L-17-072, Sixteenth Inservice Inspection Summary Report

Sixteenth Inservice Inspection Summary Report

ML17180A173
Person / Time
Site:	Perry
Issue date:	06/29/2017
From:	Hamilton D FirstEnergy Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
L-17-072
Download: ML17180A173 (33)

Text

FENOC Perry Nuclear Power Plant PO Box 97 10 Center Road FirstEnergy Nuclear Operating Company Perry-Ohl° 44081 David B. Hamilton 440-280-5382 Vice President June 29, 2017 L-17-072 10CFR50.55a(g)

ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001

SUBJECT:

Perry Nuclear Power Plant Docket No. 50-440, License No. NPF-58 Perry Nuclear Power Plant Sixteenth Inservice Inspection Summary Report In accordance with 10 CFR 50.55a, "Codes and standards," and the American Society of Mechanical Engineers Boiler and Pressure Vessel Code,Section XI, "Inservice Inspection," 2001 Edition through 2003 Addenda, Article IWA-6000, enclosed please find the inservice inspection summary reports for examinations performed prior to and during the sixteenth refueling outage at the Perry Nuclear Power Plant (PNPP).

This submittal provides the PNPP inservice inspection summary for the timeframe of April 25, 2015 to April 3, 2017.

There are no regulatory commitments contained in this submittal.

If there are any questions or if additional information is required, please contact Mr. Thomas A. Lentz, Manager - Fleet Licensing, at (330) 315-6810.

David B. Hamilton

Enclosures:

A.

Form NIS-1 Owners Report for Inservice Inspections, including attached Inservice Inspection Summary Report for the Perry Nuclear Power Plant B.

Form OAR-1 Owner's Activity Report cc:

NRC Region III Administrator NRC Resident Inspector NRC Project Manager Authorized Nuclear Inservice Inspector Ohio Department of Commerce, Boiler Inspection Section

Enclosure A L-17-072 Form NIS-1 Owners Report for Inservice Inspections, including attached Inservice Inspection Summary Report for the Perry Nuclear Power Plant (Activities performed 4/25/2015 through 5/18/2016)

Consists of Form NIS-1 (3 pages),

and its attached Summary Report P1059-016 (25 pages)

Report No.: PI059-016 Page 1 of 2 FORM NIS-1 OWNERS REPORT FOR INSERVICE INSPECTIONS As required by the provisions of the ASME Code Rules FirstEnergy Nuclear Generation, LLC, 76 South Main Street, Akron, OH 44308 (Name and Address of Owner) 1.

Owner 2.

Plant 3.

Plant Unit Perry Nuclear Power Plant, 10 Center Road, Perry, OH 44081 (Name and Address of Plant) 4.

Owner Certificate of Authorization (if required)

N/A 5.

Commercial Service Date 11/18/87 6.

National Board Number for Unit N/A 7.

Components Inspected (only the systems with Class 1 and 2 components are listed in following table)

Component or Appurtenance Reactor Vessel Reactor Vessel Nuclear Boiler System Nuclear Boiler System Reactor Recirculation System Reactor Recirculation System Control Rod Drive Hydraulic Control System Standby Liquid Control System Containment Atmosphere Monitoring Residual Heat Removal System Residual Heat Removal System Containment Spray System Low Pressure Core Spray System High Pressure Core Spray System Leak Detection System Main Steam Isolation Valve Leakage Control System Reactor Core Isolation Cooling System Manufacturer or Installer GE/CBIN GE/A&ES GE/A&ES Pullman Power Products GE/A&ES Pullman Power Products Pullman Power Products Pullman Power Products Johnson Controls Engineers & Fabricators Company Pullman Power Products Pullman Power Products Pullman Power Products Pullman Power Products Johnson Controls Pullman Power Products Pullman Power Products Manufacturer or Installer Serial No.

T-49 1B13 1B21 1B21 1B33 1B33 1C11 1C41 1D23-0064-F 1E12 1E12 1E15 1E21 1E22 1E51-0068-F 1E32 1E51 PNPP System Designation 1B13 1B13 1B21 1B21 1B33 1B33 1C11 1C41 1D23 1E12 1E12 1E15 1E21 1E22 1E31 1E32 1E51 National Board No.

15 64077 64084 109 64076 119 92 108 008 1621 83 105 85 86 15 104 84 Note:

Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8)4 in. x 11 in.

(2) 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.

This Form (E00029) may be obtained from the Order Dept., 22 Law Drive, Box 2300, Fairfield, NJ 07007-2300

ReportNo.:P1059-016 Page 2 of 2 1.

Owner FirstEnergy Nuclear Generation, LLC, 76 South Main Street, Akron, OH 44308 (Name and Address of Owner) 2.

Plant Perry Nuclear Power Plant, 10 Center Road, Perry, OH 44081 3.

Plant Unit (Name and Address of Plant) 4.

Owner Certificate of Authorization (if required)

N/A 5.

Commercial Service Date 11/18/87 6.

National Board Number for Unit N/A 7.

Components Inspected (only the systems with Class 1 and 2 components are listed in following table)

Component or Appurtenance Integrated Leak Rate System Fuel Transfer System Reactor Water Cleanup System Reactor Water Cleanup System Fuel Pool Cleaning System Suppression Pool Drain and Cleanup System Suppression Pool Makeup System Containment Vessel Purge System Drywell Vacuum Relief System Containment Vacuum Relief System Combustible Gas Control System Main Steam System Main, Reheat, and Miscellaneous Drains Feedwater System Condenser Transfer and Storage System Mixed Bed Demineralizer Water Sys.

Nuclear Closed Cooling System Containment Chilled Water System Service Air System Instrument Air System Post Accident Sampling System Containment System Manufacturer or Installer Pullman Power Products General Electric GE/A&ES Pullman Power Products Pullman Power Products Pullman Power Products Johnson Controls Pullman Power Products Pullman Power Products Pullman Power Products Pullman Power Products Pullman Power Products Pullman Power Products Pullman Power Products Pullman Power Products Pullman Power Products Pullman Power Products Pullman Power Products Fisher Controls f

Pullman Power Products Johnson Controls Newport News Manufacturer or Installer Serial No.

1E61 1F42 1G33 1G33 1G41 1G42 1G43-0065-F 1M14 1M16 1M17 1M51 1N11 1N22 1N27 1P11 1P22 1P43 1P50 6393471 1P52 1P87 NNI-OS-02 PNPP System Designation 1E61 1F42 1G33 1G33 1G41 1G42 1G43 1M14 1M16 1M17 1M51 1N11 1N22 1N27 1P11 1P22 1P43 1P50 1P51 1P52 1P87 1T23 National Board No.

120 64079 64075 100 95 96 019 113 115 87 106 111 112 89 102 73 101 103 6170 74 034 N/A

Report No.: PI059-016 FORM NIS-1 (Back) 8.

Examination Dates 4/25/2015 to 5/18/2016 9.

Inspection Period Identification:

Second Period 10.

Inspection Interval Identification:

Third 11.

Applicable Edition' of Section XI 2001 Addenda 2003 12.

Date/Revision of Inspection Plan:

PNPP Inservice Examination Program Plan Revision 17, dated 2/5/15 and Revision 18 dated 11/18/16 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 PI 059-0016*

14.

Abstract of Results of Examinations and Tests.

See attached summary report PI 059-0016*

15.

Abstract of Corrective Measures.

See attached summary report P1059-0016*

• Report is 25 pages in length.

/

We certify that a) the statements made in this report are correct b) the examinations and tests meet the Inspecuon 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 Date fe/zl/zety Signed FENOC Expiration Date N/A T

Owner 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 Hartford Steam Boiler Insp. And Ins. Co.

of Hartford. CT have inspected the components described in this Owner's Report during the period 4/25/2015 to 5/18/2016 and state that to the best of my knowledge and belief the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the inspection plan and as required by the ASME Code,Section XI.

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.

Date Commissions 13SO K

National Board, State, Province, and Endorsements

ReportNo.:P1059-016 INSERVICE INSPECTION

SUMMARY

REPORT FOR PERRY NUCLEAR POWER PLANT (PNPP)

UNIT 1

LOCATED AT:

10 Center Road

Perry, Ohio 44081 OWNER:

FirstEnergy Nuclear Generation, LLC 76 South Main Street

Akron, Ohio 44308 REACTOR SUPPLIER:

General Electric Corporation 175 Curtner Avenue San

Jose, California 95125 NRC DOCKET NUMBER:

50-440 FACILITY FULL POWER LICENSE:

NPF-58

CAPACITY, Mwe:

COMMERCIAL OPERATION DATE:

INSPECTION INTERVAL:

INSPECTION PERIOD:

REFUELING OUTAGE:

DOCUMENT COMPLETED:

1305 November 18, 1987 May 18, 2009 May 17, 2019 Second (May 18, 2013 May 17,;2017) 1R16 May 19, 2017 Page 1 of25

Report No.: PI059-016 ABSTRACT Perry Nuclear Power Plant (PNPP)

Unit 1

was shut down for twenty-nine (29) days to refuel the reactor vessel

[Refueling Outage 16(1R16)]

and perform plant maintenance commencing March 5,

2017.

During the refueling

outage, and during the preceding operating

cycle, inservice examinations were performed to comply with plant Operational Requirements Manual and the 2001 Edition through the 2003 Addenda of ASME Section XI.

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, including Class 3

and Augmented examinations, which were performed in accordance with the schedules within PNPP's Inservice Examination Program Plan (ISEP),

Revision 17 and Boiling Water Reactor Vessel and Internals Project (BWRVIP)

Program, TAI-0507 Revision 10.'

Routine Section XI volumetric, surface and visual examinations were performed on Class 1,

2 and 3

piping systems and pressure retaining components.

It should be noted that during Cycle 16, PNPP implemented Code Case N-532-5, which allows the use of Form OAR-1, "Owner's Activity Report" in lieu of Form NIS-1, "Owner's Report for Inservice Inspections".

As

such, this report will only discuss activities which were performed between the beginning of Cycle 16 (4/25/2015) until the implementation of Code Case N-532-5 (5/18/2016).

Additionally, previously submitted reports for Refueling Outages 1R14 and

1R15, Section 8.0 "Relief Requests" stated that Relief Request IR-009 had been utilized.

This was not correct as this request had not been submitted for this interval.

1R16 was the second refueling outage of the second inspection period within Perry's third 10-year inservice inspection interval.

The completion of the Cycle 15 and 1R15 examinations, combined with examinations performed in Cycle 16 and

1R16, will fulfill the required minimum percentage of exams for the second period.

^

One ASME Form NIS-2 was included in this submittal due to missing the ASME Code Data

Report, Form N-2 from the manufacturer during the previous cycle.

RRP No.

1B13-060 has been included in this submittal.

One ASME Form NIS-2 from the previous cycle has been included in this package due the form being revised after submittal to the National Board.

RRP No.

1B13-058 contained typos and has been corrected.

Page 2 of25

Report No.: PI059-016 CONTENTS PAGE

1.0 INTRODUCTION

4 2.0 REFUELING OUTAGE DURATION 4

3.0 CODE REQUIREMENTS 4

4.0 INSPECTION 4

5.0 CERTIFICATIONS 4

5.1 Personnel 4

5.2 Equipment and Materials 5

6.0 CALIBRATION STANDARDS 6

7.0 PROCEDURES 6

8.0 RELIEF REQUESTS 6

9.0 SCHEDULE CHANGES 7

10.0 EXAMINATION

SUMMARY

RESULTS 7

11.0 NIS-2/NR-1 7

APPENDICES A.

CYCLE 16 NIS-2/NR-1 FORMS 8

LAST PAGE 25 Page 3 of 25

Report No.: P1059-016

1.0 INTRODUCTION

The information provided herein is supplied to document compliance with ASME B&PV

Code,Section XI requirements for reporting inservice inspection results for Class 1

and Class 2

pressure retaining components and their supports.

Examination results of Class 3

and Augmented components and their associated supports are also 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 1R15 (April 25, 2015) through the implementation of Code Case N-532-5 (May 18, 2016).

Included in this report are the following:

Personnel and equipment listings Examination results summaries NIS-2/NR-1 Reports Other pertinent information 2.0 REFUELING OUTAGE DURATION The Perry Nuclear Power

Plant, Unit 1,

was shut down for 1R16 from March 5,

2017 to April 3,

2017.

The plant returned to commercial operation on April 3,

2017, at 11:42.

This is noted as the time when the generator was synchronized to the grid.

This report does not cover any of the activities for the outage.

These will be covered in Form OAR-1.

3.0 CODE REQUIREMENTS The inservice inspections were conducted in accordance with the requirements of ASME B&PV

Code,Section XI, Division 1,

2001 Edition through the 2003

Addenda, with Code Cases N-461-1, N-513-3, N-526, N-528-1, N-532-5, N-537, N-552, N-561-2, N-562-2 N-566-2, N-578, N-586-1, N-613-1, N-624, N-648-1, N-652-1, N-658, N-661-2, N-663, N-664, N-666, N-683, N-685, N-695, N-700, N-705, N-716-1, N-735 and N-747.

4.0 INSPECTION Inspection activities were conducted by Authorized Nuclear Inservice Inspection personnel from The Hartford Steam Boiler Inspection and Insurance Company of Connecticut.

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 16 operations.

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 non-destructive examinations in accordance with PNPP or approved vendor procedures as verified by PNPP personnel and the Authorized Nuclear Inservice Inspector.

The following is a

listing of personnel responsible for the performance of the NDE activities related to ISI during Cycle 16 operations until the implementation of Code Case N-532-5:

Page 4 of25

Report No.: PI059-016 ISI NDE PERSONNEL Name

Bares, Jeffrey

Barrett, Jennifer

Blalock, Roy

DiVito, David

Fuller, Richard Jr.

Gorski, Stan

Guerinot, Gregory

Heath, Jacob

Holz, Charles

Kostner, Tobias

Mangle, James

Mick, Andrew

Miranda, Jeffrey

Munson, Dewey

Olderman, David

Phelps, Antoinette

Pikus, Raymond Preisinger, Jon Paul

Pristov, Judith

Quick, Nathan Rasmussen, Eric

Rocker, Erica

Roth, Scott

Sayovitz, Steve

Truxall, Justin Zaharewicz, Kurt UT II*

II*

III**

II*

II*

III II*

II*

PT II III II III II MT II III II III II VT 11 +

11 +

11 +

11 +

III 11 +

11 +

11 +

11 +

II 11 +

11 +

11 +

III 11 +

11 +

11 +

11 +

11 +

11 +

11 +

11 +

11 +

11 +

11 +

11 +

+

Limited to VT-2 only Limited to ultrasonic thickness measuring only PDI qualified personnel 5.2 Equipment and Materials The equipment and materials used during the performance of the non-destructive examinations were certified and/or calibrated in accordance with site procedures or approved vendor procedures and verified by the Site NDE Level III and the Authorized Nuclear Inservice Inspector.

For the reporting

period, only visual examinations were performed.

As

such, no equipment or materials were required.

Page 5 of25

Report No.: PI059-016 6.0 CALIBRATION STANDARDS There were no ultrasonic calibration standards used for ISI related work activities during Cycle 16.

7.0 PROCEDURES The examination procedures used during Cycle 16 operations were as follows:

Perry NDE Procedures:

PROCEDURE NQI-1042 16 to 17 Visual

\\

Examination TITLE

! *~-*;

8.0 RELIEF REQUESTS 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 and approved for PNPP's third 10-year inspection interval:

RR NO/REV IR-013 R-2 IR-027 R-2 IR-030 R-l IR-043 R-2 IR-049 R-l IR-054 R-l IR-056 R-l IR-058 R-0 PT-001 R-2 SYSTEM High Pressure Core Spray Low Pressure Core Spray Residual Heat Removal Standby HPCS Diesel Fuel Oil Reactor Pressure Vessel Circumferential Welds Reactor Water Cleanup Residual Heat Removal Reactor Core Isolation Cooling High Pressure Core Spray Low Pressure Core Spray Class 1

Piping Class 1

Piping Reactor Vessel Reactor Vessel Various non-isolable (from the RPV Boundary)

Class 2

Components TYPE RELIEF No Exams Alternative Exams No Exams No Exams Alternate Examination Population, Class 1

Risk-Informed application Alternate Examination Population Alternate Examination Impracticality Alternate System and Inservice Tests

^categI:

C-G D-A B-A B-M-l B-F B-J B-D B-N-l B-N-2 F-A C-H 4ITEM,;N0 C6.10 D1.10 Bl.ll B12.30 B12.40 B5.10 B5.20 B5.30 B9.ll B9.21 B9.31 B9.32 B9.40 B3.90 B3.100 B13.10 B13.40 F1.40 C7.10 Page 6 of25

ReportNo.:P1059-016 9.0 SCHEDULE CHANGES No schedule changes were made during the period covered by this report.

10.0 EXAMINATION

SUMMARY

RESULTS 1R16 was the fourth refueling outage of Perry's third 10-Year Inservice Inspection Interval and the second of two outages in the second inspection period.

Not including pressure testing VT-2 exams that are completed every

period, Cycle 15 and 1R15 account for approximately half of the ASME Section XI Code required minimum exams to be completed by the end of the second

period, or 1R16.

Cycle 16 and 1R16 examinations resulted in a

complete and acceptable program in that all indications were evaluated for acceptance in accordance with ASME Section XI, IWA-3000, and all corrective measures or evaluations were completed.

From the end of 1R15 through the implementation of Code Case N-532-5, only VT-2 examinations as part of system leakage tests or Repair/Replacement activities occurred.

As

such, no listing of examinations is included with this report.

11.0 NIS-2/NR-1

Repairs, replacements and modifications are carried out in accordance with PNPP's Nuclear Repair Repair (non-nuclear)

Manual, which meets regulatory requirements and quality standards.

Compliance of the work is delineated on NIS-2/NR-1 forms.

Copies of the NIS-2/NR-1 forms are contained in Appendix "B"

and the corresponding starting page numbers are provided in the table below.

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 PNPP's last summary report through the implementation of Code Case N-532-5:

NR-l/NIS-2 FORMS RRP NO.

FLOC/MPL NO.

DESCRIPTION/COMMENTS CLASS PAGE Reactor and Internals (1B13)

System Cycle 16:

1B13-058 1B13-060 1B13-D0001 1B13-D0008 Replaced 2

LPRM dry tubes and 4

SRM dry tubes Replaced One Control Rod Drive Mechanism (CRDM) and replaced 1"

cap screws (8

total) 1 1

9 19 Reactor Core Isolation Cooling (1E51)

System Cycle 15 1R15 Reports:

1E51-167 1E51-H2074 Replaced PSA 1/4 snubber with new 2

24 Page 7 of25

Report No.: PI059-016 APPENDIX A

"CYCLE 16 1R16 NIS-2/NR-1 FORMS" INSERVICE INSPECTION

SUMMARY

REPORT FOR PERRY NUCLEAR POWER PLANT (PNPP)

UNIT 1

Page 8 of25

Report No.: PI059-016 1B13-058 NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As required by the Provisions of the ASME Code Section XI NOP.CC-5703-04R8V.01 1.

Owner:

2.

Plant FirstEnerqy Nuclear Generation. LLC 76 South Main Street. Akron OH 44308 Perrv Nuclear Power Plant (PNPP) 10 Center Road. Perry. Ohio 44081 Date 12/29/2015 Sheet 1

of Unit ONE 200261110 3.

Work Performed By:

FiretEnerov Nuclear Operating Company PNPP 10 Center Road. Perrv. Ohio 44081 4.

Identification of System:

PY-1B13. REACTOR AND INTERNALS (Repair Org. P.O. No., etc.)

Type Code Symbol Stamp NR Authorization No.

33 Expiration Date 9-28-2017 5.

(a) Applicable Construction Code: ASME SECTION III CLASS 1 NAME/SECTION/DIVISION/CLASS WINTER L

1971 Edition 1972 Addenda CodeCasefe)

• 1332-6.1620.1557-1.1141-1 (b)

Construction Code used for repairs, modifications, or replacements:

1974 Edition W/75 2001 Addenda 2003 (c) ASME Code Section XI applicable for Inservice Inspection:

Edition Addenda (d)

Applicable Edition of Section XI Utilized for Repairs, Modification, or Replacements:

2001.EDITION 2003 Addenda N/A Code Case(s)

N/A CodeCase(8)

(e)

Design Responsibilities FENOC CodeCase(s) 6.

Identification of Components Repaired, or Replacement Components Name of Component REACTOR VESSEL Name of Manufacturer CBI NUCLEAR COMPANY Manufacturer Serial No.

T49 Nat.

Board No.

15 Other ID.

N/A Year Built 1975

Repair, Replacement REPLACEMENT ASME Code

'Stamped (Yes or No)

YES 7.

Description of Work: PY-1B13D0001.

REPLACED REACTOR VESSEL DRY TUBES AS DETAILED IN THE REMARKS SECTION.

8.

Test Conducted:

Hydrostatic-Q Pneumatic-Nominal Operating Pressure-E3 Other-Pressure 1037 psi Test Temperature 118 degrees F Code Case(s)

N/A Pagei of 2 Page 9 of25

Report No.: PI059-016 NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As required by the Provisions of the ASME Code Section XI NOP-CC-5703-04 Rev. 01 9.

Remarks:

REPLACED LPRM DRY TUBES 08-41 WITH S/N 141021LZ AND 08-49 WITH S/N 04S85851.

REPLACED SRM DRY TUBES 16-21 WITH S/N 04S84952.16-45 WITH S/N 15B0019K. 40-21 WITH S/N 15B0019L AND 40-45 WITH S/N 15B0019J.

NO NAMEPLATeSTAMPING PERFORMED DUE TO THE INTERFACE CONTROLS OF PART 3 SECTION 1.8.6 BEING IN EFFECT AND JURISDICTIONAL AUTHORITY CONCURRENCE HAVING BEEN RECEIVED.

Note:

Attach all applicable Manufacturer's Data Reports. Supplemental sheets such as lists, sketches, or drawings may be used, provided (1) size is 81/2 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, TOBIAS J KOSTNER 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 UNR" rules.

National Board Certificate of Authorization No.

33 to use the "NR Date 20 Signed FENOC-PNPP (name of repair organization)

.expires 28 SEPT 20 17 SR. QUALITY TECH (authorized representative)

OHIO CERTIFICATE OF INSPECTION/1NSERV1CE INSPECTION ftft^

.holding a valid commission issued by The National Board of Boiler and I,

Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of, and employed bv The Hartford Steam Boiler Inspection and Insurance Company of Connecticut have inspected the repair, modlficatioh or replacement described in this report onftC.£fe. 20 lv arid 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 Date tfrftfe 20 C£c_ Signed iss of any kind arising from or connected with this inspection.

Commissions (National Board (include endorsements),

andjurisdiction, end no.)

Page 2 of 2 Page 10 of 25

Repo o: P105 PRODUCTION ORDER NUMBER: 19739871 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 1.

Manufactured nnd certified by.

GEReuter-Stokes. Inc..

8499 Danow Road. Twinsburg, Ohio 44087 (nme mi address of NTT Curtate Hoide) 2.

Manufactured for First Energy Corp P.O. Box 6100 Tohnstown. PA 15907 3.

Location of installation

4. Type:

RS-E5-121Q-201 (dnwlng na) 5.

ASME Code,Section III, Division 1:

(Mmoaad UMicn of Furrfeuor)

\\

Perry Nuclear Power Plant 10 Center Road Perry. OH 44081 (iwme N/A N/A N/A 2014 (nud'IspM. no.)

1974 Qenslfc strength)

(CR.V7 (pur hull)

Winter 1974 N/A

(<<dd<<miidjMI N/A Revision 6.

Fabricated in accordance with Const. Spec. (Div. 2 only) _

7.

Remarks:

Certified Design Specification CDS-C-272AB152-1 Rev. 0 N/A (GodeOoenft)

Date N/A Certified Design Report CDR-C-5253-23Rev. -

On File at GE Reuter-Stokes, Inc.

8. Nom. thickness (in.)

N/A Min. design thickness (in.)

N/A Dia. ID (ft & in.)

N/A Length overall (ft & ln.l N/A

9. When applicable, Certificate Holders' Data Reports are attached for each item of this report Part or Appurtenance Serial Number (1) 14I021LZ (2)

&)

(4)

(5)

(*)

(7)

(8)

(10)

(11)

(12)

(13)

(14)

(15)

(16)

(17)

(18)

(19)

(20)

(21)

(22) 24) 25)

National Board No.

in Numerical Order N/A Part or Appurtenance Serial Number (26)

(27)

(28)

(29)

(30)

(31)

(32)

(33)

(34)

(35)

(36) 07)

(38)

(39)

(40)

(41)

(42)

(43)

(44)

(45)

(46)

(47)

(48)

(49)

(50)

National Board No.

in Numerical Order 10.

Design pressure 1250 PSIG psi.

Temp.

Vessel 575*F.

Seal300°F Hydro test pressure 1975 PSIG at temp.

71CF

• Supplemental faifamtatton In the form of list*, *ketches, or drawings may be used provided (1) size b 8"/; k 11, (2) information in liens 2 ami 3 on this Data Report Is included on ench sheet P) cnch sheet is numbered and the number of sheets is recorded ci the top of this form.

(P7/10)

Page 11 of 25

Report No. :P 1059-016 PRODUCTION ORDER NUMBER:

19739871 FORM N-2 (Back-Pg. 2of 2)

Certificate Holder's Serial Nos.

N/A through N/A CERTIFICATION OF DESIGN Design specifications certified by Bill A. Balazs P-E. State CA Reg.no.

Design report* certified by Robert Scott Betechman P.E State OH Reg.no.

MF348 E-56133 CERTIFICATE OF COMPLIANCE We certify that the statements made in this report ere correct and that this (these)

Assemblies conforms to the rules of construction of the ASME Code, Section Til, Division 1.

NPT Certificate of Authorization No..

Date November 12,2014 N-2703 Name GEReutei-Stokes, Inc.

Signed (fCPTCcniltaHeHoMw)

. Expires, September 16,201,5 CERTIFICATE OF INSPECTION I,

the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and employed by H.S.B. Global Standards of HAKTFORaCT h**,* ;n<

>rtod rti^g itomc rWrih^H in Hm nata Report on f$n\\3 \\ 1^ . t.o \\ A aftd state that to the best ol my knowledge and belief, the Certificate Holder has fabricated these parts or appurtenances in accordance with the ASME, Code, Section 111, Division 1. Each part listed has been authorized for stamping on die date shown above-By signing this certificate, neither the bispector 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 dBtnage or loss of any kind arising from or connected with this inspection. Date. . Signed Commissions << M. <ind.cmlcwewenh)l stole Of lHW.<<t>di>>oJ (07/11) Page 12 of 25 PRODUCTION ORDER NUMBER; 19771917 FORM N-2 CERTIHCATE 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 Fg.lof 2 1. Manufactured and certified by GE Reuter-Stokea, Inc., 8499 Darrow Road. Twinsbtuy. Ohk> 44087 (mm? and <<Ura>>erN7rCMMBihi Hofafar)

2. Manufactured for Perrv First Energy Corp 10 Center Road PNPP TEC. Perry. OH 44081 (mine aad addios of Furth>><<<<)

3. Location of installation Pemr First Energy Corp 10 Center Road PNPP TEC, Perrv, OH 44081 (nanw and whom)

N/A N/A (mafl spec no.) 1974 4. Type: RS-E5-1500-217 (dnmfag no.) 5. ASME Code, Section HL Division 1: (tdUon) 6. Fabricated in accordance with Const Spec. (Div. 2 only) (no) CDS-C-5600-7-1 Rev.O N/A 2015 (CUM) Winter 1974 (addend* due) N/A Revision N/A N/A (CodeQMfla) Date N/A 7. Remarks: Certified Design Specification Certified Design Report CDR^C-5600-79 Rev. - On Pile at GE Beuter-Stokes, Inc. 8. Norn, thickness fin.) N/A Min. design thickness (in.) N/A Dia. ID (ft & in.) N/A Length overall fft&in.l N/A

9. When applicable, Certificate Holders' Data Reports are attached for each item of this report Part or Appurtenance Serial Number (1) 15B0019J (2) 15B0019K (3) 15B0019L (4)

(5) (6) (7) (8) (9) (10) (11) 02) (13) (14) (15) (16) (17) 08) (19) (20) (21) (22) (23) (24). (25) National Board No. in Numerical Order N/A N/A N/A Part or Appurtenance Serial Number (26) (27) (28) (29) (30) (31) (32) (33) (34) (35) (36) (37) (38) (39) (40) (41) (42) (43) (44) (45) (46) (47) (48) 449) (50) National Board No. in Numerical Order 10. Design pressure 1250 PSIG psi Temp. Vessel 575°F. SealSOOT Hydro test pressure 1950 PSIG at temp. 71°F (wfacnawlicafaiB) Surrten<<ntalinfc>rawtronintheformoftists,fikrtches,o^ included on eadi sheet, (3) each sheet is numbered and the number of sheels is recorded at the lop of this form. (07/10) Page 13 of 25 Report No.: PI059-016 PRODUCTION ORDER NUMBER: 19771917 FORM N-2 (Back - Pg. 2 of 2) Certificate Holder's Serial Nos. N/A through N//A CERTIFICATION OF DESIGN Design specifications certified by BfllA. Balazs P.E. State CA Reg.no. Design report* certified by David P. Rvzner P.E. State OH Reg.no. PE-74026 CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and that this (these) AssemblU conforms to the rules of construction of the ASME Code,Section III Division 1. MPT Certificate of Authorization No. Date February 28,2015 Name N-2703 .Expires GE Reuter-Stokes, Inc. Signed QftTCettiRcsitHoMfr) September 16.2015 u^JJLl CERT1RCATE OF INSPECTION I, the undersigned,, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and employed by H.S.B. Global Standards of HARTFORD. CT have inspected these items described m this Data Report on fg1*> Z.ft., 'UP \\ S* 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^ Aeither die inspector nor his employer shall be liable in any inanii^r for any personal injury or property damnge or loss of any kind arising from or connected with this inspection. Date >3T Signed Commissions INrfIM. (tact MdonntcnM and stat or mo* Md aoJ (07/11) Page 14 of 25 WORK ORDER NUMBER: 17916818 FORM N-2 CERTIFICATE HOLDERS' DATA REPORT FOR IDENTICAL NUCLEAR PARTS AND APPURTENANCES* As Required by the Provisions of the ASME Code, Section m Not to Exceed One Day's Production Report No.: PI059-016 Pg. 1 of 2 .1. Manufactured end certified by GE Raito-Stok*. ft*. 2, Manufacturedfor First Enerpy (HaHMdaddiwiefNFT Twinsburg. Ohio 44087

3. UctuiOTofinatalliition^Pj^

10 Center Road Perrv. OH 44081

4. Type:

RS-E5-1500-217 N/A N/A N/A 2007

5. ASME Code, Section m, Division 1:

1974 N/A

6. Fabricated in acccjdarMK with Ccmst Spec. (Drv. 2 only)

Certified Dedcn Report N/A Reviiion N/A Date N/A CDR-a5600-47Rev.0 QnFtteatGEReuter-Stoice^Inc a Nom.'IhfckneMfin.^ N/A Min. darign AkknfeM (in.) N/A Difl.lDfftAin.1 N/A Length overall (ft A in.) Ji/A.

9. When appUcable/ Certificate Holdeis' Data Reports an attached for each Hem ofthis report.

1 Part or Appurtenance Serial Number ^1) 04S84952 (2) (3) (4) (5) (6) \\7) (8) (9) ao) fll) 02) 13) 114) 15) (16) (17) (18) (19] £20 i (21) (22) (23) 24) 25) National Board No. m Numerical Order N/A Part or Appurtenance Serial Number (26) (27] (28 (29) (30) (91) (32) (33] (34] i J ( 95) 136) C37) 38) (39) (40) (41) J42) i i 43) 44) (45) (46) (47) (48) (49) <J50) National Board No. In Numerical Order Design pressure 1250 PSIG pbL Temp. Vessel 575°P. Seal300°F. Hydro, test pressure <<* <<m>>P-70°F. fachwled ao adi iheet CQ <<* *ettfe n tn6^fanncrfUrt^<<tocfaa^OTdniwl^ bdd flb tdlddttttfttbte ,A Page 15 of 25 ReportNo.:P1059-016 WORKORDERNUMBER: 17916818 FORM N-2 (Back - Pg. 2 of _Z+/- Certiflgite Holder's Serial Kin*. N/A Jhromfr N/A CERTIFICATION OF DESIGN Design specifications certified by fiifl ft, ffflfazff PJE. State CA Reg.no. MF34B Design report* certified by /WPtflfrfofct P.E. State NY Reg.no. 071638 CERTIHCATE OF COMPLIANCE conforms to the rules of construction of the ASME Code, Section m, Division 1. NPT Certificate of Authorization No. N-27Q3 Expires Date &/**/ 7 Mame GE Renter-Stoloes, Inc. INSPECTK CERnnGATE OP INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspedore and the State or Province of OHIO and employed bv H.&B. CF

of HARTFORD, CT r

ttPin<<Airrihed fatiria Date Rq>orton>

g>* -.0&i-£&crr.

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 m. Division 1. Each part listed has bem authorized for staihping to ok cUte shown above, By signing tins certificate, neither the inspector nor his <<mplover makes any warranty, expressed or implied/ concerning the; equipment described in this Data Report Furthennoie, neloW the inspector nor his employer ahajtt be Uabk in ar^ wanner for any personal injury or property damage or loss of any kind arisir^rrom or connected wiu% this inspection. Date r Page 16 of 25 WORK ORDER NUMBER: 13710 Report No.: PI059-016 16/3-058 FORM N-2 CERTinCATE 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 GE Reuter-Stokes. Inc.. 8499 Darrow Road. Twinsbure. Ohio 44087

{nameaod arfdn-u of NTT Ccrtltate Holder}

2. Manufactured for First Energy (name Bod mMna of Purchaser) 3.

Location of installation Perry Nuclear Power Plant 10 Center Road Perry. OH 44081

4. Type:

RS-E5-1210-2ffl <aBin<<mdiiildi<<B) N/A (*tewing no.)

5. ASME Code, Section m, Division 1; N/A

. no.) 1974 (ediliwi) (teniifcslrt*Afk) Winter 1974 (addenda dale) N/A Revision N/A 2005 (CRN) (yatrbuOl) N/A 6. Fabricated in accordance with Const Spec. (Div. 2 only) (n>>.)

7. Remarks:

Certified Desipn Specification CDS-O272AB152-1 N/A Dale (GxteCasen.) _N/A Certified Design Report CDR-C-5253-08 On File at GE Renter-Stokes, Inc.

6. Nom. Thickness (in.) __NZA_Min-design thickness fln.1 N/A Dia. ID (ft fe in.)

N/A Length overall (ft & irO N/A

9. When applicable, Certificate Holders' Data Reports are attached for each item of this report J-Part or Appurtenance Serial Number 0

04585851 (2) 04S85852 0) (4) (5) (6) (8) (9) ao) CI1) (12) (13) a*) (15) (16) (IT) 08) (19) (20) (21) (22) 23) 24) (25) National Board No. in Numerical Order N/A N/A Part or Appurtenance Serial Number (26) (27) (28) (29) (30) (3D (32) (33) 04) (35) (36) (37) (38) (39) (41! (42) (43) (44) (45) (46) (47) (48) (49) (50) National Board No. in Numerical Order Design pressure 1250 PSIG psi. Temp. Vessel 575T. Seal 300*7. Hydro, test pressure 1875 PSIG at temp. 70*F. MifcM)

• Supplemental information In the form of lists, sketdie^ or drawings way be used pn^ded(l)sizeis8>/axll((^infbnriaUoniniieim2mid3onthisDalaRcportit included on each sheet. (3) taeh sheet is numbered and Ihc imniber of 6heels Is recorded at the top of tins form.

(12/88) Thte form (B00M0) may b* obtained from the Order Dept, ASMS, 22 Lnw Drive, Box 230D,Falifidd,JQ<mU7>a30a. Page 17 of 25 ReportNo.:P1059-016 WORK ORDER NUMBER: 13710 /*> FORM N-2 (Back - Pg. 2 of 2) Certificate Holder's Serial Nos. N/A through N/A Imprint (7/91) Design specifications certified by Design report* certified by CERTIFICATION OF DESIGN Bill A Ralfl<< (when applicable) Ahmed I. Sabet P.E. State P.E. State (when applicable) Reg. no. Reg. no. MP348 071638 CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and that this (these) Assemblies conforms to the rules of construction of the ASME Code,Section III, Division 1. NPT Certificate of Authorization No. N-2703 Date Name GE Reuter-Stokes, Inc. Signed (NPTCertiftciUe Holder) . Expires September 16.2006 (wThoriwl npiacntolivc) CERTIFICATE OF INSPECTION u 1, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and State or Province of OHIO and employed by H.S.B. CT of HARTFORD. CT py y have inspected.these items described in this Data Report on ' 2 //> / 0 & _r ^ 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 m. 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 warrant)', expressed or nnplied, concerning Jhe 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. Signed A/X^i^ Commissions . (Ind. undoreemenls) and <<tat>> or prey. >nd no.l Page 18 of 25 Report No.: PI059-016 1B13-060 NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As required by the Provisions of the ASME Code Section XI NOP-CC-5703-04 Rev. 01 1. Owner: 2. Plant: FirstEnerov Nuclear Generation. LLC 76 South Main Street. Akron OH 44308 Perrv Nuclear Power Plant (PNPP) 10 Center Road. Perry. Ohio 44081 Date 01/18/2016 Sheet J of Unit ONE 200326644 3. Work Performed By: FirstEnerov Nuclear Operating Company PNPP 10 Center Road. Perrv. Ohio 44081 4. Identification of System: PY-1B13. REACTOR AND INTERNALS (Repair Org. P.O. No., etc.) Type Code Symbol Stamp NR Authorization No. 33 Expiration Date 9-28-2017 5. (a) Applicable Construction Code: ASME SECTION III CLASS 1 NAME/SECTION/DIVISION/CLASS 1974 Edition WINTER 1975 Addenda Code Case(s)

• 1728.1644-4. N-272 (b)

Construction Code used for repairs, modifications, or replacements: 1974 Edition W/75 (c) ASME Code Section XI applicable for Inservice Inspection: 2001 Addenda 2003 Edition Addenda (d) Applicable Edition of Section XI Utilized for Repairs, Modification, or Replacements: 2001.EDITION 2003 Addenda N/A Code Case(s) N/A Code Case(s) (e) Design Responsibilities FENOC Code Case(s) 6. Identification of Components Repaired, or Replacement Components Name of Component PIPING SYSTEM Name of Manufacturer GE Manufacturer Serial No. 1B13 Nat. Board No. 64077 Other ID. N/A Year Built 1984

Repair, Replacement REPLACEMENT ASME Code Stamped (Yes or No)

YES 7. Description of Work: 1B13D0008. REPLACED CONTROL ROD DRIVE CORE LOCATION MECHANISM A-4643 WITH REBUILT CRDM A-4063 AND INSTALLED (8) NEW 1" SA540 CAP SCREWS. 8. Test Conducted: Hydrostatic-Pneumatic-Pressure 1038 psi Test Temperature 118 Nominal Operating Pressure- ^ Other-degrees F CodeCase(s) N/A Page 1 of2 Page 19 of 25 Report No.: PI059-016 NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As required by the Provisions of the ASME Code Section XI NOP-CC-5703-04 Rev. 01 9. Remarks: NO NAMEPLATE/STAMPING PERFORMED DUE TO THE INTERFACE CONTROLS OF PART 3 SECTION 1.8.6 BEING IN EFFECT AND JURISDICTIONAL AUTHORITY CONCURRENCE HAVING BEEN RECEIVED. Note: Attach all applicable Manufacturer's Data Reports. Supplemental sheets such as lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded on the front of this form. CERTIFICATE OF COMPLIANCE '. TOBIAS J KOSTNER 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 Date 01/18 20 16 Signed FENOC-PNPP (name of repair organization) p expires 28 SEPT 20 17 SR NUC ENG SPEC. rized representative) (title) I. THOMAS G. LAPS CERTIFICATE OF INSPECTION/INSERVICE INSPECTION .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 The Hartford Steam Boiler Inspection and Insurance Company of Connecticut have inspected the repair, modification or replacement described in this report on JAVL <*P20 \\(o and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from or connected with this inspection. Date 6\\ (3k, 20 ife Signed \\ \\\\*tvuj*J ^KrAfcjQ^Commissions RS 933<£ l4 X /V (inspector) (National Board (include endorsements), andjurisdiction, and no.) Page 2 of 2 Page 20 of 25 Report No.: PI059-016 Report No.: PI059-016 tteflta 4-<8 tnct..fo be cbtnpieirdV f<<* whj^l* 'w<<Jf **f iWiHa, lacktfs.pi' ipvkctcd y.e**eli, o>> -h<<HJ>> ol h*>>< *rch>>i>>"f<<erf'. Girth 6. If 7.

• 8.

T.-S,: ,. bol ta ^ 9 and lO.rt0 b* 9. 'Tub* SKect: (Kind

• 10.

Tube<<: hi.

• <<>>>>**)>>

<<>> V) ll-U'inleL <<* be kro<<!ll>l<<<<<<d for inner <<cs'*el'f,' or eh(uin<<lj of fcc<< 11. SKell: M<<iefi<<l. -T.J5* ^_ Srims: Qirth. R..T. R.t. Efficiency^ u No. p( C .T.S; LscMlmi

Top, bo<<ofi>>,

Crewip ComciM-(f remotr*i>>ie, boll-* uacd (*). .ff. .55 below ro be.vofnpleted. fot <<1l vciitls.-where ijppiicabie ?L Safety VaWe Outlet ai Nunvber. Location. I*. u(4*f.' T t?. In-tpeciion Manholes*. No,', Thfeade^, "V**- (8. Supportt: t.u<<>> Vi*e.__i. <<Lf Location _L_ Page" 22 of25 Report No.: PI059-016 ReportNo.:P1059-016 1E51-167 NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As required by the Provisions of the ASME Code Section XI NOP-CC-5703-04 Rev. 01 1. Owner: 2. Plant: FirstEnerqy Nuclear Generation. LLC 76 South Main Street. Akron OH 44308 Perrv Nuclear Power Plant (PNPP) 10 Center Road. Perrv. Ohio 44081 Date 10/02/2015 Sheet 1 of 1 Unit ONE 200389590 3. Work Performed By: FiretEneroy Nuclear Operating Company PNPP 10 Center Road, Perrv. Ohio 44081 (Repair Org. P.O. No., etc.) Type Code Symbol Stamp NR Authorization No. 33 Expiration Date 9-28-2017 4. Identification of System: PY-1E51. RX CORE ISOLATION COOLING v 1974 Edition 1975 Addenda Code Casefe)

• 1644-5.1728.N-224.N-241.N-242.N-272.N-275.

5. (a) Applicable Construction Code: ASME SECTION III CLASS 2 NAME/SECTION/DIVISION/CLASS WINTER N-413 (b) Construction Code used for repairs, modifications, or replacements: 1974 Edition W/75 2001 Addenda 2003 (c) ASME Code Section XI applicable for Inservice Inspection: Edition Addenda (d) Applicable Edition of Section XI Utilized for Repairs, Modification, or Replacements: 2001.EDITION 2003 Addenda N/A Code Case(s) N/A CodeCase(s) (e) Design Responsibilities FENOC Code Case(s) 6. Identification of Components Repaired, or Replacement Components Name of Component PIPING SYSTEM Name of Manufacturer PULLMAN POWER Manufacturer Serial No. 1E51 Nat. Board No. 84 Other ID. N/A Year Built 1985

Repair, Replacement REPLACEMENT ASME Code Stamped (Yes or No)

YES 7. Description of Work: 1E51H2074. REPLACE EXISTING PSA 1/4" SNUBBER fS/N 34879) WITH NEW PSA 1/4" SNUBBER fS/N 44139). 8. Test Conducted: Hydrostatic-Pneumatic-Nominal Operating Pressure-Other-Pressure N/A psi Test Temperature N/A degrees F Code Case(s) N/A Page 1 of 2 Page 24 of 25 Report No.: PI059-016 NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As required by the Provisions of the ASME Code Section XI NOP-CC-5703-04 Rev. 01 9. Remarks: NO NAMEPLATE/STAMPING PERFORMED DUE TO THE INTERFACE CONTROLS OF PART 3 SECTION 1.8.6 BEING IN EFFECT AND JURISDICTIONAL AUTHORITY CONCURRENCE HAVING BEEN RECEIVED. Note: Attach all applicable Manufacturer's Data Reports. Supplemental sheets such as lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded on the front of this form. CERTIFICATE OF COMPLIANCE I, TOBIAS J KOSTNER 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. Date alB 25 33 20 Signed FENOC-PNPP (name of repair organization) expires 28 SEPT 20 17. SR. QUALITY TECH representative) (title) CERTIFICATE OF INSPECTION/INSERV1CE INSPECTION I, THwUS G. LAP_S .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 STP>>. of -lUKTfp Kb have inspected the repair, modification or replacement described in this report on OCT. 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. A Date lOj'X . 20 [£" Signed \\r*ru4 (National Board (include endorsements), andjurisdiction, and no.) Page 2 of 2 Page 25 of 25 Enclosure B L-17-072 Form OAR-1 Owner's Activity Report (Activities performed 5/19/2016 through 4/03/2017) (2 Pages Follow) Report No.: PI 059-016 FORM OAR-1 OWNER'S ACTIVITY REPORT Report Number Plant P1059-0016, Perry Nuclear Power Plant, J 0 Center Road, Perry, OH 44081 Unit No. 1 Commercial service dale November 18,1987 Refueling outage no. 1R16 Third (irappEcsble) Current inspection interval Current inspection period (1st, 2nd73rd) Edition and Addenda of Section XI applicable to the inspection plans 2001 Edition through 2003 Addenda (1st, 2nd, 3rd. potter) Second Date and revision of inspection plans Inservice Examination Plan (1SEP) Revision 17 dated 2/5/15 and Revision 18 dated 11/18/16 Edition and Addenda of Section XI applicable to repair/replacement activities, if different than the inspection plans N/A Code Cases used for inspection and evaluation: The following are permitted by the 1SEP-. N-461-1, N-S13-3, N-S26, N-528-1 (if applicable, including cues modified by CsseN-532 and later revuions) N-532-S, N-S37, N-552, N-S61-2, N-562-2, N-566-2, N-S78, N-586-I.N-613-1, N-624, N-648-1. N-652-1. N-658, N-661-2, N-663. N-664. N-665.N-666, N-683, N-68S, N-695, N.700, N-705, N-716-1, N-73S, N-747 CERTIFICATE OF CONFORMANCE 1 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) the repair/replacement activities and evaluations supporting the completion of Conform to the requirements of Section XI. Signed (refudine ouiaee number) CERTIFICATE OF INSERVICE INSPECTION [, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and employedby grt^eam Boiler Inspection and Insurance rf ^^ ^ having fflSpected ^ items dcscribcd in ^ Owner's Activity Report, and state that, to the best of my knowledge and belief, the Owner has performed all activities represented by this report in accordance with the requirements of Section XI. By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning die repair/replacement activities and evaluation described in this 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 connect with this inspection. Commission kIR<3^1FS kL X A (National Board Number and Endorsement) Date (06/11) Page 1 of 2 Report No.: P1059-016 TABLE 1 Items with Flaws or Relevant Conditions That. Required Evaluation for Continued Service Examination Caiegory and Item Number None Item Description N/A Evaluation Description N/A TABLE 2 Abstract of Repair/Replacement Activities Required for Continued Service Code Class 1 3 3 2 ] I 1 3 2 2 3 3 2 3 Item Description Pipe Support 1E12-H0739 Snubber 1G33-H0147 Flexible Hose 1B21-D0030C Snubber 1E12-H0280 Bolting hardware 1B13-N8-B Bolting hardware 1B13-0168-B Bolting hardware 1E51-0001-B Flexible Hose 1E22-D5013A Valve 1G33-F0039 Valve 1P51-F0530 2" Threaded Flange Valve 1G33-F0032 Support 1 El 2-H0121 Flexible Hose IE22-D5013A Description of Work Replace U-Bolt and nuts Replace snubber due to failed function test Replace flexible hose to SRV due to air leakage Replace snubber due to failed function test Replaced hardware due to damage during removal Replaced hardware due to failure to perform VT-1 during prior outage Replaced hardwaie due to damage during removal Replaced damaged flexible hose due to air leakage Replaced stem and gate Replace check valve with one with stainless internals Replaced flange with new due to air leakage Replaced valve with new Replaced support bolts higher strength bolts Replaced flanged connection to flexible hose due to air leakage Date Completed 3/23/17 3/23/17 3/28/17 3/17/17 4/1/17 3/15/17 4/1/17 9/11/16 4/3/17 3/29/17 6/27/16 3/29/17 3/26/17 5/12/16 Repair/Replacement Plan Number 200647792 200709856 200709841 200646511 200664434 200670394 200664434 200691719 200636659 200638222 200640995 200559380 200708094 200682438 Page 2 of 2