3. Location of installation PERRY. O1 (name and address)4. Model No.. Series No.. or Type CVIB-0430-SSB-N Drawing DS-C99934 Rev. B CRN N/A 5. ASME Code, Section IIt, Division 1: 1974 W'75 2 N/A.(edition) (addenda date) (class) (Code Case to.)6. Pump or valve VALVE Nominal inlet size 4 Outlet size 4 (in.) (in.)7. Material: (a) valve (b) pumip Body SA182 GR.F316 30rme t Casting Cover Disk .A479 GR.F3t6 Bolting Boltwg Cert.Ho-lul's Serial No.N99934-0/)-Q0001 (b)N;t'l Board No.(c)Body/Casing Serial No.BODY DISC HtP4GE PIN HUStING HINGE [US BUSHrNG HEX HEAD CAPSCREW SLOTTED NUT (d )Borine riCo ver Serial No.N9()00406-3[-U{00l 1,900408-3 1 -0001 N9(X)416-3 1 -(")2 N900416-31 -UtY)I N98~354-34-0005 N978S60-33-0007 (e)Disk.Serial No.SupplemenoI information w form of Iists, sketches.

or drawings may be used prooided (1) size is 8-1/2 X 11. (2) i'ifornadoon in items I through 4 on this Data Report is included an each sheet. (3) each sheet is numbered and the number of sheets is rccorded at die top of this forna.This form (E00037) may be obtuincd from the Order Dept.. ASMtE. 22 Law Drire. Bui, 2300, Fasirirld, NJ 07007-2300. IT .180 Q.C.-398, Rev. B Side 2 FORMVI NPV-I (Back -- Pg. 2 of 2 Certificate Holder's Serial No. N99934-00-00U1) Form NPV-1 8. Design conditions 500 psi 0 (pressure) (temperature)

9. Cold working pressure 720 psi at 100°F' Fof valve pressure class ANSI CL 300 10. Hydrostatic test 11. Rcinarks _1125 psi... Disk differential test pressure N/A psi CERTIfICATE OF. DESIGN Design Specification certified by WALTER C. FLENSBURG P.E State OI Rcg No. 419729 Design Report certified by N/A P.E. State Reg. No.CERTIFICATE OF COMPLIANCE We certify that the statement5 made in this report ale Correct and that this pump or v:lve cutidorms to [he rules fir construction of the ASME Code. Section 111. Division 1.N Certificate of Authorization No. N-1876 Expires 30 SEPTEM E 2 3ER 2007 Date c--/-7i-x/-

.7 Name ANDERSON GREFNWOOD/CROS"Y -Sighed ._(N Certificate Holder) (authorized represenitative) CERTIFICATE OF INSPECTION 1, the undersigned, holding a valid commission issued by tdic National Board of 'Boiler and Pressure V essel Inspectors and the State or Province of Massathusetts _and employed by HSB-CT of HARTFORD, CT have inspected the pump, or valve, described in this Data Report on.-,Z> -I ,, and state that to the best of mykcnovledge and belief, the Cerlificate Holder has con-structed this pump, or valve, in accordance with the ASME Code, Section III, Division I.-By signing this certificate, neither the inspector nor his employer makes any warranty, expressed or implied, concerning the component described in this Data Report. Furthermore, ucither the inspector nor his employer shall be liable in any manner for any personal injury or property damag or a loss of any kind arising from or connected with this inspection. DateJ,/._ 1 , 4 7 Signed .- Commissions MA-1420 A,N,I,S (Auth ed Inspector) (Nat'l. Bd. (incl. Endorsements) and state or prov. and ao.)/}}

@@ Line 2: / Line 2: @@
 | number = ML072250365
 | issue date = 08/07/2007
-| title = Perry, Unit 1 - Submittal of Eleventh Inservice Inspection Summary Report
+| title = Submittal of Eleventh Inservice Inspection Summary Report
 | author name = Allen B S
 | author affiliation = FirstEnergy Nuclear Operating Co

ML072250365: Difference between revisions

Revision as of 08:37, 10 February 2019

Contents

Text

Subject:

Enclosure:

SUMMARY

1.0 INTRODUCTION

4.0 INSPECTION

5.1 Personnel

5.2 Equipment

6.0 CALIBRATION

7.0 PROCEDURES

8.0 RELIEF

9.0 SCHEDULE

SUMMARY

SUMMARY

1.0 INTRODUCTION

2.0 REFUELING

9.0 SCHEDULE

SUMMARY

SUMMARY

SUMMARY

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ML072250365: Difference between revisions

Revision as of 08:37, 10 February 2019

Text

Subject:

Enclosure:

SUMMARY

1.0 INTRODUCTION

4.0 INSPECTION

5.1 Personnel

5.2 Equipment

6.0 CALIBRATION

7.0 PROCEDURES

8.0 RELIEF

9.0 SCHEDULE

SUMMARY

SUMMARY

1.0 INTRODUCTION

2.0 REFUELING

9.0 SCHEDULE

SUMMARY

SUMMARY

SUMMARY

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