ML20115D696
| ML20115D696 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 06/20/1996 |
| From: | Cobb D CENTERIOR ENERGY |
| To: | |
| Shared Package | |
| ML20115D690 | List: |
| References | |
| NP0059-0005, NP59-5, NUDOCS 9607150235 | |
| Download: ML20115D696 (587) | |
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PERRYHCIEARP0MPIANI PNPP RFO-5 KEYS TO SUCCESS f ? Communication h" 6 Accountability %
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The Cleveland Electric illuminating Co.
Perry Nuclear Power Plant Unit 1
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ISI Summary Report . . . No. NP0059-0005 Results for Outage 5 (1996) Third Period, First Interval
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Page 1 of 2 FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS i As required by the Provisions of the ASME Code Rules
- 1. Owner Cleveland Electric Illtatnating Canpany, P.O. Box SU10, Cleveland. 01 44101 (Name and Address of Owner)
Perry Nuclear Power Plant, 10 Center Pd., Perry, 01 44081
- 2. Plant (Name and Address of Plant) l I 4. Owner Certificate of Authorization (if required) N/A
- 3. Plant Unit
- 5. Commercial Service Date II/I8/87 6. National Board Number for Unit N/A
- 7. Components inspected (Class I and 2)
Manufacturer Manufacturer or Installer National l Component or or installer Serial No. FNPP MPL No. Board No.
Appurtenance Rx Vessel CE/CBIN T-49 IBl3 15 Rx fesse'l' GE/MES - IBl3 IBl3 64077 Nuclear-- * ,
IB21 IB21 64084 l Boiler System GE/MES l Nuclear IB21 1821 109 Boiler System Pull =n Power Prndirts Reactor IB33 IB33 64076
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m Recire. System GE/MES V Reactor Recire. System Pn11=n Power Prnerets 1B33 IB33 119 CRD Hydraulic ICi1 92 Control System Pn11=n Power PrMrts IC11 Low Pressure IE21 85 Pit 11mnn P nw r Pendime c IP '1 1
' Core Sorav Residual Heat IE!2 IEl2 83 Re m val System Pullmn Power PrMets High Pressure IE22 lE22 86 Core Sprav Pull = n Power Prndi_ets IESI lE51 84 RCIC System Pu11msnPcwrProducts i
IG33 IG33 64075 FWCU System CE/MES IG33 IG33 100 RWCLI System Pull =n Power Prndirts Leak Detectioa 1F31 15 System Johnson Controls IE51-OO68-F INII INII i1i Main Steam Pull =n Power PrMets IN77 IN77 M Feedwater System Pulltrnn Power Prodtets Note. Supplemental sheets in form of lists, sketches, or drawmgs may be used, provided (1) size is 8% m. x il m..
h (2) mformation in items I through 6 on this report isincluded on each sheet, and (3) each sheet is numbered and the nmnher of sheets is recorded at the top of this form.
(12/86) This Form (E00029) may ne otatainea f rom tne Order ocot.. ASME 345 E. 47th St.. New York, N.Y.10017
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FORM NIS-1 (Back)
- 8. Examination Dates _0SLL4/94 to 04/10/96 9. Inspection interval from _n/JR/R7to !!/17/47
- 10. Abstract of Examinations. Include a list of examinations and a statement concerning status of work required for current interval.
Cee attached sununary report NP0059-0005*
- 11. Abstract of Conditions Noted.
See attachedosununary report NP0059-0005*
- 12. Abstract of Corrective Measures Recommended and Taken See attached summary report NP0059-0005*
- Report is 37 4 pages in length.
We certify that the statements made in this report are correct and the examinations and corrective mea-sures taken conform to the rules of the ASME Code,Section XI.
Certificate of Authorization No.(if applicable) N/A Expiration Date N/A _
Date ## 19 b signed CEI gy jr .
WD Alternate for Don Cobb CERTIFICATE OF INSERVICE INSPECTION 1, the unde'siped, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of nhin and employed by ArkwriRht Mutual . Ins , of Norwood, MA have inspected the components described in this Owner's Report during the period 08/14/94 to 04/10/96 . 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 this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personalinjury or property damage or a loss of any kind arising from or connected with this inspection.
owie Q
Nemu 2 - MM Commissions NB-9330 Ohio 1 4 cc4g, National Board, State, Province, and Endorsements Inspector's Siyature Date )UdC ll 19 'h (12/82)
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l FORM NIS-1 OWNER 3 REPORT FOR INSERVICE INSPECTIONS '
As required by the Provisions of the ASME Code Rules
- 1. Owner _ Cleveland Electrie Tiluminating-Co P-.O._ Box _5000, 41eveland,_.OR 44101 (Name and Address oIOwner)
- 2. Plant Perry Nuclear Power Plant, 10 Center Rd., Perry,':0H 44081 0
(Name and Address of Plant) l 3. Plant Unit 1 4. Owner Certificate of Authorization (if required) N/A l 5. Commercial Service Date 11/18/87 6. National Board Number for Unit N/A a l
- 7. Components inspected (Class 1 and 2) d Manufacturer Component or Manufacturer or Installer National
, Appurtenance or Installer Serial No. PNPP MPL No. Board No.
Integrated i Leak Rate Sys Pullman Power Products IE61 IF61 17A
! Penetration 737,738 Press. Sv d ~ Wo61v 743.744 1P53 717 Fire Protection
- System Pullman Pnwer Prnd. IP54 199& 7A l Main, Reheat j Misc. Drain Pullman Power Products IN22 IN22 112
- Nuclear Closed I Cnnling Ryn Pullmnn Pnwar Prndnere IPA 1 1DAt 101 1
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REPORT NO. NP0059-0005 O
INSERVICE INSPECTION SUbMARY REPORT FOR PERRY NUCLEAR POWER PLANT (PNPP)
UNIT #1 LOCATED AT: 10 Center Road Perry, Ohio 44081 OWNER: The Cleveland Electric Illuminating Company P.O. Box 5000 Cleveland, Ohio 44108 O
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: 1205 COMMERCIAL OPERATION DATE: November 18, 1987 INS 1SCTION INTERVAL: November 18, 1987 - November 17, 1997 INSPECTION PERIOD: Third (August 14, 1994 - November 17, 1997)
REFUELING OUTAGE: RFO-5 DOCUMENT COMPLETED: June 20, 1996 O
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REPORT NO. NP0059-0005 O
{ ABSTRACT i
PNPP Unit #1 was shutdown for approximately ten weeks to refuel the reactor vessel (RFO-5) and perfonn plant naintenance commencing January 27, 1996. During this time period, inservice examinations were performed to comply with plant Technical Specifications and the 1983
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Edition of ASME Section XI including Addenda through the Summer 1983.
i ASME Section XI requires reporting of examination results for Class 1 l and 2 pressure retaining components and their supports. This report summarizes the results of examinations performed on Class 1, 2, 3 and augmented pressure retaining components and their supports as listed in the PNPP Inservice Examination Program (ISEP, Operations Manual OM7D).
Successive examinations were performed on flaws within two feedwater
! nozzle inner radii and two feedwater nozzle to safe-end welds. The i
nozzle inner radii flaws, reported and evaluated as acceptable for continued service in RFO4, were determined to be non-relevant indications. The nozzle to safe-end flaws, found in RF02 and mechanically stress improved in RF03, were found to be essentially unchanged.
In-vessel examinations consisted of the required code examinations along with augmented examinations of the core spray piping and headers, jet
- pump assemblies, separator shroud head stud bolts, and the access hole 4 cover. In accordance with the Boiling Water Reactor Vessel and Internals Project (BWRVIP) inspection guidelines, Perry was still a
- category A plant for RF05 and thus no core shroud examinations were
! performed. No in-vessel problems were found.
i component support examinations resulted in 3 nonconformance reports. 1 of the nonconformance reports was dispositioned as operable and "use-as-is" and the other 2 were dispositioned as operable with rework to be performed. Of the 3, 2 did not meet ASME XI acceptance criteria.
, Additional examinations of similar component supports did not identify any further problems.
) Other than described above, there were no reportable indications.
RFO-5 examinations completed approximately 55% of those examinations j scheduled for the third inspection period. The remaining period three l j examinations will be completed by the end of RFO-6. The RFO-5 l i examinations resulted in a complete and acceptable program in that all j indications were evaluated for acceptance in accordance with ASME Section XI, IWA-3000 and all required corrective actions and/or j evaluations were completed.
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REPORT NO. NP0059-0005 CONTENTS i
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1.0 INTRODUCTION
4 2.0 RE FUELING OUTAG E DU RAT; 94 ------------------------ ------------ l i l i
i 3.0. CODE REQUIREMENTS --------------------------------------------- 4 l
1 4.0 INSPECTION ---------------------------------------------------- 4 5.0 CERTIFICATIONS ------------------------------------------------ 4 1
5.1 Personnel ----------------------------------------------- 5 5.2 Equipment and Materials --------------------------------- 6 Thermometers ------------------------------------------ 6 Magnetic Particle Equipment --------------------------- 7 Magnetic Particle Materials --------------------------- 7 Dye Penetrant Materials ------------------------------- 7 I Ultrasonic Flaw Detectors ----------------------------- 7 Ultrasonic Couplants ---------------------------------- 7 Transducers ------------------------------------------- 7 6.0. CALIBRATION STANDARDS ----------------------------------------- 9 7.0 PROCEDURES AND INSPECTION PLANS-------------------------------- 9 8.0 RELIEF REQUESTS ----------------------------------------------- 10 9.0 SCHEDULE CHANGES ---------------------------------------------- 12 10.0. EXAMINATION
SUMMARY
RESULTS ---------------------------------- 13 11.0 NIS-2/NR-1 ---------------------------------------------------- 14 APPENDIX A. RFO-5 EXAMINATIONS RESULTS
SUMMARY
19 APPENDIX i
B. NIS-2/NR-1 FORMS ------------------------------------------ 124 i 1
LAST PAGE ---------------------------------------------------------- 374 i
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REPORT No. NP0059-0005
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1.0 INTRODUCTION
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The information provided herein is supplied to document compliance with ASME B&PV Code,Section XI requirements for reporting inservice l inspection results for Class 1 and Class 2 pressure retaining components 1 and their supports. Examination results of Class 3 components and their I associated supports are included in this report as supplemental information.
This report covers those inservice inspection activities commencing with PNPP's return to commercial operation after RFO-4 until the completion of RFO-5.
Included in this report are the following:
- Personnel and Equipment Listings
- Examination Results Summaries
- NIS-2/NR-1 Reports
- Other Pertinent Information 2.0 REFUELING OUTAGE DURATION The Perry Nuclear Power Plant, Unit #1, was shutdown for RFO-5 from O. January 27, 1996 to April 10, 1996. The plant returned to commercial operation on April 10, 1996 at 10:00 am. This is noted as the time when l the generator was synchronized to the grid. l 3.0 CODE REQUIREMENTS The inservice inspections were conducted in accordance with the requirements of ASME B&PV Code,Section XI, Division 1, 1983 Edition including Addenda up through and including Summer 1983 with Code cases N-235, N-356, N-408-2, N-416-1, N-429-1, N-435-1, N-448, N-457, N-460, N-461, N-491, and N-498.
4.0 INSPECTION Inspection activities were conducted by Authorized Nuclear Inservice Inspection personnel from Arkwright Mutual Insurance Company, Factory Mutual Engineering Association.
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 RFO-5. Certification records for personnel and equipment are g~ kept on site and are available for review.
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REPORT NO. NP0059-0005 5.1 Personnel NDE personnel were qualified and certified to perform specific non-destructive examinations in accordance with PNPP or approved vendor procedures as verified by the Quality Assurance Department 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 RFO-5:
-: Name -- PIN UT/ PT- MT- VT.
Anderson,< M.- A7814- NA? NA- NA- II++'
Andrie, B. A3521 NA NA NA II Bausmer,zF. B4655- NA NA- NA -II -
Bazenas, J. B5937 NA NA NA II++
Bowne, L. B2228 II** II- NA :- NA Bowser, J. B6441 NA NA NA II Breza, J. B4612 NA' II I -- :NA -
Briggs, J. B7695 NA NA NA III Catron,:E. 'C8297 III** NA- nae NA-Carson, J. C2679 NA NA NA II Clement s , - - J . C4889' NA- NA NA- II+-
Congos, C. C2693 NA NA NA II coyne, B. C5616 NA- NA - NA: II-Crane, M. C9831 II** NA NA NA g Crom, K. C6225- NA- NA- NA II
- DeLuna, C. D0960 II Donley, M. D5392' II- NA NA- - NA-Dummer, B. D6288 III NA NA NA Erbacher, L. E0936 NA- NA - NA- II-Ewing, J. E5521 II III III II Graham, D. G0809 NA- NA ' NA -II+-
Hamrr.nt r e e , S. H5445 II** II II NA Hang, D. H4619 NA' NA - NA- II.
Harris, S. H8634 NA NA NA II Heath,-M. H6465- III**- III: III -- III Hewitt, W. W1105 NA NA NA II+
Hinnebusch, R .' H2414- NA. NA NA' II H8104 Hofer, T. NA NA NA II++
Huskey, T. H6695- NA II II II Hutton, S. H9952 NA NA NA II+
Jopko, S. J9965- NA NA NA -- II Knopsider, D. K2975 NA NA NA III Kozlowski, E. K0626- NA- NA- NA- II' Laws, J. L8885 NA NA NA II++
Locklers K. L1105 -- II -- NA- NA. NA --
Lynch, N. L3427 NA NA NA II+
McIntyre, D. -M5609- NA- NA- NA -II+'
McCool, C. M0960 I II II NA Moore, D. M8891 II II II NA Moore, D. M4779 NA NA NA II Neville, K. N7937 II** II II II O' Bannon, T. 08017 II NA NA NA Page 5
REPORT NO. NP0059-0005 1
NDE Personnel Continued
- Name -- PIN UT -PT MT- VT Phillips, A. .P7919> NA- NA NA< 7. I+ -
Price, D. P4886 NA NA NA II I Price,-J. .P6724- NA :- II II- ~ II:. j Portmann, R. P6096 NA III III III ;
l Sellers,'J. -S6468- NA- II- NA- II Richardt, J.
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l RS641 NA NA NA II+
Robideau,:K. - R 4168 >
NA NAx NA: II++
Seman, S. S6347 NA NA NA II+ i Sharlow,: M.- S2379:- NA: NA NA II++= '
Shamblin, P. S9339 II** NA NA NA Sholtis, P. S9441o nae NA, NA- II-Swartz, R. S5034 NA NA NA II+
Trotter,>E. :T2289- II * * -- II: II. NA-Thomas, D. T9854 NA NA NA II++ i Thomas,-N. T3074 NA -- NA - NA9 I I .- l Wirtz, C. W9385 NA NA NA III
+ - Limited to VT-2 only
++ - iimited to in-vessel VT-1 and VT-3 examinations only
- - EPRI registered personnel for manual and/or automated UT of IGSCC 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 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 RFO-5:
THERMOMETERS
' Manufacturer- Model No. -PNPP-M&TE No. !
OMEGA 450: Digital L70M019D-OMEGA 450 Digital L70M019E OMEGA 450 Digital L70M019F OMEGA 450 Digital L70M019H l OMEGA. 450 Digital .L70M019J l OMEGA 450 Digital L70M019K OMEGA 450 Digital sL70M019M OMEGA 450 Digital L70M019Q O
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.. . s.-..n- ~ -.u- ,..un +a.a---- ~ ws . ~ . - - - ~ . .u -- . . . , ,
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REPORT NO. NP0059-0005 O ' Manuf acturer --
MAGNETIC PARTICLE EQUIPMENT Model No. GE Ser/PNPP M&TE No.
.Magnaflux .Y-6 AC Yoke' -PAR-ACMT-023 - 5156-Magnaflux Y-6 AC Yoke PAR-ALW -026 - 5365 ,
-Spectraline- UV-Meter- -L700321C: :1 l
MAGNETIC PARTICLE MATERIALS
--Manufacturer - Type- - Batch No .
'Magnaflux 8A Red Powder: 92A052 ,
l Magnaflux 3A Black Powder 95LO66 Magnaflux- -Magnaglo.'14AM- 94C02P' DYE PENETRANT MATERIALS
-Cleaner ' Penetrant- Developer-1 SKC-S 94B03P- SKL-SP- :93G02K? SKD-32.94C10K-SKC-S 95F14K ULTRASONIC FLAW DETECTORS
- Manuf acturer -- - Model:- Serial No. I Krautkramer- .USK-7: 27276-4950-Krautkramer USK-7 27276-4940 Stavely- .. SONIC-13 6 - :781J: j Stavely SONIC-136 788J -
Stavely : SONIC-136- 7661-Stavely SONIC-136 717H Tecrad Tomoscan. TTS10091108*-
Kinetic Systems CAMAC Crate 1502-310 2-2213**
- - GE's "GERIS 2000" Automated Nozzle Examination System l l
ULTRASONIC COUPLANTS
-Manufaeturer Type: Batch No.
-Echo Ultrasound- Ultragel II- :092031-Echo Ultrasound I Ultragel II 8981 TRANSDUCERS Manufacturer Type Size Angle Freq. Ser No.
KB Aerotech- MSEB2 10mm Dia. .co. '4:MHz 00984-KB Aerotech Gamma .25" Dia. 45o 2.25 MHz 016543 KB Aerotech. Gamma. .25":Dia. -45': 2.25 MHz B03420 KB Aerotech Gamma .5" Dia. 45o 2.25 MHz C28119 l
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REPORT NO. NP0059-0005 l i
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v TRANSDUCERS CONTINUED Manufacturer: .Typer : Size' . Angle 'Freq. Ser No.
KB Aerotech-> Gammac .75">Dia. oo: .5 MHz.. E25310.
KB Aerotech Gamma .375" Dia. 00 2.25 MHz F12230 KB Aerotech Gamma- .75" Dia. 0o: 2:.25 MHz; K27306 KB Aerotech Gamma .25" Dia. 45o 2.25 MHz LO5759 KB:Aerotech:- . Gamma .- ..5" Dia. 45',600. .2.25 MHz?
M17325-
' & 7 0* :'
Megasonic MST .375" Dia. 45o 2.25 MHz D0217 Megasonic MSTa -.375" Dia.; 45'&600- 2.25 MHz. D0915:
Megasonic MST .375" Dia. 45o 2.25 MHz D0916 Megasonic- MST- . 3 7 5" : Di a . ':: '600- 2.25 MHz-: E03597 Megasonic CGD 2(14x30)mm 45'RL 4.0 MHz E0525 ;
Harisonic: CM- .5":Dia.: 00: 10 MHzc 96A043;
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Harisonic DUAL .25"x.5" 45'RL 2.25 MHz K7218 )
Panametrics Allis .5"_Dia. Oo- 10.MHz 207286 I RTD* T1-St 32x22 mm 45o 1.0 MHz 94-111 )
RTD* T1-St, '32x18 mm. 600 1.0 MHz: 94-113- I RTD* L2.25 1.0" Dia. oo 2.25 MHz 94-507 '
RTD*. : T2-St 1 32x16 mm 65 : 2 . 0 MHz;95-189; RTD* T2-St 32x16 mm 65o 2.0 MHz 95-190 RTD*- T2-St -32x16:mm 680- 2.0 MHz.95-193' s RTD* T2-St 32x16 mm 68o 2.0 MHz 95-194 KB Aerotech*- Gamma- .5"x1.0" :60',6707 2.25.MHzc- H14165-
-& 70' KB Aerotech* Gamma .5"x1.0" 60',67o 2.25 MHz H14166
& 70' KB Aerotech* Gamma: .75" Dia. 21'.2o- 2.25-MHz- M22817.
KB Aerotech* Gamma .75" Dia. 21.2o 2.25 MHz M22819 KB Aerotech*-- Gammac .75".Dia.- 28,40 :2.25 MHz- M22821 KB Aerotech* Gamma .75" Dia. 28.40 2.25 MHz M22822 KB Aerotech** Gamma: .5x1.0"- -
70o.: 2.25 MHz. E09400 KB Aerotech** Gamma 1.0" Dia. oo 2.25 MHz E13607 KB Aerotech** Gamma-- . 5x1. 0" - 44o 1.0 MHz- M21322..
KB Aerotech** Gamma .5x1.0" 58o 1.0 MHz M21323 KB Aerotech**- Gamma- .5x1.0" 60o 2.25 MHz D23456 RTD+ TRL2 2(10x18)mm 60 RL 2.0 MHz 88-258 RTD+ TRL2 2(10x18)mm 4 5*RL 2.0 MHz: 88-272-RTD+ TRCr2 2(10x15)mm ODCR 2.0 MHz t0-282 RTD+ TRL2- -12x22mm :60o 1.0 MHz 93-416 KB Aerotech+ Gamma .5" Dia. 45'S 2.25 MHz 0014PD
- - Transducers used for "GERIS" automated nozzle exams.
- - Transducers used by "GERIS" group for manual nozzle exams.
+ - Transducers used for " SMART" automated safe-end exams.
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REPORT NO. NP0059-0005 O 6.0 CALIBRATION STANDARDS l
V l Ultrasonic during RFO-5calibration standards are as listed below: used for ISI related work activities CALIBRATION STANDARD IDENTIFICATION NUMBERS PY-4-XX1-SS PY-12-120-CS PY-20-40-CS PY-6-80-CS PY-NUT-1-RPV-A PY-12-CLAD-SS PY-20-80-CS PY-STUD-1-RPV-A PY-6-120-CS PY-12-PEN-CS PY-20-120-CS PY-SE-BI-l PY-6-XX1-CS PY-12-STD-CS PY-24-40-CS PY-SE-BI-3 PY-8-100-CS PY-12-XX1-SS PY-24-STD-CS PY-SE-BI-4 PY-10-80-CS PY-14-XX1-CS-F PY-26-80-CS PY-SE-BI-5 PY-10-100-CS PY-16-100-CS PY-26-XX1-CS PY-VALVE-XX1-CS PY-12-40-CS PY-16-100-SS PY-124-1-RPV PY-12-80-CS PY-VALVE-XX2-CS PY-18-40-CS PY-127-1-RPV PY-12-100-CS PY-18-STD-CS PY-128-1-RPV 7.0 PROCEDURES AND INSPECTION PLANS The examination procedures and inspection plans used during RFO-5 were as follows:
Number l Rev. l Title Perry NDE Procedures:
NQI-0941 6 Liquid Penetrant Examinations NQI-0942 5 Magnetic Particle Examinations
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/N NQI-1042 NQI-0944 6
5 Visual Examinations (VT-1,2,3)
Ultrasonic Examinations Inspection Plans used with NOI-0944:
NDE-008 4 Manual Ultrasonic Examinations of Piping Welds NDE-017 3 Ultrasonic Examination of Corrosion Resistant Clad (CRC) and Dissimilar Metal Piping Welds NDE-018 4 Ultrasonic Examination of Stainless Steel (Austenitic) Piping Welds for Intergranular Stress Corrosion Cracking NDE-019 2 Ultrasonic Examination of Flued Head Penetration Attachment Welds NDE-020 0 Ultrasonic Examination of Reactor Pressure Vessel (RPV) Nut Threads and Flange Threads NDE-030 0 Manual Ultrasonic Examination of Valve Body Welds GE Inspection Service NDE Procedures:
UT-PER-105VO O Procedure for Manual Ultrasonic Examination of VT-PER-206VO Dissindlar Metal Nozzle to Safe-end Welds O
Procedure for Invessel Visual Inspection (IVVI)
UT-PER-207VD for BWR6 Reactor Pressure Vessel Internals 0
Procedure for Automated (SMART 2000) Ultrasonic Planar Flaw Sizing UT-PER-209VO O Procedure for Automated Ultrasonic Examination of UT-PER-300VO Dissimilar Metal Nozzle to Safe-end Welds O
Procedure for Manual Examination of Reactor Vessel Assembly Welds UT-PER-307V1 0 Procedure for Ultrasonic Examination of Pressure Retaining Bolting Greater Than 4" in Diameter 7~, UT-PER-311VO O t a Procedure for Manual Ultrasonic Examination of L/ Nozzles Inner Radius and Bore Regions l
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REPORT NO. NP0059-0005 Procedures Continued
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Number l Rev. l Title-Perry HDE Procedures:
UT-PER-702VO 0 Procedure for GERIS 2000 Ultrasonic OD Examination 1 of RPV Assembly Welds '
UT-PER-703VO O Procedure for the GERIS Ultrasonic Examination of RPV Nozzle Inner Radius and Bore Regions 8.0 RELIEF REQUESTS Due to geometric, metallurgical, and physical limitations, some of the items scheduled for examination during RFO-5 received partial or no examinations. Within the limitations, examinations were completed to the greatest extent practical.
Where it has been determined that conformance with ASME Section XI code requirements is impractical, PNPP requested relief from the examination requirements.
Prior to RFO-5, relief requests IR-001 through IR-015 and IR-018 through IR-027 were submitted to, and approved by, the NRC. As a result of RFO-5 examinations, it was necessary to revise relief requests IR-05 and IR-021. The revisions add or delete components to the tables within the relief requests. The basis for relief is the same as that for the previously identified components. In anticipation of the close out of the first ten year interval exams in RFO6, two new relief requests have js been generated. The revised and new relief requests have been submitted
( ,) to the NRC. Additionally, with the use of Code Case N-491, relief request IR-022 is no longer necessary and is being withdrawn.
The following listing summarizes the relief requests submitted to date:
RR NUMBER SYSTEM TYPE RELIEF CATEG. ITEM NO.
IR-001 R-1 Reactor Pressure Vessel Partial Exams B-A Bl.21 B1.22 Bl.40 B-D B3.90 B3.100 B4.11 B-F B5.10 IR-002 R-0 Reactor Recirculation Partial Exams B-G-1 B6.180 IR-003 R-0 Reactor Pressure Vessel Partial Exams B-G-1 B6.40 IR-004 R-1 Main Steam Partial Exams B-J 39.11 Residual Heat Removal B9.12 High Pressure Core Spray Reactor Recirculation IR-005 R-1 Reactor Recirculation Partial Exams B-J B9.11 IR-006 R-0 Reactor Recirculation Partial Exams B-J B9.12 O
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1 REPORT NO. NP0059-0005 l
i RELIEF REQUESTS CONTINUED RR NUMBER SYSTEM TYPE RELIEF CATEG. ITEM NO.
IR-007 R-0 Residual Heat Removal Partial Exams B-K-1 B10.10 Low Pressure Core Spray l High Pressure Core Spray Reector Core Isolation-Cooling ;
Feedwater Reactor Water Cleanup Main Steam )
IR-008 R-0 Residual Heat Removal Partial Exams B-M-1 B12.40 Low Pressure Core Spray High. Pressure Core Spray
- Reactor Core Isolation- !'
Cooling Reactor Water Cleanup IR-009 R-0 Reactor Pressure Vessel Partial Exams B-O B14.10
! IR-010 R-0 Residual Heat Removal Partial Exams C-A C1.20 l IR-011 R-0 Residual Heat Removal Partial Exams C-B C2.21
! IR-012 R-1 Main Steam Partial Exans C-C C3.10 l Residual Heat Removal C3.20 High Pressure Core Spray l
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IR-013 R-0 High Pressure Core Spray No Exans C-G C6.10
. Low Pressure Core Spray l Residual Heat Removal i
IR-014 R-1 High Pressure Core Spray Partial Exams C-G C6.20 IR-015 R-0 Reactor Water Cleanup Partial Exams C-C C3.20 Residual Heat Removal Low Pressure Coolant-l Injection IR-016 WITHDRAWN IR-017 WITHDRAWN IR-018 R-1 Residual Heat Removal Partial Exams B-K-1 B10.10 l
IR-019 R-0 Control Rod Drive Partial Exams C-C C3.20 Residual Heat Removal High Pressure Core Spray IR-020 R-0 Reactor Core Isolation- Partial Exams C-F-2 C5.51 Cooling IR-021 R-3 Main Steam No Exams D-B D2.20 Emergency Closed Cooling
- Emergency Service Water Page 11
1 REPORT NO. NP0059-0005 A
t 4 RELIEF REQUESTS CONTINUED V
RR NUMBER SYSTEM TYPE RELIEF CATEG. ITEM NO.
IR-022 WITHDRAWN i l
IR-023 R-0 All (Snubbers) Alternate Tech- N/A Sampling Plan Spec IR-024 R-0 Reactor Pressure Vessel Partial Exams B-F B5.10 IR-025 R-0 Main Steam Alternative Exams B-K-1 B10.10 IR-026 R-0 Main Steam Alternative Exams C-C C3.20 Feedwater IR-027 R-0 Standby & HPCS Diesel Alternative Exams D-B D2.20 Fuel Oil IR-028 R-0 Reactor Recirculation No Exams for 9 of B-M-2 B12.50 Residual Heat Removal 21 Valve Groups Low Pressure Core Spray High Pressure Core Spray Reactor Core Isolation-Cooling Reactor Water Cleanup Feedwater IR-029 R-0 Reactor Recirculation Alternate Weld B-J B9.11 I
() PT-001 R-1 Various non-isolable Selection Alternative Syst. C-H B9.12 C7.30 l (from RPV Boundary) Inservice Tests C7.70 Class 2 components l
PT-002 R-1 Various non-isolable Alternative Syst. C-H C7.40 1 (from RPV Boundary) Hydrostatic Tests C7.80 Class 2 components Relief requests applicable to RFO-5 examinations are referenced in the
" remarks" column of the RFO-5 Examinations Results Summary (Appendix A) for the affected examination items.
9.O SCHEDULE CHANGES Scheduling changes were made during RFO-5 to facilitate the examinations or for unforeseen system / component availability's. These changes differ from the schedule in Revision 3 of FNPP's Inservice Examination Program (ISEP) subndtted to the NRC.
The changes, which will be incorporated in the next revision / change to the ISEP, are as follows:
O Page 12
REPORT NO. NP0059-0005 COMPONENT O CODE /AUG.
ITEM NO. MARK NO. CHANGE B12.50 lE51-F0066-IS Added VT-3 of valve interior to the schedule. Within Section 2.6 of the ISEP, lE51-F0065-IS is scheduled for period 3 as the group XXIII selection, but IE51-F0066's (also a group XXIII valve) interior was accessible in RFO-5. The ISEP will be revised to reflect lE51-F0065-IS as not scheduled and lE51-F0066-IS as scheduled.
C5.51 1E12-0689 Upon uninsulating lE12-0689, it was found to be obstructed by a rubber penetration boot. As 1E12-0689 was a random selection, the adjacent weld, 1E12-0688, I was examined in its place. Section 3.6 of j the ISEP will be revised to reflect 1E12-0689 as not scheduled and 1E12-0688 as scheduled.
D3.20 1P45-H0216-WA Pre-outage walkdowns found that piping 1P45-H0374-WA attachments for these supports were mechanical not welded. Their VT-3 exams were deleted from the schedule and they will be deleted from Section 4.6 of the ISEP.
I O D3.20 1P45-H0274-WA Deleted VT-3 from the schedule. The welded attachments were found to be buried within a BISCO sealed floor penetration. Relief has been granted for similar situations under Inservice Relief :
Request IR-021. A revision to IR-021, I reflecting the addition of this item has been submitted and Section 4.6 of the i ISEP will be revised to reflect such. I 10.0 EXAMINATION
SUMMARY
RESULTS RFO-5 examinations completed approximately 55% of those examinations scheduled for the third inspection period. The 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 actions and/or evaluations were completed. As this was the first of two outages scheduled for the third inspection period, the completion percentages will not be reported until the next summary report.
Appendix "A" is a computer generated summary of the RFO-5 examination results. Component identifications (Mark Nos.) and order of appearance may differ slightly from that listed in Revision 3 of PNPP's Inservice Examination Program. The differences are to accommodate the data base soft-ware program. Original examination data reports are on file and available for review at the site.
O Page 13
! l REPORT NO. NP0059-0005 I
l 11.0 NIS-2/NR-1 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 l
delineated on NIS-2/NR-1 Forms. I l
The following is a listing of NIS-2/NR-1 forms applicable to this report l (Class 1 and 2 only) which have been completed since PHPP's last summary
! report:
l CYCLE 5 AND RFO-5 NIS-2/NR-1 FORMS
-. SYS/NO. -l E -MPL No.- l DESCRIPTION /CCheENTS. l class l0PG.
Reactor Pressure Vessel (1B13):
l 1B13-010 1B13-D0008 Replaced CRDM 0 core location 26-39 1 125
! and its capscrews 1B13-011 1813-D0008 Replaced CRDM 0 core location 54-27 1 128 and its capscrews 1B13-012 1B13-D0008 Replaced CRDM 0 core location 18-11 1 131 and its capscrews 1B13-013 1B13-D0008 Replaced CRDM 0 core location 26-31 1 134 and its capscrews 1B13-014 1B13-D0008 Replaced CRDM 0 core location 10-15 1 137 ,
and its capscrews 1B13-015 1B13-D0008 Replaced CRDM 0 core location 06-19 1 140 and its capscrews 1B13-016 1B13-D0008 Replaced CRDM 0 core location 46-31 1 143 and its capscrews 1B13-017 IB13-D0008 Replaced CRDM 0 core location 46-11 1 146 and its CapsCreWs 1B13-018 1B13-D0008 Replaced CRDM 0 core location 42-47 1 149 and its capscrews 1B13-019 1B13-D0008 Replaced CRDM 0 core location 42-07 1 152 and its capscrews 1B13-020 1B13-D0008 Replaced CRDM 0 core location 46-07 1 155 and its capscrews 1B13-021 1B13-D0008 Replaced CRDM 0 core location 58-27 1 158 '
and its capscrews 1B13-022 1B13-D0008 Replaced CRDM 0 core location 42-55 1 161 and its capscrews 1B13-023 1B13-D0008 Replaced CRDM 0 core location 42-31 1 164 and its capscrews 1813-024 1B13-D0008 Replaced CRDM @ core location 30-23 1 167 and its capscrews 1813-025 1813-D0008 Replaced CRDM 0 core location 22-51 1 170 and its capscrews 1B13-026 1B13-D0008 Replaced CRDM 0 core location 46-51 1 173 and its capscrews 1B13-027 1B13-D0008 Replaced CRDM 0 core location 26-59 1 176 l and its capscrews l
1B13-028 IB13-D0008 Replaced CRDM 0 core location 50-15 1 179 and its capscrews 1B13-029 1B13-D0008 Replaced CRDM 0 core location 30-07 1 182 and its capscrews
!O l
Page 14
.- - .~ . .- .
REPORT NO. NP0059-0005 l
SYS/NO. l -MPL NO.' Ms O l DESCRIPTION / COMMENTS-Reactor Pressure Vessel (1B13) Continued:
1B13-030 1B13-D0008 Replaced CRDM 0 core location 34-03 l:cIAss l 1 185 and its capscrews 1B13-031 1B13-D0008 Replaced CRDM 0 core location 38-31 1 188 '
, and its capscrews 1B13-032 1B13-D0008 Replaced CRDM 0 core location 50-11 1 191 and its capscrews 1B13-033 1B13-D0008 Replaced CRDM 0 core location 02-23 1 194 and its capscrews 1B13-034 1B13-D0008 Replaced CRDM 0 core location 22-59 1 197 1 and its capscrews Main Steam (1B21) System:
1B21-242 1B21-H0455 Replaced snubber with like snubber 1 200 1821-246 1B21-F0051A Replaced SRV with like SRV 1 201 1B21-247 1B21-F0051B Replaced SRV with like SRV 1 203 1B21-248 1B21-F0051C Replaced SRV with like SRV 1 205 !
1B21-249 1B21-F0051D Replaced SRV with like SRV 1 207 l 1B21-250 1B21-F0051G Replaced SRV with like SRV 1 209 1B21-251 1B21-F0047B Replaced SRV with like SRV 211 1B21-252 1B21-F0047C Replaced SRV with like SRV 1
1 213
)
1B21-253 1B21-F0047D Replaced SRV with like SRV 1 215 1B21-254 1B21-F0047F Replaced SRV with like SRV 1 217 I 1B21-255 1B21-F0047G Replaced SRV with like SRV 1 219 1B21-256 1B21-F0047H Replaced SRV with like SRV 1 221 1821-257 1B21-F0041A Replaced SRV with like SRV 1 223 l 1B21-258 1B21-F0041B Replaced SRV with like SRV 1 225 4
1821-259 1B21-F0041C Replaced SRV with like SRV 1 227 )
1B21-260 1B21-F0041D Replaced SRV with like SRV 1 229 1B21-261 1B21-F0041E Replaced SRV with like SRV 1 231 1B21-262 1B21-F0041F Replaced SRV with like SRV 1 233 1B21-263 1821-F0041G Replaced SRV with like SRV 1 235 1B21-264 1B21-F0041K Replaced SRV with like SRV 1 237 Reactor Recirculation (1B33) System: i 1B33-104 1833-C0001A Replaced pump seal cartridge assembly 1 239 1B33-105 1833-C0001B Replaced pump seal cartridge assembly 1 241 l 1B33-106 1833 Modified instrument line to add vent 2 243 I valve 1B33-F688B i 1833-107 1833 Modified instrument line to add vent 2 245 valve 1B33-F688A 1B33-108 1B33 Replaced blind flanges at A and B 1 247 loop decon connections and bolting at the B loop decon suction flange Control Rod Drive (IC11) System:
1Cll-028 1Cll-H0694 Replaced pipe attachment 2 248 1C11-029 1C11-F0183 Removed and reinstalled support by 2 249 welding 1C11-030 1C11-D0001 Replaced bonnet of 1" valve in insert 2 250 riser assembly S/N 0795 1C11-031 1C11-D0001 Replaced bonnet of 1" valve in insert 2 252 riser assembly S/N 1046 O
Page 15
REPORT NO. NP0059-0005 2
SYS/NO. l = .' MPL NO. -l- : DESCRIPTION / COMMENTS { - l cws l; m :
A Residual Heat Removal (lE12) System:
1E12-185 lE12-H0679 Replaced pipe clamp and load studs 2 374 1E12-186 1E12-C0003 Modified waterleg pump piping and 2 254 lE12-F0616A supports, and added globe valves and ;
1E12-F0616B an orifice / flow element 1E12-F0617 1E12-F0618 1E12-H2219 J 1E12-H1000 1E12-H1001
- 1E12-H1002 1E12-N0704 lE12-187 1E12-H0588 Replaced pipe clamp 2 260 lE12-188 lE12-H2051 Replaced load pin 2 261
] 1E12-189 1E12-H0303 Replaced load pin 2 262 2
lE12-190 1E12-F0605A Replaced valve bolting 2 263 1E12-191 1E12-H0293 Replaced mechanical snubbers with 2 265 l hydraulic snubbers
] lE12-192 1E12-H0729 Replaced load pin 2 266 4
1E12-193 1E12-H0521 Replaced snubber with like snubber 2 267
- 1E12-194 1E12-H0035 Replaced pipe clamp bolting 2 269 l lE12-195 1E12-F0581 Replaced vent valve and vent pipe 2 270 i
1E12-196 1E12-N0012 Replaced flow element flange bolting 2 273 1 1E12-197 1E12-H0759 Replaced pipe clamp bolting 2 274 lE12-198 1E12-H0169 Modified pipe support 2 275
- lE12-199 1E12-H0171 Replaced mechanical snubber with 2 276 j hydraulic snubber 1E12-200 1E12-H0170 Replaced mechanical snubber with 2 277
. hydraulic snubber 4
lE12-201 1E12-F0073B Replaced valve disc assembly 2 278 i lE12-202 1E12-F0046B Modified valve internals 2 279 j 1E12-203 1E12-F0050A Repaired valve internals 2 280 5 Low Pressure Core Spray (lE21) System:
lE21-025 1E21-C0002 Modified waterleg pump piping and 2 281 1E21-F0617A supports and added globe valves and 1E21-F0617B an orifice / flow element q 1E21-F0618 4
1E21-F0619 l lE21-H1001 I 1E21-N0656 i 1E21-026 1E21-H1019 Replaced component support bolting 2 296
- 1E21-027 1E21-H0038 Replaced mechanical snubbers with 2 297
- 1E21-H0039 hydraulic snubbers
" i 1E21-H0050 i 1E21-H0053 High Pressure Core Spray (1E22) System:
1E22-042 1E22-H0021 Deleted component supports (snubbers) 2 298 )
1E22-H0024 1E22-H0035 l 1E22-043 1E22-H0094 Modified component support 2 299 lE22-044 1E22-F0007 Replaced valve cap 2 300 1E22-045 1E22-F0621 Added vacuum breaker check valves 2 302 1E22-F0622 O
Page 16
REPORT No. NP0059-0005 SYS/NO. : l - - MPL NO. - -l " DESCRIPTION / COMMENTS' l CLAS8 l . PG -
p/
\, High Pressure Core Spray (1E22) System Continued:
lE22-046 1E22-C0003 Modified waterleg pump piping and 2 303 1E22-F0618A supports, and added globe valves and 1E22-F0618B an orifice / flow element 1E22-F0619 1E22-F0620 1E22-H1011 1E22-H1031 1E22-N0737 Leak Detection (1E31) System:
1E31-005 l lE31-F0543A l Replaced valve with like valve l 2 l 305 MSIV Leakage Control (lE32) System:
1E32-074 1E32-H0152 Replaced component support bolting 2 308 1E32-075 1E32-H0201 Replaced component support bolting 2 309 lE32-076 1E32-F0001N Replaced two valve gate halves 1 310 I 1E32-077 lE32-F0002J Replaced one valve gate half 2 312 )
lE32-078 lE32-F0009 Replaced'two valve gate halves 2 314 1 1E32-079 lE32-H0160 Replaced snubbers with like snubbers 1 316 1E32-081 1E32-H0192 Replaced component support bolting 2 318 lE32-082 1E32-F0007 Replaced globe valve with like valve 2 320 1E32-083 1E32-F0006 Replaced globe valve with like valve 2 322 lE32-084 lE32-H0158 Replaced snubber with like snubber 2 324 Reactor Core Isolation Cooling (1E51) system: i 1E51-087 1E51-C0003 Modified waterleg pump piping and 2 325 '
1E51-F0579A added globe valves and an 1E51-F0579B orifice / flow element :
f r- lE51-F0580
( f 1E51-F0581 1E51-N0708
,1E51-088 1E51-H1051 Added component support 2 330 lE51-089 lE51-H0132 Replaced pipe clamp bolting 2 331 lE51-090 1E51-H0074 Replaced snubber with like snubber 1 332 1E51-091 1E51-H2078 Replaced snubber with like snubber 2 333 1E51-092 1E51-H1052 Added component support 2 334 1E51-093 1E51-H0061 Modified component support and 2 335 1E51-F0059 replaced valve with a similar valve 1E51-094 N/A Replaced RPV Head Spray bolting 1 340 1E51-095 lE51-F0066 Replaced valve bolting 1 341 1E51-096 1E51-H2023 Replaced piping and orifice flange 2 342 1E51-D0004 bolting and removed and reinstalled component support welds 1E51-097 lE51-H5002 Removed and reinstalled component 1 343 support welds Integrated Leak Rate (1E61) Systems lE61-002 l lE61-D0009 l Replaced flange bolting l 2 l 344 Reactor Water Cleanup (1033) System 1G33-126 l 1G33-H0025 l Replaced strut paddles l 1 l 345 Combustible Gas Control (LM51) System:
1M51-023 N/A Modified piping on both sides of 2 346 1M51-F0250A Main, Reheat, Extraction, and Misc. Drains (IN22) System:
IN22-059 1B21-F0067A Replaced valve bonnet and repaired 1 347 valve body
[% IN22-060 IN22-F0420D Replaced valve plug 2 349
(,) IN22-061 IN22-F0420B Replaced valve plug and stem assy 2 351 Page 17
l REPORT NO. NP0059-0005
.SYS/NO.:l" MPL NO.' l -DESCRIPTION / COMMENTS-- - l cws l 7 po .
Feedwater (1N27) System:
IN27-035 1N27-Hll45 Replaced mechanical snubber with 2 353 hydraulic snubber 1N27-036 1N27-F0559A Repaired valve seat hard surfacing 1 354 Nuclear Closed Cooling (1P43) System:
1P43-010 l 1P43-F0721 l Replaced duo check with swing check l 2 l 356 Pet.etration Pressurization (1P53) System:
1P53-064 1P53-F0577A Replaced ball in valves 2 358 i 1P53-F0578A
! 1P53-F0579A 1PS3-F0580A l 1P53-065 1P53-F0591A Replaced ball in valves 2 359 l 1P53-F0592A l 1P53-F0593A
! 1P53-F0594A 1P53-066 1P53-F0591B Replaced ball in valves 2 360 1P53-F0592B.
1P53-067 1P53-F0591A "heplaced ball in valves 2 361 1P53-F0592A 1P53-F0593A 1P53-F0594A 1P53-068 1P53-F0591A Replaced ball in valves 2 362 1P53-F0592A 1P53-F0593A 1P53-F0594A 1P53-069 1P53-F0587B Replaced check valve with like valve 2 363 O 1P53-070 1P53-F0591B 1P53-F0592B Replaced ball in valves 2 365 1P53-F0593B 1P53-F0594B 1P53-071 1PS3-A0312A Modified upper airlock inner and 2 366 1P53-A0312B outer doors 1PS3-072 1P53-F0591A Replaced ball in valves 2 367 1P53-F0592A 1P53-F0593A I 1P53-F0594A l 1P53-073 1P53-F0577A Replaced ball in valves 2 368 1P53-F0578A 1PS3-F0579A 1PS3-F0580A 1P53-074 1P53-F0577B Replaced ball in valves 2 369 1P53-F0578B 1P53-F0579B 1PS3-F0580B 1P53-075 1P53-A0305A Modified lower airlock inner and 2 370 1P53-A0305B outer doors Fire Protection (1P54) System:
1P54-006 l 1P54-F5604 l Replaced relief valve with like valve l 2 l 371 Copies of the NIS-2/NR-1 forms are contained in Appendix "B" (appropriate page nos. are given in the above listing) for reference.
O Page 18
REPORT NO. NP0059-0005 O
l l
APPENDIZ A "RFO-5 EIANINATION RESULTS
SUMMARY
$ l 4
)
i INSERVICE INSPECTION SUNNARY REPORT 1
i j
O PERRY NUCLEAR POWER PLANT i
4
) (PNPP) i A
i j UNIT #1 i
I l
\
Page 19
s l DJM SYSTEMS ENGINEERING, INC.
ISIC ISI Data Managtment System REPORT NO. NP0059-0005 tO C/
l 9 ,
5
\
THE CLEVELAND ELECTRIC ILLUMINATING CO PERRY NUCLEAR POWER PLANT UNIT 1 ISI
SUMMARY
REPORT NO. NP0059-0005 COMPLETED COMPONENTS FIRST INTERVAL, THIRD PERIOD, FIRST OUTAGE (96RF)
April 4, 1996 Prepared By: bI A Date U yi 9c Reviewed By: [#h Date d M Approved By Date Alternate for Don Cobb r
i Page 20
I REPORT NO. NPOO59-OOO5 l
DATE: 04/04/96 PERRY NUCLEAR POWER PLANT UNIT 1 PAGE: 1 REVISION: 5 ISI
SUMMARY
REPORT NO. NP0059-0005
[ FIRST INTERVAL, THIRD PERIOD, FIRST OUTAGE (96RF)
's CLASS 1 COMPLETED COMPONENTS REACTOR SYSTEM N O ASME O G T SEC. XI R E N
SUMMARY
EXAMINATION AREA CATGY EXAM E O E NUMBER $1ZE SCHEDULE-LINE SPEC ITEM NO METHOD NDE REPORTS C M R REMARKS (REF. DWG. NO. SS-305-006-112) 005110 1B13 F4-N B-G 1 UT 0944/20 96-0001 X NONE.
RPV CLOSURE HEAD NUT B6.10 5" -N/A -N/A MT 0942-96A-0040 X 005120 1B13 F4 S B-G-1 UT 1Q800-96-0019 X NONE.
RPV PLOSURE HEAD CTUD B6.20 -
(GE M6-307 01) 5" *N/A -N/A UT 1Q800-96 0020 X (CE M 6-307-02) 005140 1B13 F4 T BG1 UT 0944/20-96-0002 X EXAM LIMITED TO 92% COMPLETE BY THE RPV SHELL, THREADS IN FLANGE B6.40 FLANGE GEOMETRY (IR-003).
AREA 5" -N/A -N/A 150 1B13 F4-W B-G-1 VT 1 1042-96A 0110 X NONE.
RPV CLOSURE HEAD WASHER B6.50 5" -N/A -W/A 005160 1813 F5-N B-G 1 UT 0944/20 96-0001 X NONE.
RPV CLOSURE HEAD NUT B6.10 5" N/A N/A MT 0942-96A-0040 X 005170 1813-F5-S B-G 1 UT 1Q800 96-0019 X NONE.
RPV CLOSURE HEAD STUD B6.20 -
(GE M6-307-01) ;
5" -N/A -N/A UT 1Q800-96-0020 X (CE M6-307-02) 005190 1B13-F5 T B G-1 UT 0944/20-96-0002 X EXAM LIMITED TO 92% COMPLETE BY THE RPV SHELL, THREADS IN FLANGE B6.40 FLANGE GEOMETRY (IR-003).
AREA 5" N/A -N/A Page 21
REPORT NO. NP0059-0005 DATE: 04/04/96 PERRY NUCLEAR POWER PLANT UNIT 1 l PAGE: 2 REVISION: 5 IS!
SUMMARY
REPORT NO. NP0059-0005 FIRST INTERVAL, THIRD PERIOD, FIRST CUTAGE (96RF)
CLASS 1 COMPLETED COMPONENTS REACTOR SYSTEM N O ASME O G T SEC. XI R E H
SUMMARY
EXAMINATION AREA CATGY EXAM E O E NUMBER SIZE SCHEDULE-LINE SPEC ITEM NO METHOD NDE REPORTS C M R REMARKS (REF. DWG. NO. SS-305-006-112) 005200 1B13-F5-W B G-1 VT-1 1042-96A 0110 X NONE.
RPV CLOSURE HEAD WASHER B6.50 5" -N/A -N/A 005210 1B13-F6 N B-G-1 UT 0944/20 96 0001 X NONE.
RPV CLOSURE HEAD NUT B6,10 5" -N/A -N/A MT 0942-96A-0040 X 005220 1813-F6 S B G-1 UT 1Q800 96 0019 X NONE.
RPV CLOSURE HEAD STUD B6.20 -
(CE #96-307-01) 5" -N/A -N/A UT 10800-96-0020 X (GE #96-307-02)
{"3240 1B13-F6 T B-G 1 UT 0944/20 96-0002 X RPV SHELL, THREADS IN FLANCE EXAM LIMITED TO 92% COMPLETE BY THE B6.40 AREA FLANGE GEOMETRY (!R-003).
5" -N/A -N/A 005250 1B13-F6 W B-G-1 VT-1 1042 96A 0110 X NONE.
RPV CLOSURE HEAD WASHER B6.50 5" -N/A N/A 005260 1813-F7-N BG1 UT 0944/20-96-0001 X NONE.
RPV CLOSURE HEAD NUT B6.10 5" -N/A -N/A MT 0942-96A-0040 X 005270 1813-F7-S B G-1 UT 1Q800-96-0019 X NONE.
RPV CLOSURE HEAD STUD B6.20 -
(GE #96-307-01) 5" -N/A -N/A UT 1Q800-96 0020 X (GE #96 307 02) 005290 1B13-F7 T BG1 UT 0944/20-96-0002 X RPV SHELL, THREADS IN FLANGE EXAM LIMITED TO 92% COMPLETE BY THE B6.40 AREA FLANGE GEOMETRY (IR 003).
5" -N/A -N/A Page 22
l REPORT NO. NPOO59-OOO~
l DATE: 04/04/96 PERRY NUCLEAR POWER PLANT UNIT 1 PAGE: 3 REVISION: 5 IS!
SUMMARY
REPORT NO. NP0059-0005 FIRST INTERVAL, THIRD PERIOD, FIRST OlfiAGE (96RF)
C CLASS 1 COMPLETED COMPONENTS l
REACTOR SYSTEM N O ASME O G T SEC. XI R E H
SUMMARY
EXAMINATION AREA CATGY EXAM E O E NUMBER SIZE SCHEDULE LINE SPEC ITEM NO METHOD NDE REPORTS C M R REMARKS (REF. DWG. NO. SS-305 006-112) 005300 1813-F7-W B-G 1 VT 1 1042-96A-0110 X NONE.
RPV CLOSURE HEAD WASHER B6.50 5" -N/A -N/A 005310 1813 F8-N BG1 UT 0944/20-96-0001 X NONE.
RPV CLOSURE HEAD NUT B6.10 5" -N/A N/A MT 0942-96A-0040 X 005320 1B13 F8 S B G-1 UT 1Q800-96 0019 X NONE.
RPV CLOSURE HEAD STUD B6.20 -
(GE M6-307-01) 5" N/A N/A UT 1Q800-96 0020 X (CE M6 307-02) l D j340 1813-F8-T B-G 1 UT 0944/20-96-0002 X EXAM LIMITED TO 92% COMPLETE BY THE RPV SHELL, THREADS IN FLANGE B6.40 FLANGE GEOMETRY (IR 003). l AREA l 5" N/A -K/A l
005350 1813 F8 W BG1 VT 1 1042 96A 0110 X NONE.
RPV CLOSURE HEAD WASHER B6.50 5" -N/A N/A 005360 1813-F9-N B G-1 UT 0944/20 96-0001 X NONE.
RPV CLOSURE HEAD NUT B6.10 5" -N/A -N/A MT 0942-96A 0040 X 005370 1813-F9-S B-G-1 UT 1Q800-96-0019 X NONE. j RPV CLOSURE HEAD STUD B6.20 -
(CE M 6 307 01) l 5" -N/A -N/A UT 1Q800-96 0020 X (GE M6 307-02) 005390 1813 F9 T B-G 1 UT 0944/20-96 0002 X EXAM LIMITED TO 92% COMPLETE BY THE RPV SHELL, THREADS IN FLANGE B6.40 FLANGE GEOMETRY (IR-003).
AREA 5" -N/A -N/A Paga 23
REPORT NO. NP0059-0005 DATE: 04/04/96 PERRY NUCLEAR POWER PLANT UNIT 1 PAGE: 4 REVISION: 5 IS!
SUMMARY
REPORT NO. NP0059 0005 FIRST INTERVAL, THIRD PERIOD, FIRST OUTAGE (96RF)
CLASS 1 COMPLETED COMPONENTS REACTOR SYSTEM N O ASME D G T SEC. XI R E H SUMMRY EXAMINATION AREA CATGY EXAM E 0 E NUM6ER SIZE SCHEDULE LINE SPEC ITEM NO METHOD NDE REPORTS CM R REMARKS (REF. DWG. NO. SS-305 006-112) l 005400 1813 F9-W B-G-1 VT 1 1042-96A 0110 X NONE.
RPV CLOSURE HEAD WASHER B6.50 5" -N/A N/A 005410 1B13-G1-N B C-1 UT 0944/20-96-0001 X NONE.
RPV CLOSURE HEAD NUT B6.10 5" -N/A N/A MT 0942-96A-0040 X j 005420 1B13-Gi-S B G-1 UT 1Q800 96-0019 X NONE.
RPV CLOSURE HEAD STUD B6.20 -
(GE #96-307-01) 5" N/A -N/A UT 10800-96 0020 X (CE #96-307-02) l
~5440 1813-G1 T B-G-1 UT 0944/20-96-0002 X EXAM LIMITED TO 92% COMPLETE BY THE i
RPV SHELL, TilREADS IN FLANGE B6.40 FLANGE GEOMETRY (IR-003).
AREA 5" -N/A N/A 005450 1813-G1 W B-G-1 VT 1 1042-96A-0110 X NONE.
RPV CLOSURE HEAD WASHER B6.50 5" -N/A N/A 005460 1813 G2-N B G-1 UT 0944/20-96-0001 X NONE.
RPV CLOSURE HEAD NUT B6.10 5" -N/A -N/A MT 0942-96A 0040 X l
005470 1813-G2-S B G-1 UT 1Q800-96 0019 X NONE.
RPV CLOSURE HEAD STUD B6.20 -
(GE #96-307-01) 5" N/A N/A UT 10800-96-0020 X (GE #96 307-02) 1 005490 1B13-G2 T B-G-1 UT 0944/20-96-0002 X EXAM LIMITED TO 92% COMPLETE BY THE RPV SHELL, THREADS IN FLANGE B6.40 FLANGE GEOMETRY (IR-003).
AREA 5" -N/A N/A t
O l
Page 24 !
l l
J
REPORT No. NPOO59-DOO5 DATE: 04/04/96 PERRY NUCLEAR POWER PLANT UNIT 1 PAGE: 5 I REVISION: 5 IS!
SUMMARY
REPORT NO. NP0059-0005 FIRST INTERVAL, THIRD PERIOD, FIRST OUTAGE (96RF)
CLASS 1 COMPLETED COMPONENTS REACTOR SYSTEM N O ASME D G T SEC. XI R E H
SUMMARY
EXAMINATION AREA CATGY EXAM E O E NUMBER SIZE SCHEDULE LINE SPEC ITEM NO METHOD NDE REPORTS C M R REMARKS (REF. DWG. NO. SS 305-006 112) 003500 1B13-G2-W BG1 VT-1 1042-96A-0110 X NONE.
RPV CLOSURE HEAD WASHER B6.50 5" -N/A N/A l
l
- 005510 1913-G3 N B-G-1 UT 0944/20-96-0001 X NONE.
RPV CLOSURE HEAD NUT B6.10 5" -N/A -N/A MT 0942-96A 0040 X l
l 005520 1813-G3 S B-G-1 UT 10800-96-0019 X NONE.
RPV CLOSURE HEAD STUD B6.20 -
(GE M6-307-01) l 5" -N/A N/A UT 1Q800-96-0020 X l
(GE M6 307 02)
{ ,
' 7540 1B13-G3 T B-C-1 UT 0944/20 96-0002 X EXAM LIMITED TO 92% COMPLETE BY THE RPV SHELL, THREADS IN FLANGE B6.40 FLANGE GEOMETRY (IR 003).
AREA 5" -N/A -N/A 005550 1B13-G3-W B-G-1 VT 1 1042-96A-0110 X NONE.
RPV CLOSURE HEAD WASHER 86.50 l 5" N/A N/A l
l l 005560 1B13 G4-N B-G-1 UT 0944/20-96 0001 X NONE.
( RPV CLOSURE HEAD NUT B6.10 l 5" N/A -N/A MT 0942 96A 0040 X l
! i 005570 1h15 G4-S BG1 UT 10800-96-0019 X NONE.
i l RPV CLOSURE HEAD STUD B6.20 -
(GE M6-307-01)
Sa -N/A N/A UT 10800-96-0020 X l
(CE M6-307-02) 005590 1813 G4-T B-G 1 UT 0944/20 96 0002 X EXAM LIMITED TO 92% COMPLETE BY THE RPV SHELL, THREADS IN FLANGE B6.40 FLANGE GEOMETRY (IR-003).
A"4EA 5" W/A N/A I
i i
?
Page 25
REPORT No. NP0059-0005 DATE: 04/04/96 PERRY NUCLEAR POWER PLANT UNIT 1 PAGE: 6 REVISION: 5 ISI
SUMMARY
REPORT No. NP0059-0005 FIRST INTERVAL, THIRD PERIOD, FIRST GUTAGE (96RF)
Os CLASS 1 COMPLETED COMPONENTS REACTOR SYSTEM N O i ASME O G T l SEC. XI R E H
(
SUMMARY
EXAMINATION AREA CATGY EXAM E O E l NUMBER SIZE SCHEDULE-LINE SPEC ITEM NO METHOD NDE REPORTS C M R REMARKS (REF. DWG. NO. SS-305-006-112)
{ 005600 1B13-G4-W BG1 VT 1 1042-96A 0110 X NONE.
l RPV CLOSURE HEAD WASHER B6.50 1 5" N/A -N/A l
l 005610 1813 GS N B-G-1 UT 0944/20-96-0001 X NONE.
RPV CLOSURE HEAD NUT B6.10 5" N/A N/A MT 0942-96A 0040 X l
005620 1813 G5-S B-G-1 UT 1Q800 96 0019 X NONE.
RPV CLOSURE HEAD STUD B6.20 -
(GE #96-307 01) 5" N/A N/A UT 1Q800-96-0020 X (GE #96-307-02) l
- f640 1B13-G5-T B-G-1 UT 0944/20 96 0002 X EXAM LIMITED TO 92% COMPLETE BY THE RPV SHELL, THREADS IN FLANGE B6.40 FLANGE GEOMETRY (IR-003).
l AREA l 5" N/A N/A 005650 1B13-G5-W B-G-1 VT 1 1042-96A-0110 X NONE.
RPV CLOSURE HEAD WASHER B6.50 l 5" -N/A -N/A 005660 1B13-G6-N B-G-1 UT 0944/20-96 0001 X NONE.
RPV CLOSURE HEAD NUT B6.10 5" N/A -N/A MT 0942 96A-0040 X I l
005670 1813-06 S B-G-1 UT 10800 96 0019 X NONE.
RPV CLOSURE HEAD STUD B6.20 -
(GE #96-307 01) ;
5" -N/A N/A UT 1Q800-96-0020 X l
(CE #96-307-02) l J 005690 1813-06-T BG1 UT 0944/20-96-0002 X EXAM LIMITED TO 92% COMPLETE BY THE RPV SHELL, THREADS IN FLANGE B6.40 FLANGE GEOMETRY (IR 003).
AREA
, 5" -N/A -N/A l
J Page 26
REPORT NO. NP0059-0005 DATE: 04/04/96 PERRY NUCLEAR POWER PLANT UNIT 1 PAGE: 7 REVISION: 5 ISI
SUMMARY
REPORT NO. NP0059 0005 FIRST INTERVAL, THIRD PERIOD, FIRST OUTAGE (96RF)
CLASS 1 COMPLETED COMPONENTS REACTOR SYSTEM N O ASME O G T SEC. XI R E N
SUMMARY
EXAMINATION AREA CATGY EXAN E O E NUMBER SIZE SCHEDULE-LINE SPEC ITEM NO METHOD NDE REPORTS C M R REMARKS (REF. DWC. NO. $$ 305-006 112) 005700 1813-06 W B-G 1 VT 1 1042 96A 0110 X NONE.
RPV CLOSURE HEAD WASHER B6.50 5" -N/A N/A 005710 1B13 G7-N B-G-1 UT 0944/20 96-0001 X NONE.
RPV CLOSURE HEAD NUT B6.10 5" -N/A N/A MT 0942-96A-0040 X 005720 1B13-G7-S B G-1 UT 10800- & 0019 X NONE.
RPV CLOSURE HEAD STUD B6.20 -
(GE #96-307-01) 5" -N/A N/A UT 1Q800- W OO20 X (CE #96-307-02) 740 1B13-G7-T B G-1 UT 0944/20-96-0002 X EXAM LIMITED TO 92% COMPLETE BY THE
{"1 RPV SHELL, THREADS IN FLANCE B6.40 FLANGE GEOMETRY (IR-003).
AREA 5" N/A -N/A 005750 1813 G7 W B-G-1 VT 1 1042 96A-0110 X NONE.
RPV CLOSURE HEAD WASHER B6.50 5" -N/A -N/A 005760 1813-G8-N B-G-1 UT 0944/20-96-0001 X NONE.
RPV CLOSURE HEAD NUT B6.10 5" -N/A N/A MT 0942-96A-0040 X 005770 1813-G8-S B-G 1 UT 1Q800 96 0019 X NONE.
RPV CLOSURE HEAD STUD B6.20 -
(GE #96 307-01) 5" -N/A -N/A UT 1Q800 96-0020 X (CE #96-307 02) 005790 1813-G8-T B G-1 UT 0944/20 96-0002 X EXAM LIMITED TO 92% COMPLETE BY THE RPV SHELL, THREADS IN FLANGE B6.40 FLANGE GEOMETRY (IR-003).
AREA 5" N/A N/A Page 27
. .. - .m__ _ . . . - - - m .__. _ - _ . _ _ _ _ ---. . . _ . _ _ . . . . . . .. _ -. _ _ _ . _.
l l REPCRT N3. NP0059-0005 ,
l DATE: 04/04/96 PERRY NUCLEAR POWER PLANT UNIT 1 PAGE: 8 REV!$ ION: 5 IS!
SUMMARY
REPORT NO. NP0059-0005 FIRST INTERVAL, THIRD PERIOD, FIRST DUTAGE (96RF)
CLASS 1 COMPLETED COMPONENTS REACTOR SYSTEM N O ASME O G T SEC. XI R E N
SUMMARY
EXAMINATION AREA CATGY EXAM E O E NUMBER $12E SCHEDULE LINE SPEC ITEM NO METHOD NDE REPORTS C M R REMARKS (REF. DWG. NO. SS-305-006-112) 005800 1B13-G8-W BG1 VT 1 1042-96A 0110 X NONE. t RPV CLOSURE HEAD WASHER 86.50 5" N/A -N/A 005810 1813-G9-N BG1 UT 0944/20-96-0001 X NONE.
! RPV CLOSURE HEAD NUT B6.10 i 5" -N/A -N/A MT 0942-96A 0040 X l
005320 1813 G9-S BG1 UT 1Q800-96-0019 X NONE.
RPV CLOSURE HEAD STUD B6.20 -
(CE #96 307 01) 5" N/A N/A UT 10800-96-0020 X (CE #96-307 02) l I
- 5840 1B13-G9-T BG1 UT 0944/20-96-0002 X EXAM LIMITED TO 92% COMPLETE BY THE RPV SHELL, THREADS IN FLANGE B6.40 FLANGE GEOMETRY (IR 003).
AREA l 5" -N/A N/A 005650 1B13 G9-W B-G 1 VT 1 1042-96A 0110 X NONE.
RPV CLOSURE HEAD WASHER B6.50 ,
j 5" N/A -N/A l I
005860 1813 H1-N B-G 1 UT 0944/20-96-0001 X NONE.
RPV CLOSURE HEAD NUT B6.10 5" -N/A N/A MT 0942-96A 0040 X 005870 1813 H1 S B G-1 UT 10800-96-0019 X NONE.
j RPV CLOSURE HEAD STUD B6.20 -
(GE #96 307-01) l 5" N/A -N/A UT 1Q800 96 0020 X (GE #96-307 02) 005890 1B13 H1-T BG1 UT 0944/20-96-0002 X EXAM LIMITED TO 92% COMPLETE BY THE RPV SHELL, THREADS IN FLANGE B6.40 FLANGE GEOMETRY (!R-003).
AREA 5" N/A N/A i
Page 28
[ REPORT NO. NP0059-0005 l
DATE: 04/04/96 PERRY NUCLEAR POWER PLANT UNIT 1 PAGE: 9 REVISION: 5 ISI
SUMMARY
REPORT NO. NP0059-0005
! FIRST INTERVAL, THIRD PERIOD, FIRST CUTAGE (96RF)
CLASS 1 COMPLETED COMPONENTS REACTOR SYSTEM N O ASME O G T SEC. XI R E H
SUMMARY
EXAMINATION AREA CATGY EXAM E O E NUMBER SIZE-SCHEDULE LINE SPEC ITEM NO METHOD NDE REPORTS C M R REMARKS (REF. DWG. NO. SS-305-006-112) 005900 1B13-H1 W BG1 VT 1 1042 96A 0110 X NONE.
RPV CLOSURE HEAD WASHER B6.50 5" -N/A -N/A 005910 1B13 H2-N B G-1 UT 0944/20-96-0001 X NONE.
RPV CLOSURE HEAD NUT B6.10 5" -N/A N/A MT 0942 96A 0040 X l
003920 1B13-H2-S BG1 UT 10800-96-0019 X NONE.
l RPV CLOSURE HEAD STUD B6.20 -
(GE #96 307-01) 5" -N/A N/A UT 10800-96-0020 X (GE #96-307-02)
"940 1B13-H2 T BG1 UT 0944/20-96-0002 X EXAM LIMITED TO 92% COMPLETE BY THE j RPV SHELL, THREADS IN FLANGE B6.40 FLANGE GEOMETRY (IR-003).
AREA 5" N/A N/A 005950 1813 H2 W BG1 VT 1 1042-96A-0110 X NONE.
RPV CLOSURE HEAD WASHER B6.50 5" N/A N/A 005960 1B13 H3-N B-G 1 UT 0944/20-96-0001 X NONE.
! RPV CLOSURE HEAD NUT B6.10 I
5" -N/A N/A MT 0942 96A-0040 X 005970 1B13-H3-S B G-1 UT 10800-96-0019 X NONE.
RPV CLOSURE HEAD STUD B6.20 -
(GE #96 307-01) 5" -N/A -N/A UT 10800-96-0020 X (CE #96 307-02) 005990 1813-H3 T B-G-1 UT 0944/20 96-0002 X EXAM LIMITED TO 92% COMPLETE BY THE RPV SHELL, THREADS IN FLANGE B6.40 FLANGE GEOMETRY (IR 003).
AREA 5" *N/A N/A l
l i v
?
l Page 29
REPORT NO. NP0059-0005 DATE: 04/04/96 PERRY NUCLEAR POWER PLANT UNIT 1 PAGE: 10
. REVISION: 5 ISI
SUMMARY
REPORT NO. NP0059 0005 I\* ')> FIRST INTERVAL, THIRD PERIOD, FIRST DUTAGE (96RF)
CLASS 1 COMPLETED COMPONENTS REACTOR SYSTEM N O ASME O G T SEC. XI R E H j
SUMMARY
EXAMINATION AREA CATGY EXAM E O E I NUMBER SIZE SCHEDULE LINE SPEC ITEM NO METHOD NDE REPORTS C M R REMARKS (REF. DWG. NO. SS-305-006-112) I l
006000 1B13 H3 W BG1 VT 1 1042-96A-0110 X NONE.
RPV CLOSURE HEAD WASHER B6.50 ;
5" N/A N/A 006010 1813 H4-N B-G 1 UT 0944/20 96 0001 X N ONE .
RPV CLOSURE HEAD NUT B6.10 5" N/A N/A MT 0942-96A-0040 X 006020 1B13 d4-S BG1 UT 1Q800-96-0019 X NONE.
RPV CLOSURE HEAD STUD B6.20 -
(GE #96-307-01) 5" N/A N/A UT 1Q800 96 0020 X (CE #96-307-02)
,r""*t040 1813-H4-T BG1 UT 0944/20 96-0002 X EXAM LIMITED TO 92% COMPLETE BY THE I. RPV SHELL, THREADS IN FLANGE B6.40 FLANGE GE0 METRY (IR-003).
AREA 5" *N/A N/A 006050 1813 H4 W B-G 1 VT 1 1042-96A 0110 X NONE.
RPV CLOSURE HEAD WASHER B6.50 5" -N/A N/A 006060 1813 H5 N BG1 UT 0944/20 96-0001 X NONE.
RPV CLOSURE HEAD NUT B6.10 5" N/A -N/A MT 0942-96A 0040 X 006070 1B13 H5-S B-G 1 UT 1Q800-96-0019 X NONE.
RPV CLOSURE HEAD STUD B6.20 -
(GE #96-307 01) 5" N/A N/A UT 1Q800 96-0020 X (CE #96-307 02) 006090 1B13-H5-T BG1 UT 0944/20 96 0002 X EXAM LIMITED TO 92% COMPLETE BY THE RPV SHELL, THREADS IN FLANGE B6.40 FLANGE GEOMETRY (IR 003).
AREA 5" N/A -N/A l
b Page 30 l
REPORT NO. NP0059-0005 DATE: 04/04/96 PERRY NUCLEAR POWER PLANT UNIT 1 PAGE: 11 REY!SION: 5 IS!
SUMMARY
REPORT NO. NP0059-0005 FIRST INTERVAL, THIRD PERIOD, FIRST OUTAGE (96RF)
CLASS 1 COMPLETED COMPONENTS REACTOR SYSTEM N 0 ASME O G T SEC. XI R E H
$UMMARY EXAMINATION AREA CATGY EXAM E O E NUMBER SIZE SCHEDULE-LINE SPEC ITEM NO METHOD NDE REPORTS C M R REMARKS (REF. DWG. NO. SS-305-006-112) 006100 1B13 H5-W B-G-1 vi-1 1042-96A-0110 X NONE. ,
RPV CLOSURE HEAD WASHER B6.50 l 5" -N/A N/A 006110 1813-H6-N B-G-1 UT 0944/20 96-0001 X NONE.
RPV CLOSURE HEAD NUT B6.10 5" -N/A -N/A MT 0942-96A-0040 X 006120 1813*H6-S B-G 1 UT 10800 96-0019 X NONE.
RPV CLOSURE HEAD STUD B6.20 -
(CE #96-307 01) 5" -N/A N/A UT 10800-96-0020 X (GE #96-307-02) l
(*$140 1813-H6-T B-G-1 UT 0944/20-96-0002 X EX81; LIMITED TO 92% COMPLETE BY THE l
RPV SHELL, THREADS IN FLANGE B6.40 FLANGE GEOMETRY (IR 003).
AREA l
1 5" N/A N/A I 006150 1B13-H6-W B-G-1 VT 1 1042-96A 0110 X NONE.
RPV CLOSURE HEAD WASHER 86.50 5" -N/A -N/A 006160 1813-H7-N B G-1 UT 0944/20-96-0001 X NONE.
RPV CLOSURE HEAD NUT B6.10 5" -N/A -N/A MT 0942-96A 0040 X 006170 1B13-H7-S B-G-1 UT 1Q800 96 0019 X NONE.
RPV CLOSURE HEAD STUD B6.20 -
(CE #96-307-01) 5" *N/A -N/A UT 10800 96-0020 X (CE #96-307 02) 006190 1B13-H7-T B G-1 UT 0944/20-96 0002 X EXAM LIMITED TO 92% COMPLETE BY THE RPV SHELL, THREADS IN FLANCE B6.40 FLANGE GEOMETRY (IR-003).
AREA 5" -N/A -d/A Page 31
l REPORT No. NP0059-0005 DATE: 04/04/96 PERRY NUCLEAR POWER PLANT UNIT 1 PAGE: 12 REVISION: 5 IS!
SUMMARY
REPORT NO. NP0059 0005 FIRST INTERVAL, THIRD PERIOD, FIRST OUTAGE (96RF)
CLASS 1 COMPLETED COMPONENTS REACTOR SYSTEM N O AME D G T SEC. XI R E H
SUMMARY
EXAMINATION AREA CATGY EXAM E O E NUMBER SIZE SCHEDULE LINE SPEC ITEM NO METHOD N0E REPORTS C M R REMARKS (REF. DWG. NO. SS-305-006-112) 006200 1B13 H7-W B-G 1 VT-1 1042 96A 0110 X NONE.
RPV CLOSURE HEAD WASHER B6.50 5" N/A -N/A 006210 1813-H8-N B G-1 UT 0944/20-96-0001 X NONE.
RPV CLOSURE HEAD NUT B6.10 5" -N/A -W/A MT 0942-96A 0040 X l
006220 1B13-H8-S B-G-1 UT 10800-96-0019 X NONE.
RPV CLOSURE HEAD STUD B6.20 *
(CE #96-307-01) ;
5" -N/A -N/A UT 10800-96 0020 X '
(GE #96-307 02)
"N240 1B13-H8-T B-C-1 UT 0944/20-96 0002 X EXAM LIMITED TO 92% COMPLETE BY THE RPV SHELL, THREADS IN FLANGE B6.40 FLANGE GEOMETRY (IR-003).
AREA I 5" -N/A -N/A 006250 1813 H8 W B-G-1 VT 1 1042-96A 0110 X NONE.
RPV CLOSURE HEAD WASHERS B6.50 5" -N/A N/A 006260 1B13-H9 N BG1 UT 0944/20-96-0001 X NONE.
RPV CLOSURE HEAD NUT B6.10 5" -N/A -N/A MT 0942-96A 0040 X 006270 1B13-H9-S BG1 UT 1a800 96 0019 X NONE.
RPV CLOSURE HEAD STUD B6.20 -
(GE #96-307-01) ;
5" N/A -N/A UT 10800 96-0020 X !
(GE #96-307 02) 006290 1813-H9 T B-G-1 UT 0944/20 96 0002 X EXAM LIMITED TO 92% COMPLETE BY THE RPV SHELL, THREADS IN FLANGE B6.40 FLANGE GEOMETRY (IR-003).
AREA 5" N/A -N/A O
Page 32
r 1 l
1 REP RT NO. NP0059-0005 DATE: 04/04/96 PERRY NUCLEAR POWER PLANT UNIT 1 PAGE: 13 ,
t REY!SION: 5 ISI
SUMMARY
REPORT NO. NP0059-0005 I I O L/
FIRST INTERVAL, THIRD PERIOD, FIRST GUTAGE (96RF)
CLASS 1 COMPLETED COMPONENTS i
l l REACTOR SYSTEM 1 N O l ASME D G T SEC. XI R E H !
SUMMARY
EXAMINATION AREA CATGY EXAM E O E NUMBER SIZE-SCHEDULE-LINE SPEC ITEM NO METHOD NDE REPORTS C M R REMARKS l l ....... .............................. ....... .......... ................ . . . ........................................ 1 (REF. DWG, NO. SS-305-006-112) 006300 1B13 H9-W BG1 VT-1 1042-96A 0110 X NONE.
RPV CLOSURE HEAD WASHERS B6.50 5" -N/A -N/A (REF. DVG. NO. SS-305-006-107) 006310 1813-N1A-!R BD M-UT 10800-96-0064 X CE0 METRIC AND NON RELEVANT INDICATIONS l RECIRC OUTLET N0ZZLE N1A INNER B3.100 -
(CE #96-703-22) RECORDED. ;
RADIUS l
22" -N/A -N/A I i
006320 1813-N1A-KA B-D M-UT 10800-96-0042 X GEOMETRIC AND NON RELEVANT INDICATIONS I RECIRC OUTLET N0ZZLE N1A TO B3.90 -
(CE #96-702-20) RECORDED. EXAM LIMITED TO 69% COMPLETE j VESSEL BY N0ZZLE GEOMETRY AND ADJACENT N2 q 22" -N/A -N/A N0ZZLES (!R 001). j 006330 1B'3 N1A-KB B-F M UT 1Q800-96-0088 X GEOMETRIC AND NON RELEVANT INDICATIONS j RECIPO OUTLET N0ZZLE N1A To B5.10 -
(CE #96-209-23) RECORDED. EXAM LIMITED TO 93% COMPLETE l SAFE-END PT BY N0ZZLE GEOMETRY (IR-001). PT 22" -1.51" -N/A PERFORMED WITH AUGMENTED UT EXAM IN l RF02. l I
1 006350 1813-N1B !R BD M-UT 10600-96 0065 X GEOMETRIC AND NON RELEVANT INDICATIONS RECIRC OUTLET N0ZZLE N1B INNER B3.100 -
(CE #96-703-23) RECORDED.
RADIUS 22" -N/A -N/A l
l 006360 1813 N1B KA B-D M-UT 10800-96 0043 X GEOMETRIC AND NOW RELEVANT INDICATIONS RECIRC OUTLET N0ZZLE N1B TO B3.90 -
(CE #96-702 21) RECORDED. EXAM LIMITED TO 69% COMPLETE VESSEL BY N0ZZLE GEOMETRY AND ADJACENT N2 22" -N/A -N/A N0ZZLES (!R 001).
006370 1B13-N18-KB BF M-UT 1Q800-96-0087 X GEOMETRIC AND NON RELEVANT INDICATIONS i RECIRC. DUTLET N0ZZLE N1B TO B5.10 -
(GE #96-209 22) RECORDED. EXAM LIMITED TO 93% COMPLETE l SAFE-END PT BY N0ZZLE CEOMETRY (!R-001). PT 22" -1.51" -N/A PERFORMED WITH AUGMENTED UT EXAM IN RF02.
I f
\.
Page 33
REPORT No. NP0059-OOO5 1
DATE: 04/04/96 PERRY NUCLEAR POWER PLANT UNIT 1 PAGE: 14 REVISION: 5 ISI
SUMMARY
REPORT NO NP0059-0005 FIRST INTERVAL, THIRD PERIOD, FIRST DUTAGE (96RF)
CLASS 1 COMPLETED COMPONENTS REACTOR SYSTEM N O ASME D G T SEC. XI R E H
SUMMARY
EXAMINATION AREA CATGY EXAM E O E l NUMBER SIZE-SCHEDULE-LINE SPEC ITEM NO METHOD NDE REPORTS C M R REMARKS l ....... .............................. ....... .......... ................ . . . ........................................
(REF. DWG. NO. SS-305-006 107) 006390 1B13 N2A-IR BD M-UT 10800-96-0063 X GEOMETRIC AND WON RELEVANT IMDICATIONS RECIRC INLET N0ZZLE N2A INNER B3.100 -
(GE #96-703-21) RECORDED.
RADIUS
( 12" N/A N/A I 006400 1813-N2A KA B-D M-UT 10800-96-0041 X GEOMETRIC AND NON RELEVANT IN0! CATIONS i RECIRC INLET N0ZZLE NZA TO 83.90 -
(GE #96-702-19) RECORDED. EXAM LIMITED TO 72% COMPLETE VESSEL BY N0ZZLE GEOMETRY (!R-001).
12" W/A -N/A 006410 1B13-N2A KB B-F M-UT 10800 96-0G81 X NON RELEVANT INDICAT!DNS RECORDED. EXAM RECIRC. INLET N0ZZLE NZA To B5.10 -
(CE #96 209-16) LIMITED TO 91% COMPLETE BY N0ZZLE SAFE-END PT GEOMETRY (IR-001). PT PERFORMED WITH 12" -1.125" -N/A AUGMENTED UT EXAM IN RF02.
l l
uo6430 1B13-N28 !R B-D M-UT 10800-96-0060 X GEOMETRIC AND NON RELEVANT INDICATIONS RECIRC INLET N0ZZLE N2B INNER B3.100 -
(GE #96-703-18) RECORDED.
RADIUS 12" -N/A -W/A I
006440 1813-N28-KA BD M-UT 1Q800 96-0038 X GEOMETRIC AND NON RELEVANT INDICAT!DNS i RECIRC INLET N0ZZLE N2B TO B3.90 -
(CE #96-702 16) RECORDED. EXAM LIMITED TO 72% COMPLETE VESSEL BY N0ZZLE GEDMETRY (IR 001). i 12" -N/A -N/A 006450 1813 N28-KB BF M-UT 10800-96 0086 X NON RELEVANT INDICATIONS RECORDED. EXAM RECIRC. INLET N0ZZLE N2B To B5.10 -
(GE #96 209 21) LIMITED TO 91% COMPLETE BY N0ZZLE SAFE END PT GEOMETRY (IR-001). PT PERFORMED WITH 12" 1.125" -N/A AUGMENTED UT EXAM IN RF02.
006500 1B13 N2C KB G XG M-UT 1Q800-96 0080 X NON RELEVANT INDICAT!DNS RECORDED. EXAM l RECIRC. INLET N0ZZLE N2C To X0.12 -
(CE #96-209-15) LIMITED TO 91% COMPLETE BY N0ZZLE SAFE-END GEOMETRY.
l 12" -1.125" W/A I
I Page 34
1 REPSRT NO. NP0059-0005 DATE: 04/04/96 (2RRY NUCLEAR POWER PLANT UNIT 1 PAGE: 15 REVISION: 5 ISI
SUMMARY
REPORT NO. NP0059-0005 FIRST INTERVAL, THIRD PER100, FIRST OUTAGE (96RF)
CLASS 1 COMPLETED COMPONENTS REACTOR SYSTEM N O ASME O G T SEC. XI R E H
SUMMARY
EXAMINAT!DN AREA CATGY EXAM E O E NUMBER SIZE SCHEDULE-LINE SPEC ITEM No METHOD NDE REPORTS C M R REMARKS l
(REF. DWG. NO. SS-305-006-107) l 006510 1B13 N2D IR B-D M-UT 1Q800-96-0057 X GEOMETRIC AND NON RELEVANT INDICATIONS RECIRC INLET N0ZZLE N2D INNER 83.100 -
(GE #96-703-15) RECORDED.
RADIUS 12" N/A -N/A 006520 1813 N20-KA B-D M UT 1Q800 96 0036 X GEOMETRIC AND NON RELEVANT INDICATIONS RECIRC INLET N0ZZLE N2D To B3.90 -
(CE #96-702-14) RECORDED. EXAM LIMITED TO 70% COMPLETE VESSEL BY N0ZZLE GEOMETRY AND ADJACENT N9 12" N/A -N/A N0ZZLE (IR-001).
006530 1813-N2D-KB BF M-UT 1Q800-96-0085 X NON RELEVANT INDICATIONS RECORDED. EXAM RECIRC. INLET N0ZZLE N2D To B5.10 -
(CE #96-209 20) LIMITED TO 91% COMPLETE BY N0ZZLE SAFE END PT GEOMETRY (IR 001). PT PERFORMED WITH 12" -1.125" -N/A AUGMENTED UT EXAM IN RF02.
(/
006550 1813-N2E IR BD M UT 1Q800-96-0062 X GEOMETRIC AND NON RELEVANT INDICATIONS RECIRC INLET N0ZZLE N2E INNER 83.100 -
(GE #96 703-20) RECORDED.
RADIUS 12" -N/A -N/A 006560 1313-N2E KA BD M-UT 1Q800-96 0040 X GEOMETRIC AND NON RELEVANT INDICATIONS 1 RECIRC INLET N0ZZLE N2E TO B3.90 -
(CE #96-702-18) RECORDED. EXAM LIMITED TO 72% COMPLETE VESSEL BY N0ZZLE GEOMETRY (IR 001).
12" N/A N/A 006570 1B13-N2E KB B-F M-UT 1Q800-96 0079 X GEOMETRIC AND NON RELEVANT INDICATIONS RECIRC. INLET N0ZZ.E N2E To B5.10 -
(CE #96-209-14) RECORDED. EXAM LIMITED TO 91% LOMPLETE SAFE END PT BY N0ZZLE GEOMETRY (IR 001). PT 12" -1.125" -N/A PERFORMED WITH AUGMENTED UT EXAM IN RF02.
006590 1813 N2F lR BD M-UT 1Q800-96-0059 X GEOMETRIC AND NON RELEVANT INDICATIONS RECIRC INLET N0ZZLE N2F INNER B3.100 -
(CE #96-703-17) RECORDED.
RADIUS 12" -N/A -N/A l
1 1
Page 35
REPORT N3. NP0059-0005 l DATE: 04/04/96 PERRY NUCLEAR POWER PLANT UNIT 1 PAGE: 16 4 REVISION: 5 ISI
SUMMARY
REPORT NO. NP0059 0005 l FIRST INTERVAL, THIRD PERIOD, FIRST CUTAGE (96RF)
} CLASS 1 COMPLETED COMPONENTS REACTOR SYSTEM N O ASME O G T SEC. XI R E H
SUMMARY
EXAMINATION AREA CATGY EXAM E oE l NUMBER SIZE-SCHEDULE LINE SPEC ITEM NO METHOD NDE REPORTS C M R REMARKS (REF. DWG. NO. S$-305-006 107)
( 006600 1B13 N2F KA B-D M-UT 1Q800-96-0037 X GEOMETRIC AND NON RELEVANT INDICATIONS RECIRC INLET N0ZZLE N2F TO B3.90 -
(GE #96-702 15) RECORDED. EXAM LIMITED TO 72% COMPLETE VESSEL BY N0ZZLE GEOMETRY (IR-001). l 12" -N/A -N/A 006610 1813-N2F-KB B-F M UT 10800-96-0084 X NON RELEVANT INDICATIONS RECORDED. EXAM RECIRC. INLET N0ZZLE N2F TO 85.10 -
(CE #96 209-19) LIMITED TO 91% COMPLETE BY N0ZZLE SAFE-END PT GEOMETRY (IR-001). PT PERFORMED WITH l 12" -1.125" -N/A AUGMENTED UT EXAM IN RF02.
006630 1813-N2G-!R BD M-UT 1Q800 96-0061 X G50 METRIC AND NON RELEVANT INDICATIONS RECIRC INLET N0ZZLE N2G INNER B3.100 -
(CE #96-703 19) RECORDED.
RADIUS 12" N/A -N/A '
%.) 1 006640 1813-N2G KA SD M-UT 10800-96 0039 X GEOMETRIC AND NON RELEVANT INDICATIONS RECIRC INLET N0ZZLE N2G TO B3.90 -
(GE #96 702 17) RECORDED. EXAM LIMITED To 72% COMPLETE VESSEL BY N0ZZLE GEOMETRY (IR 001).
12" -N/A -N/A 006650 1813 N2G-KB BF M-UT 10800-96-0078 X NON RELEVANT INDICATIONS RECORDED. EXAM RECIRC. INLET N0ZZLE N2G To B5.10 -
(CE #96-209-13) LIMITED TO 91% COMPLETE BY N0ZZLE SAFE END PT GEOMETRY (IR*001). PT PERFORMED WITH ,
12" 1.125" -N/A AUGMENTED UT EXAM IN RF02. l 006670 1B13 N2H-IR B-D M-UT 1Q800-96 0058 X GEOMETRIC AND NON RELEVANT INDICATIONS RECIRC INLET N0ZZLE N2H INNER B3.100 -
(CE #96 703-16) RECORDED.
RADIUS 12" -N/A -W/A 006680 1813 N2H KA B-D M UT 10800 96 0035 X GEOMETRIC AND NON RELE/ ANT INDICATIONS RECIRC INLET N0ZZLE N2H TO B3.90 -
(CE #96-702-13) RECORDED. EXAM LIMITED TO 70% COMPLETE VESSEL BY N0ZZLE GEOMETRY AND ADJACENT N9 12" -N/A -N/A N0ZZLE (IR-001).
O Page 36
REPORT NO. NP0059-0005 DATE: 04/04/96 PERRY NUCLEAR POWER PLANT UNIT 1 PAGE: 17 i I ISI
SUMMARY
REPORT NO. NP0059 0005 5 l l l'_ REVISION:
\ FIRST INTERVAL, THIRD PERIOD, FIRST OUTAGE (96RF) l CLASS 1 COMPLETED COMPONENTS REACTOR SYSTEM i N O l l
ASME O G T l SEC. XI R E H l
SUMMARY
EXAMINATION AREA CATGY EXAM E O E NUMBER SIZE-SCHEDULE-LINE SPEC ITEM NO METHOD NDE REPORTS C M R REMARKS (REF. DWG. NO. SS-305-006-107) 006690 1B13 N2H KB B-F M-UT 1Q800-96 0083 X NON RELEVANT INDICATIONS RECORDED. EXAM .
REC!RC. INLET N0ZZLE N2H TO B5.10 -
(CE #96-209-18) LIMITED TO 91% COMPLETE BY N0ZZLE l SAFE END PT GEOMETRY (IR-001). PT PERFORMED WITH 12" -1.125" -N/A AUGMENTED UT EXAM IN RF02. ,
1 006740 1813-N2J-KB Q X-G M-UT 10800 96 0077 X NON RELEVANT INDICATIONS RECORDED. EXAM RECIRC. INLET N0ZZLE N2J TO X0.12 -
(CE #96 209-12) LIMITED TO 91% COMPLETE BY N0ZZLE SAFE-END GEOMETRY. i 12" -1.125" -N/A l 006750 1B13-N2K-IR B-D M UT 1Q800 96-0056 X GEOMETRIC AND NON RELEVANT INDICATIONS RECIRC INLET N0ZZLE N2K INNER 83.100 -
(GE #96-703-14) RECORDED.
RADIUS 12" N/A -N/A (3
x) 006760 1813-N2K-LA BD M-UT 1Q800-96-0034 X GEOMETRIC AND NON RELEVANT INDICATIONS RECIRC INLET NO22LE N2K TO B3.90 -
(GE #96-702-12) RECORDED. EXAM LIMITED TO 72% COMPLETE VESSEL BY N0ZZLE GEOMETRY (IR-001).
12" N/A -N/A 006760 1B13-N2K KB 9 X-G M UT 10800-96-0082 X NON RELEVANT INDICATIONS RECORDED. EXAM RECIRC. INLET N0ZZLE N2K TO X0.12 -
(GE #96-209 17) LIMITED TO 91% COMPLETE BY N0ZZLE SAFE-END GEOMETRY.
12" -1.125" -N/A (PEF. DWG. NO. $$-305-006-105) 006320 1813 N38 IR BD M UT 10800 96 0052 X GEOMETRIC AND NON RELEVANT INDICATIONS MS N0ZZLE N38 INNER RADIUS B3.100 -
(CE #96-703-10) RECORDED.
26" -N/A -N/A 006830 1813 N38-KA B-D M UT 10800-96-0031 X GEOMETRIC AND NON RELEVANT INDICATIONS MS N0ZZLE N3B TO VESSEL B3.90 -
(CE #96-702-09) RECORDED. EXAM LIMITED TO 71% COMPLETE 26" N/A -N/A BY N0ZZLE GEOMETRY.
- O Page 37 l
i I
REP 3RT No. NP0059-0005 DATE: 04/04/96 PERRY NUCLEAR POWER PLANT UNIT 1 PAGE: 18 REVISION: 5 ISI
SUMMARY
REPORT NO. NP0059-0005
) FIRST INTERVAL, THIRD PERIOD, FIRST OUTAGE (96RF)
CLASS 1 COMPLETED COMPONENTS l REACTOR SYSTEM N O ASME O G T SEC. XI R E H
SUMMARY
EXAMINATION AREA CATGY EXAM E O E l NUMBER SIZE SCHEDULE-LINE SPEC ITEM NO METHOD NDE REPORTS C M R REMARKS '
(REF. DWG. NO. SS-305-006-105) 006840 1813 N38-KB BF UT 0944/08 96-0031 X NONE. I MS N0ZZLE N38 To SAFE-END B5.10 26" 1.88" -N/A MT 0942-96A-0047 X 006350 1B13-N3C-!R B-D M-UT 1Q800 96-0053 X GEOMETRIC AND NON RELEVANT INDICATIONS MS N0ZZLE N3C INNER RADIUS B3.100 -
(GE #96-703 11) RECORDED.
26" N/A -N/A 006860 1B13-N3C-KA BD M UT 10800-96-0033 X GEOMETRIC AND NON RELEVANT INDICATIONS MS N0ZZLE N3C TO VESSEL B3.90 -
(GE #96 702-11) RECORDED. EXAM LIMITED TO 71% COMPLETE 26" -N/A -N/A BY N0ZZLE GEOMETRY.
006870 1B13 N3C KB BF UT 0944/08-96-0032 X NONE.
MS N0ZZLE N3C TO SAFE-END B5.10 IO 26" 1.88" -N/A MT 0942-96A-0047 X 006880 1813-N30-IR B-D M-UT 1Q800 96-0054 X GEOMETRIC AND NON RELEVANT INDICATIONS MS N0ZZLE N3D INNER RADIUS B3.100 - (GE #96-703-12) RECORDED.
26" -N/A -N/A 006890 1813 N30 KA B-D M-UT 1Q800-96-0030 X CE0 METRIC AND NON RELEVANT INDICATIONS MS N0ZZLE N3D TO VESSEL B3.90 -
(GE #96 702-08) RECORDED. EXAM LIMITED TO 71% COMPLETE 26" -N/A -N/A BY N0ZZLE GEOMETRY.
006900 1813-N3D KB B-F UT 0944/08-96 0030 X NONE.
MS N0ZZLE N30 TO SAFE END B5.10 26" 1.88" -N/A MT L942-96A-0046 X (REF. DWG. NO. SS-305 006-108) 006920 1B13-N4A IR BD M-UT 10800 96 0050 X GEOMETRIC AND NON RELEVANT INDICATIONS FW N0ZZLE N4A INNER RADIUS B3.100 -
(CE #96-703 08) RECORDED.
12" -N/A -N/A O
Page 38
l REPCRT NO. NP0059-0005 DATE: 04/04/96 PERRY NUCLEAR POWER PLANT UNIT 1 PAGE: 19 REVISION: 5 ISI
SUMMARY
REPORT NO. NP0059 0005
[T FIRST INTERVAL, THIRD PERIOD, FIRST OUTAGE (96RF)
CLASS 1 COMPLETED COMPONENTS REACTOR SYSTEM N O ASME O G T SEC. XI R E H
SUMMARY
EXAMINATION AREA CATGY EXAM E O E NUMBER SIZE SCHEDULE-LINE SPEC ITEM NO METHOD NDE REPORTS C M R REMARKS (REF. DWG. No. SS-305-006-108) 006930 1B13 N4A-KA B-D M-UT 10800-96-0025 X GEOMETRIC AND NON RELEVANT INDICATIONS FW N0ZZLE N4A TO VESSEL B3.90 -
(GE #96-702-03) RECORDED. EXAM LIMITED TO 73% COMPLETE 12" N/A N/A BY N0ZZLE GEOMETRY (!R 001).
006940 1B13-N4A KB B-F M-UT 1Q800-96 0069 X GEOMETRIC AND NON RELEVANT INDICATIONS FEEDWATER N0ZZLE N4A TO B5.10 -
(CE #96 209-04) RECORDED. EXAM LIMITED TO 94% COMPLETE SAFE-END PT BY N0ZZLE GEOMETRY (IR 001). PT 12" -1.16" -N/A PERFORMED WITH AUGMENTED UT EXAM IN RF02.
006970 1B13-N4B-!R B-D M UT 1Q800-96-0047 X GEOMETAIC AND NON RELEVANT INDICATIONS FW N0ZZLE N4B INNER RADIUS B3.100 -
(GE #96-703 04) RECORDED. INDICATIONS RECORDED IN RF04 12" -N/A -N/A AS CORNER FLAWS (REFERENCE NR 94 S-248)
WERE DETERMINED TO BE NON RELEVANT.
9 06980 1813-N48 KA BD M-UT 10800-96-0024 X GEOMETRIC AND NON RELEVANT INDICATIONS FW N0ZZLE N48 TO VESSEL B3.90 -
(GE #96-702-02) RECORDED. EXAM LIMITED TO 73% COMPLETE 12" -N/A -N/A BY N0ZZLE GEOMETRY (IR-001).
006990 1813 N4B-KB B-F M UT 10800-96-0068 X GEOMETRIC AND NON RELEVANT INDICATIONS FEEDWATER N0ZZLE N48 To B5.10 -
(CE #96-209 03) RECORDED. EXAM LIMITED TO 94% COMPLETE SAFE END PT BY N0ZZLE GEOMETRY (IR-001). PT 12" -1.16" N/A PERFORMED WITH AUGMENTED UT EXAM IN RF02.
007025 1813-N4C-IR G X-C M-UT 1Q800-96-0045 X CE0 METRIC AND NON RELEVANT INDICATIONS FW N0ZZLE N4C INNER RADIUS X0.6 -
(GE #96-703 02) RECORDED.
12" -N/A -N/A 007050 1B13 N4C-KB G XG M-UT 10800 96 0066 X X RESIZED FLAW INDICATION WHICH WAS j FEEDWATER N0ZZLE N4C TO X0.13 -
(CE #96 209-01) DISCOVERED IN RF02 AND STRESS IMPROVED '
SAFE END IN RF03. FLAW WAS $1 ZED .08" DEEPER, BUT 12" 1.16" -N/A CHANGE IS ATTRIBUTED TO DIFFERENT PERS., ;
EQUIP., AND TECHN! QUES, NOT AN ACTUAL PHYSICAL CHANCE. P!F 96 1015 WRITTEN TO TREND $1 ZING.
b U
Page 39
REPERT N3. NP0059-0005 DATE: 04/04/96 PERRY NUCLEAR POWER PLANT UNIT 1 PAGE: 20 REVISION: 5 ISI
SUMMARY
REPORT NO. NP0059-0005
[]
V FIRST INTERVAL, THIRD PERIOD, FIRST OUTAGE (96RF)
CLASS 1 COMPLETED COMPONENTS REACTOR SYSTEM N O ASME O G T SEC. XI R E H
SUMMARY
EXAMINATION AREA CATGY EXAM E O E NUMBER SIZE SCHEDULE-LINE SPEC ITEM NO METHOD NDE REPORTS C M R REMARKS (REF. DWG. NO. SS-305-006-108) 007070 1813-N4D-IR B-D M-UT 10800 96 0089 X GEOMETRIC AND NON RELEVANT INDICATIONS FW N0ZZLE N40 INNER RADIUS B3.100 -
(GE #96-703 06) RECORDED.
12" -W/A -N/A 007080 1913-N4D-KA B-D M-UT 1Q800-96-0026 X GEOMETRIC AND NON RELEVANT INDICATIONS FW N0ZZLE N40 TO VESSEL B3.90 -
(GE #96-702 04) RECORDED. EXAM LIMITED TO 73% COMPLETE 12" -N/A -N/A BY N0ZZLE GEOMETRY (IR 001).
007090 1813 N40-KB B-F M-UT 1Q800-96-0071 X GEOMETRIC AND NON RELEVANT INDICAT10NS FEEDWATER N0ZZLE N4D To B5.10 -
(GE #96-209-06) RECORDED. EXAM LIMITED TO 94% COMPLETE SAFE-END PT BY N0ZZLE GEOMETRY (IR 001). PT 12" ~1.16" N/A PERFORMED WITH AUGMENTED UT EXAM IN RF02.
b g /120 1813 N4E !R B-D M UT 1Q800 96-0044 X GEOMETRIC AND NON RELEVANT INDICATIONS FW N0ZZLE N4E INNER RADIUS B3.100 -
(CE #96-703-01) RECORDED. INDICATIONS RECORDED IN RF04 12" -N/A -N/A AS CORNER FLAWS (REFERENCE NR 94-S-248)
WERE DETERMINED TO BE NON RELEVANT.
007130 1813 N4E-KA B-D M UT 10800-96-0023 X GEOMETRIC AND NON RELEVANT INDICATIONS FW N0ZZLE N4E TO VESSEL B3.90 -
(GE #96-702-01) RECORDED. EXAM LIMITED TO 73% COMPLETE 12" -N/A -N/A BY N0?ZLE GEOMETRY (IR-001).
007140 1813 N4E-KB B-F M UT 1Q800 96-0067 X X RES! ZED FLAW INDICATION THAT WAS FEEDWATER N0ZZLE N4E To B5.10 -
(CE #96-209 02) DISCOVERED IN RF02 AND STRESS IMPROVED SAFE-END PT IN RF03. SIZE WAS FOUND TO BE 12" -1.16" -N/A ESSENTIALLY THE SAME. PIF 96-1015 WRITTEN TO TREND SIZING. N0ZZLE GEOM LIMITS EXAM COVERAGE TO 94% (IR-001). PT PERFORMED WITH AUG UT IN RF02. l l
007175 1813 N4F-!R S XC M UT 1Q800-96-0046 X GEOMETRIC AND NON RELEVANT INDICATIONS FW N0ZZLE N4F INNER RADIUS X0.6 -
(CE #96-703-03) RECORDED.
12" -N/A -N/A O
Page 40
. - _ ~ . - _ ~ . . _ - -- . - - .-. . - - _ _ _ _
REPORT NO. NP0059-0005 DATE: 04/04/96 PERRY NUCLEAR POWER PLANT UNIT 1 PAGE: 21
+
REVISION: 5 ISI
SUMMARY
REPORT NO. NP0059-0005 FIRST INTERVAL, THIE PERIOD, FIRST OUTAGE (96RF)
CLASS 1 COMPLETED COMPONENTS REACTOR SYSTEM N O ASME O G T SEC. XI R E H
SUMMARY
EXAMINATION MEA CATGY EXAM E O E NUMBER SIZE SCHEDUlli LINE SPEC ITEM NO METHOD NDE REPORTS C M R REMARKS (REF. DV4. NO. SS 305-006-108) 007200 1B13-H F KB B XG M-UT 1Q800-96-0070 X CE0 METRIC AND NON RELEVANT INDICATIONS FEED?A1ER N0ZZLE N4F TO X0.12 -
(CE #96 209-05) RECORDED. EXAM LIMITED TO 94% COMPLETE SAF4-END BY N0ZZLE GEOMETRY.
1I9 -1.16" -N/A (REF. DWG. NO, SS-305-006-109) 007210 1813 NSA !R B-D M-UT 10800-96-0049 X GEOMETRIC AND NON RELEVANT INDICATIONS 1 CS N0ZZLE NSA INNER RADIUS B3.100 -
(CE #96-703-07) RECORDED.
. 12" -N/A -N/A 007220 1813-N5A-KA B-D M-UT 10800-96-0028 X GEOMETRIC AND NON RELEVANT INDICATIONS CS N0ZZLE NSA TO VESSEL B3.90 -
(GE #96 702 06) RECORDED. EXAM LIMITED TO 73% COMPLETE 12" -N/A -N/A BY N0ZZLE GEOMETRY (IR-001).
7230 1813 NSA-KB B-F M UT 10800-96-0072 X GEOMETRIC AND NON RELEVANT INDICATIONS LOW PRES. CORE SPRAY N0ZZLE To B5.10 -
(GE #96 209-07) RECORDED. EXAM LIMITED TO 84% COMPLETE SAFE-END PT BY N0ZZLE GEOMETRY (IR-001). PT 12" 1.125" -N/A PERFORMED WITH AUGMENTED UT EXAM IN RF02.
007260 1B13 N58-IR BD M-UT 10800-96 0048 X CE0 METRIC AND NON RELEVANT INDICATIONS i CS N0ZZLE NSB INNER RADIUS B3.100 -
(CE #96-703 05) RECORDED.
12" N/A -N/A 007270 1B13-N58 KA B-D M-UT 10800-Y6-0027 X CE0 METRIC AND NON RELEVANT INDICATIONS CS N0ZZLE NSB TO VESSEL B3.90 -
(GE #96 702 05) RECORDED. EXAM LIMITED To 73% COMPLETE 12" -N/A N/A BY N0ZZLE GEOMETRY (IR 001).
4 007250 1813-N58 KB B-F M-UT 1Q800-96 0073 X GEOMETRIC AND NON RELEVANT INDICATIONS HIGH PRES. CORE SPRAY N0ZZLE B5.10 -
(CE #96-209 08) RECORDED. EXAM LIMITED TO 84% COMPLETE TO SAFE-END PT BY N0ZZLE GEOMETRY (IR-001). PT 12" -1.125" N/A PERFORMED WITH AUGMENTED UT EXAM IN RF02.
4
- V Page 41 1
REPORT ND. NP0059-0005 DATE: 04/04/96 PERRY NUCLEAR POWER PLANT UNIT 1 PAGE: 22 REVISION:
~
5 ISI
SUMMARY
REPORT NO. NP0059-0005 FIRST INTERVAL, THIRD PERIOD, FIRST OUTAGE (96AF)
.k CLASS 1 COMPLETED COMPONENTS REACTOR SYSTEM N O ASME O G T SEC. XI R E H
SUMMARY
EXAMINATION AREA CATGY EXAM E O E NUMBER SIZE SCHEDULE-LINE SPEC ITEM NO METHOD NDE REPORTS C M R REMARKS (REF. DWG. NO. SS-305-006-109) 007310 1B13-N6A IR B-D M-UT 10800-96-0055 X CEOMETRIC AND NON RELEVANT INDICATIONS RHR N0ZZLE N6A INNER RADIUS B3.100 -
(GE #96-703-13) RECORDED.
12" -N/A -N/A 007320 1B13 N6A-KA B-D M UT 1Q800 96-0032 X GEOMETRIC AND WON RELEVANT INDICATIONS RHR N0ZZLE N6A TO VESSEL B3.90 -
(CE #96-702 10) RECORDED. EXAM LIMITED TO 74% COMPLETE 12" N/A -N/A BY N0ZZLE GEOMETRY (IR-001).
007330 1813 N6A-KB B-F M-UT 1Q800-96-0075 X GEOMETRIC AND NON RELEVANT INDICATIONS RHR N0ZZLE N6A TO SAFE-END B5.10 -
(CE #96-209-10) RECORDED. EXAM LIMITED TO 93% COMPLETE 12" -1.125" -N/A PT BY N0ZZLE GEOMETRY (IR-C01). PT PERFORMED WITH AUG UT EXAM IN RF02.
C 7360 1813 N68-!R B-D M-UT 10800 96-0051 X GEOMETRIC AND NON RELEVANT INDICATIONS Q RHR N0ZZLE N6B INNER RADIUS 12" -N/A -N/A B3.100 -
(GE #96-703 09) RECORDED.
007370 1B13-N68-KA BD M-UT 10800-96-0029 X GEOMETRIC AND NON RELEVANT INDICATIONS RHR N0ZZLE N68 TO VESSEL B3.90 -
(CE #96 702-07) RECORDED. EXAM LIMITED TO 74% COMPLETE 12" -N/A -N/A BY N077LE GEOMETRY (IR-001).
007380 1813 N68 KB B-F M-UT 1Q800-96-0076 X GEOMETRIC AND NON RELEVANT INDICATIONS RHR N0ZZLE N6B TO SAFE-END B5.10 -
(GE #96-209-11) RECORDED. EXAM LIMITED TO 93% COMPLETE 12" -1.125" -N/A PT BY N0ZZLE GEOMETRY (IR-001). PT PERFORMED WITH AUG UT EXAM IN RF02.
007440 1813 N6C-KB E X-G M-UT 1Q800-96-0074 X CE0 METRIC AND NON RELEVANT INDICATIONS RHR N0ZZLE N6C TO SAFE END X0.12 -
(CE #96-209-09) RECORDED. EXAM LIMITED TO 93% COMPLETE 12" -1.125" -M/A BY N0ZZLE GEOMETRY.
(REF. DWG. NO. SS-305-006-103) 007490 1813-W8 B B-G-2 VT-1 1042 96A-0233 X 12 STUDS & NUTS EXAMINED IN PLACE UPON RPV HEAD SPRAY N0ZZLE N8 TO B7.10 REACTOR HEAD SPRAY REASSEMBLY.
FLANGE BOLTING 6" W/A N/A O
l Page 42
REPORT NO. NP0059-0005 DATE: 04/04/96 PERRY NUCLEAR POWER PLANT UNIT 1 PAGE: 23 REVISION: 5 ISI
SUMMARY
REPORT NO. NP0059-0005
[# 'l FIRST INTERVAL, THIRD PERIOD, FIRST OUTAGE (96RF)
(./ CLASS 1 COMPLETED COMPONENTS REACTOR SYSTEM N O ASME O G T SEC. XI R E H
SUMMARY
EXAMINATION AREA CATGY EXAM E O E NUM8ER SIZE-SCHEDULE LINE SPEC ! TEM NO METHOD NDE REPORTS C M R REMARKS (REF. DWG. NO. SS-305-006-106) 007550 1813 N9A KB G X-G UT 10B00-96 0001 X NONE.
I JET PUMP INSTRUMENT N0ZZLE N9A X0.12 -
(GE #96-105-01) l TO SAFE-END
! 4" -N/A -N/A l
l 00 75 70 1813 N9A-KC 9 XG UT 0944/18-96-0003 X WONE.
JET PUMP INSTR. N0ZZLE N9A X0.12 SAFE-END TO PENE. SEAL 4" -N/A N/A 007580 1813-N98-IR 8-D UT 1Q800 96-0022 X NONE.
JET PUNP N0ZZLE N9B INNER B3.100 -
(CE #96-311-01)
RADIUS 4" -N/A N/A l
7590 1B13 N98-KA B-D UT 10800-96 0021 X NONE.
JET PUMP WOZZLE N98 TO VESSEL B3.90 -
(GE #96-300-01) 4" -N/A -N/A 007610 1813 W98-KB G XG UT 10800-96-0002 X NONE.
JET PUMP INSTRUMENT NO2ZLE N98 X0.12 -
(CE #96-105-02)
TO SAFE-END 4" -N/A -N/A 007630 1B13-N98 KC G XG UT 0944/18-96-0003 X NONE.
JET PUMP INSTR. N0ZZLE N98 X0.12 SAFE END TO PENE. SEAL 4" N/A -N/A (REF. DWG. NO. SS-305-006-101) 008360 1813 CSS XA VT-1 1Q800 96 0013 X NONE.
, RPV CORE SPRAY SPARGER X0.5 -
(GE #96-206-11) l N/A -N/A -N/A l
i i
l l
4 l (m_l l
Page 43 l
l l
i REPCRT NO. NP0059-0005 DATE: 04/04/96 PERRY NUCLEAR POWER PLANT UNIT 1 FAGE: 24 l
. REVISION: 5 ISI
SUMMARY
REPORT NO. NP0059-0005 FIRST INTERVAL, THIRD PERIOD, FIRST OUTAGE (96RF)
OA CLASS 1 COMPLETED COMPONENTS REACTOR SYSTEM N O l ASME O G T SEC. XI R E H
SUMMARY
EXAMINATION AREA CATGY EXAM E D E NUMBER SIZE-SCHEDULE-LINE SPEC ITEM NO METHOD NOE REPORTS C M R REMARKS 1 l (REF. DWG. NO. SS-305-006-101) 008550 1813-CSS WA B-N 2 VT-3 1Q800-96-0005 X NONE.
RPV CORE SPRAY SPARGER B13.30 - (GE #96-206-03) l BRACKET / VESSEL WELDED ATT.
N/A -N/A N/A l 008560 1813-CSSB-B X-A VT 3 10800-96-0004 X NONE.
i RPV CORE SPRAY SPARGER X0.4 -
(GE #96-206-02)
BRACKETS AND BOLTING N/A -N/A N/A 008600 1813 FS-WA B-N 2 VT-3 1Q800-96-0012 X NONE.
RPV FW SPARGER BRACKET / VESSEL B13.30 -
(GE #96-206-10)
( WELDED ATTACHMENT l N/A -N/A -N/A i
(%)
008610 1813 FSB X-A VT-3 1Q800 96-0011 X NONE.
RPV FEEDWATER SPARGER BRACKET X0.11 -
(GE #96-206-09)
N/A -N/A N/A 008630 1B13-GRa3 X-A VT-3 1Q800-96-0006 X NONE.
RPV GUIDE ROD SUPPORT BRACKET X0.11 -
(CE #96-206-04)
N/A -N/A -N/A 008640 1813-GRSB-WA BN2 VT-3 1Q800 96-0007 X NONE.
RPV GUIDE ROD SUPPORT B13.30 -
(CE #96-206-05)
BRACKET / VESSEL WELDED ATT.
N/A -N/A -N/A 008660 1813-INTER 10R BN1 VT 3 10800-96-0018 X NONE.
REACTOR VESSEL INTERIOR REGION B13.10 -
(GE #96-206-16)
N/A -N/A -N/A i r t
Page 44 l
REPORT NO. NP0059-0005 DATE: 04/04/ % PERRY NUCLEAR POWER PLANT UNIT 1 PAGE: 25
. REVISION: 5 ISI
SUMMARY
REPORT NO. NP0059-0005 FIRST INTERVAL, THIRD PERIOD, FIRST OUTAGE (96RF)
CLASS 1 COMPLETED COMPONENTS RFACTOR SYSTEM N O ASME O G T SEC. XI R E H
SUMMARY
EXAMINATION AREA CATGY EXAM E O E NUMBER SIZE-SCHEDULE LINE SPEC ITEM NO METHOD NDE REPORTS C M R REMARKS (REF. DWG. NO. SS-305-006-101) 008950 1813-JPLAW P01 X-A VT 3 10800 96-0014 X NONE.
JET PUMP SENSING LINE X0.3 -
(GE M6-206-12)
ATTACHMENT WLLDS N/A N/A N/A ,
l J
008960 1B13 JPLAW-P02 X-A VT-3 10800 96-0014 X NONE.
JET PUMP SENSING LINE X0.3 -
(GE M6-206-12)
ATTACHMENT WELDS N/A -N/A N/A 008970 1813 JPLAW-P03 X-A VT-3 10800-96-0014 X NONE.
JET PUMP SENSING LINE X0.3 -
(GE M6-206-12)
ATTACHMENT WELDS N/A N/A -N/A O008980 1813-JPLAW-PO4 X-A VT-3 10800 96-0014 X NONE.
JET PUMP SENSING LINE X0.3 -
(GE M6-206-12)
ATTACHMENT WELDS N/A N/A N/A 008990 1813-JPLAW-P05 X-A VT-3 10800 96-0014 X NONE.
JET PUMP SENSING LINE X0.3 -
(GE M6-206-12)
ATTACHMENT WELDS N/A N/A -N/A 009000 1813-JPLAW-P06 X-A VT-3 1Q800-96-0014 X NONE.
JET PUMP SENSING LINE X0.3 -
(GE M6-206-12)
ATTACHMENT WELDS N/A N/A N/A 009010 1B13-JPLAW P07 X-A VT-3 10800 96-0014 X NONE.
JET PUMP SENSING LINE X0.3 -
(CE M6-206-12)
ATTACHMENT WELDS N/A -N/A -N/A Page 45
REPORT No. NP0059-Q005 l DATE: 04/04/96 PERRY NUCLEAR POWER PLANT UNIT 1 PAGE: 26 REVIS10W: 5 ISI
SUMMARY
REPORT NO. NP0059-0005 O FIRST INTERVAL, THIRD PERIOD, FIRST OUTAGE (96RF) I U CLAs$ 1 COMPLETED COMPONENTS l REACTOR SYSTEM I N 0 ASME O G T SEC. XI R E H
SUMMARY
EXAMINATION AREA CATGY EXAM E D E NUMBER SIZE-SCHEDULE-LINE SPEC ITEM NO METHOD NDE REPORTS C M R REMARKS (REF. DWG. NO. SS-305 006-101) '
009020 1B13 JPLAW-P08 XA VT 3 1Q800-96 0014 X NONE.
l JET PUMP SENSING LINE X0.3 -
(GE #96-206 12)
ATTACHMENT WELDS N/A -N/A -N/A 009030 1B13-JPLAW-P09 X-A VT-3 10800-96-0014 X NONE.
JET PUMP SENSING LINE X0.3 -
(GE #96-206 12)
ATTACHMENT WELDS N/A -N/A N/A 009040 1B13-JPLAW-P10 X-A VT-3 10800-96-0014 X NONE.
JET PUMP SENSING LINE X0.3 -
(GE #96-206 12)
ATTACHMENT WELDS N/A -N/A -W/A 9 09050 1813 JPLAW-P11 X-A VT-3 1Q800-96-0014 X NONE.
JET PUMP SENSING LINE X0.3 -
(GE #96 206-12)
ATTACHMENT WELDS N/A -N/A -N/A I 009060 1B13-JPLAW P12 X-A VT 3 1Q800- % 0014 X NONE.
JET PUMP SENSING LINE X0.3 -
(GE #96-206-12)
ATTACHMENT WELDS N/A -N/A N/A 009070 1B13-JPLAW-P13 X-A VT-3 1Q800-96-0014 X NONE.
JET PUMP SENSING LINE X0.3 -
(CE #96-206-12)
ATTACHMENT WELDS N/A N/A -N/A 009080 1B13-JPLAW-P14 XA VT 3 1Q800-96-0014 X NONE.
JET PUMP SENSING LINE X0.3 -
(CE #96-206-12)
ATTACHMENT WELDS N/A N/A -N/A b
Q Page 46
-. _ -.. . .-. . - _ - - ~
l t
REPSRT NO. NP0059-0005 DATE: 04/04/ % PERRY NUCLEAR POWER PLANT UNIT 1 PAGE: 27 REVISION: 5 ISI SUMC4ARY REPORT NO. NP0059-0005 FIRST INTERVAL, THIRD PERIOD, FIRST OUTAGE (96RF)
CLASS 1 COMPLETED COMPONENTS REACTOR SYSTEM N O ASME O G T SEC. XI R E H
SUMMARY
EXAMINATIGN AREA CATGY EXAM E O E NUMBER SIZE-SCHEDULE-LINE SPEC ITEM NO METHOD NDE REPORTS C M R REMARKS I l
l (REF. DWG. NO. SS 305-006-101)
I l 009090 1B13 JPLAW P15 XA VT-3 10800-96 0014 X NONE.
l JET PUMP SENSING LINE X0.3 -
(GE #96 206 12) ;
l ATTACHMENT WELOS ;
N/A -N/A -N/A '
l l
1 009100 1B13-JPLAW-P16 XA VT-3 10800 96 0014 X NONE. l JET PUMP SENSING LINE X0.3 -
(GE #96-206 12) !
ATTACHMENT WELDS N/A -N/A N/A l
009110 1B13-JPLAW-P17 X-A VT-3 10800-96 0014 X NONE.
JET PUMP SENSING LINE X0.3 -
(CE #96-206 12)
)
ATTACHMENT WELDS N/A -N/A -N/A i O
I l
4
/ 1 UO9120 1B13-JPLAW-P18 X-A VT-3 10800-96-0014 X NONE.
JET PUMP SENSING LINE X0.3 -
(CE #96-206 12)
ATTACHMENT WELDS N/A -N/A -N/A 009130 1813-JPLAW P19 X-A VT-3 10800 96 0014 X NONE.
JET PUMP SENSING LINE X0.3 -
(CE #96 206 12)
ATTACHMENT WELDS N/A N/A N/A 009138 1813-
- LAW-P20 X-A VT-3 10800-96-0014 X NONE.
JET PUMP SENSING LINE X0.3 -
(GE #96-206-12)
ATTACHMENT WELDS N/A -N/A -N/A 009110 1B13 JPRB P1/P2 X-A VT-3 10800 96 0016 X NONE.
JET PUMP RISER BRACE X0.14 -
(GE #96-206 14)
N/A -N/A -N/A f
\
Page 47
REPORT N3. NP0059-0005 PAGE: 28 DATE: 04/04/96 PERRY WUCLEAR POWER PLANT UNIT 1 REVISION: 5 ISI
SUMMARY
REPORT NO. NP0059-0005 FiRST INTERVAL, THIRD PERIOD, FIRST OUTAGE (96RF)
O REACTOR SYSTEM CLASS 1 COMPLETED COMPONENTS N O ASME D G T SEC. XI R E H
SUMMARY
EXAMINATION AREA CATGY EXAM E O E NUMBER SIZE-SCHEDULE-LINE SPEC ITEM NO METHOD NDE REPORTS C M R REMARKS (REF. DWG. No. SS-305-006-101)
XA VT-3 10800-96-0016 X NONE.
009141 1913 JPRB P3/P4 JET PUMP RISER BRACE X0.14 -
(GE M6-206-14)
N/A N/A -N/A X-A VT 3 10800-96-0016 X NONE.
009142 1B13-JPRB P5/P6 JET PUMP RISER BRACE X0.14 -
(GE M6-206-14)
N/A -N/A -N/A 009143 1913-JPRB-P7/PB X-A VT-3 10800- % -0016 X NONE.
JET PUMP RISER BRACE X0.14 -
(GE M6-206-14)
N/A -N/A -N/A 009144 1813-JPRB-P9/P10 X-A VT-3 10800- % -0016 X NONE.
/ JET PUMP RISER BRACE X0.14 -
(GE M6-206-14)
N/A -N/A N/A 009145 1813-JPRB-P11/P12 X-A VT-3 10800- % -0016 X NONE.
JET PUMP RISER BRACE X0.14 -
(GE #96-206-14)
N/A N/A -N/A 009146 1B13-JPRB P13/P14 X-A VT-3 1Q800-96-0016 X NONE.
JET PUMP RISER BRACE X0.14 -
(GE #96 206-14)
N/A -N/A N/A 009147 1B13-JPRB-P15/P16 X-A VT-3 10800-96-0016 X NONE.
JET PUMP RISER BRACE X0.14 -
(GE #96-206-14)
N/A -N/A -N/A 009148 1B13-JPRB P17/P18 XA VT-3 10800-96-0016 X NONE.
JET PUMP RISER BRACE X0.14 -
(GE #96-206-14)
N/A -N/A -N/A 1
Page 48 i l
)
_ i
_ 2- . . _ _ - _ - m----m.
1 REP RT N3. NP0059-0005 DATE: 04/04/96 PERRY NUCLEAR POWER PLANT UNIT 1 PAGE: 29 REVISION: 5 Isl
SUMMARY
REPORT NO. NP0059-0005 ;
[ FIRST INTERVAL, THIRD PERIOD, FIRST CUTAGE (96RF)
CLASS 1 COMPLETED COMPONENTS REACTOR SYSTEM N O ASME D G T SEC. XI R E H
SUMMARY
EXAMINATION AREA CATGY EXAM E O E NUMBER SIZE SCHEDULE-LINE SPEC ITEM NO METHOD NDE REPORIS C M R REMARKS (REF. DWG. NO. 55-305-006-101) 009119 1B13-JPRS P19/P20 X-A VT-3 10800-96 0016 X NONE.
JET PUMP RISER BRACE X0.14 -
(GE #96-206-14)
N/A N/A N/A 009150 1813-JPTW-P01 XA VT-3 1Q800-96-0015 X NONE.
JET PUMP RESTRAINER ADJUSTING X0.15 -
(GE M6-206-13)
SCREW TACK WELDS N/A N/A N/A 009160 is13-JPTW-P02 X-A VT-3 10800-96-0015 X NONE.
JET PUMP RESTRAINER ADJUSTING X0.15 -
(GE M6-206-13)
SCREW TACK WELDS N/A -N/A -N/A A
(h170 1813-JPTW-P03 JET PUMP RESTRAINER ADJUSTING X0.15 X-A VT-3 10800-96-0015 (GE M6-206-13)
X NONE.
SCREW TACK WELDS N/A -N/A -N/A 009180 1B13 JPTW-PO4 XA VT-3 10800-96-0015 X NONE.
JET PUMP RESTRAINER ADJUSTING X0.15 -
(CE M6 206-13)
SCREW TACK WELDS !
N/A -N/A -N/A I l
1 1
009190 1B13 JPTW-P05 XA VT 3 10800-96-0015 X NONE.
JET PUMP RESTRAINER ADJUSTING X0.15 -
(GE M6-206-13)
SCREW TACK WELDS N/A -N/A -N/A 009200 1B13-JPTW P06 X-A VT-3 10800-96 0015 X NONE.
JET PUMP RESTRAINER ADJUSTING X0.15 -
(GE M6-206-13)
SCREW TACK WELDS l N/A -N/A N/A
\
Page 49
REPORT NO. NP0059-0005 DATE: 04/04/96 PERRY NUCLEAR POWER PLANT UNIT 1 REVISION: 5 PAGE: 30 ISI
SUMMARY
REPORT No. NP0059 0005 I FIRST INTERVAL, THIRD PERICO, FIRST OUTAGE (96RF)
CLASS 1 COMPLETED COMPONENTS REACTOR SYSTEM N O ASME O G T SEC. XI R E H
SUMMARY
EXAMINATION AREA CATGY EXAM E O E NUMBER SIZE-SCHEDULE LINE SPEC ITEM No METHOD NDE REPORTS C M R REMARKS (REF. DVG. No. $$ 305-006-101) 009210 1813-JPTW-P07 X-A VT-3 1G800-96-0015 X NONE.
JET PUMP RESTRAINER ADJUSTING X0.15 -
(CE #96-206-13)
SCREW TACK WELDS N/A N/A -N/A 009220 1B13-JPTW P08 X-A VT-3 10800-96-0015 X NONE.
JET PUMP RESTRAINER ADJUSTING X0.15 -
(CE #96 206-13)
SCREW TACK WELDS N/A -N/A -N/A 009230 1B13-JPTW-P09 X-A VT-3 1Q800-96-0015 X NONE.
JET PUMP RESTRAINER ADJUSTING X0.15 -
(CE #96-206-13)
SCREW TACK WELDS N/A -N/A -N/A O 009240 1B13-JPTW-P10 XA VT-3 1Q800-96-0015 X NONE.
JET PUMP RESTRAINER ADJUSTING X0.15 -
(CE #96-206-13)
SCREW TACK WELDS N/A N/A -N/A 009250 1813-JPTW P11 XA VT-3 10800-96-0015 X NONE.
JET PUMP RESTRAINER ADJUSTING X0.15 -
(GE #96 206 13)
SCREW TACK WELDS N/A N/A -N/A 009260 1813-JPTW-P12 X-A VT-3 1Q800-96-0015 X NONE.
JET PUMP RESTRAINER ADJUSTING X0.15 -
(CE #96-206-13)
SCREW TACK WELDS N/A -N/A -N/A 009270 1813-JPTW P13 X-A VT-3 1Q800-96-0015 X NONE.
JET PUMP RESTRAINER ADJUSTING X0.15 -
(GE #96-206-13)
SCREW TACK WELOS N/A -N/A -N/A O
Page 50
l l
REP 5RT N3. NP0059-0005 l
)
DATE: 04/04/96 PERRY NUCLEAR POWER PLANT UNIT 1 PAGE: 31 l _ REVISION: 5 IS! SUW4ARY REPORT NO. NP0059-0005
) FIRST INTERVAL, THIRD PERIOD, FIRST OUTAGE (96RF)
CLASS 1 COMPLETED COMPONENTS ,
REACTOR SYSTEM j N 0 ASME O G T SEC. XI R E N SUNMARY EXAMINATION AREA CATGY EXAM E O E I
, t*JMBER SIZE SCHEDULE-LINE SPEC ITEM NO METHOD NDE REPORTS C M R REMARKS I
(REF. DWG. NO. SS 305-006 101) 009280 1B13-JPTW-P14 X-A VT-3 10800 % 0015 X NONE.
JET PUMP RESTRAINER ADJUSTING X0.15 -
(GE #96 206 13)
SCREW TACK WELDS 4 N/A N/A N/A i
- 009290 1B13 JPTW P15 X-A VT 3 10800-96-0015 X NONE.
I JET PUMP RESTRAINER ADJUSTING X0.15 -
(CE #96-206-13)
I SCREW TACK WELDS N/A -N/A -N/A 009300 1813 JPTW-P16 X-A VT 3 10800- % 0015 X NONE.
JET PUMP RESTRAINER ADJUSTING X0.15 -
(GE #96-206-13)
SCREW TACK WELDS N/A N/A -N/A
- 009310 1B13 JPTW-P17 XA VT-3 10800 96 0015 X NONE.
- JET PUMP RESTRAINER ADJUSTING X0.15 -
(GE #96 206 13) i SCREW TACK WELDS
s JET PUMP RESTRAINER ADJUSTING 10.15 -
(CE #96-206-13)
] SCREW TACK WELDS i N/A -N/A -N/A
}
4 009330 1B13 JPTW-P19 X-A VT-3 10800 96 0015 X NONE.
JET PUMP RESTRAINER ADJUSTlWG X0.15 -
(GE #96 206 13)
SCREW TACK WELDS N/A -N/A -N/A 009340 1813 JPTW-P20 XA VT-3 1Q800-96-0015 X NONE.
JET PUMP RESTRAINER ADJUSTING X0.15 -
(GE #96-206-13)
SCREW TACK WELDS N/A N/A -N/A O
LJ Page 51
1 i
l REPORT N3. NP0059-0005 l DATE: 04/04/96 PERRY NUCLEAR POWER PLANT UNIT 1 PAGE: 32 l REVISION: 5 ISI
SUMMARY
REPORT No. NP0059 0005
)
O REACTOR SYSTEM FIRST INTERVAL, THIRD PERIOD, FIRST DUTAGE (96RF)
CLASS 1 COMPLETED COMPONENTS N O ASME O G T SEC. XI R E H
SUMMARY
EXAMINATION AREA CATGY EXAM E O E NUMBER SIZE-SCHEDULE-LINE SPEC ITEM NO METHOD NDE REPORTS C M R REMARKS (REF. DWG. NO. SS-305-006-101) !
1 009660 1813 RNR/LPCI X-A VT-3 10800-96-0008 X NONE. !
RPV RHR/LPCI LINES X0.11 -
(GE #96-206-06) )
N/A N/A -N/A 1 l
009710 1813-SHSB X-A VT-3 10800-96-0003 X OF THE 19 REMAINING SHSB'S, ONLY 5 RPV SHROUD HEAD STUD BOLTS X0.5 -
(CE #96-206-01) EXHIBITED AN INCREASE IN WEAR. ONE FROM N/A -N/A -N/A VERY SLIGHT TO SLIGHT, THREE FROM SLIGHT TO MODERATE, AND ONE RF04 REPLACEMENT HAD SLIGHT WEAR ALREADY. No EXCESSIVE WEAR WAS FOUND. PIF 96-559 WRITTEN TO TPEND THE WEAR.
009790 1815-SSANC X-A VT 1 1Q800-96-0017 X NONE.
l RPV SHROUD SUPPORT ACCESS HOLE X0.11 -
(GE #96-206-15) l COVER WELD l
.I N/A -N/A -N/A I i
D09800 1B13-S$H 1 X-A VT 3 1Q800-96-0009 X NONE.
RPV SURVEILLANCE SAMPLE HOLDER X0.11 -
(GE #96-206-07) )
AT 3 DEG
, N/A -N/A -N/A l i
009810 1B13 SSH-2 X-A VT-3 1Q800-96-0009 X NONE.
3 RPV SURVEILLANCE SAMPLE HOLDER X0.11 -
(GE #96-206-07)
AT 177 DEG s
N/A -N/A -N/A l
4
. 009820 1813 SSH-3 X-A VT-3 1Q800-96-0009 X NONE.
l RPV SURVEILLANCE SAMPLE HOLDER X0.11 -
(CE #96 206-07)
AT 183 DEG N/A -N/A -N/A 1
i 009830 1813 SSH-WA-1 B-N 2 VT-1 1Q800-96-0010 X NONE.
RPV SAMPLE HOLDER, WELDED B13.20 -
(CE #96-206-08) j ATTACHWENT AT 3 DEG
, H/A -N/A -N/A i
a Page 52
r I
REPORT NO. NP0059-0005 DATE: 04/04/ % PERRY NUCLEAR POWER PLANT UNIT 1 PAGE: 33 I REVISION: 5 ISI
SUMMARY
REPORT No. NP0059-0005
! FIRST INTERVAL, THIRD PERIOD, FIRST GUTAGE (96RF)
}
d CLASS 1 COMPLETED COMPONENTS REACTOR SYSTEM N O ASME O G T SEC. XI R E H
SUMMARY
EXAMINATION AREA CATGY EXAM E O E l NUMBER SIZE-SCHEDULE LINE SPEC ITEM NO METHOD NDE REPORTS C M R REMARKS j l
(REF. DWG. NO. SS-305-006-101) l 009840 1813-SSH-WA-2 B-N-2 VT 1 1Q800-96-0010 X NONE.
RPV SAMPLE HOLDER, WELDED B13.20 -
(GE #96-206-08) i ATTACHMENT AT 177 DEG N/A -N/A -N/A
( 009850 1813-SSH-WA-3 BN2 VT-1 1Q800-96-0010 X NONE.
l RPV SAMPLE HOLDER, WELDED B13.20 -
(GE #96-206-08) 1 ATTACHMENT AT 183 DEG l N/A -N/A -N/A i l \
l l
[ !
l l
l t
I i
l l
l t
l l
I l
l l
l 1
I l
i Page 53
l REPORT NO. NP0059-0005 DATE: 04/04/ % PERRY NUCLEAR POWER PLANT UNIT 1 PAGE: 34 REVISION: 5 ISI
SUMMARY
REPORT NO. NP0059-0005 FIRST INTERVAL, THIRD PERIOD, FIRST OUTAGE (96RF)
O' MAIN STEAM CLASS 1 COMPLETED COMPONENTS N O ASME O G T SEC. XI R E H
SUMMARY
EXAMINATION AREA CATGY EXAM E O E NUMBER $1ZE-SCHEDULE-LINE SPEC ITEM NO METHOD NDE REPORTS C M R REMARKS l (REF. DWG. No. SS-305-605-104) l
! 010360 1B21-0038 BJ UT 0944/08-96-0024 X NONE.
N0ZZLE N3D SAFE-END TO 26" 89.11 PIPE MT 0942-96A 0044 y 26" -1.1%" -D1-1 (REF. DWG. No. SS-305-605-106) 011660 1821-0149 BJ PT 0941 96A-0018 X NONE.
3" PIPE TO B.W. CONNECT 10N B9.21 (HIGH STRESS) 3" 160 -D1-1 011700 1B21 0153 8J PT 0941-96A-0012 X NONE.
2" PIPE TO ELBOW (HIGH STRESS) 89.21 p 2" -160 -D1-1 o
011740 1821-0157 B-J PT 0941-96A-0012 X NONE.
2" PIPE TO ELBOW (HIGH STRESS) B9.21 2" -160 -D1 1 1 011860 1B21-0168 B B-G-2 VT-1 1042-96A-0234 X 8 STUDS & 16 NUTS EXAMINED IN PLACE UPON
, HEAD VENT / POOL FLOOR FLANGE B7.50 REACTOR HEAD SPRAY REASSEMBLY.
l CONNECTION BOLTING I 2" -160 -D1 1 (REF. DWG. NO. SS-305-605-105) )
i 012050 1821-0186-B B-G-2 VT-1 1042-96A-0235 x 8 STUDS & 16 NUTS EXAMINED IN PLACE UPON l RPV UPPER HEAD SPRAY N0ZZLE B7.50 REACTOR HEAD SPRAY REASSEMBLY.
FLANGE BOLTING 1 4" N/A -D1-1 l l
(REF. DWG. NO. SS-305-605-106)
, 012080 1821 0194 B-J PT 0941-96A-0012 X NONE.
l 2" VALVE F002 TO PIPE (HIGH B9.40 l STRESS) 2" 160 -D1-1 4
( Page 54 l
I l
l REPORT NO. NP0059-0005 )
DATE: 04/04/96 PERRY NUCLEAP POWER PLANT UNIT 1 PAGE: 35 REVISION: 5 ISI
SUMMARY
REPORT Wo. NP0059 0005 O FIRST INTERVAL, THIRD PERIOD, FIRST OUTAGE (96RF)
V CLASS 3 COMPLETED COMPONENTS MAIN STEAM N 0 ASME D G T SEC. XI R E H
SUMMARY
EXAMINATION AREA CATGY EXAM E O E NUM8ER SIZE-SCHEDULE-LINE SPEC I ITEM NO METHOD NDE REPORTS C M R REMARKS
)
1 (REF. DWG. No. SS-305-605-127) 012210 1821-B0102C-WA D-B VT-3 1042-96A-0081 N NONE.
INTEGRAL ATTACHMENT, RIGID D2.20 STRUT MPL 1821G7006 10" -N/A -G1 3 {
(REF. DWG. NO. SS-305-605-1, u 012345 1821-F0041A-IS 3-M-2 VT-3 1042-95A-0009 X EXAMS PERFORMED ON THE REPLACEMENT VALVE SRV, INTERNAL SURFACE B d.50 VT 3 1042-96A-0241 X WHILE STILL IN BANNING, CA.
(GROUPING NUMBER 1) REFURBISHMENT SHOP AND ON THE REPLACED 10" -N/A -D1-1 VALVE AFTER IT HAD BEEN REMOVED AND PLACED IN THE HOT SHOP.
l 015160 1821 F041A B B-G-2 VT-1 1042-96A-0185 X EXAMINATION OF THE FLANGE SURFACES, STUD SRV BOLT!NG, 12 EACH B7.50 VT-1 1042-96A-0186 X HOLES, STUDS AND NUTS FOR REPLACEMENT j 10" N/A -D1-1 VALVE S/N 160846.
1 (REF. DWG. NO. SS-305-605-102) 015180 1821-F0418-B B-G 2 VT 1 1042-96A 0187 X EXAMINATION OF THE FLANGE SURFACES, STUD SRV BOLTING, 12 EACH B7.50 VT 1 1042-96A-0184 X HOLES, STUDS AND NUTS FOR REPLACEMENT 10" -N/A D1-1 VT-1 1042-96A-0188 X VALVE S/W 160871.
(REF. DWG. NO. SS 305 605-103) 015190 1821-F041C B B-G-2 VT-1 1042-96A-0189 X EXAMINATION OF THE FLANGE SURFACES, STUD SRV BOLTING, 12 EACH B7.50 VT 1 1042 96A-0190 X HOLES, STUDS AND NUTS FOR REPLACEMENT 10" -N/A -D1-1 VT-1 1042-96A-0184 X VALVE S/N 160845. INITIAL EXAM FOUND VT-1 1042-96A-0191 X DEFICIENT STUDS AND STUD HOLES. THE STUDS WERE REPLACED. PIF 96-531 WAS WRITTEN FOR THE STUD HOLES AND DISPOSITIONED "USE-AS-IS".
(REF. DWG. NO. SS-305-605-104) 015200 1821-F041D-B B G-2 VT-1 1042-96A-0192 X EXAMINATION OF THE FLANCE SURFACES, STUD SRV BOLTING,12 EACH B7.50 VT-1 1042-96A-0184 X HOLES, STUDS AND NUTS FOR REPLACEMENT 10" -N/A -D1-1 VT 1 1062 96A-0193 X VALVE S/N 160849.
Page 55
REP 3RT N3. NP0059-OOO5 DATE: 04/04/96 PERRY NUCLEAR POWER PLANT UNIT 1 PAGE: 36 l
REVISION: 5 ISI
SUMMARY
REPORT NO. NP0059-0005 FIRST INTERVAL, THIRD PERIOD, FIRST OUTAGE (96RF)
~}
CLASS 1 COMPLETED COMPONENTS MAIN STEAM N O ASME O G T SEC. XI R E H
SUMMARY
EXAMINATION AREA CATGY EXAM E O E I NUMBER SIZE-SCHEDULE LINE SPEC ITEM NO METHOD NDE REPORTS C M R REMARKS l ....... .............................. ....... .......... ................ . . . ........................................
l (REF. DWG. NO. SS-305 605-101) 015210 1821-F041E-B B-G-2 VT-1 1042-96A-0194 X EXAMINATION OF THE FLANGE SURFACES, STUD SRV BOLTING, 12 EACH B7.50 VT 1 1042 96A-0184 X HOLES, STUDS AND NUTS FOR REPLACEMENT 10" - K'A -D1-1 VT 1 1042-96A-0196 X VALVE S/N 160850.
vi-1 1042-96A-0195 x (REF. DWG. NO. SS-305-605-102) 015220 1B21-F041F-B B-G-2 VT-1 1042-96A-0197 X EXAMINATION OF THE FLANGE SURFACES, STUD SRV BOLTING, 12 EACH B7.50 VT-1 1042-96A-0184 X HOLES, STUDS AND NUTS FOR REPLACEMENT 10" -N/A D1-1 VT 1 1042-96A-0198 X VALVE S/N 160851.
(REF. DWG. NO. SS-305-605-103) 015230 1821 F041G-B B-G-2 VT 1 1042-96A 0199 X EXAMINATION OF THE FLANCE SURFACES, STUD SRV BOLTING, 12 EACH B7.50 VT 1 1042-96A-0184 X HOLES, STUDS AND NUTS FOR REPLACEMENT 10" -N/A -D1-1 VT-1 1042-96A-0200 X VALVE S/N 160852. EXAMS FOUND DEFICIENT VT-1 1042- M -0242 X STUDS AND STUD HOLE. THE STUDS WERE VT-1 1042- W -0201 X REPLACED. PIF 96-650 WAS WRITTEN FOR THE STUD HOLE AND DISPGSITIONED "USE-AS IS".
(REF. DWG. NO. SS-305-605 102) 015240 1B21-F041K-B B-G-2 VT-1 1042- W -0202 X EXAMINATION OF THE FLANGE SURFACES, STUD SRV BOLTING, 12 EACH B7.50 VT-1 1042-96A 0203 X HOLES, STUDS AND NUTS FOR REPLACEMENT 10" -N/A -D1 1 VT 1 1042-96A 0184 X VALVE S/N 160888. IN'TIAL EXAM FOUND A VT 1 1042-96A 0204 X DEFICIENT STUD. THE STUD WAS REPLACED.
015250 1B21-F0478 B B-G 2 VT-1 1042-96A-0205 X EXAMINATION OF THE FLANGE SURFACES, STUD SRV BOLTING, 12 EACH B7.50 VT 1 1042-96A-0206 X HOLES, STUDS AND NUTS FOR REPLACEMENT 10" N/A -D1 1 VALVE S/N 160853.
(REF. DWG. NO. SS-305-605-103) 015260 1821-F047C-B B-G-2 VT-1 1042-W-0M7 X EXAMINATION OF THE FLANCE SURFACES, STUD SRV BOLTING, 12 EACH B7.50 VT-1 1042-96A-0'u8 X HOLES, STUDS AND NUTS FOR REPLACEMENT 10" -N/A -D1-1 VALVE $/N 160854.
l l
l Page 56
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REPORT N3. NP0059-0005 DATE: 04/04/96 PERRY NUCLEAR POWER PLANT UNIT 1 PAGE: 37 5 ISI
SUMMARY
REPORT No. NP0059-0005
[ REVISION: FIRST INTERVAL, THIRD PERIOD, FIRST OUTAGE (96RF)
CLASS 1 COMPLETED COMPONENTS MAIN STEAM N 0 l ASME D G T I SEC. XI R E H
SUMMARY
EXAMINATION AREA CATGY EXAM E O E NUMBER SIZE
- SCHEDULE LINE SPEC ITEM NO METHOD NDE REPORTS C M R REMARKS (REF. DWG. NO. SS-305-605-104) 015270 1821-F047D-B B-G-2 VT-1 1042-96A-0209 X EXAMINATION OF THE FLANGE SURFACES, STUD SRV BOLTING, 12 EACH B7.50 VT 1 1042-96A-0184 X HOLES, STUDS AND NUTS FOR REPLACEMENT 10" N/A -D1 1 VT-1 1042 96A 0210 X VALVE S/W 160855.
(REF. DWG. NO. SS-305-605-102) 015280 1B21-F047F-B B-G-2 VT-1 1042-96A-0211 X EXAMINATION OF THE FLANGE SURFACES, STUD SRV BOLTING, 12 EACH BT.50 VT 1 1042-96A-0137 X HOLES, STUDS AND NUTS FOR REPLACEMENT 10" -N/A -D1-1 VT-1 1042-96A-0212 X VALVE S/N 160856.
(REF. DWG, NO. SS-305-605-103) 015290 1821-F047G B BG2 VT-1 1042 96A-0213 X EXAMINATION OF THE FLANGE SURFACES, STUD SRV BOLTING, 12 EACH B7.50 VT-1 1042-96A 0214 X HOLES, STUDS AND NUTS FOR REPLACEMENT 10" -N/A -DI-1 VALVE S/N 160893.
Ct (REF. DWG. NO. SS-305-605-104) 015300 1821-F047H-B B-G-2 VT-1 1042-96A-0215 X EXAMINATION OF THE FLANGE SURFACES, STUD SRV BOLTING, 12 EACH B7.50 VT 1 1042-96A-0184 X HOLES, STUDS AND NUTS FOR REPLACEMENT i
10" -N/A -01 1 VT-1 1042-96A-0216 X VALVE S/N 160875. ;
I (REF. DWG. NO. SS 305-605-101) 015310 1821-F051A-B B G-2 VT-1 1042-96A-0217 X EXAMINATION OF THE FLANGE SURFACES, STUD SRV BOLTING, 12 EACH B7.50 VT 1 1042-96A-0184 X HOLES, STUDS AND NUTS FOR REPLACEMENT 10" N/A D1-1 VT-1 1042-96A-0218 X VALVE S/N 160859.
(REF. DVG. NO. SS-305-605-102) 015320 1821-F0518 B B G-2 VT-1 1042-96A-0219 X EXAMINATION OF THE FLANCE SURFACES, STUD SRV BOLTING, 12 EACH B7.50 VT 1 1042-96A-0220 X HOLES, STUDS AND NUTS FOR REPLACEMENT 10" -N/A -D1 1 VALVE S/W 160882.
I O
l Page 57
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i REPORT NO. NP0059-0005 DATE: 04/04/96 PERRY NUCLEAR POWER PLANT UNIT 1 PAGE: 38 REVISION: 5 ISI
SUMMARY
REPORT NO. NP0059-0005 FIRST INTERVAL, THIRD PERIOD, FIRST GUTAGE (96RF)
%.,/ CLASS 1 COMPLETED COMPONENTS MAIN STEAM N O ASME G G T SEC. XI R E N
SUMMARY
EXAMINATION AREA CATGY EXAM E O E NUMBER SIZE-SCHFDULE-LINE SPEC ITEM NO METHC0 NDE REPORTS C M R REMARKS (REF. DWG. NO. $$-305-605-103) 015330 1B21 F051C-B B G-2 VT 1 1042-96A 0221 X EXAMINATION OF THE FLANGE SURFACES, STUD SRV BOLTING, 12 EACH B7.50 VT-1 1042-96A-0222 X HOLES, STUDS AND NUTS FOR REPLACEMENT 10" N/A -D1 1 VT 1 1042-96A-0184 X VALVE S/W 160861. INITIAL EXAM FOUND VT 1 1042-96A-0223 X DEFICIENT STUDS. THE STUDS WERE REPLACED.
(REF. DWG. NO. SS-595-60r-104) 015340 1B21 F051D B B-G-2 VT-1 1042-96A-0224 X EXAMINATION OF THE FLANGE SURFACES, SitX)
SRV BOLTING,12 EACH B7.50 VT-1 1042-96A-0184 X HOLES, STUDS AND NUTS FOR REPLACEMENT 10" N/A -D1-1 VT-1 1042-96A-0225 X VALVE S/W 160862.
f (REF. DWG. NO. $$-305-605-103) 1B21*F051G-B B-G 2 VT-1 1042-96A-0226 X EXAMINATION OF THE FLANGE SURFACES, STUD d('535010"SRV BOLTING, 12 EACH
-N/A -D1-1 B7.50 VT 1 VT-1 1042-96A-0227 1042-96A-0184 X
X HOLES, STUDS AND NUTS FOR REPLACEMENT VALVE S/N 160863. INITIAL EXAM FOUND VT-1 1042-96A-0228 X DEFICIENT STUDS AND STUD HOLES. THE STUDS WERE REPLACED. PIF 96-531 WAS WRITTEN F0k THE STUD HOLES AND DISPOSITIONCD "USE-AS-IS".
015410 1B21 0101C-WA BK1 VT-3 1042-96A-0121 X NONE.
INTEGRAL ATTACHMENT RIGID B10.10
( GUIDE MPL 1B21G7032 l 26" -N/A -D1 1 (REF. DWG. NO. SS-305-605-128) 015510 1821 H0004 F-A VT-3 1042-96A-0102 X NONE.
MECHANICAL SNUBBER F1.3SN 14" N/A -G1-3 015560 1821-H0007-WA D-B VT-3 1042-96A-0103 X NONE.
INTEGRAL ATTACHMENT MECHANICAL D2.20 SNUBBER 14" N/A G1 3 O
Page 58
I 1 4
i l
l REPORT N3. NPOO59-0005 DATE: 04/04/96 PERRY NUCLEAR POWER PLANT UNIT 1 PAGE: 39 REVISION: 5 ISI
SUMMARY
REPORT NO. NP0059-0005 1
'\ FIRST INTERVAL, THIRD PERIOD, FIRST DUTAGE (96RF) l
_// CLASS 3 COMPLETED COMPONENTS MAIN STEAM i
N O I ASME O G T i SEC. XI R E H l
SUMMARY
EXAMINATION AREA CATGY EXAM E O E NUMBER SIZE-SCHEDULE LINE SPEC ITEM NO METHOD NDE REPORTS C M R REMARKS (REF. DWG. NO. SS-305-605-127) 015620 1B21 H0011 WA D-B VT 3 1042-96A 0083 X NONE.
INTEGRAL ATTACHMENT ANCHOR D2.20 10" -N/A -G1-3 l
l l
1 l
l (REF. DWG. NO. SS-305-605-130) l 016140 1821-H0053 FA VT-3 1042 Y6A-0076 X NONE.
l VARIABLE SPRING (WA) F1.3SP 14" -N/A -G1-3 016150 1821 H0053 WA D-B VT 3 1042-96A-0088 X NONE.
INTEGRAL ATTACHMENT VARIABLE D2.40 SPRING 14" N/A -G1-3 16190 1821-H0056-WA DB VT-3 1042-96A-0104 X NONE.
INTEGRAL ATTACHMENT MECHANICAL D2.30 SNUBBER 14" -N/A -G1 3 016210 1821-H0057 WA D-B VT-3 1042-96A-0105 X NONE. j INTEGRAL ATTACHMENT MECHANICAL D2.30 SNUBBER 14" -h/A -Gi-3 (REF. DWG. NO. SS-305-605-123) 016900 1821-H0106-WA D-B VT-3 1D42-96A-0100 X NONE.
INTEGRAL ATTACHMENT MECHANICAL D2.30 SNUBBER 12" -N/A -G1-3 (REF. DWG. NO. SS-305-605-122) 016950 1821-H01 D9-WA DB VT-3 1042-96A-0079 X NONE.
INTEGRAL ATTACHMENT ANCHOR D2.20 10" N/A -G1-3 O
Page 59
REPCRT NO. NP0059-0005 l
DATE: 04/04/96 PERRY NUCLEAR POWER PLANT UNIT 1 PAGE: 40 ,
! 5 ISI
SUMMARY
REPORT NO. NP0059 0005 l
[, REVISION: FIRST INTERVAL, THIRD PERIOD, FIRST GUTAGE (96RF)
CLASS 3 COMPLETED COMPONENTS MAIN STEAM N O ASME O G T SEC. XI R E H
SUMMARY
EXAMINATION AREA CATGY EXAM E O E NUMBER SIZE-SCHEDULE-LINE SPEC ITEM No METHOD NDE REPORTS C M R REMARKS (REF. DWG. No. SS-305-605-122) 017020 1821 H0115-WA D-B VT 3 1042-96A 0096 X NONE.
INTEGRAL ATTACHMENT MECHANICAL D2.30 SNUBBER 10" -N/A -G1 3 017060 1821 H0117-WA D-B VT-3 1042-96A-0101 X NONE.
INTEGRAL ATTACHMENT MECHANICAL D2.30 SNUBBER 10" N/A -G1-3 017080 1821-H0119 F-A VT 3 1042-96A-0106 X NONE.
MECHANICAL SNUBBER (WA) F1.3SN (TANDEM) 12" -N/A Gi-3 0 017090 1B21-H0119-WA DB VT-3 1042-96A-0107 X NONE. j l
INTEGRAL ATTACHMENT MECHANICAL D2.30 SNUBBER 12" -N/A -Gi-3 (REF. DWG. No. SS-305-605-129) 1 017210 1821 H0127-WA DB VT-3 10 @ 96A-0108 X NONE. I l
INTEGRAL ATTACHMENT MECHANICAL D2.30 SNUBBER 14" N/A -G1-3 (REF. DWG. NO. FS-305-605-124) 017280 1821-H0132-WA DB VT 3 1042-96A-0089 X NONE.
INTEGRAL ATTACHMENT VARIABLE D2.40 SPRING 12" N/A G1 3 O
Page 60
REPORT NO. NP0059-0005 DATE: 04/04/96 PERRY NUCLEAR POWER PLANT UNIT 1 l
PAGE: 41 )
REVISION: 5 ISI
SUMMARY
REPORT NO. NP0059-0005 I
) FIRST INTERVAL, THIRD PERIOD, FIRST CUTAGE (96RF)
L/
CLASS 3 COMPLETED COMPONENTS MAIN STEAM N O ASME O G T SEC. XI R E H
SUMMARY
EXAMINATION AREA CATGY EXAM E O E NUMBER SIZE SCHEDULE-LINE SPEC ITEM No METHOD NDE REPORTS C M R REMARKS CREF. DWG. NO. SS-305-605-127) 017300 1821 H0133-WA D-B VT-3 1042-96A-0097 X NONE.
INTEGRAL ATTACHMENT MECHANICAL D2.30 SNUBBER 12" -N/A -G1-3 (REF. DWG NO. SS-305-605-126) 017400 1821-H0140-WA DB VT-3 1042-96A-0111 X NONE.
INTEGdAL ATTACHMENT MECHANICAL D2.30 SNUBBER 12" -N/A Gi 3 (REF. DWG. NO. SS-305-605 124) 0 1821-H0161-WA D-B VT-3 1042-96A-0082 X NONE.
INTEGRAL ATTACHMENT RIGID D2.40 STRUT 12" -N/A -G1-3 017700 1821-H0162-WA DB VT-3 1042-96A u112 X NONE.
INTEGRAL ATTACHMENT MECHANICAL D2.30 SNUBBER 10" -N/A -G1-3 (REF. DWG. No. SS-305-605-121) 017920 1821-H0169 FA VT-3 1042-96A-0078 X NONE.
RIGID STRUT F1.3ST 12" -N/A -G1-3 (REF. DWG. NO. SS-305 605-125) 018720 1B21-H0409-WA DB VT-3 1042-96A-0087 X NONE.
INTEGRAL ATTACHMENT VARIABLE D2.40 SPRING 12" N/A -G1-3 Paga 61
_ _ __ _ _ . _ - _ _ _ ~_ __ _
l REPORT NL NP0059-0005 DATE: 04/04/96 PERRY NUCLEAR POWER PLANT UNIT 1 PAGE: 42 EVISION: 5 ISI SUMMART REPORT NO. NP0059 0005 FIRST INTERVAL, THIRD PERIOD, FIRST OUTAGE (96RF)
CLASS 3 COMPLETED COMPONENTS MAIN STEAM f M 0
! ASME D G T I SEC. XI R E H
SUMMARY
EXAMINATION AREA CATGY EXAM E O E NUMBER $!ZE-SCHEDULE-LINE SPEC ITEM NO METHOD NDE REPORTS C M R REMARKS l (REF. DWG. NO. SS-305 605-129) l
- 018970 1821 H0433-WA D-B VT-3 1042-96A-0086 X NONE.
INTEGRAL ATTACHMENT VARIABLE D2.40 SPRING l 14" N/A -G1-3 i
l l (REF. DWG, NO. $$-305-605-105) 019270 1B21-H0489 F-A VT-3 1042-96A-0047 X EXAMINED BEFORE HEAD SPRAY PIPING RIGID GUIDE F1.1G REMOVAL.
2" *N/A -D1-1
- (REF. DWG. NO. SS-305-605-107) l 019440 1821-P124-WA B-K-1 MT 0942-96A-0053 X NONE.
l
- /~ P124 FLUED HD FITTING TO B10.10 l
(]) PROCESS PIPE ATTACH WELD 26" - 1.1% -DI-1 019450 1821 P124-WA 9 X-E UT 0944/19-96-0001 X SPOT INDICATIONS (SLAG) REPORTED IN P124 FLUED HD FITTING TO X0.1 PRESERVICE EXAMS SEEN AT SIMILAR PROCESS PIPE ATTACH WELD AMPLITUDES AND SWEEP POSITIONS.
l 26" 1.196 -D1-1 l (REF. DWG. NO. SS-305 605-101) 019900 1821 S102A F-A VT-3 1042 96A-0061 X NONE.
HYDRAULIC SNUBBER MPL F1.1SN 1821G7072 26" -N/A -D1 1 l
(REF. DWG. NO. SS-303-605-103) 020090 1821-S107C F-A VT 3 1042-96A-0098 X NONE.
HYDRAULIC SNUBBER MPL F1.1SN 1B21G7091 26" -N/A -D1-1 4
l Page 62
l REPORT NO. NP0059-0005 DATE: 04/04/96 PERR. NUCLEAR POWER PLANT UNIT 1 PAGE: 43 REVISION: 5 ISI StAMARY REPORT NO. WP0059 0005
) FIRST INTER'.AL, ;HIRD PERIOD, FIRST GUTAGE (96RF) ,
s't AS',1 COMPLETED COMPONENTS I REACTOR RECIRCULATION SYSTEM N 0 ASME O G T SEC. XI R E H
SUMMARY
EXAMINATION AREA CATGY EXAM E O E NUMBER SIZE SCHEDULE LINE SPEC ITEM NO METHOD NDE REPORTS C M R REMARKS (REF. DWG. NO. SS-305-602-102) 020950 1833-0017-8 BG2 VT-1 1042-96A-0119 X EXAM PERFORMED ON 8 STUDS AND 16 NUTS IN BLANK FLANGE DECON CONNECTOR B7.50 PLACE UNDER TENSION PRIOR TO DISASSEMBLY 4" -N/A -D2-1 FOR CHEMICAL DECON.
(REF. DWG. NO. $$-305-602-101) 022520 1833-0054 BJ UT 0944/17-96 0001 X NONE.
12" PIPE TO N0ZZLE N2D SAFE B9.11 END (CRC)(HIGH CTRESS) PT 0941 96A-0025 x 12" .575" -D2-1.
022540 1833-0054-U B-J UT 0944/17-96 0001 X GEOMETRIC INDICATIONS REPORTED IN PIPE SEAM, UPSTREAM 89.12 UT 0944/18-96 0002 X PRESERVICE EXAMS SEEN AT SIMILAR 12" .575" -D2-1 PT 0941-96A-0025 X AMPLITUDES AND SWEEP POSITIONS.
(REF. DWG. NO. SS-305-602-103) i 024260 1833-0090 B-J UT 0944/18-96-0001 X NONE.
l 16" PIPE TO 16" X 12" 89.31 SWEEPOLET PT 0941 96A-0013 X 16" .951" -D2-1 (REF. DWG. NO. SS-305-602 102) 026410 1833-H301A F-A VT 3 1042-96A-0092 X NONE.
CONSTANT SUPPORT, PUMP, MPL F1.40 1833G7013A N/A -N/A -D2-1 026450 1933-H303A FA VT-3 1042-96A-0090 X NONE.
CONSTANT SUPPORT, PUMP, MPL F1.40 1833G7015A N/A N/A -D2 1 l
l Page 63 l
1
REPORT NO. NPOO59-0005 DATE: 04/04/ % PERRY NUCLEAR POWER PLANT UNIT 1 PAGE: 44 REVISION: 5 ISI
SUMMARY
REPORT NO. NP0059-0005
/
) FIRST INTERVAL, THIRD PERIOD, FIRST OUTAGE (96RF)
CLASS 1 COMPLETED COMPONENTS REACTOR REclRCULATION SYSTEM N O ASME O G T SEC. XI R E H
SUMMARY
EXAMINATION AREA CATGY EXAM E O E I NUMBER SIZE SCHEDULE-LINE SPEC ITEM NO METHOD NDE REPORTS C M R REMARKS 1
LREF. DWG, NO. SS-305-602-102)
- 026470 1833 N304A F-A VT 3 1042-96A 0091 X NONE.
l CONSTANT SUPPORT, PUMP, MPL F1.40 j 1833G7016A j N/A N/A -D2 1 1
l J
4 i
027180 1833-S371A FA VT-3 1042-96A-0109 X NONE.
1 HYDRAULIC SNUBBER, PUMP, MPL F1.40 1 1833G7066A
! N/A -N/A -D2-1
?
i 1
J
)
l 4
4 i
3 l
t i
t 4
J
?
l l
i i
d a
i 4
4 3
2 4
1 1
j Page 64 i
i i
REPORT N3. NPOO59-0005 DATE: 04/04/96 PERRY NUCLEAR POWER PLANT UNIT 1 PAGE: 45 5 ISI
SUMMARY
REPORT NO. NP0059-0005
[. REVISION: FIRST INTERVAL, THIRD PERIOD, FIRST OUTAGE (96RF)
\ CLASS 2 COMPLETED COMPONENTS CONTROL RG) DRIVE HYDRAutlC CONTROL SYSTEM N O ASME O G T SEC. XI R E H SUMARY EXAMINATION AREA CATGY EXAM E O E NUMBER SIZE SCHEDULE-LINE SPEC ITEM NO METHOD NDE REPORTS C M R REMARKS (REF. DWG. NO. SS-305-871-104) 027710 1C11 0033 C-F-2 UT 0944/08- % -0016 X NONE.
8" P!PE TO TEE C5.51 8" -100 -E1-2 MT 0942-96A-0032 X (REF. DWG. NO. SS-305-871-101) 027850 1C11-0047 C-F-2 UT 0944/08 96 0015 X GEOMETRIC INDICATIONS REPORTED IN 8" X 12" REDUCING ELBOW TO C5.51 PRESERVICE EXAMS SEEN AT SIMILAR PIPE MT 0942 96A-0032 X AMPLITUDES AND SWEEP POSITIONS.
12" 100 -E1-2 (REF. DWG. No. SS-305-871-105) l 028270 1C11-0087 X-B PT 0941 96A-0001 X NONE.
l f^g 2 1/2" PIPE TO ELBOW X0.1 Q 2-1/2" 80 -C2-2 028290 1C11-0089 XB PT 0941-96A 0002 X NONE.
2 1/2" PIPE TO ELBOW X0.1 2-1/2"-80 -C2-2 028300 1C11-0090 X-B PT 0941-96A-0003 X NONE.
2 1/2" VALVE F083 TO PIPE X0.1 2-1/2"-80 -C2 2 1
l l 028302 1C11-0091 XB PT 0941-96A-0004 X NONE.
2 1/2" PIPE TO VALVE F083 X0.1 2-1/2=-80 -C2 2 (REF. DWG. NO. SS-305-871 104) 028430 1C11 H0040 F-A VT-3 1042-96A-0093 X WONE.
RIGID GUIDE (WA) F1.2G
, 8" -N/A -E1-2 l
l 1
O Page 65
REPERT NO. NPOO59-0005 DATE: 04/04/96 PERRY NUCLEAR POWER PLANT UNIT 1 PAGE: 46 REVISION: 5 !$1
SUMMARY
REPORT NO. NP0059-0005 l , FIRST INTERVAL, THIRD PERIOD, FIRST OUTAGE (96RF)
(-)/ CLASS 2 COMPLETED COMPONENTS CONTROL ROD DRIVE HYDRAUl!C CONTROL SYSTEM N 0 l ASME O G T l
SEC. XI R E H
SUMMARY
EXAMINATION AREA CATGY EXAN E O E NUMBER $1ZE SCHEDULE LINE SPEC ITEM NO METHOD NDE REPORTS C M R REMARKS 1
(REF. DWG. NO. SS-305-871-104) 0284t0 1C11 H0040-WA CC PT 0941-96A-0011 X SCHEDULED FOR MT, BUT TUBE STEEL AROUND PIPING SUPPORT WELDED C3.20 LUCS PROHIBITED YOKE ACCESS AND A PT WAS ATTACHMENT PERFORMED INSTEAD.
8" -N/A -E1 2 (REF. DWG, NO. SS-305-871-101) 028600 1C11-H0050 F-A VT-3 1042-96A 0085 X NONE.
RIGID STRUT F1.2ST 8" N/A -El-2 028795 1C11-H0461-WA CC MT 0942-96A-0032 X NONE.
PIPING SUPPORT WELDED C3.20 ATTACHMENT Q 8" -N/A -E1-2 (REF. DWG. NO. SS-305-871-103) 028820 1C11-H0663 FA VT-3 1042-96A-0099 X NONE.
MECHANICAL SNUBBER F1.2SN 8" N/A -E1-2 028865 1C11 H0667-WA C-C MT 0942-96A-0033 X NONE.
P! PING SUPPORT WELDED C3.20 ATTACHMENT 88 -N/A -E1-2 028875 1C11-H0668-WA C-C MT 0942-96A-0033 X NONE.
PIPING SUPPORT WELDED C3.20 ATTACHMENT 8" -N/A -E1-2 O
C/
Page 66
REPORT N3. NP0059-0005 DATE: 04/04/96 PERRY NUCLEAR POWER PLANT UNIT 1 PAGE: 47 5 ISI
SUMMARY
REPORT NO. NP0059 0005
[_ REVISION: FIRST INTERVAL, THIRD PERIOD, FIRST GUTAGE (96RF)
CLASS 2 COMPLETED COMPONENTS RESIDUAL HEAT REMOVAL SYSTEM N O ASME D G T SEC. XI R E H
SUMMARY
EXAMINATION AREA CATGY EXAM E O E NUMBER SIZE SCHEDULE LINE SPEC ITEM NO METHOD NOE REPORTS C M R REMARKS l
(REF. DWG. NO. SS-305 642-110) 030170 1E12-0055 C-F-2 UT 0944/08- % -0003 X NONE.
18" P!PE TO VALVE F067 C5.51 18" -40 -G1-2 MT 0942-96A-0007 X 030180 1E12-0056 C-F-2 UT 0944/08 96 0003 X NONE.
VALUE F067 TO 18" PIPE C5.51 18" -40 -G1-2 MT 0942-96A-0009 x (REF. DWG. NO. SS-305-642-114) 030520 1E12-0086 C F-2 UT 0944/08 96-0011 X SRANCH CONNECTION LIMITS EXAMINATION 24" PIPE TO FLANGE C5.51 COVERAGE TO 94%.
24" 40 -G1 2 MT 0942-96A-0025 X O
(REF. DWG. No. SS-305-643-113) 031710 1E12-0205 C F-2 UT 0944/08 96-0013 X NONE.
20" PIPE TO HEAT EXCHANGER C5.51 B0010 INLET N0ZZLE MT 0942 96A 0029 X 20" -40 G1-2 (REF. DWG. NO. SS-305-643-117) 031810 1E12-0215 C-F-2 UT 0944/08-96-0004 X NONE.
18" VALVE F029C TO PIPE C5.51 18" -40 -GI-2 MT 0942-96A-0008 x (REF. DWG. NO. SS-305-642-120) 033160 1E12-0339 a X-B UT 0944/08-96-0047 X NONE.
12" PIPE TO 12" X 6" SWEEPOLET X0.1 RWCU INTERTIE 12" -120 -D1-2 Page 67
1 REPORT NO. NP0059-0005 DATE: 04/04/96 PERRY NUCLEAR POWER PLANT UNIT 1 PAGE: 48 5 ISI
SUMMARY
REPORT NO. NP0059-0005
[ REVISION: FIRST INTERVAL, THIRD PERIOD, FIRST CUTAGE (96RF)
CLASS 2 COMPLETED COMPONENTS RESIDUAL HEAT REMOVAL SYSTEM N O ASME D G T ;
R E H SEC. XI
SUMMARY
EXAMINATION AREA CATGY EXAM E O E l NUMBER SI2E-SCHEDULE-LINE SPEC ITEM NO METHOD NDE REPORTS C M R REMARKS (REF. DWG. No. SS-305-642-131) 035450 1E12-0583 a X-B UT 0944/08 %-0048 X GEOMETRIC INDICATIONS REPORTED IN 1 12" P!PE TO VALVE F0508 X0.1 PRESERVICE EXAMS SEEN AT SIMILAR j 12" -100 -D1 2 AMPLITUDES AND SWEEP POSITIONS.
i 035470 1E12-0584 a X-B UT 0944/08-96-0049 X NONE-12" VALVE F0508 TO PIPE X0.1 12" -120 -D1-2 l l
(REF. DWG. NO. SS-305 643-109)
I 036060 1E12-0638 C F-2 UT 0944/08 96-0007 X OBSERVED ROOT GEOMETRY BELOW RECORDABLE ELBOW TO 18" PIPE C5.51 LEVELS.
18" -STD -L1-2 MT 0942-96A-0014 X
]
l b C-F-2 MT 0942-96A-0010 X NONE.
Q 1190 1E12-0648 18" X 6" WELDOLET TO 18" PIPE C5.81 6" -40 -L1-2 (REF. DWG. No. SS-305-642-136) 036600 1E12 0688 C-F-2 UT 0944/08-96-0010 X GEOMETRIC INDICATIONS REPORTED IN 12" ELBOW TO PIPE C5.51 PRESERVICE EXAMS SEEN AT SIMILAR 1 12" 40 -G1-2 MT 0942-96A-0024 X AMPLITUDES AND SWEEP POSITIONS.
(REF. DWG. NO. SS-305-642-137) 036690 1E12 0696 B-J UT 0944/08-96-0043 X WONE.
12" ELBOW TO PIPE (HIGH B9.11 STRESS) MT 0942-96A-0054 X 12" -80 -D1 1 (REF. DWG. NO. SS-305-642-141) 036910 1E12-0718 B-J UT 0944/08-96-0050 X GEOMETRIC INDICATIONS REPORTED IN 12" P!PE TO ELBOW (HIGH B9.11 PRESERVICE EXAMS SEEN AT SIMILAR STRESS) MT 0942-96A-0059 X AMPLITUDES AND SWEEP POS!110NS.
12" -80 -D1-1 O
G Page 68
REPORT ND. NP0059-0005 DATE: 04/04/ % PERRY WUCLEAR POWER PLANT UNIT 1 PAGE: 49 EVISION: 5 ISI
SUMMARY
REPORT NO. NP0059-0005 FIRST INTERVAL, THIRD PERIOD, FIRST GUTAGE (96AF)
CLASS 1 COMPLETED COMPONENTS 1ESIDUAL HEAT REMOVAL SYSTEM N O ASME D G T l SEC. XI R E N
SUMMARY
EXAMINATION AREA CATGY EXAM E O E NUMBER SIZE SCHEDULE-LINE SPEC ITEM NO METHOD NDE REPORTS C M R REMARKS l
(REF. DWG. NO. SS-305-642-141) 036920 1E12 0719 BJ UT 0944/08-96-0050 X GEOMETRIC INDICATIONS REPORTED IN l 12" ELBOW TO PIPE (HIGH B9.11 PRESERVICE EXAMS SEEN AT SIMILAR STRESS) MT 0942-96A-0059 X AMPLITUDES AND SWEEP POSITIONS.
! 12" -80 -D1-1 1
036930 1E12-0720 BJ UT 0944/08-96-0036 X NONE.
12" PIPE TO N68 SAFE-END EXT. B9.11 (HIGH STRESS & USE) MT 0942-96A-0050 X 12" -80 -D1-1 (REF. DWG. NO. S$-305-643-120) 037980 1E12-0839 C-F-2 UT 0944/08-96-0012 X NONE.
18" P!PE TO 18" X 18" X 18" C5.51 TEE MT 0942-96A-0028 X Q 18" -40 Gi 2 (REF. DWG. NO. SS 305-642-142) 038260 1E12-0864 B-J UT 0944/08-96-0051 X GEOMETRIC INDICATIONS REPORTED IN 12" PIPE TO ELBOW (HIGH B9.11 PRESERVICE EXAMS SEEN AT SIMILAR STRESS) MT 0942 96A-0060 X AMPLITUDES AND SWEEP POSITIONS.
12" -80 -D1 1 038270 1E12-0865 B-J UT 0944/08-96-0051 X GEOMETRIC INDICATIONS REPORTED IN 12" ELBOW TO PIPE (HIGH B9.11 PRESERVICE EXAMS SEEN AT SIMILAR STRESS) MT 0942-96A-0060 X AMPLITUDES AND SWEEP POSITIONS.
12" 80 D1-1 038290 1E12-0867 B-J UT 0944/08-96-0044 X NONE.
12" PIPE TO ELBOW (HIGH B9.11 STRESS) MT 0942-96A-0055 X 12" -80 -D1-1 O
Page 69
l REPORT NO. NP0059-0005 DATE: 04/04/96 PERRY NUCLEAR POWER PLANT UNIT 1 PAGE: 50 5 !$1
SUMMARY
REPORT NO. NP0059-0005 FIRST INTERVAL, THIRD PERIOD, FIRST CUTAGE (96RF)
O' REVISION: CLASS 1 COMPLETED COMPONENTS l RESIDUAL NEAT REMOVAL SYSTEM N O ASME O G T SEC. XI R E H
SUMMARY
EXAMINATION AREA CATGY EXAM E O E NUMBER SIZE-SCHEDULE-LINE SPEC ITEM NO METHOD NDE REPORTS C M R REMARKS l ....... .............................. ....... .......... ................ . . . ........................................
(REF. DWG. NO. SS-305-642-142) 038300 1E12 0868 B-J UT 0944/08-96-0044 X NONE.
12" ELBOW TO PIPE (HIGH B9.11 STRESS) MT 0942-96A-0055 x 12" 80 -D1-1 (REF. DWG. NO. SS-305-642-145) 038470 1E12-0885 BJ UT 0944/08-96-0045 X GEOMETRIC INDICATIONS REPORTED IN 12" PIPE TO ELBOW (HIGH B9.11 PRESERVICE EXAMS SEEN AT SIMILAR STRESS) MT 0942-96A-0056 X AMPLITUDES AND SWEEP POSITIONS.
12" 80 D1-1 (REF. DWG. NO. SS-305-641-112) 1E12-0968 C F-2 UT 0944/08-96-0046 X GEOMETRIC INDICATIONS REPORTED IN 6050 10" X 10" X 10" TEE TO 10" PIPE C5.51 MT 0942-96A 0057 X PRESERVICE EXAMS SEEN AT SIMILAR AMPLITUDES AND SWEEP POSITIONS.
10" -80 D1 2 (REF. DWG. NO. SS-305-643-102) 039140 1E12-0976 C-F 2 UT 0944/08-96 0005 X GEOMETRIC INDICATIONS REPORTED IN 10" ELBOW TO PIPE C5.51 PRESERVICE EXAMS SEEN AT SIMILAR 10" 100 -D1-2 MT 0942 96A-0012 X AMPLITUDES AND SWEEP POSIT]ONS.
(REF. DWG. NO. SS-305-643-122) 040640 1E12 C002C-004 C-G MT 0942-96A 0018 X NONE.
HEAD FLANGE TO HEAD SHELL C6.10 N/A -N/A -N/A 040690 1E12-C002C-009 C-G MT 0942-96A-0016 X MT WAS SUPPLEMENTED BY A PT EXAM TO GAIN HEAD SHELL TO HEAD CWER C6.10 PT 0941-96A-0005 X COVERAGE IN AN AREA WHERE THE YOKE COULD N/A -N/A -N/A NOT ACCESS. 5.4% OF THE EXAMINATION AREA WAS OBSTRUCTED BY PAINTED VIBRATION ANALYSIS MARKS.
Page 70
I REPORT N3. NP0059-0005 DATE: 04/04/96 PERRY NUCLEAR POWER PLANT UNIT 1 PAGE: 51 R 5 ISI
SUMMARY
REPORT NO. NP0059 0005
[EVISION: FIRST INTERVAL, THIRD PERIOD, FIRST OUTAGE (96RF)
'N.- CLASS 2 COMPLETED COMPONENTS RESIDUAL HEAT REMOVAL SYSTEM N O ASME O G T SEC. XI R E H
SUMMARY
EXAMINATION AREA CATGY EXAM E O F NUMBER SI2E SCHEDULE-LINE SPEC ITEM NO METHOD NDE REPORTS C M R REMARKS (REF. DWG. NO. SS 305-643-122) 040700 1E12-C002C-010 C-G MT 0942-96A 0018 X NONE.
HEAD SHELL LONGITUDINAL SEAM C6.10 N/A N/A -N/A (REF. DWG. NO. SS-305-642-142) 041280 1E12-H0027 F-A VT-3 1042 96A-0130 X NONE. I RIGID GUIDE F1.1G 12" -N/A -D1-1 .
I (REF. DWG. NO. SS-305-642-135) 041340 1E12-H0036 F-A VT-3 1042-96A-0114 X NONE.
MECHANICAL SNUBBER F1.1SN I 12" -N/A -D1-1 (REF. DWG NO. SS-305 642-137) 041460 1E12-H0051 F-A VT-3 1042-96A-0115 X NONE.
MECHANICAL SNUBSER F1.1SN 12" -N/A -D1-1 (REF. DWG. NO. SS-305-642-149) 041610 1E12-H0062 F-A VT-3 1042-96A-0132 X NONE.
RIGID GUIDE (WA) F1.3G 12" -N/A -L2-3 041620 1E12-H0062-WA D-8 VT-3 1042 96A-0133 X NONE.
INTEGRAL ATTACHMENT RIGID D2.20 GUIDE 12" -N/A -L2-3 sm Page 71
REPORT N3. NP0059-0005 DATE: 04/04/96 PERRY NUCLEAR POWER PLANT UNIT 1 PAGE: 52 REVISION: 5 ISI
SUMMARY
REPORT NO. NP0059 0005
[~ FIRST INTERVAL, THIRD PERIOD, FIRST DUTAGE (96RF)
CLASS 2 COMPLETED COMPONENTS RESIDUAL HEAT REMOVAL SYSTEM N O ASME O G T SEC. XI R E H
SUMMARY
EXAMINATION AREA CATGY EXAM E O E NUMBER SIZE-SCHEDULE-LINE SPEC ITEM NO METHOD NDE REPORTS CM R REMARKS (REF. DWG. NO. SS-305 642 132) 042040 1E12-H0123 F-A VT-3 1042-96A-0058 X NONE.
RIGID STRUT F1.2ST 12" -N/A G1-2 (REF. DWG. NO. SS-305 642-110) 042370 1E12-H0173 WA C-C MT 0942 96A 0015 X NONE.
PIPING SUPPORT WELDED C3.20 i ATTACHMENT 18" -N/A -G1-2 (REF. DWG. NO. SS 305 643-113) ,
l 042790 1E12 H0237 F-A VT 3 1D42-96 0001 X NONE.
VARIABLE SPRING F1.2SP l
( 18" -N/A -G1 2 (REF. DWG. NO SS-305-643-102) 043000 1E12-H0281 WA C-C MT 0942-96A 0026 X NONE.
PIP!NG FUPPORT WELDED C3.20 ATTACHt4ENT 10" -N/A -D1-2 (REF. DWG, NO. SS-305-642-114) 043300 1E12 H0365 F-A VT 3 1042 95A 0007 X SCHEDULED EXAM VERIFIED PREVIOUSLY MECHANICAL SNUBBER F1.2SN VT 3 1042 95A-0008 X IDENTIFIED EXCESSIVE GAP. GAP WAS 24" N/A -G1 2 SUBSEQUENTLY CORRECTED AND A PS! EXAM PERFORMED.
043910 1E12 H0369-WA C-C MT 0942-96A 0027 X NONE.
PIPING SUPPORT WELDED C3.20 ATTACHMENT 24" -N/A -Gi-2 O
Page 72
REPORT N3. NP0059-0005 DATE: 04/04/96 PERRY NUCLEAR POWER PLANT UNIT 1 PAGE: 53 REVISION: 5 ISI SUMARY REPORT NO. NP0059-0005
%/
} FIRST INTERVAL, THIRD PERIOD, FIRST CUTAGE (96RF)
CLASS 2 COMPLETED COMPONENTS RESIDUAL HEAT REMOVAL SYSTEM N O ASME O G T SEC. XI R E H
SUMMARY
EXAMINATION AREA CATGY EXAM E 0 E NUMBER SIZE-SCHEDULE-LINE SPEC ITEM NO METHOD NDE REPORTS C M R REMARKS (REF. DWG. NO. SS-305-642-114) l 043910 1E12-H0369 WA C-C MT 0942 96A 0027 X NONE.
3 PIPING SUPPORT WELDED C3.20 ATTACHMENT 24" N/A -Gi-2 (REF. DWG. NO. SS-305-642-102) 044010 1E12-H0378 FA VT-3 1042 96A 0042 X EXAM FOUND THE INBOARD BOLT, NUT, AND MECHANICAL SNUBBER F1.2SN VT 3 1042-96A 0044 X LOCKNUT OF THIS 3 BOLT CLAMP TO BE 18" N/A -G1-2 LOOSE. CAUSE WAS UNIQUE TO REWORK PERFORMED IN RF04, NOT SERVICE RELATED.
PIF 96 140 WRITTEN AND DISPOSITIONED OPERABLE WITH REWORK. REWORK AND A PSI EXAM WERE COMPLETED.
( (REF. DWG. NO. SS-305-642-101) 044120 1E12-H0390 FA VT-3 1042-96-0002 X NONE.
VARIABLE SPRING F1.2SP 20" -N/A -G1-2 (REF. DWG. NO. SS-305-642-109) 048.230 1E12-H0401-WA C-C MT 0942-96A-0031 X LUG CEOMETRY AND DOSE CONSIDERATIONS '
PIPING SUPPORT WELDED C3.20 LIMITED COMPLETION OF THE WELD ATTACHMENT PREPARATION, AND CONSEQUENTLY THE 18" -N/A -G1-2 EXAMINATION, TO 92%.
(REF. DWG. NO. SS-305-643 109) 045510 1E12-H0556 F-A VT 3 1042-96A-0075 X NONE.
MECHANICAL SNUBBER (TANDEM) F1.2SN 18" -N/A -L1-2 O
Page 73
REPCRT ND. NP0059-?005 DATE: 04/04/ % PERRY NUCLEAR POWER PLANT UNIT 1 PAGE: 54
! REVISION: S ISI
SUMMARY
REPORT NO. NP0059-0005 O FIRST INTERVAL, THIRD PERIOD, FIRST CUTAGE (96RF)
CLASS 1 COMPLETED COMPONENTS RESIDUAL HEAT REMOVAL SYSTEM N O ASME U u i SEC. XI R E H
SUMMARY
EXAMINATION AREA CATGY EXAM E O E NUMBER SIZE-SCHEDULE-LINE SPEC ITEM NO METHOD NDE REPORTS C M R REMARKS (REF. DWG. NO. SS 305-642-141) 046140 1E12-H0675 F-A VT-3 1042-96A 0145 X NONE.
VARIABLE SPRING F1.1SP 12" -N/A -D1-1 (REF. DWG. h0. SS-305-642-137) 046310 1E12 H0693 F-A VT 3 1042-96A 0131 X NONE.
RIGID GUIDE F1.2G 12" -N/A -G1-2 (REF. DWG. NO. SS-305-642 149) 046320 1E12-H0694 F-A VT 3 1042 96A-0116 X NONE.
MECHANICAL SNUB 8ER F1.3SN q 12" -N/A -L2 3 (REF. DWG. NO. SS-305-643 117) 046400 1E12-H0708 FA VT 3 1042-96A-0036 X NONE.
RIGID STRUT (WA) F1.2ST 18" N/A G1-2 046410 1E12 H0708-WA C-C MT 0942-96A-0023 X NONE.
PIPING SUPPORT WELDED C3.20 ATTACHMENT 18" -N/A -Gi-2 (REF. DWG. No. SS-305-642-141) 046560 1E12-H0726 FA VT-3 1042-96A-0067 X NONE.
HYDRAULIC SNUBBER F1.1SN 12" -W/A -D1 1 l
?
Page 74
- . . . - . - _ . .. . . . . . - . . ~ . . . . . . - . - _ . _ . .- - . . . . -- . - . . - _ . . - . -
.t 1
i REPCRT NO. NP0059-0005 DATE: 04/04/ % PERRY NUCLEAR POWER PLANT UNIT 1 PAGE: 55 REVISION: 5 ISI St.MMARY REPORT NO. NP0059-0005 I
bI FIRST INTERVAL, THIRD PERIOD, FIRST GUTAGE (96RF)
! V CLASS 1 COMPLETED COMPONENTS
- RESIDUAL HEAT REMOVAL SYSTEM j N O ASME O G T
! SEC. XI R E H I
SUMMARY
EXAMINATION AREA CATGY EXAM E D E NUM8ER SIZE SCHEDULE-LINE SPEC ITEM NO METHOD NDE REPORTS C M R REMARKS (PEF. DWG. NO. SS-305 642-141) 7
- 046730 1E12-H0748 FA VT 3 1042-96A-0159 X NONE.
l RIGID GUIDE F1.1G j 12" -N/A -D1-1 I
1 l (REF. DWG. No. SS-305-642-133) i 047070 1E12 P407-WA C-C MT 0942 96A 0058 X NONE.
PEN. P407 ANCHOR PLATE TO C3.20
! PROCESS PIPE WELDED ATT.
- 18" -N/A -L1-2 O
Page 75
REPORT NO. NP0059-0005
)
56 l DATE: 04/04/96 PERRY NUCLEAR POWER PLANT UNIT 1 PAGE:
REVISION: 5 ISI
SUMMARY
REPORT NO. WP0059-0005 FIRST INTERVAL, THIRD PERIOD, FIRST OUTAGE (96RF)
) CLASS 1 COMPLETED COMPONENTS ,
LOW PRISSURE CORE SPRAY SYSTEM i N O ASME O G T SEC. XI R E H
SUMMARY
EXAMINATION AREA CATGY EXAM E O E NUMBER SIZE SCHEDULE LINE tPEC ITEM NO METHOD NDE REPORTS C M R REMARKS (REF. DWG. NO. SS-305-705-111) 047150 1E21 0001 B-J UT 0944/08 W D026 X ROOT GEOMETRY NOTED BELOW RECORDING 12" PIPE TO N5A SAFE END B9.11 LEVELS.
EXTENSION MT 0942-96A-0042 X 12" 80 D1-1 l
l i
l l
)
c, l
1 I
Page 76
REPORT N3. NP0059-0005 DATE: 04/04/96 PERRY NUCLEAR POWER PLANT UNIT 1 PAGE: 57 5 !$1
SUMMARY
REPORT NO. NP0059-0005
[ REVISION:
T FIAST INTERVAL, THIRD PERIOD, FIRST OUTAGE (96RF) ks CLASS 1 COMPLETED COMPONENTS HIGN PRESSURE CORE SPRAY SYSTEM N O ASME O G T SEC. XI R E H
SUMMARY
EXAMINATION AREA CATGY EXAM E O E NUMBER SIZE-SCHEDULE-LINE SPEC ITEM NO METHOD NDE REPORTS C M R REMARKS (REF. DWG. NO. SS-305-701-111) 049310 1E22-0001 B-J UT 0944/08-96-0025 X GEOMETRIC INDICATIONS REPORTED IN 12" PIPE TO NSB SAFE-END B9.11 PRESERVICE EXAMS SEEN AT SIMILAR EXTENSION MT 0942-96A-0041 X AMPLITUDES AND SWEEP POSITIONS.
12" -80 -D1 1 049320 1E22-00Gi B-J UT 0944/08-96 0019 X ROOT GEOMETRY NOTED BELOW RECORDING 12" ELBOW TO PIPE (HIGH B9.11 LEVELS.
STRESS) MT 0942-96A 0036 X 12" -80 -D1-1 U<EF. DWG. NO. SS-305-701-103) 049890 1E22-0055 C-F-2 UT 0944/08 96-0006 X ROOT GEOMETRY RECORDED.
16" FLANGE TO PIPE C5.51 16" 100 D1 2 MT 0942-96A-0017 X U
049900 1E22-0056 C-F-2 UT 0944/08-96-0002 X NONE.
24" PIPE TO FLANGE C5.51 24" -STD -L1-2 MT 0942-96A-0006 X (REF. DWG. NO. SS-305-701-105) 050200 1E22-0087 C-F-2 UT 0944/08-96-0001 X GEOMETRIC INDICATIONS REPORTED IN 12" P!PE TO ELBOW C5.51 PRESERVICE EXAMS SEEN AT SIMILAR 12" -100 -D1-2 MT 0942 96A-0005 X AMPLITUDES AND SWEEP POSITIONS.
CREF. DWG. NO. $$-305-701 114) 050660 1E22-C001-008 C-G MT 0942-96A-0001 X NONE.
24" SUCTION FLANGE TO 24" C6.10 SUCTION P!PE 24" -N/A -N/A l
O l
Page 77
REPORT N3. NP0059-0005 DATE: 04/04/96 PERRY NUCLEAR POWER PLANT UNIT 1 PAGE: 58 REVISION: 5 15!
SUMMARY
REPORT NO. NP0059 0005 FIRST INTERVAL, THIRD PERIOD, FIRST OUTAGE (96RF) l CLASS 2 COMPLETED COMPONENTS HIGN PRESSURE CORE SPRAY SYSTEM N O )
ASME C G T SEC. XI R E H
SUMMARY
EXAMINATION AREA CATGY EXAM E O E NUMBER SIZE-SCHEDULE LINE SPEC ITEM NO METHOD NDE REPORTS C M R REMARKS (REF. DWG. NO. SS-305-701-114) 050670 1E22-C001-009 C-G MT 0942-96A-0001 X NONE.
24" SUCTION PIPE TO HEAD SHELL C6.10 N/A -N/A -N/A 050680 1E22-C001-010 C-G MT 0942-96A-0002 X 2% OF EXAMINATION AREA OBSTRUCTED BY HEAD SHELL TO HEAD COVER C6.10 PAINTED VIBRATION ANALYSIS MARKS.
N/A -N/A -N/A 050700 1E22-C001-012 C-G MT 0942-96A-0001 X NONE.
24" SUCTION PIPE LONGITUDINAL C6.10 SEAM N/A -N/A -N/A 50 1E22-F026-SEAM C-G MT 0942-96A 0004 X NONE.
6" GATE VALVE BODY WELD C6.20 6" -N/A -D1-2 (REF. DWG. NO. $$-305-701-111) 050870 1E22-F036-SEAM B-M-1 UT 0944/30-96-G002 X GEOMETRIC INDICATIONS REPORTED IN 12" GATE VALVE BODY WELD B12.40 PRESEVICE EXAMS SEEN AT SIMILAR (GROUPING NO. XVill) AMPLITUDES AND SWEEP POSITIONS.
12" -N/A -D1-1 050920 1E22 H0005 F-A VT-3 1042-96A-0095 X NONE.
MECHANICAL SNUBBER F1.1SN 12" -N/A D1 1 050930 1E22 H0006 F-A VT-3 1042-96A-0077 X NONE.
VARIABLE SPRING F1.1SP 12" -W/A -D1-1 O
O Page 78 l
REPORT N3. NP0059-0005 DATE: 04/04/96 PERRY NUCLEAR POWER PLANT UNIT 1 PAGE: 59 REVISION: 5 ISI
SUMMARY
REPORT NO. NP0059-0005
\ FIRST INTERVAL, THIRD PERIOD, FIRST OUTAGE (96RF)
CLASS 2 COMPLETED COMPONENTS HIGH PRESSURE CORE SPRAY SYSTEM N O ASME O G T SEC. XI R E H
SUMMARY
EXAMINATION AREA CATGY EXAM E 0 E NUMBER SIZE-SCHEDULE-LINE SPEC ITEM NO METHOD NDE REPORTS C M R REMARKS (REF. DWG. NO. SS 305-701-1021 051160 1E22-N0033 F-A VT-3 1042-96A 0049 X MINOR CRACKING IN THE BASEPLATE GROUT; RIGID GUIDE F1.2G WITHIN ACCEPTANCE CRITERIA.
24" -N/A -L1 2 (REF. DWG. NO. SS-305-701 101) 051220 1E22 H0038-WA CC MT 0942-96A 0011 X NONE.
PIPING SUPPORT WELDED C3.20 ATTACHMENT 24" -N/A -L1-2 051230 1E22-H0039 F-A VT-3 1042-96A-0053 X AS-FOUND ISI EXAM WAS PERFORMED THEN A VARIABLE SPRING F1.2SP VT-3 1042-96A-0153 X PSI EXAM FOLLOWING REVISION OF SETTINGS 24" N/A -L1 2 PER DCP 92-0071.
O O (REF. DWG. NO. SS 305-701-106) 051100 1E22-H0057 FA VT 3 1042-96A 0060 X NONE.
MECHANICAL SNUB 8ER F1.2SN 16" -N/A -D1 2 (REF. DWG. NO. SS-305-701-107) 051470 1E22 H0063 F-A VT 3 1042 96A-0056 X STRUT BUSHING IS SLIGHTLY (1.E. <1/32")
RIGID STRUT F1.2ST DISPLACED AT THE STRUCTURAL ATTACHMENT 16" -N/A D1-2 END.
(REF. DWG. NO. SS-305 701-112) 051690 1E22 H0085-WA C-C MT 0942-96A-0019 X NONE.
PIPING SUPPORT WELDED C3.20 ATTACHMENT 12" -N/A D1 2 n
%J Page 79
REPORT NO NP0059-OOO5 DATE: 04/04/96 PERRY NUCLEAR POWER PLANT UNIT 1 PAGE: 60 REVISION: 5 ISI
SUMMARY
REPORT NO. NP0059 0005 FIRST INTERVAL, THIRD PERIOD, FIRST GUTAGE (96RF)
CLASS 3 COMPLETED COMPONENTS I HIGH PRESSURE CORE SPRAY SYSTEM N O l ASME O G T '
SEC. XI R E H
SUMMARY
EXAMINATION AREA CATGY EXAM E O E ,
l NUMBER $1ZE SCHEDULE-LINE SPEC ITEM NO METHOD NDE REPORTS C M R REMARKS 1 ....... .............................. ....... .......... ................ . . . ........................................
l (REF. DWG. NO. SS-305-355-101) l l
051870 1E22-H0133 F-A VT 3 1042-96A 0052 X NONE.
RIGID STRUT (WA) F1.3ST
! 24" -N/A L1 3 051880 1E22-H0133 WA D-B VT-3 1042-96A-0051 X NONE.
INTEGRAL ATTACHMENT RIGID 02.20 STRUT 24" -N/A -L1-3 I 051990 1E22-H0146 F-A VT 3 1042-96A-0050 X NONE.
I RIGID GUIDE F1.3G l 22" -N/A -L1 3 1 ;
l l : (REF. DWG. NO. SS-305 351-101) 052100 1E22-$004B-SP F-A VT-3 0142-96A-0054 X NONE.
AIR RECEIVER TANK SUPPGli (WA) F1.40 N/A -H/A -N/A l i
l 1
052110 1E22-S0048-WA DB VT 3 1042 96A 0048 X NONE.
INTEGRAL ATTACHMT AIR RECEIVER D2.20 TANK SUPPORT ANCHOR l N/A N/A N/A 1
l i
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. O Page 80
l REPORT NO. NP0059-0005 DATE: 04/04/96 PERRY NUCLEAR POWER PLANT UNIT 1 PAGE: 61 d
REVISION: 5 ISI
SUMMARY
REPORT No. NP0059-0005
+
b FIRST INTERVAL, THIRD PERICD, FIRST GUTAGE (96RF)
CLASS 1 COMPLETED COMPONENTS j MSIV LEAKAGE CONTROL SYSTEM N O ASME 0 G T SEC. XI A E H
SUMMARY
EXAMINATION AREA CATGY EXAM E O E NUMBER SIZE SCHEDULE-LINE SPEC ITEM NO METHOD NDE REPORTS C M R REMARKS (R2F. DWG. NO. SS-305-341-101) 052500 1E32-0218 a XB PT 0941-96A-0032 X NONE.
2" TEE TO PIPE X0.1 2" -160 -D1-1 052540 1E32-0220 9 XB PT 0941-96A-0032 X NONE.
2" X 2 1/2" REDUCER To 2 1/2" X0.1 PIPE 2 1/2"-160 -DI 1 052580 1E32-0222 a XB PT 0941-96A-0031 X SUPPORT 1E32-H0125 LIMITS THE 1 1/2" ELBOW TO PIPE X0.1 EXAd! NATION COVERAGE FOR THIS AUGMENTED 2-1/2" 160 -D1-1 EXAM TO 87% OF THE CODE VOLUME.
2590 1E32-0223 B-J PT 0941-96A-0033 X REMOVAL OF 1E32-H02648S CLAMP PROVIDED
{Q 2 1/2" PIPE TO 1 1/2" BR.
CONN. (COUPLING) 89.32 F0k !N THE WORK ORDER, BUT THE EXAM WAS ABLE TO BE COMPLETED WITHOUT THE 1 1/2"-160 -DI-1 REMOVAL.
052640 1E32-0225 9 X-B PT 0941-96A 0034 X NONE.
1 1/2" PIPE TO ELBOW X0.1 1-1/2" 160 -D1 1 052700 1E32-0228 9 X-B PT 0941-96A-0034 X NONE.
1 1/2" VALVE F025A TO P!PE X0.1 1-1/2"-160 -D1 1 (REF. DWG. No. SS-305-341-103) l 053120 1E32-0254 a XB PT 0941-96A 0021 X NONE.
2" TEE To 2" X 1" REDUCER X0.1 2" -160 -D1-1
)
Page 81
REPORT NO. NP0059-0005 DATE: 04/04/96 PERRY NUCLEAR POWER PLANT UNIT 1 PAGE: 62
. REVISION: 5 ISI
SUMMARY
REPORT NO. NP0059-0005 FIRST INTERVAL, THIRD PERIOD, FIRST OUTAGE (96RF)
CLASS 1 COMPLETED COMPONENTS MSIVifAKAGECONTROLSYSTEM W 0 ASME O G T SEC. XI R E H OJMpedY ZXAMIK,9 10N AREA CATGY EXAM E O E l Nik8F3 " 2E. SCHEDULE LINE SPEC ITEM NO METHOD NDE REPORTS C M R REMARKS j ...... .............................. ....... .......... ................ . . . ........................................
l (REF. DW NO. SS-305-341 19)),
053140 1E32 0255 a X-B PT 0941-96A-0021 X NONE.
l 2" TEE TO PIPE X0.1 l 2" -160 -D1-1 l 053180 1E32-0257 a X-B PT 0941-96A-0021 X NONE. I I
2" X 2 1/2" REDUCER TO 2 1/2" X0.1 P!PE 2-1/2" 160 -D1-1
(
i i
1 053260 1E32-0261 a X-B PT 0941-96A 0027 X NONE.
l 1 1/2" ELBOW TO PIF'd X0.1 I 1-1/2"-160 -D1-1 l
1E32-0265 a X-B PT 0941-96A-0028 X REMOVAL OF 1E32-H02668S CLAMP PROVIDED j
{)I340
( 2 1/2" PIPE TO ELBOW X0.1 FOR IN THE WORK ORDER, BUT THE EXAM WAS
! 2 1/2"-160 -Dial ABLE TO BE COMPLETED WITHOUT REMOVAL.
l l 053380 1E32-0267 a X-B PT 0941-96A-0022 X REMOVAL OF 1E32 40093'S CLAMP PROVIDED l 2 1/2" PIPE TO VALVE F001J X0.1 FOR IN THE WORK ORDER, BUT THE EXAM WAS l 2-1/2" 160 -D1-1 ABLE TO BE COMPLETED WITHOUT REMOVAL.
l I
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f f Page 82
l I
REPaRT N3. NP0059-0005 DATE: 04/04/96 PERRY NUCLEAR POWER PLANT UNIT 1 PAGE: 63 5 !$1
SUMMARY
REPORT NO. WP0059-0005 7_ REVISION:
h FIRST INTERVAL, THIRD PERIOD, FIRST OUTAGE (96RF)
(O CLASS 1 COMPLETED COMPONENTS l REACTOR CORE ISOLATION COOLING SYSTEM l N O
! ASME O G T SEC. XI R E H
SUMMARY
EXAMINATION AREA CATGY EXAM E O E j NUMBER SIZE SCHEDULE-LINE SPEC ITEM No METHOD NDE REPORTS C M R REMARKS CREF. DWG. No. SS-305-631-ifG) 053640 1E51-0001 B B-G-2 VT-1 1042-96A-0236 X 12 STUDS & 24 NUTS EXAMINED IN PLACE 6" FLANGE BOLTING B7.50 UPON REACTOR HEAD SPRAY REASSEMBLY.
I 6" N/A D1 1 053730 1E51-0009-B B-G-2 VT 1 1042-96A-0237 X 12 STUDS & 24 NUTS EXMINED IN PLACE l
6" FLANGE SOLTING B7.50 UPON REACTOR HEAD SPRAY REASSEMBLY.
6" -N/A -D1 1 053740 1E51 0010 BJ UT 0944/08-96-0014 X GEOMETRIC INDICATIONS REPORTED IN 6" ELBOW TO PIPE (HIGH STRES$) 89.11 PRESERVICE EXAMS SEEN AT SIMILAR 6" -80 -D1 1 MT 0942-96A-0030 X AMPLITUDES AND SWEEP POSITIONS.
(REF. DWG. No. SS 305-631-106) 870 1E51 0023 B-J UT 0944/08-96-0033 X NONE.
6" PIPE TO VALVE F065 (HIGH 89.11 STRESS) MT 0942-96A 0048 X 6" 80 -D1-1 (REF. DWG. NO. SS-305-631-102) 0E4050 1E51-0039 C-F 2 UT 0944/08-96-0008 X X GEOMETRIC INDICATIONS REPORTED IN I 6" PIPE TO TEE C5.51 PRESERVICE EXAMS SEEN AT SIMILAR l 6" 120 -D1 2 MT 0942 96A-0021 AMPLITUDES AND SWEEP POSITIONS.
(REF. DWG. NO. SS-305-632-103) 054630 1E51-0097 C-F-2 UT 0944/08-96-0009 X NONE.
8" X 12" X 12" TEE TO 12" P!PE C5.51 BEND MT 0942-96A-0022 X 12" -STD -L1-2 (REF. DWG. NO. $$ 305-632-102) 054770 1E51-0120 B-J UT 0944/08-96-0038 X NONE.
10" PIPE TO VALVE F064 (HIGH B9.11 l
STRES$) MT 0942-96A-0051 X 10" 80 -D1-1 s
l t
Page 83
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i l
REPORT N3. NP0059-0005 DATE: 04/04/96 PERRY NUCLEAR POWER PLANT UNIT 1 PAGE: 64 l REVISION: 5 ISI
SUMMARY
REPORT NO. NP0059 0005 l FIRST INTERVAL, THIRD PERICO, FIRST GUTAGE (96RF)
\ CLASS 1 COMPLETED COMPONENTS REACTOR CORE ISOLATION COOLING SYSTEM N O l
ASME O G T j SEC. XI R E H
SUMMARY
EXAMINATION AREA CATGY EXAM E O E
, NUMBER SIZE SCHEDULE LINE SPEC ITEM NO METHOD NDE REPORTS C M R REMARKS (REF. DWG. NO. SS-305-632-101) 054840 1E51 0123 a XB UT 0944/08-96-0020 X GEOMETRIC INDICATIONS REPORTED IN 10" VALVE F063 TO PIPE X0.1 PRESERVICE EXAMS SEEN AT SIMILAR 10" -80 -D1 1 AMPLITUDES AND SWEEP POSITIONS.
(REF. DWG. NO. SS-305-631-109) 054960 1E51 C001-002 C-G PT 0941 96A-0006 X NONE.
RCIC PUMP CASING TO SUCTION C6.10 N0ZZLE 6" -N/A -L1-2 051990 1E51 C001-A-WA CC PT 0941 96A-0007 x LUG CONFIGURATION LIMITS PREPARATION AND PUMP SUPPORT WELDED ATTACHMENT C3.30 EXAM To 83% (IR-012).
N/A -N/A -L1-2 55000 1E51-C001-B WA CC PT 0941 96A-0008 X LUG CONFIGURATION LIMITS PREPARATION AND PUMP SUPPORT WELDED ATTACHMENT C3.30 EXAM TO 83% (IR-012).
N/A -N/A -L1-2 055010 1E51-C001-C-WA C-C PT 0941-96A 0009 X LUG CONFIGURATION LIMITS PREPARATION AND PUMP SUPPORT WELDED ATTACHMENT C3.30 EXAM TO 83% (IR-012).
N/A -N/A -L1-2 l
055020 1E51-C001 D-WA C-C PT 0941 96A-0010 X LUG CONFIGURATION LIMITS PREPARATION AND PUMP SUPPORT WELDED ATTACHMENT C3.30 EXAM To 83% (IR 012).
N/A -W/A *L1-2 055030 1E51-C001 SP F-A VT-3 1042-96A-0066 X e NONE.
ANCHOR, PUMP (WA) F1.40 N/A -N/A -L1-2 055070 1E51-F0013-SEAM B-M-1 UT 0944/30 96 0001 X GEOMETRIC INDICATIONS REPORTED IN 6" GATE VALVE BODY WELD B12.40 0944/30-96-0003 X PRESERVICE EXAMS SEEN AT SIMILAR (GROUPING NO. XXI) AMPLITUDES AND SWEEP POSITIONS. CODE 6" -1.500" -D1 1 PLATE OBSTRUCTION LIMITS EXAM COVERAGE TO 94%.
l l ,
Page 84
l l
REP 3RT N3. NP0059-0005 DATE: 04/04/96 PERRY NUCLEAR POWER PLANT UNIT 1 PAGE: 65
, . REVISION: 5 ISI
SUMMARY
REPORT No. NP0059-0005 l [*
l FIRST INTERVAL, THIRD PERIOD, FIRST DUTAGE (96AF)
CLASS 1 COMPLETED COMPONENTS REACTOR CORE ISOLATION COOLING SYSTEM N O ASME O G T SEC. XI R E H
SUMMARY
EXAMINATION AREA CATGY EXAM E 0 E NUMBER SIZE-SCHEDULE-LINE SPEC ITEM NO METHOD NDE REPORTS C M R REMARKS
[ (REF. DWG. NO. SS-305-632-102)
I I 055100 1E51 F0064 SEAM B-M 1 UT 0944/30-96-0004 X EXAM COVERAGE LIMITED TO 93% BY CODE l 10" GATE VALVE BODY WELD B12.40 PLATE.
(GROUP!NG NO. XXil) 10" 2.200" -D1-1 (REF. DWG. NO. SS-305-631-108) 055120 1E51-F0066 Is B-M 2 VT-3 1042-96A-0157 X WONE.
6" CHECK VALVE INTERNAL B12.50 SURFACE (GROUPING No. XXI!!)
6" N/A -D1 1 i
(REF. DWG. No. SS-305-631-109) l l /~5130 1E51-F0502-SEAM C-G MT 0942 96A-0013 X NONE.
6" GATE VALVE BODY WELD C6.20 l 6" 1.500" -D1-2 l
l (REF. DWG No. SS-305-631-102) 055360 1E51 H0042-WA C-C MT 0942-96A-0020 X NONE.
PIPING SUPPORT WELDED C3.20 ATTACHMENT
! 6" -N/A -D1-2 i
l l :
l I
(REF. DWG. NO. SS-305-632-104) l 055440 1E51-H0056 F-A VT-3 1042-96A 0057 X DURING EXAMINATION, CLIPS WERE INSTALLED MECHANICAL SNUBBER F1.2SN AT BOTH ENDS OF THE SNUBBER TO CORRECT 128 -N/A -L1 2 EXCESSIVE CAP. I l
I (REF. DWG. NO. SS-305-632-102) 055750 1E51-H0141 F-A VT-3 1042-96A 0126 X NONE .
VARIABLE SPRING F1.2SP l 10" -N/A -D1-2 I
t I i
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REPORT ND. NP0059-0005 DATE: 04/04/96 PERRY NUCLEAR POWER PLANT UNIT 1 PAGE: 66 REVISION:
5 Ist
SUMMARY
REPORT NO. NP0059-0005 FIRST INTERVAL, THIRD PERIOD, FIRST OUTAGE (96RF)
CLASS 1 COMPLETED COMPONENTS REACTOR CORE ISOLATION COOLING SYSTEM N O j ASME O G T SEC. XI R E H SLMMARY EXAMINATION AREA CATGY EXAM E O E NUMBER SIZE SCHEDULE LINE SPEC ITEM NO METHOD NDE REPORTS C M R REMARKS (REF. DWG. NO. SS-305-631-107) 1 i
055780 1E51 H0151 F-A VT 3 1042 96A 0080 X NONE.
RIGID STRUT F1.1ST 6" -N/A -D1 1 (REF. DWG. No. SS-305-631-106) 055870 1E51-P123-WA B-K-1 MT 0942 96A-0052 X NONE.
P123 FLUED HEAD FITTING TO B10.10 PROCESS P!PE ATTACH WLD 6" -N/A -D1 1 l
l 3
1 O
U Page 86
REPORT N2. NP0059-0005 DATE: 04/04/96 PERRY NUCLEAR POWER PLANT UNIT 1 PAGE: 67 REVISION: 5 ISI
SUMMARY
REPORT NO. NP0059 0005 h
d FIRST INTERVAL, THIRD PERIOD, FIRST OUTAGE (96RF)
CLASS 1 COMPLETED COMPONENTS REACTOR WATER CLEANUP SYSTEM N 0 ASME O G T SEC. XI R E H
SUMMARY
EXAMINATION AREA CATGY EXAM E O E NUM8ER $1ZE-SCHEDULE LINE SPEC ITEM NO METHOD NDE REPORTS C M R REMARKS l
(REF. DWG. No. SS-305-671-101) 055940 1G33-0005 B-F PT 0941-96A-0026 X NONE.
2" SS ELBOW TO CS P!PE B5.140 2" 160 -D1 1 055980 1G33-0007B B-F PT 0941-96A-0036 X NONE.
2" CS TEE TO 2" X 3/4" SS B5.150 REDUCING INSERT 2" -160 -D1-1 056060 1G33 0013A B-F PT 0941-96A-0029 X NONE.
2" X 1 1/4" CS RED. INSERT TO 85.150 SS THERM. ELEMENT 1 1/4"-160 -D1-1 (REF. DWG. NO. SS-305-671-104) 056690 1G33 0063 B-J UT 0944/08-96-0023 X GEOMETRIC INDICATIONS REPORTED IN 6" P131 PROCESS PIPE TO PIPE 89.11 PRESERVICE EXAMS SEEN AT SIMILAR (HIGH STRESS & USE) MT 0942-96A-0043 X AMPLITUDES AND SWEEP POSITIONS.
6" -80 -D1-1 (REF. DWG. NO. SS-305-672-102) 057450 1G33-0120 a XB UT 0944/08-96-0027 X NONE.
6" ELBOW TO PIPE X0.1 6" 120 -D1-2 (REF. DWG. No. SS-305-672-101) 057470 1G33 0121 a XB UT 0944/08-96-0035 X WONE.
6" PIPE TO 6" X 6" X 6" TEE X0.1 6" -120 D1-2 D
d Page 87
.______.._m__.__=_ . . - . _ _ . _ . . _ _ _ _ _ _ _ _ . . _ . _ _ _ _ _ . . _ . . _ _ _ _ _ _ ,
i 1
REP 5RT N3. NP0059-0005 f DATE: 04/04/96 PERRY NUCLEAR POWER PLANT UNIT 1 PAGE: 68 REVISION: 5 ISI
SUMMARY
REPORT NO. NP0059 0005 1
FIRST INTERVAL, THIRD PERIOD, FIRST OUTAGE (96RF)
CLASS 2 COMPLETED COMPONENTS REACTOR WATER CLEANUP SYSTEM g N O ASME D G T SEC. XI R E N
SUMMARY
EXAMINATION AREA CATGY EXAM E O E NUMBER SIZE SCHEDULE-LINE SPEC ITEM NO METHOD NDE REPORTS CM R REMARKS j (REF. DWG, NO. SS-305-672-101) j' 057480 1G33-0122 CF2 UT 0944/08 96 0034 X NONE.
6" X 6" X 6" TEE TO VALVE C5.51 ,
F051A MT 0942-96A 0049 X !
- 6" -120 -D1-2 I 1
057730 1G33-0133 a XB UT 0944/08-96-0037 X PLATE OF SPRING SUPPORT 1G33 H0188 6" PIPE TO VALVE F051B X0.1 LIMITS COVERAGE FOR THIS AUGMENTED EXAM 4
6" -120 -D1-2 TO B6%.
l
+
! 057750 1G33-0134 a XB UT 0944/08-96-0037 X NONE.
6" VALVE F0518 TO ELBOW X0.1 ,
6" -120 -D1-2 l
i I j ["+7770 1G33-0135 a XB UT 0944/08-96-0037 x U BOLT AND PLATE OF SNUBBER SUPPORT l
- 6" ELBOW TO PIPE X0.1 1G33-H0224 LIMIT COVERAGE FOR THIS l 6" -120 -D1-2 AUGMENTED EXAM TO 76%. GEOMETRIC INDICATIONS REPORTED IN PRESERVICE EXAMS l SEEN AT $1MILAR AMPLITUDES AND SWEEP POSITIONS.
057830 1G33-0138 a XB UT 0944/08 96-0035 X NONE.
6" P!PE TO VALVE F052B X0.1 6" -120 -D1 2 057050 1G33-0139 a X-B UT 0944/08-96-0035 X NONE. I 6" VALVE F0528 TO PIPE X0.1 6" -120 -D1 2 057870 1G33-0140 a X-B UT 0944/08 96-0035 X GEOMETRIC INDICATIONS REPORTED IN 6" PIPE TO ELBOW X0.1 PRESERVICE EXAMS SEEN AT SIMILAR 6" -120 -D1-2 AMPLITUDES AND SWEEP POSITIONS.
Page 88
REPORT N3. NP0059-0005 DATE: 04/04/96 PERRY NUCLEAR POWER PLANT UNIT 1 PAGE: 69 REVISION: 5 ISI
SUMMARY
REPORT NO. WP0059-0005 h
d FIRST INTERVAL, THIRD PERIOD, FIRST OUTAGE (96RF)
CLASS 2 COMPLETED COMPONENTS REACTOR WATER CLEANUP SYSTEM N O i ASME O G T SEC. XI R E H
SUMMARY
EXAMINATION AREA CATGY EXAM E O E NUMBER SIZE-SCHEDULE LINE SPEC ITEM NO METHOD NDE REPORTS C M R REMARKS (REF. DWG. NO. SS-305-672-101) I 057890 1G33-0141 a XB UT 0944/08-96-0035 X NONE.
6" ELBOW TO PIPE X0.1 6" 120 -D1-2
)
057910 1G33-0142 S XB UT 0944/08-96-0035 X GEOMETRIC INDICATIONS REPORTED IN 6" PIPE TO ELBOW X0.1 PRESERVICE EXAMS SEEN AT SIMILAR 6" -120 -D1-2 AMPLITUDES AND SWEEP POSITIONS.
I 057930 1G33-0143 9 XB UT 0944/08-96-0034 X GEOMETRIC INDICATIONS REPORTED IN ;
6" ELBOW TO WELDOLET X0.1 PRESERVICE EXAMS SEEN AT SIMILAR l 6" -120 D1-2 AMPLITUDES AND SWEEP POSITIONS.
(REF. DWG. NO. SS-305-671-107) l O F-A VT-3 1K 7 96A 0068 THE SPHERICAL BEARING, FOUND i;ROKEN AND Q 3240 1G33-H0020 X RIGID STRUT F1.1ST REPA! RED IN RF04, WAS FOUND TO BE OK IN 4" -N/A -D25-1 THIS SUCCESSIVE EXAMINATION.
(REF. DWG. NO. SS-305-671 104) 059010 1G33-P131-WA B-K-1 MT 0942 96A 0043 X NONE.
PEN.P131 FLUED HD. FITTING TO B10.10 PROCESS PIPE ATT. WLD 6" -N/A D1 1 O
Page 89
REPORT N3. NPOO59-0005 DATE: 04/04/ % PERRY NUCLEAR POWER PLANT UNIT 1 PAGE: 70 REVISION: 5 ISI
SUMMARY
REPORT NO. NP0059-0005 O FIRST INTERVAL, THIRD PERIOD, FIRST CUTAGE (96RF)
CLASS 3 COMPLETED COMPONENTS
! SUPPRESSION POOL DRAIN AND CLEAN UP SYSTEM l
N O ASME O G T SEC. XI R E H
SUMMARY
EXAMINATION AREA CATGY EXAM E O E NUMBER SIZE SCHEDULE-LINE SPEC ITEM NO METHOD NDE REPORTS C M R REMARKS j ....... .............................. ....... .......... ................ . . . ........................................
i (kEF. DWG. NO. SS 305 655-101) 062800 1G42-H0005 WA D-C VT-3 1042 96A-0040 X NONE.
INTEGRAL ATTACHMENT RIGID D3.20 GUIDE
, 10" -N/A L1 3 l
l l
062890 1G42-H0013-WA D-C VT 3 1042-96A-0037 X NONE.
INTEGRAL ATTACHMENT MECHANICAL D3.30 l SNUB 8ER 10" -N/A L1-3 1
I l
062920 1G42-H0016 FA VT-3 1042-96A-0039 X NONE.
RIGID ROD F1.3R j
10" -N/A -L1 3 l
l l
l i l l l
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- d Page 90 i
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REPORT NO. NP0059-0005 DATE: 04/04/96 PERRY NUCLEAR POWER PLANT UNIT 1 PAGE: 71 REVISION: 5 ISI
SUMMARY
REPORT NO. WP0059-0005
[] FIRST INTERVAL, THIRD PERIOD, FIRST GUTAGE (96RF)
L/ CLASS 2 COMPLETED COMPONENTS MAIN & REHEAT STEAM SYSTEM N O ASME O G T SEC. XI R E H
SUMMARY
EXAMINATION AREA CATGY EXAM E O E NUMBER $1ZE SCHEDULE *LINE SPEC ITEM NO METHOD NDE REPORTS C M R REMARKS (REF. DWG. NO. SS-305-605 107) 063015 1N11-H0223-WA C-C VT-1 1042 96A-0156 X NONE.
INTEGRAL ATTACHMENT RIGID C3.20 GUIDE 28" N/A -D1-2 1
(REF. DWG. NO. SS-301 605 109) 063025 1N11-H0224-WA CC VT-3 1042-96A-0154 X NONE.
INTEGRAL ATTACIMENT RIGID C3.20 GUIDE 28" -N/A -Di-2 l l
l l
O Page 91
REPORT N3. NP0059-0005 DATE: 04/04/ % PERRY NUCLEAR POWER PLANT UNIT 1 PAGE: 72 REVISION: 5 ISI
SUMMARY
REPORT NO. NP0059-0005 O FIRST INTERVAL, THIRD PERIOD, FIRST OUTAGE (96RF)
V CLASS 1 COMPLETED COMPONENTS MAIN. REHEAT. EXTRACTION AND MISC. DRAINS SYSTEM N 0 ASME 0 G T SEC. XI R E H
SUMMARY
EXAMINATION AREA CATGY EXAM E O E NUMBER SI2E-SCHEDULE-LINE SPEC ITEM NO METHOD NDE REPORTS C M R REMARKS (REF. DWG. NO. SS-305 121 102) 063160 1N22-0027 a XB PT 0941-96A 0015 X NONE.
2" PIPE TO ELBOW X0.1 2" -160 -D1 1 063200 1N22-0029 G X-B PT 0941-96A 0015 X NONE.
2" PIPE TO ELBOW X0.1 2" -160 -D1 1 s
063200 1N22-0030A a XB PT 0941-96A-0015 X NONE.
2" PIPE TO COUPl.!NG X0.1 2" -160 D1 1 0633t0 1N22 0033 G X-B PT 0941-96A 0020 X NONE.
2" PIPE TO ELBOW X0.1 O 2" -160 -D1-1 063380 1N22-0035 9 X-B PT 0941-96A 0023 X NONE.
2" P!PE TO ELBOW X0.1 2" -160 D1-1 (REF. DWG. NO. SS-305 121-103) 063680 1N22-0071 S XB PT 0941-96A-0030 X NONE.
3" X 3" X 2" TEE TO 3" PIPE X0.1 3" -160 -D1-1 l
063700 1N22-0072 a XB PT 0941-96A 0030 X REMOVAL OF 1N22-H0130'S CLAMP PROVIDED l 3" PIPE TO 3" X 3" X 2" TEE X0.1 FOR IN THE WORK ORDER, BUT THE EXAM WAS 3" +160 -D1-1 ABLE TO BE COMPLETED WITHOUT REMOVAL.
063720 1N22-0073 a X-B PT 0941-96A 0024 X NONE.
3" X 3" X 2" TEE TO 3" PIPE X0.1 3" 160 D1-1 s i Page 92
REPSRT N3. NP0059-0005 DATE: 04/04/96 PERRY NUCLEAR POWER PLANT UNIT 1 PAGE: 73 i REVISION: 5 ISI
SUMMARY
REPORT NO. NP0059-0005 FIRST INTERVAL, THIRD PERIOD, FIRST OUTAGE (96RF)
CLASS 1 COMPLETED COMPONENTS '
MAtW. REHEAT. EXTRACTION AND MISC. DRAINS SYSTEM N O l ASME O G T SEC. XI R E N
SUMMARY
EXAMINATION AREA CATGY EXAM E O E
] NUMBER SIZE SCHEDULE LINE SPEC ITEM No METHOD NDE REPORTS C M R REMARKS !
j (REF. DWG. NO. 5S-305 121-103) 1 1
063730 1N22-0074 BJ PT 0941 96A-0024 X NONE. i 3" PIPE TO VALVE F016 B9.21 !
, 3" -160 -D1-1 j i 063760 1N22-0075 S X-B PT 0941-96A-0024 X NONC.
3" VALVE F016 TO P423 PROCESS X0.1 PIPE 3" -160 -D1-1 (REF. DWG. NO. SS-305-121 102) 064170 1N22-0136 BJ PT 0941 96A 0015 X NONE.
VALVE F022A TO 2" PIPE (HIGH 89.40 STRESS)
, 2" -160 D1 1 064200 1W22-0137 a X-B PT 0941 96A-0017 x EXAM FOUND TWO ACCEPTABLE 3/32" ROUNDED 2" PIPE TO ELBOW X0.1 INDICATIONS.
4 2" -160 -D1-1 064260 1N22 0140 G X-B PT 0941-96A-0016 X EXAM FOUND AN ACCEPTABLE 1/8" LINEAR 2" ELBOW TO PIPE X0.1 INDICATION ON THE SOCKET ELBOW FITTING 2" -160 -DI 1 (COLD LAP).
064310 1N22-0143 8-J PT 0941-96A-0019 X EXAM FOUND TWO ACCEPTABLE 3/32" ROUNDED 2" PIPE TO ELBOW (HIGH STRESS) B9.40 INDICATIONS.
2" 160 -D1-1 064330 1N22 0144 B-J PT 0941-96A 0035 X FOUND THAT THE CLAMP OF 1N22 H0126 IS AT 2" ELBOW TO PIPE (HIGH STRESS) 89.40 THE TOE OF THE WELD. WORK ORDER WAS 2" -160 -D1-1 REVISED TO PROVIDE FOR REMOVAL OF THE CLAMP AND THE EXAM WAS COMPLETED.
O Page 93
. ._. ~ . - . _ . .
REPORT NO. NP0059-0005 DATE: 04/04/96 PERRY NUCLEAR POWER PLANT UNIT 1 PAGE: 74 REVISION: 5 ISI SUMARY REPORT NO. NP0059-0005 FIRST INTERVAL, THIRD PERIOD, FIRST OUTAGE (96RF) i CLASS 1 COMPLETED COMPONENTS MAIN, REHEAT. EXTRACTION AND MISC. DRAINS SYSTEM N 0 ASME O G T SEC. XI R E H SUMARY EXAMINATION AREA CATCY EXAM E O E NUMBER SIZE-SCHEDULE LINE SPEC ITEM NO METHOD NDE REPORTS C M R REMARKS 6
4 (REF. DWG. NO. SS-305-121 102) 064350 IN22-0145 B-J PT 0941 96A 0023 X NONE.
2" PIPE TO ELBOW (NIGH STRESS) 89.40
! 2" -160 -D1 1 f
1 064370 1N22-0146 BJ PT 0941-96A-0023 X NONE.
2" ELBOW TO PIPE (HIGH STRESS) B9.40 i 2" -160 -D1 1 t
A
.i 064630 1N22 H0129 F-A VT-3 1042-96A-0120 X NONE.
MECHANICAL SNU8BER F1.1SN
- k" -N/A -D1-1 a
(REF. DWG. NO. SS-305-121-103)
D
- ( G 710P423 1N22-P423-WA FLUED HD. FITTING TO B-K-1 B10.10 MT 0942-96A-0037 X NONE.
1 PROCESS PIPE ATTACH. WLD 3"
N/A -D1 1 1
i
. l 1
f I
l l
I i
l
(
V)
Page 94
REPORT NO. NP0059-0005 DATE: 04/04/96 PERRY NUCLEAR POWER PLANT UNIT 1 PAGE: 75 +
REVISION: 5 ISI
SUMMARY
REPORT NO. NP0059-0005 FIRST INTERVAL, THIRD PERIOD, FIRST GUTAGE (96RF)
CLASS 1 COMPLETED COMPONENTS FEEDWATER SYSTEM N 0 ASME D G T SEC. XI R E N Sul#4ARY EXAMINATION AREA CATGY EXAM E O E NUMBER SI2E SCNEDULE LINE SPEC ITEM NO METHOD NDE REPORTS C M R REMARKS (REF. DWG. NO. SS-305-082-102) 064800 1N27-0007 a XB UT 0944/08 96-0052 X NONE.
20" VALVE F559A TO PIPE XL, 1 20" 80 -D1 1 (REF. DWG, NO. SS 305-082-101) l 064900 1N27-0011 a XB UT 0944/08 % -0042 X NONE.
20" x 20" X 14" TEE TO P!PE X0.1 I 20" -120 -D1-2 1
064920 1N27-0011A a XB UT 0944/08-96 0041 X GEOMETRIC INDICATIONS REPORTED IN j 20" X 20" X 14" TEE TO 14" X X0.1 PRESERVICE EXAMS SEEN AT SIMILAR 12" REDUCER AMPLITUDES AND SWEEP POSITIONS. )
20" 100 -D1-2 I b /
%.64940 U 1N27-0012 a XB UT 0944/08-96-0040 X NONE.
20" PIPE TO 20" X 20" X 14" X0.1 TEE 20" -100 -D1-2 (REF. DWG. NO. $$-305-082-103) 065300 1N27-0033 B-J UT 0944/08 96 0028 X GEOMETRIC INDICATIONS REPORTED IN 12" ELBOW TO PIPE (HIGH 89.11 PRESERVICE EXAMS SEEN AT SIMILAR STRESS) MT 0942 96A 0039 X AMPLITUDES AND SWEEP POSITIONS.
12" 80 -D1-1 i 065310 1N27 0034 BJ UT 0944/08-96-0017 X NONE.
12" PIPE TO N4C SAFE-END (HIGH 89.11 STRESS) MT 0942-96A 0034 X 12" -80 -D1 1 065470 1N27-0049 BJ UT 0944/08-96-0021 X NONE.
12" PIPE TO N4A SAFE END (HIGH 89.11 STRESS) MT 0942-96A-0039 X 12" 80 -D1 1 Page 95
l REPORT NO. NP0059-0005 l DATE: 04/04/96 PERRY NUCLEAR POWER PLANT UNIT 1 PAGE: 76 REVISION: 5 ISI
SUMMARY
REPORT NO. NP0059-0005 FIRST INTERVAL, THIRD PERIOD, FIRST OUTAGE (96RF) d CLASS 1 COMPLETED COMPONENTS FEEDWATER SYSTEM N 0 ASME O G T SEC. XI R E H
SUMMARY
EXAMINATION AREA CATGY EXAM E O E NUMBER SIZE SCHEDULE-LINE SPEC ITEM NO METHOD NDE REPORTS C M R REMARKS (REF. DWG. NO. SS-305-082-106) 1 065530 1N27-0055 B-J UT 0944/08-96-0018 X NONE.
12" P!PE TO N40 SAFE-END (HIGH 89.11 STRESS) MT 0942- M -0035 X 12" -80 -D1-1 065700 1N27 0070 B-J UT 0944/08-96-0022 X NONE.
12" PIPE TO N4F SAFE-END (HIGH B9.11 STRESS) MT 0942- W -0038 X 12" -80 -D1 1 (REF. DWG. NO. SS-305-971-101) 065840 1N27-0084 X-B PT 0941-96A-0014 X NONE.
1 1/2" PIPE TO CROSS X0.1
(] 1-1/2"-160 -D1-2 i U l (REF. DWG. NO. SS-305-082-103) 066040 1N27-H0010 WA B-K 1 MT 0942 W -0039 X NONE.
INTEGRAL WELDED ATTACHMENT FOR B10.10 VARIABLE SPRING 12" N/A -D1-1 (REF. DWG. NO. SS-305-082-101) 066300 1N27-H0032-WA C-C VT-3 1042-96A-0128 X NONE.
PIPING SUPPORT WELDED C3.20 ATTACHMENT 20" -N/A -D1 1 (REF. 0WG. NO. SS-305-971 101) 066324 1N27 H1127 F-A VT 3 1042-96A 0117 X NONE.
RIGID GUIDE ( %tMENTED F1.50 HEP!BER) 1 1/2"-N/A D1-2 i
L Page 96
REPORT N3. NP0059-0005 DATE: 04/04/96 PERRY NUCLEAR POWER PLANT UNIT 1 PAGE: 77 REYISION: 5 ISI
SUMMARY
REPORT No. NP0059-0005 FIRST INTERVAL, THIRD PERIOD, FIRST CUTAGE (96RF)
CLASS 2 COMPLETED COMPONENTS lifB ATER STSTEM N O ASME D G T SEC. XI R E H
SUMMARY
EXAMINATION AREA CATGY EXAM E O E NUMBER $1ZE SCHEDULE-LINE SPEC ITEM No METHOD NDE REPORTS C M R REMARKS (REF. DWG. No. SS-305 971-101) 066326 1N27-H1129 FA VT-3 1042-96A-0118 X NONE.
RIGID GUIDE (AUGMENTED F1.50 NEPIBER) 1-1/2"-N/A -D1-2
(
l j
l
\
Page 97
I REPORT N3. NPOO59-0005 DATE: 04/04/96 PERRY NUCLEAR POWER PLANT UNIT 1 PAGE: 78 j REVISION: 5 ISI
SUMMARY
REPORT NO. NP0059-0005
[N FIRST INTERVAL, THIRD PERIOD, FIRST OUTAGE (96AF)
CLASS 3 COMPLETED COMPONENTS EMERGENCY CLOSED COOLING SYSTEM N 0 ASME O G T SEC. XI R E H
SUMMARY
EXAMINATION AREA CATGY EXAM E O E NUMBER SIZE-SCHEDULE LINE SPEC ITEM NO METHOD NDE REPORTS C M R REMARKS q (REF. DWG. NO. SS-305-621-108) 066600 1P42-H0108-WA D-8 VT-3 1042-95B 0007 X NONE.
INTEGRAL ATTACHMENT RIGID D2.20 STRUT 12" -N/A -L1-3 (REF. DWG. NO. SS-305-621 106) 066770 1P42 H0120-WA D-B VT-3 1042-95B-0009 X NONE.
INTEGRAL ATTACHMENT VARIABLE D2.40 SPRING 10" *N/A -L1-3 (REF. DWG. NO. SS-305-621-109)
$940 1P42-H0148-WA DB VT-3 1042-958-0011 X GENERAL SURFACE CORROSION NOTED ON THE INTEGRAL ATTACHMENT MIGID D2.20 LUGS.
GUIDE l 12" -N/A -L1-3 (REF. DWG. NO. SS-305 621-110) 067050 1P42-H0163 F-A VT-3 1042-95B-0002 X NONE.
RIGID GUIDE F1.3G
]
12" -N/A -L1-3 (REF. DWG. NO. SS-305-621-109) 067350 1P42-H0219-WA DB VT-3 1042-95B-0010 X NONE.
INTEGRAL ATTACHMENT ANCHOR D2.20 10" N/A L1-3 (REF. DWG. No. SS-305-621-104) 067620 1P42-H0241-WA D-B VT-3 1042 95A-0006 X NONE.
INTEGRAL ATTACHMENT RIGID D2.20 STRUT 10" N/A -L1-3
/
\
Page 98
REPT.RT ND. NP0059-0005 DATE: 04/04/96 PERRY NUCLEAR POWER PLANT UNIT 1 PAGE: 79
' REVISION: 5 IS!
SUMMARY
REPORT NO. WP0059 0005 FIRST INTERVAL, THIRD PERIOD, FIRST GUTAGE (96RF)
CLASS 3 COMPLETED COMPONENTS EMERGENCY CLOSED C00t!NG SYSTEM N O ASME O G T SEC. XI R E H
SUMMARY
EXAMINATION AREA CATGY EXAM E O E NUM8ER SIZE SCHEDULE LINE SPEC ITEM NO METHOD NDE REPORTS C M R REMARKS (REF. DWG. No. SS-305-621-104) 067640 1P42 H0242-WA DB VT-3 1042-958-0005 X NONE.
INTEGRAL ATTACHMENT RIGID D2.20 STRUT 10" -N/A -L1-3 1
1 I
l l
l 1
O O
1 O
Page 99
__ ___m .~ _ . _ _ . . _ - -. -- -
l REPERT NO. NP0059-0005 l DATE: 04/04/96 PERRY NUCLEAR POWER PLANT UNIT 1 PAGE: 80 RE 5 ISI
SUMMARY
REPORT NO. NP0059-0005 O' VISION: FIRST INTERVAL, THIRD PERIOD, FIRST DUTAGE (96RF)
CLASS 3 COMPLETED COMPONENTS EMERGENCY SERVICE WATER SYSTEM N O ASME O G T SEC. XI R E H
SUMMARY
EKAMINATION AREA CATGY EXAM E O E NUMBER SIZE SCHEDULE-LINE SPEC ITEM NO METHOD NDE REPORTS CM R REMARKS (REF. DWG. No. SS-305-791-107) 067760 1P45 0003-SP FA VT 3 1042-96A 0002 X TANK AND SUPPORT LEG TO TANK WELDS ARE ANCHOR, FILTER SUPPORT (WA) F1.40 COVERED WITH MASTIC INSULATION.
N/A -N/A -
(REF. DWG, NO. SS 305-792-116) 068250 1P45-H0047-WA DB VT-3 1042-96A 0065 X NONE.
INTEGRAL ATTACHMENT ANCHOR D2.20 14" N/A -L1-3 (REF. DWG. NO. SS-305 792-112) 068410 1P45 H0060-WA D-B VT-3 1042-96A-0064 X NONE.
INTEGRAL ATTACHMENT ANCHOR D2.20 16" -N/A -L1 3 068440 1P45 H0063 FA VT 3 1042-96A-0003 X NONE.
RIGID GUIDE F1.3G 16" -N/A L1 3 (REF. DWG. NO. SS-305-792-113) 068610 1P45 H0077-WA D-B VT-3 1042-958 0015 X NONE .
INTEGRAL ATTACHMENT ANCHOR D2.20 20" N/A L1-3 (REF. DWG, NO. SS-305 792-118) 068740 1P45 H0089-WA D-B VT-3 1042 96A-0055 X NONE.
INTEGRAL ATTACHMENT ANCHOR D2.20 20" -N/A L1-3 j
i (REF. DWG. NO. SS-305 791-111) l 068880 1P45-H0100 WA DB VT-3 1042-96A-0004 X APPR0XIMATELY 1/3 0F WELD SURFACE INTEGRAL ATTACHMENT ANCHOR D2.20 PAINTED, HOWEVER NO CRACKING OR 24" N/A L1-3 DEGRADATION OF PAINTED SURFACE WAS NOTED.
I Page 100 j
l REPURT NO. NP0059-0005 I
DATE: 04/04/96 PERRY NUCLEAR POWER PLANT UNIT 1 PAGE: 81 REYlSION: 5 ISI
SUMMARY
REPORT No. NP0059 0005 FIRST INTERVAL, THIRD PERIOD, FIRST DUTAGE (96RF)
,,, CLAS3 3 COMPLETED COMPONENTS EMERGENCY SERVICE WATER SYSTEM N O ASME O G T SEC. XI R E H
SUMMARY
EXAMINAT!DN AREA CATGY EXAM E O E NUMBER SIZE SCHEDULE-LINE SPEC ITEM NO METHOD NDE REPORTS C M R REMARKS (REF. DWG. No. SS-305-791 113) 070080 1P45-H0210 WA DB VT 3 1042-95B 0014 X N ONE .
INTEGRAL ATTACHMENT ANCHOR D2.20 14" *N/A L1 3 l
(REF. DWG. NO. SS-305-791-112) 070160 1P45-H0216 F-A VT-3 1042-96A-0043 X NONE.
MECHANICAL SNUBBER F1.3SN 24" N/A L1 3 (REF. DWG. NO. SS 305 791 103) 070530 iP45-H0249 F-A VT 3 1042-96A-0005 X NONE.
RIGID GUIDE F1.3G 8" -M/A -L1 3 (REF. DWG. NO. SS-305-791-104) !
l 070790 1P45 H0272 WA D-B VT 3 1042 958 0012 X NONE.
INTEGRAL ATTACHMENT VARIABLE D2.40 SPRING 8" N/A L1 3 070810 1P45 H0273 WA DB VT-3 1042-95B-0020 X NONE.
INTEGRAL ATTACHMENT RIGID 02.20 STRUT 8" -N/A L1 3 (REF. DWG. No, SS-305-792-115) 071210 1P45 H0309-WA DB VT-3 1042-96A 0006 X NONE.
l INTEGRAL ATTACHMENT R!GID ROD 02.20 8" N/A -L1-3 i
\ l'~~\
l N, I l
Page 101
._.. .__. ._. - _ =_ _ _ __ _ _ _ _ ,
l REPORT NO. NP0059-0005 DATE: 04/04/96 PERRY NUCLEAR POWER PLANT UNIT 1 PAGE: 82 l REVISION: 5 ISI SUMMAY REPORT NO. NP0059 0005 l FIRST INTERVAL, THIRD PER100, FIRST GUTAGE (96RF)
\
CLASS 3 COMPLETED COMPONENTS EMERGENCY SERVICE WATER SYSTEM N O ASME O G T SEC. XI R E H
SUMMARY
EXAMINATION AREA CATGY EXAM E O E NUMBER SIZE
- SCHEDULE-LINE SPEC ITEM NO METHOD NDE REPORTS C M R REMARKS (REF. DWG. NO. S$-305 792-116) 071430 1P45 H0360 FA VT 3 1042-96A-0007 X NONE.
RIGID GUIDE F1.3G 14" N/A -L1-3 (REF. DWG. NO. SS-305-791-1011 071910 1P45-H0405 F-A VT-3 1042-96A-0035 X NONE.
RIGID STRUT F1.3ST 8" -N/A L1-3 071940 1P45-H0408 FA VT 3 1042 958-0001 X NONE.
RIGID GUIDE F1.3G 8" -N/A L1-3 i 3 (Q (REF. DWG. NO. SS-305-791-102) 072180 1P45-H0428-WA D-B VT-3 1042 96A-0001 X NONE.
INTEGRAL ATTACHMENT RIGID D2.20 GUIDE 8" N/A L1-3 (REF. DWG. NO. SS-305-792-114) 072480 1P45-H0511-WA DB VT-3 1042-96A 0046 X WONE.
INTEGRAL ATTACHMEN1 RIGID D2.30 STRUT 8" -N/A L1 3 (REF. DWG. NO. SS-305-792-111) 072500 1P45 H0512-WA DB VT-3 1042 96A-0045 X NONE.
INTEGRAL ATTACHMENT MECHANICAL D2.30 SNU8BER 8" -N/A -L1-3 a
O Page 102
i l
REPORT NO. NP0059-0005 DATE: 04/04/96 PERRY NUCLEAR POWER PLANT UNIT 1 PAGE: 83 j REVISION: 5 IS!
SUMMARY
REPORT NO. NP0059-0005 i r FIRST INTERVAL, THIRD PERIOD, FIRST OUTAGE (96RF) l CLASS 3 COMPLETED COMPONENTS j EMERGENCY SERVICE WATER SYSTEM N O \
ASME O G T SEC. XI R E H j
SUMMARY
EXAMINATION AREA CATGY EXAM E O E NUM8ER SIZE SCHEDULE-LINE SPEC ITEM NO METHOD NDE REPORTS C M R REMARKS (REF. DWG. NO. SS-305-791 113) l I
072830 1P45 H0605 FA VT 3 1042-96A-0008 X NONE.
RIGID GUIDE F1.3G 14" -N/A L1-3 ;
1 072340 1P45-H0606 F-A VT 3 1042-96A-0031 X THIS SUCCES$1VE EXAM FOUND THAT THE R!telD GUIDE F1.3G CONDITION OF THE W8X17" ! BEAM FLANGE, 14" -N/A L1-3 WHICH WAS FOUND BENT IN RF04 AND EVALUATED AS USE-AS-IS BY NR-94-S-069, WAS UNCHANGED.
4 072850 1P45 H0607 F-A VT 3 1042-96A-0009 X NONE.
RIGID GUIDE F1.3G l 14" -M/A -L1-3 (REF. DWG. No. SS-305-791 110) 073220 1P45-H0654 WA D-B VT-3 1042-96A-0030 X NONE.
j INTEGRAL ATTACHMENT RIGID D2.20 GUIDE 14" N/A -L1-3 i 073250 1P45-H0656-WA D-B VT-3 1042-96A 0029 X NONE.
j INTEGRAL ATTACHMENT RIGID D2.20 GUIDE i 14" N/A L1 3 i (REF. DWG. NO. SS-305-791-112) 073480 1P45 H5003 F-A VT-3 1042-95B 0003 X NONE.
RIGID STRUT (WA) F1.3ST 24" N/A L1 3 l
1 073490 1P45-H5003-WA D-B VT-3 1042-95B 0004 X NONE.
INTEGRAL ATTACHMENT RIGID D2.20 STRUT 24" N/A -L1-3 4
O V
Page 103 l
REPORT N3. NP0059-0005 DATE: 04/04/96 PERRY NUCLEAR POWER PLANT UNIT 1 PAGE: 86 REVISION: 5 ISI
SUMMARY
REPORT NO. NP0059-0005 O FIRST INTERVAL, THIRD PERIOD, FIRST GUTAGE (96RF)
STANDBY DIESEL EXHAUST. INTAKE & CRANKCASE SYSTEM CLASS 3 COMPLETED COMPONENTS N O ASME O G T 4
SEC. XI R E H
SUMMARY
EXAMINATION AREA CATGY EXAM E O E f NUMBER SIZE SCHEDULE-LINE SPEC ITEM NO METHOD NDE REPORTS C M R REMARKS ,
- (REF. DWG. NO. SS 305-355-104) 076650 1R48-D001B SP F-A VT-3 1042 96A-0038 X EXAM FOUND GROUT AND CONCRETE CRACKS. l 4
ANCHOR, STANDBY DIESEL F1.40 THE CRACKS WERE PREVIOUSLY IDENTIFIED IN )
SILENCER (WA) NONCONFORMANCE REPORTS 91-N-059 AND 068,
. N/A N/A -N/A AND WERE DISPOSITIONED "USE-AS-IS."
076662 1R48-D0015 WA D-B VT 3 1042 96A-0062 X NONE.
r INTEGRAL ATTACHMENT STANDBY D2.20 DIESEL $!LENCER ANCHOR N/A -N/A -N/A (REF. DWG. NO. SS-305-355-102)
?
, ANCHOR; STANDBY DIESEL F1.40 ACCEPTANCE CRITERIA.
l '
{
(
SILENCER (WA)
N/A -N/A -N/A 076670 1R48-0002B-WA D-B VT-3 1042-96A-0022 X NONE.
INTEGRAL ATTACHMENT STANDBY D2.20 DIESEL SILENCER ANCHOR
. N/A -N/A -N/A
, 076676 1R48-D003B-SP FA VT-3 1042-96A-0024 X SLIGHT CRACKING AT CONCRETE; WITHIN ANCHOR; STANDBY DIESEL F1.40 ACCEPTANCE CRITERIA.
SILENCER (WA)
N/A N/A -N/A 076678 1R48-00038-WA D-B VT-3 1042-96A 0026 X NONE.
INTEGRAL ATTACHMENT STANDBY D2.20 DIESEL SILENCER ANCHOR N/A N/A -N/A (REF. DWO. No. SS-305-355-106) 076684 1R48-D010B SP F-A VT-3 1042-96A-0027 X EXAM FOUND CONCRETE CRACKS WHICH ARE ANCHOR; STANDBY DIESEL F1.40 SIMILAR IN LOCATION AND SEVERITY TO SILENCER THOSE OF 1R48-D010A-SP, WHICH WERE N/A N/A -N/A PREVIOUSLY IDENTIFIED AND DISPOSIONED "USE-AS-IS." Plf 96-178 WAS WRITTEN AND Q ALSO DISPOSITIONED "USE-AS-IS."
Page 106
REPORT N3. NP0059-0005 DATE: 04/04/ % PERRY NUCLEAR POWER PLANT UNIT 1 PAGE: 85 REVISION: 5 ISI
SUMMARY
REPORT NO. NP0059-0005 O FIRST INTERVAL, THIRD PERIOD, FIRST CUTAGE (96RF)
U CLASS 3 COMPLETED COMPONENTS CONTROL COMPLEX CHILLER WATER SYSTEM N O ASME O G T SEC. XI R E N
SUMMARY
2XAMINATION AREA CATGY EXAM E O E NUMBER SIZE SCHEDULE LINE SPEC ITEM NO METHOD NDE REPORTS C M R REMARKS (REF. DWG. NO. SS-305-002-110) 074780 1P47-H0215-WA DB VT 3 1042-96A-0016 X WELDS EXHIBITED MINIMAL FLAKY RUST.
INTEGRAL ATTACHMENT AM. HOR D2.20 10" N/A -L1-3 (REF. DWG. NO. SS-305-002-103) 074800 1P47-H0218-WA DB VT-3 1042-96A-0017 X NONE.
l INTEGRAL ATTACHMENT ANCP.OR D2.20 10" -N/A L1-3 1 (REF. DWG. NO. SS-305-002-110) 075390 1P47-H0287-WA D-B VT 3 1042 96A 0018 X NONE.
INTEGRAL ATTACHMENT RIGID D2.20 l A STRUT 10" -N/A L1-3 (REF. DWG. NO. $$-305-002-1131 075720 1P47-H0349-WA DB VT-3 1042-96A 0019 X ALL LUGS EXHIBIT MINIMAL FLAKY RUST.
INTEGRAL ATTACHMENT RIGID D2.20 STRUT 8" -N/A -L1-3 (REF. DWG. NO. $$-305-002-108) 075990 1P47 H0381-WA D-B VT-3 1042-96A-0020 X NONE.
INTEGRAL ATTACHMENT VARIABLE D2.40 SPRING 10" -N/A -L1-3 (REF. DWG. NO. $$-305-002 113) 076040 1P47-H0385 F-A VT 3 1042-96A-0021 X PIPE CLAMP BOLTING EXHIBITS MINIMAL RIGID STRUT F1.3ST FLAKY RUST.
8" N/A L1-3 O
Page 105
1 l
l REPORT N3. NPOO59-0005 DATE: 04/04/% PERRY NUCLEAR POWER PLANT UNIT 1 PAGE: 84
_ REVISION: 5 ISI
SUMMARY
REPORT NO. NP0059-0005
( FIRST INTERVAL, THIRD PERIOD, FIRST GUTAGE (96RF)
CLASS 3 COMPLETED COMPONENTS CONTROL COMPLEX CHILLER WATER SYSTEM N O ASME O G T SEC. XI R E H
SUMMARY
EXAMINATION AREA CATGY EXAM E O E NUMBER SIZE-SCHEDULE LINE SPEC ITEM NO METHOD NDE REPORTS C M R REMARKF (REF. DWG. NO. SS-305 002 1011 073860 1P47 H0015 WA D-B VT-3 1042- M -0012 X LUGS EXHIBITED MINIMAL FLAKY RUST. ,
INTEGRAL ATTACHMENT RIGID D2.20 GUIDE 10" -N/A -L1 3 1
(REF. DWG. NO. SS-305-002-102) 073880 1P47-H0016-WA DB VT-3 1042- M -0013 X NONE.
j INTEGRAL ATTACHMENT RIGID D2.20 1 GUIDEUPPORT j 10" N/A L1-3 1 l
\
I (REF. DWG. NO. SS-305-002-103) l 71040 1P47 H0031 F-A VT-3 1042- N -0010 X NONE.
l RIGID GUIDE (WA) F1.3G 10" -N/A L1-3 074050 1P47-H0031-WA D-B VT-3 1042 M -0011 X WELD EXHIBITED MINIMAL FLAKY RUST.
INTEGRAL ATTACHMENT RIGID D2.20 GUIDE 10" N/A -L1-3 (REF. DWG. NO.1S-305-002 107) 074220 1P47-H0046-WA D-B VT 3 1042- M -0014 X NONE.
INTEGRAL ATTACHMENT RIGID D2.20 STRUT 10" -N/A L1 3 (REF. DWG. NO. SS-305-002-102) 074280 1P47-H0053 F-A VT-3 1042 96A 0015 X ITEMS A AND B WERE COVERED WITH RIGID STRUT F1.3ST INSULATION, HOWEVER NO DAMAGE TO 10" N/A -L1 3 INSULATION WAS OBSERVED.
O Page 104
REPORT N3. NP0059-0005 DATE: 04/04/96 PERRY WUCLEAR POWER PLANT UNIT 1 PAGE: 87 REVISION: 5 !$1 SUNMARY REPORT NO. NP0059-0005 i FIRST INTERVAL, THIRD PERIOD, FIRST OUTAGE (96RF)
V CLASS 3 COMPLETED COMPONENTS STANDBY DIESEL-EXHAUST. INTAKE & CRANKCASE SYSTEM N O ASME O G T SEC. XI R E H
SUMMARY
EXAMINATION AREA CATGY EXAM E O E NUMBER SIZE SCHEDULE-LINE SPEC ITEM NO METHOD NDE REPORTS C M R REMARKS (REF. DWG. NO. SS-305 355-102) 077000 1R48 H0024-WA D-B VT 3 1042-96A-0023 X NONE.
INTEGRAL ATTACNMENT ANCHOR D2.20 24" N/A -L1 3 (REF. DWG. NO. SS-305 355-104) l l
077100 1R48-H0033 F-A VT-3 1042-96A-0032 X NONE.
VARIABLE SPRING F1.3SP l 26" N/A -L1 3 077120 1R48-H0034-WA DB VT-3 1042-96A 0033 X NONE. I INTEGRAL ATTACHMENT MECHANICAL D2.20 SNUBBER '
36" N/A L1 3 1 D
)
077220 1R48 H0042-WA D-B VT 3 1042-96A-0063 X POWER WIRE BRUSH WELD PREPARATION WAS INTEGRAL ATTACHMENT VARIABLE D2.40 REQUIRED PRIOR TO EXAMINATION.
SPRING 48" N/A -L1 3 (REF. DWG. NO. SS 305-355-106]
077260 1R48 H0045-WA D-B VT-3 1042-96A-0028 X NONE.
INTEGRAL ATTACHMENT RIGID D2.20 GUIDE 16" -W/A L1-3 (REF. DWG. N0. SS 305-355 108) 077410 1R48-PH005 F-A VT 3 1042 96A 0034 X NONE.
RIGID ROD F1.3R 6" N/A -L1-4 D
0 Page 107
1 REPORT NO. NPOO59-OOO5 DATE: 04/04/96 PERRY NUCLEAR POWER PLANT UNIT 1 PAGE: 88 REVISION: 5 ISI
SUMMARY
REPORT NO. NP0059-0005 l
h FIRST INTERVAL, THIRD PERIOD, FIRST OUTAGE (96RF)
I CLASS 3 COMPLETED COMPONENTS
- EMERGENCY CLOSED COOLING SYSTEM I N 0 ;
I l ASME O C T SEC. XI R E H
[
SUMARY EXAMINATION AREA CATGY EXAM E 0 E NUMBER SIZE SCHEDULE LINE SPEC ITEM NO METHOD NDE REPORTS C M R REMARKS l
....... .............................. ....... .......... ................ . . . ........................................ i
! l (REF. DWG. NO. SS-305-623-110) 07710 2P42-H0026-WA D-B VT 3 1042 95B-0008 X NONE.
I INTEGRAL ATTACHMENT RIGID D2.20 ,
STRUT
! 12" N/A L1 3 (REF. DWG. No. SS-305-623-101) l 077980 2P42-H0039-WA D-B VT 3 1042-959-0017 X NONE.
INTEGRAL ATTACHMENT ANCHOR D2.20 I 10" -N/A -L1 3 l
l I
(REF. DWG. NO. SS-305-623-104) '
078530 2P42-H0148 F-A VT-3 1042-959-0018 X NONE.
(^g RIGID STRUT (WA) F1.3ST y/ 10" -N/A -L1-3 078510 2P42-H0148-WA DB VT-3 1042 958-0019 X NONE.
INTEGRAL ATTACHMENT RIGID D2.20 STRUT 10" N/A -L1 3 (REF. DWG. NO. SS-305-623-103) 078600 2P42-H0153-WA D-B VT 3 1042-958 0013 X NONE.
INTEGRAL ATTACHMENT RIGID D2.20 STRUT 10" -N/A L1 3 (REF. DWG. NO. SS-305-623-104) 078630 2P42-H0265-WA D-B VT-3 1042 958-0016 X NONE.
INTEGEAL ATTACHMENT ANCHOR D2.20 10" -N/A -L1-3 l
2 1
Page 108
l REPURT N3. NP0059-0005 DATE: 04/04/96 PERRY NUCLEAR POWER PLANT UNIT 1 PACE: 89 REVISION: 5 ISI
SUMMARY
REPORT NO. NP0059-0005 FIRST INTERVAL, TNIRD PERIOD, FIRST GUTAGE (96RF)
'N CLASS 1 COMPLETED COMPONENTS REACTOR SYSTEM N O ASME D G T SEC. XI R E H
SUMMARY
EXAMINATION AREA CATGY EXAM E O E ,
NUMBER $1ZE-SCHEDULE-LINE SPEC ITEM NO METH00 NDE REPORTS C M R REMARKS (REF. DWG. NO. SS-305-NO-DWG) 078742 CLASS 1, PIPING B-P VT-2 SEE REMARKS COMPLETED BY APPLICABLE ISI INSTRUCTIONS PIPING-SYSTEM LEAKAGE TEST B15.50 0F OPERATIONS MANUAL OM7B.
N/A N/A -N/A 078746 CLASS 1, PUMPS BP VT-2 SEE REMARKS COMPLETED BY APPLICABLE ISI INSTRUCTIONS PUMPS-SYSTEM LEAKAGE TEST B15.60 0F OPERATIONS MANUAL OM7B.
N/A -N/A -N/A 078752 CLASS 1, VALVES BP VT-2 SEE REMARKS COMPLETED BY APPLICABLE ISI INSTRUCTIONS VALVES-SYSTEM LEAKAGE TEST B15.70 0F OPERATIONS MANUAL OM78.
N/A -N/A -N/A (REF. DWG. NO. SS-305-006-101) y 758 CLASS 1, PR COMPONENTS BP VT 2 SEE REMARKS COMPLETED BY APPLICABLE ISI INSTRUCTIONS REACTOR VESSEL-SYSTEM LEAKAGE B15.10 0F OPERATIONS MANUAL OMTS.
TEST N/A -N/A -N/A Page 109
DJM SYSTEMS ENGINEERING, INC.
ISIC ISI Data Managemtnt System REPORT NO. NP0059-0005 iQ lV i
' ;h k' .
l l
l O THE CLEVELAND ELECTRIC ILLUMINATING CO PERRY NUCLEAR POWER PLANT UNIT 1 l l
l NP0059-0005 ADDENDUM; CYCLE S AND RFOS PSI EXAMS BASELINE / PSI COMPLEfE COMPONENTS FIRST INTERVAL, THIRD PERIOD, FIRST CUTACE (96RF) l i
April 4, 1996 l
Prepared By: Date 9 kl, n.vieww sy: da~ o.t. 4/Je/+
g g 6 r' c o n y,,,o 6 Zo-96 wrova v o.
Alternate for Don Cobb
~O Page 110
I 1
REP 3RT N3. NP0059-0005 1 DATE: 04/04/96 PERRY NUCLEAR POWER PLANT UNIT 1 PAGE: 1 REVISION: 5 l NP0059-0005 ADDENDUM; CYCLE 5 AND RF05 PS! EXAMS h FIRST INTERVAL, THIRD PERIOD, FIRST OUTAGE (96RF)
CLASS 1 BASELINE / PSI COMPLETE COMPONENTS REACTOR SYSTEM N O ASME O G T SEC. XI R E H
SUMMARY
EXAMINATION AREA CATGY EXAM E O E NUMBER $!ZE SCHEDULE-LINE SPEC ITEM NO METHOD NDE REPORTS C M R REMARKS (REF. DWG. NO. SS-305-006-110) 000010 1913-02/23-B B-G-2 VT-1 1042-96A 0141 X CRDM DISASSEMBLED FOR REBU4LD AND ALL CRD FLANGE BOLTING b1.83 VT-1 1042-96A 0160 X NEW CAP SCREWS AND WASHERS WERE N/A N/A -N/A INSTALLED. BOTH THE NEW BOLTING AND THE REMOVED BOLTING (NEW STYLE ONLY, 4EA.)
WERE EXAMINED.
000070 1813-06/19-B B-G-2 VT 1 1042-96A-0141 X CRDM DISASSEMBLED FOR REBUILD AND ALL CRD FLANGE BOLTING B7.80 VT 1 1042-96A-0161 X NEW CAP SCREWS AND WASHERS WERE N/A -N/A -N/A INSTALLED. BOTH THE NEW BOLTlWG AND THE REMOVED BOLTING (NEW STYLE, 4EA.) WERE EXAMINED.
000160 1813 10/15-B B-G 2 VT 1 1042-96A-0141 X CRDM DISASSEMBLED FOR REBUILD AND ALL CRD FLANGE BOLTING B7.80 VT-1 1042-96A-0162 X NEW CAP SCREWS AND WASHERS WERE A N/A -N/A -N/A INSTALLED. BOTH THE NEW BOLTING AND THE REMOVED BOLTING (NEW STYLE, 4EA.) WERE EXAMINED.
000400 1B13 18/11-B B G-2 VT-1 1042-96A-0141 X CRDM DISASSEMBLED FOR REBUILD AND ALL CRD FLANGE BOLTING B7.80 VT-1 1042-96A-0240 X NEW CAP SCREWS AND WASHERS WERE N/A -N/A -N/A INSTALLED. THE NEW BOLTING AND THE REMOVED BOLTING (NEW STYLE ONLY, 4EA.) j WERE EXAMINED.
)
000640 1B13-22/51-B B-G-2 VT-1 1042-96A-0139 X CRDM DISASSEMBLED FOR REBUILD AND ALL CRD FLANGE BOLTING B7.80 VT 1 1042-96A-0143 X NEW CAP SCREWS AND WASHERS WERE N/A -N/A -N/A VT-1 1042-96A-0163 X INSTALLED. BOTH THE NEW BOLTING AND THE i REMOVED BOLTING (NEW STYLE, 4EA.) WERE l EXAMINED. ,
i 000660 1B13-22/59-8 B G-2 VT-1 1042-96A-0141 X CRDM DISASSEMBLED FOR REBUILD AND ALL CRD FLANGE BOLTING B7.80 VT-1 1042-96A-0164 X NEW CAP SCREWS AND WASHERS WERE N/A -N/A -N/A INSTALLED. BOTH THE NEW BOLTING AND THE REMOVED BOLTING (NEW STYLE, 4EA.) WERE EXAMINED.
(
Page 111
REPORT N3. NP0059-0005 l DATE: 04/C4/96 PERRY NUCLEAR POWER PLANT UNIT 1 PAGE: 2
. REVISION: 5 NP0059-0005 ADDENDUM; CYCLE 5 AND RF05 PSI EXAMS I FIRST INTERVAL THIRD PERIOD, FIRST OUTAGE (96RF)
CLASS 1 BASELINE /PS! COMPLETE COMPONENTS j REACTOR SYSTEM i N O l ASME O G T SEC. XI R E H q
SUMMARY
EXAMINATION AREA CATGY EXAM E O E l NUMBER SIZE-SCHEDULE-LINE SPEC ITEM NO METHOD NDE REPORTS C M R REMARKS (REF. DWG. NO. SS-305 006-110) l 000740 1813 26/31-B B-G-2 VT-1 1042-96A 0142 X CRDM DISASSEMBLED FOR REBUILD AND ALL CRD FLANGE BOLTING B7.80 VT-1 1042-96A-0165 X NEW CAP SCREWS AND WASHERS WERE l N/A -N/A -N/A INSTALLED. BOTH THE NEW BOLTING AND THE REMOVED BOLTING (NEW STYLE, 4EA.) WERE EXAMINED.
000760 1813-26/39-B B-G-2 VT-1 1042-96A-0139 X CRDM DISASSEMBLED FOR REBUILO AND ALL l
CRD FLANGE BOLTING B7.80 VT-1 1042 96A-0143 X NEW CAP SCREWS AND WASHERS WERE l N/A -N/A -N/A VT-1 1042-96A-0166 X INSTALLED. BOTH THE NEW BOLTING AND THE REMOVED BOLTING (NEW STYLE, 4EA.) WERE EXAMINED.
i 000810 1813-26/59-B B-G-2 VT-1 1042 96A-0142 X CRDM DISASSEMBLED FOR REBUILD AND ALL CRD FLANGE BOLTING B7.80 VT-1 1042-96A-0167 X NEW CAP SCREWS AND WASHERS WERE N/A -N/A -N/A INSTALLED. BOTH THE NEW BOLT!NG AND THE l t
(~ REMOVED BOLTING (NEW STYLE, 4EA.) WERE i EXAMINED.
000830 1B13 30/07 B B G-2 VT-1 1042-96A-0141 X CRDM DISASSEMBLED FOR KEBUILD AND ALL CRD FLANGE BOLTING B7.80 VT 1 1042-96A-0168 X NEW CAP SCREWS AND WASHERS WERE N/A -N/A -N/A INSTALLED. BOTH THE NEW BOLTING AND THE REMOVED BOLTING (NEW STYLE, 4EA.) WERE EXAMINED.
t 000870 1813-30/23 B B-G-2 VT-1 1042-96A-0142 X CRDM DISASSEMBLED FOR REBUILD AND ALL CRD FLANGE BOLTING B7.80 VT-1 1042-96A-0169 X NEW CAP SCREWS AND WASHERS WERE
! N/A -N/A -M/A INSTALLED. BOTH THE NEW BOLTING AND THE REMOVED BOLTING (NEW STYLE, 4EA.) WERE EXAMINED.
000970 1813-34/03 B B G-2 VT-1 1042-96A-0142 X CRDM DISASSEMBLED FOR REBUILD AND ALL CRD FLANGE BOLT!NG B7.80 VT-1 1042-96A-0170 X NEW CAP SCREWS AND WASHERS WERE N/A -N/A -N/A INSTALLED. BOTH THE NEW BOLTING AND THE REMOVED BOLTING (NEW STYLE, 4EA.) WERE i EXAMINED.
O Page 112 l
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REPORT NO. NP0059-0005 DATE: D4/04/96 PERRY NUCLEAR POWER PLANT UNIT 1 PAGE: 3 REVISION: 5 NP0059 0005 ADDENDUM; CYCLE 5 AND RF05 PSI EXAMS g
FIRST INTERVAL, THIRD PERIOD, FIRST DUTAGE (96RF)
SUMMARY
EXAMINATION AREA CATGY EXAM E O E NUMBER SIZE-SCHEDULE-LINE SPEC ITEM No METHOD NDE REPORTS C M R REMARKS l (REF. DWG. NO. SS-305-006-110) l
, 001190 1B13 38/31 8 B-G-2 VT 1 1042-96A-0139 X CRDM DISASSEMBLED FOR REBUILD AND ALL l
CRD FLANGE BOLTlWG B7.80 VT-1. 1042-96A-0143 X NEW CAP SCREWS AND WASHERS WERE N/A N/A -N/A VT-1 1042-96A-0171 X INSTALLFD. BOTl! THE NEW BOLTING AND THE REMOVED BOLTING (NEW STYLE, 4EA.) WERE EXAMINED.
001270 1813-42/07-B B-C-2 VT-1 1042-96A-0142 X CRDM DISASSEMBLED FOR REBUILD AND ALL CRD FLANGE BOLTING B7.80 VT-1 1042-96A-0172 X NEW CAP SCREWS AND WASHERS WERE N/A -N/A -N/A INSTALLED. BOTH THE NEW BOLTING AND THE REMOVED BOLTING (NEW STYLE, 4EA.) WERE EXAMINED.
001330 1813 42/31-B B-G-2 vi-1 1042-96A-0139 X CRDM DISASSEMBLED FOR REBUILD AND ALL CRD FLANGE BOLTING B7.80 VT-1 1D42-96A-0143 X NEW CAP SCREWS AND WASHERS WERE p'"'s N/A -N/A -N/A VT 1 1042-96A-0173 X INSTALLED. BOTH THE NEW BOLTING AND THE I REMOVED BOLTING (NEW STYLE, 4EA.) WERE EXAMINED.
l 001370 1B13 42/47-B B G-2 VT 1 1042-96A-0139 X CRDM DISASSEMBLED FDR REBUILD AND ALL l CRD FLANGE BOLTING B7.80 VT 1 1D42-96A-0143 X NEW CAP SCREWS AND WASHERS WERE ,
I N/A N/A -N/A VT 1 1042 96A-0174 X INSTALLED. BOTH THE NEW BOLTING AND THE REMOVED BOLTING (NEW STYLE, 4EA.) WERE EXAMINED.
001390 1813-42/55 B B-G-2 VT 1 1042-96A-0139 X CRDM DISASSEMBLED FOR REBUILD AND ALL CRD FLANGE BOLTING B7.80 VT-1 1042-96A-0138 X NEW CAP SCREWS AND WASHERS WERE N/A -N/A -N/A VT 1 1042-96A-0143 X INSTALLED. BOTH THE NEW BOLTING AND THE VT 1 1042-96A-0175 X REMOVED BOLTING (NEW STYLE, 4EA.) WERE EXAMINED.
l l
001400 1813-46/07-B BG2 VT-1 1042-96A 0139 X CRDM DISASSEMBLED FOR REBUILD AND ALL '
CkD FLANGE BOLTING B7.80 VT-1 1D42-96A-0143 X NEW CAP SCREWS AND WASHERS WERE N/A -N/A N/A VT-1 1042-96A-0176 X INSTALLED. BOTH THE NEW BOLTING AND THE REMOVED BOLTING (NEW STYLE, 4EA.) WERE ;
l EXAMINED.
I 1
l t"\
l \~_/l t
Page 113
REPORT NO. NP0059-0005
]
DATE: 04/04/96 PERRY NUCLEAR POWER PLANT UNIT 1 PAGE: 4 REVISION: 5 NP0059 0005 ADDENDUM; CYCLE 5 AND RF05 PS! EXAMS
[ -
FIRST INTERVAL, THIRD PERIOD, FIRST OUTAGE (96RF)
CLASS 1 BASELINE / PSI COMPLETE COMPONENTS REACTOR SYSTEM N O ASME O G T SEC. XI R E H
SUMMARY
EXAMINATION AREA CATGY EXAM E oE NUMBER SIZE SCHEDULE-LINE SPEC ITEM NO METHOD NDE REPORTS C M R REMARKS
....... .............................. ....... .......... ................ . . . ........................................ l (REF. DWG. No. SS-305-006-110) 1 1
001410 1813-46/11-B B-G 2 VT-1 1042- m 0142 X CRDM DISASSEMBLED FOR REBUILD AND ALL CRD FLANGE BOLTING B7.80 VT-1 1042 96A-0177 X NEW CAP SCREWS AND WASHERS WERE N/A -N/A N/A INSTALLED. BOTH THE NEW BOLTING AND THE REMOVED BOLTING (NEW STYLE, 4EA.) WERE EXAMINED.
001460 1B13-46/31-B B 0-2 VT-1 1042-96A-0139 X CRDM DISASSEMBLED FOR REBUILD AND ALL CRD FLANGE BOLTING B7.80 VT 1 1042-96A-0143 X NEW CAP SCREWS AND WASHERS WERE N/A -N/A -N/A VT-1 1042-96A-0178 X INSTALLED. BOTH THE NEW BOLTING AND THE REMOVED BOLTING (NEW STYLE, 4EA.) WERE EXAMINED.
001510 1813-46/51 B B G-2 VT-1 1042 96A-0139 X CRDM DISASSEMBLED FOk REBUILD AND ALL CRD FLANGE BOLTING B7.80 VT-1 1042-96A-0143 X NEW CAP SCREWS AND WASHERS WERE fm N/A -N/A -N/A VT 1 1042-96A-0179 X INSTALLED. BOTH THE NEW BOLTING AND THE i REMOVED BOLTING (NEW STYLE, 4EA.) WERE EXAMINED.
l l
, 001530 1813-50/11-B B-G-2 VT 1 1042-96A-0142 X CRDM DISASSEMBLED FOR REBUILD AND ALL CRD FLANGE BOLTING B7.80 VT-1 1042-96A-0180 X NEW CAP SCREWS AND WASHERS WERE N/A -N/A -N/A INSTALLED. BOTH THE NEW BOLTING AND THE REMOVED BOLTING (NEW STYLE, 4EA.) WERE EXAMINED.
001540 1813-50/15-B B-G-2 VT-1 1042-96A 0142 X CRDM DISASSEMBLED FOR REBUILD AND ALL CRD FLANGE BOLTING B7.80 VT-1 1042-96A-0181 X NEW CAP SCREWS AND WASHERS WERE N/A -N/A -N/A INSTALLED. BOTH THE NEW BOLTING AND THE REMOVED BOLTING (NEW STYLE, 4EA.) WERE )
EXAMINED.
001670 1813 54/27 B B-G-2 VT-1 1042-96A-0139 X CRDM DISASSEMBLED FOR REBUILD AND ALL l
-CRD FLANGE BOLTING B7.80 VT-1 1042-96A-0143 X NEW CAP SCREWS AND WASHERS WERE N/A -N/A -N/A VT-1 1042-96A-0182 X INSTALLED. BOTH THE NEW BOLTING AND THE REMOVED BOLTING (NEW STYLE, 4EA.) WERE EXAMINED.
I (D
U i
l Page 114 l
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l REPORT NO. NP0059-0005 DATE: 04/04/96 PERRY NUCLEAR POWER PLANT UNIT 1 PAGE: $
REVISION: 5 NP0059-0005 ADDENDUM; CYCLE 5 AND RF05 PSI EXAMS O REACTOR SYSTEM FIRST INTERVAL, THIRD PERIOD, FIRST GUTAGE (96RF)
CLASS 1 BASELINE / PSI COMPLETE COMPONENTS N O ASME O G T SEC. XI R E H
SUMMARY
EXAMINATION AREA CATGY EXAM E O E NUMBER SIZE SCHEDULE-LINE SPEC ITEM NO METHOD NDE REPORTS C M R REMARKS (REF. DWG. NO. SS-305-006-110)
) '
001740 1813 58/27-B B-G-2 VT-1 1042-96A-0139 X CRDM DISASSEMBLED FOR REBUILD AND ALL l CRD FLANGE BOLTING B7.80 VT-1 1042-96A 3138 X NEW CAP SCREWS AND WASHERS WERE N/A N/A N/A VT-1 1042-96A-0143 X INSTALLED. BOTH THE NEW BOLTING AND THE
. VT-1 1042-96A-0183 X REMOVED BOLTING (NEW STYLE, 4EA.) WERE
, EXAMINED.
i J
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1 Page 115 2
4 i
REP *RT No. NP0059-0005 DATE: 04/04/96 PERRY NUCLEAR POWER PLANT UNIT 1 PAGE: 6 i REVISION: 5 NP0059-0005 ADDENDUM; CYCLE 5 AND RF05 PSI EXAMS i
h V
FIRST INTERVAL, THIRD PERIOD, FIRST OUTAGE (96RF)
CLASS 3 BASELINE / PSI COMPLETE COMPONENTS MAIN STEAM
- N O ASME D G T SEC. XI R E H I
SUMMARY
EXAMINATION AREA CATGY EXAM E O E a
NUMBER SIZE-SCHEDULE-LINE SPEC ITEM NO METHOD NDE REPORTS C M R REMARKS (REF. DWG. NO. SS-305-605-120) 015920 1821 H0038 F-A VT 3 1042-96A-0113 X PSI EXAM FOLLOWING REPLACEMENT OF I RIGID STRUT F1.3ST SNUBBER WITH A STRUT PER DCP 89-161.
i 12" N/A -G1 3 f (REF. DWG. No. SS-305 605 106) 019080 1821-H0445 F-A VT-3 1042-96A-0148 X PSI EXAM FOLLOWING REPLACEMENT OF HYDRAULIC SNUBBER F1.1SN PHOENIX SNUBBER WITH LIKE $NUBBER PER 2" *N/A -D1-1 PIF 96-683.
O
'1 Page 116
f
< l 1 I REPORT N3. NP0059-0005 l i
DATE: 04/04/96 PERRY NUCLEAR POWER PLANT UNIT 1 PAGE: 7 l REVISION: 5 NP0059-0005 ADDENDUM; CYCLE 5 AND RF05 PSI EXAMS
\
FIRST INTERVAL, THIRD PERIOD, FIRST OUTAGE (96RF)
- CLASS 1 BASELINE / PSI COMPLETE COMPONENTS 1
REACTOR RECIRCULATION SYSTEM N O ASME D G T SEC. XI R E H
SUMMARY
EXAMINATION AREA CATGY EXAM E O E 1 NUM6ER SIZE-SCHEDULE-LINE SPEC ITEM NO METHOD NDE REPORTS C M R REMARKS i
- ....... .............................. ....... .......... ................ . . . ........................................ 1 1
(REF. DWG. NO. SS-305-602-104) 4
- 023380 1833-0072 B B-G 2 VT 1 1042-96A-0238 X EXAMINATION OF REPLACEMENT BOLTING USED BLANK FLANGE DECON CONNECTOR B7.50 VT-1 1042-96A-0239 X UPON REASSEMBLY FOLLOWING USE FOR I
4" -N/A -D2 1 VT 1 1042-96A-0244 X CHEMICAL DECON. FIRST 2 0F 8 STUDS AND 4 j OF 16 NUTS WERE REPLACED, THEN ANOTHER 4 q AND 8 RESPECTIVELY.
1 4
J
'i 1
4 1
- ty s
j i
h 4
I l
Page 117
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REPORT N). NP0059-0005 DATE: 04/04/96 PERRY NUCLEAR POWER PLANT UNIT 1 PAGE: 8 REVISION: 5 NP0059-0005 ADDENDUM; CYCLE 5 AND RF05 PSI EXAMS i ,h FIRST INTERVAL, THIRD PERIOD, FIRST GUTAGE (96RF)
V CLASS 1 BASELINE / PSI COMPLETE COMPONENTS RESIDUAL HEAT REMOVAL SYSTEM N O ASME O G T j SEC. XI R E H l
SUMMARY
EXAMINATION AREA CATGY EXAM E D E NUMBER $12E-SCHEDULE-LINE SPEC ITEM NO METHOD NDE REPORTS C M R REMARKS 4
l (REF. DWG. No. SS-305-642-135) 041330 1E12-H0035 F-A VT 3 1042-96A-0134 X PSI EXAM FOLLOWING FUNCTIONAL TESTING OF MECHANICAL SNUBBER F1.1SN VT-3 1042-96A-0135 X SNUBBER AND REPLACEMENT OF SUPPORT 12" *N/A -D1-1 BOLTING.
(REF. DWG. NO. SS-305-642-111) i 042310 1E12-H0169 FA VT 3 1042-96A-0229 X PSI EXAM FOLLOWING REPLACEMENT OF PSA ,
HYDRAULIC SNUBBER (WA) F1.2SN MECHANICAL SNUBBER WITH A LISEGA I (TANDEM) HYDRAULIC SNUBBER PER DCP 95-5027. l 24" -N/A -G1-2 I 042330 1E12-H0170 F-A VT 3 1042 96A-0230 X PSI EXAM FOLLOWING REPLACEMENT OF PSA HYDRAULIC SNUBBER F1.2SN MECHANICAL $NUBBER WITH A LISEGA 24" *N/A Gi 2 HYDRAULIC SNUBBER PER DCP 95-5027.
O 042340 1E12 H0171 F-A VT 3 1042 96A 0231 X PSI EXAM FOLLOWING REPLACEMENT OF PSA l HYDRAULIC SNUBBER F1.2SN MECHANICAL $NUBBER WITH A LISEGA 1 24" N/A -G1-2 HYDRAULIC SNUBBER PER DCP 95 5027. !
i (REF. DWG. NO. SS-305-641-101) 043210 1E12-H0293 F-A VT 3 1042-96A-0127 X PSI EXAM FOLLOWING REPLACEMENT OF PSA HYDRAULIC SNUBBER (TANDEM) F1.2SN MECHANICAL SNUBBERS WITH LISEGA 24" -N/A -G1 2 HYDRAULIC SNUBBERS PER DCP 95-5026.
(REF. DWG. NO. SS-305-642-101_)
046580 1E12 H0729 F-A VT-3 1042-96A-0136 X PSI EXAM FOLLOWING REPLACEMENT OF LOAD MECHANICAL SNUBBER F1.2SN PIN AND FUNCTIONAL TEST]NG PER NR ;
18" -N/A -Gi 2 95-S 317.
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REPORT NO. NP0059-0005 DiTE: 04/04/96 PERRY NUCLEAR POWER PLANT UNIT 1 PAGE: 9 i REVISION: 5 NP0059-0005 ADDENDUM; CYCLE 5 AND RF05 PSI EXAMS l O LOW PRESSURE CORE SPRAY SYSTEM FIRCT INTERVAL, THIRD PERIOD, FIRST OUTAGE (96RF)
CLASS 2 BASELINE / PSI COMPLETE COMPONENTS l
N O ASME O G T SEC. XI R E H
SUMMARY
EXAMINATION AREA CATGY EXAM E O E NUMBER SIZE-SCHEDULE-LINE SPEC ITEM No METHOD NDE REPORTS C M R REMARKS ;
....... .............................. ....... .......... ................ . . . ........................................ j (REF. DWG. No. SS-305-705-104) 049000 1E21-H0038 F-A VT 3 1042-96A-0124 X PSI EXAM FOLLOWING REPLACEMENT OF PSA HYDRAULIC SNUBBER F1.2SN MECHANICAL SNUBBER WITH A LISEGA 14" *N/A -Gi-2 HYDRAULIC SNUBBER PER DCP 95-5028.
049010 1E21-H0039 F-A VT-3 1042-96A-0125 X PS! EXAM FOLLOWING REPLACEMENT OF PSA l MECHANICAL SNUBBER F1.2SN MECHANICAL SNUBBER WITH A LISEGA l 14" -N/A G1-2 HYDRAULIC SNUBBER PER DCP 95-5028.
l I
(REF. DWG. No. SS-305 705 101) )
049070 1E21-H0050 F-A VT-3 1042-96A-0122 X PSI EXAM FOLLOWING REPLACEMENT OF PSA HYDRAULIC SNUBBER (TANDEM) F1.2SN MECHANICAL $NUBBERS WITH LISEGA 24" N/A -L1-2 HYDRAULIC SNUBBERS PER DCP 95 5028.
b)
( {RfF. DWG. NO. S$-305-705 104) 1 049090 1E21 H0053 F-A VT 3 1042-96A-0123 X PSI CXAM FOLLOWING REPLACEMENT OF PSA '
HYDRAULIC SNUBBER F1.2SN MECHANICAL SNUBBER WITH A LISEGA ;
14" -N/A -G1 2 HYDRAULIC SNUBBER PER DCP 95-5028.
i l
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i REPORT N3. NP0059-0005 DATE: 04/04/96 PERRY NUCLEAR POWER PLANT UNIT 1 PAGE: 10
- REVISION
- 5 NP0059-0005 ADDENDUM; CYCLE 5 AND RF05 PSI EXAMS FIRST INTERVAL, THIRD PERIOD, FIRST GUTAGE (96RF)
^
CLASS 2 BASELINE / PSI COMPLETE COMPON2NTS HIGH PRESSURE CORE SPRAY SYSTEM N 0 ASME O G T ;
4 SEC. XI R E H j
SUMMARY
EXAMINATION AREA CATGY EXAM E oE ;
NUMBER SIZE SCHEDULE LINE SPEC ITEM NO METHOD NDE REPORTS C'M R REMARKS 1
i I (REF. DWG. NO. SS-305-701-103) l 051070 1E22-H0025 F-A VT-3 1042-96A-0150 X PSI EXAM FOLLOWING REVISION OF SETTINGS VARIABLE SPRING F1.2SP PER DCP 92-0071.
16" N/A -L1-2 (REF. DWG. NO. SS-305-701-102) i i
051110 1E22*H0028 FA VT 3 1042-961.-0153 X PSI EXAM FOLLOWING REVISION OF SETTINGS
, VARIABLE SPRING F1.2SP PER DCP 92-0071.
- 24" -N/A -L1 2 f
! l 4
i, t
. i 1
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REPORT N3. NP0059-0005 DATE: 04/04/96 PERRY NUCLEAR POWER PLANT UNIT 1 PAGE: 11 REVISION: 5 NP0059 0005 ADDENDUM; CYCLE 5 AND RFOS PSI EXAMS
[3 FIRST INTERVAL, THIRD PERIOD, FIRST OUTAGE (96RF)
C/ CLASS 1 BASELINE / PSI COMPLETE COMPONENTS REACTOR CORE ISOLATION COOLING SYSTEM N O ASME O G T i SEC. XI R E H
SUMMARY
EXAMINATION AREA CATGY EXAM E O E NUMBER SIZE SCHEDULE-LINE SPEC ITEM NO METHOD NDE REPORTS C M R REMARKS (REF. DW0. NO. SS-305-631-108) ,
055500 1E51-H0074 F-A VT 3 1042-96A-0149 X PSI EXAM FOLLOWING REPLACEMENT OF i HYDRAULIC SNUBBER F1.1SN PHOENIX SNUBBER WITH A LIKE SNUBBER PER I 6" N/A D1 1 PIF 96-0710.
l j (REF. DWG. NO. SS-305-632-101) 055840 1E51-H5002 F-A VT-3 1042 96A 0243 X PSI EXAM FOLLOWING DISASSEMBLY AND RIGID GUIDE F1.1G REASSEMBLY (INCLUDING SOME CUTTING AND 10" -N/A -D1-1 RE-WELD 1h'G) 0F THIS SUPPORT TO FACILITATE 1E51 F0063 kiWORK.
O Page 121
REPORT NO. NP0059-0005 DATE: 04/04/ % PERRY NUCLEAR POWER PLANT UNIT 1 PAGE: 12 REVISION: 5 NP0059-0005 ADDENDUM; CYCLE 5 AND RF05 PS! EXAMS FIRST INTERVAL, THIRD PERIOD, FIRST GUTAGE (96RF)
%/ CLASS 3 BASELINE / PSI COMPLETE COMPONENTS EMERGENCY CLOSED COOLING SYSTEM N O ASME O G T SEC. XI R E H
SUMMARY
EXAMINATION AREA CATGY EXAM E O E NUMBER SIZE-SCHEDULE-LINE SPEC ITEM NO METHOD WDE REPORTS C M R REMARKS (REF. DWG. No. 55-305-621-111) 067642 1P42 M1426 F-A VT 3 1042-96A-0245 X PRESERVICE EXAM OF NEW COMPOWENT SUPPORT RIGID SUPPORT F1.3R INSTALLED PER DCP 94-027.
12" N/A -L1-3 l l
l 067644 1P42 H1427 F-A VT-3 1042-96A-0246 X PRESERVICE EXAM OF NEW COMPONENT SUPPORT RIGID GUIDE F1.3G INSTALLED PER DCP 94-027.
8" -N/A -L1-3 (REF. DWG. NO. SS-305-621-110) 067646 iP42-H1428 F-A VT 3 1042-96A-0247 X PRESERVICE EXAM OF NEW COMPONENT SUPPORT RIGID SUPPORT F1.3R INSTALLED PER DCP 94-027.
12" N/A -L1-3 A l 648 iP42-H1429 F-A VT-3 1042-96A-0248 X PRESERVICE EXAM OF NEW COMPONENT SUPPORT RIGID GUIDE F1.3G INSTALLED PER DCP 94 027.
8" N/A -L1-3 O
Page 122
i REPORT NO. NP0059-0005 DATE: 04/04/96 PERRY NUCLEAR POWER PLANT UNIT 1 PAGE: 13 REVISION: 5 NP0059-0005 ADDENDUM; CYCLE 5 AND RF05 PSI EXAMS I
h V
FIRST INTERVAL, THIRD PERIOD, FIRST GUTAGE (96RF)
CLASS 3 BASELINE / PSI COMPLETE COMPONENTS 1
EMERGENCY SERVICE WATER SYSTEM N 0
- ASME O G T 4
SEC. XI R E H
SUMMARY
EXAMINATION AREA CATGY EXAM E O E
- NUMBER SIZE-SCHEDULE-LINE SPEC ITEM NO METHOD NDE REPORTS C M R REMARKS I
(REF. DWG. NO. SS-305-791-106) l 069800 1P45-H0183 F-A VT-3 1042-96A-0146 X PS! EXAM FOLLOWING REPLACEMENT OF !
MECHANICAL SNUB 8ER (WA) F1.3SN $NUBBER PIPE ATTACHMENT LUGS WITH A REAR l 24" -N/A -L1 3 BRACKET PER PIF 96-0993.
l
)
)
(REF. DWG. NO. SS-305-791-112) l i
070100 1P45 H0212 F-A VT-3 1042-96A-0147 X PSI EXAM FOLLOWING REPLACEMENT OF 1
MECHANICAL SNUBBER (WA) F1.3SN SNUBBER PIPE ATTACHMENT LUGS WITH A REAR l 24" -N/A -L1-3 BRACKET PER PIF 96-0870. !
070230 1P45 H0222 FA VT-3 1042-96A-0155 X PSI EXAM FOLLOWING REPLACEMENT OF MECHANICAL SNUBBER (WA) F1.3SN SNUBBER PIPE ATTACHMENT LUGS WITH A REAR 24" -N/A -L1-3 BRACKET PER PIF 95-0869.
i t a g
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l REPORT NO. NP0059-0005 O
APPENDIX B "NIS-2/NR-1 FORMS" l
l l
l INSERVICE INSPECTION SUNNARY REPORT I
FOR O PERRY NUCLEAR POWER PLANT l
(PNPP) ;
UNIT #1 !
l l
O Page 124
REPORT N3. NP0059-0005 l
l I
l 1B13-010 l NIS-2/NR-109tER'S REPORT POR REPAIRS OR REPLACEMENTS l
As required by the Provisions of the ASME Code Section XI PNPP No. 9308 Rev. 6/93
.. Jvner Cleveland Electric Illuminating Company Date 3/27/06 P.O. Box 5000, Cleveland, Ohio 44108 Sheet 1 of 3 l
- 2. Plant Perry Nuclear Power Plant Unit One 10 Center Road, North Perry, Ohio 44081 W.O. 95-5175 R/0 (Repair Org., P.O. No., etc)
- 3. Work Performed By: Cleveland Electric Illuminating Co. Type Code Symbol Stamp NR 10 Center Rd, North Perry, Ohio 44081 Authorization No. 33 Expiration Date 7/18/96
- 4. Identification of System: 1B13 Reactor & Internals j l
l
- 5. (a) Applicable Construction Code: ASME Section III, NB , 1974 Edition Vinter 1975 Addenda, Code case 1728, 1644-4 7 -272 Alao1 /30/-a. Erst spfg.
1 (b) Applicable Edition of Section II Utilized for Repairs or Replacements: 1983 l Summer 1983 Addenda
\
U 6. Identification of Components Repaired, Hodified, or Replacement Components
! Name of Name of Manufacturer Hat. Other Year Repair ASME Component Manufacturer Serial No. Board ID. Built Replacement Code No. or Modification Stamped Piping General '
1813 System Electric IBI3 64077 D0008 1984 Replacement Yes
- 7. Description of Work: Replaced Control Rod Drive Mechanisms (CRDH) and l" capscrews. See Remarks
- 8. Test Conducted: Hydrostatic- [ j Pneumatic- { ] Nominal Operating Pressure- [X]
l Other- [ ] 175 degrees F j Pressure 1038 psi Test Temperature i
O I
l Page 125 i
1
3 NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS i
Installed a replacement CRDM in core location 26-39 S/N A4450 using
- 9. Remarks:
(A) I"-8x5) 1Ig. capscrews ASME SA 540 Cr. B23 (4) Hti 61811 and (4) Hti 99896.
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 (X)MPLIANCE Ve certify that the statements in this report are correct and that allconforms design, to material and workmanship on this Replacement (repair, replacement, or modification) applicable section of the ASME Code.
33 _ to use the NR tamp expires 7/18/96 Certificatfyof Aut,hfrha$1on J o Quf& tina.,
Signed Aki im 6<1Atud (Ovner or Owner's Designee, fitle)
Date 4(Lt i '2A 19 (&
CERTIFICATE OF INSERVICE INSFECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the State or Province of OHIO and employed by *ARKVRIGHT MUTUAL INS. CO. of NORV00D, MA. have inspected* the repair, modification or replacement
, and state that todescribed the best in this report on /44u;, .:8 , s19 P(.
of my knowledge and belief, this repair,' modification or_ replacement has been made or constructed in accordance with Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. l By signing this certificate, neither the Inspector nor his employer makes any j warranty, expressed or implied, concerning the repair, modification or ;
replacement described in this report. Furthermore, neither the Inspector nor j his employer shall be liable in any manner for any personal injury or property i damage or a lo s of an kind from or connected with this inspection.
Commissions AA MKey 1-~ %n a a. l eW(Inspector's Signature) a
- FACTORY MUTUAL ENG. ASSOC.
Date At%z .:e
- 19 %
O
1 1
REPORT NO. NP0059-0005 t IBl3-010 l '
. Sheet 2 of 3 l ,s Sheet 1 of 2 g ,.. .
FORM N.2 NFT CERTIFICATE Hot.DERS* DATA REPORT FOR NUCLEAR PART AND APPURTENANCES
- As required by the Provison of the ASME Code Rules. Section !!!. Div. !
l l
g, g,3 u ,,,g.,,,,ed by General Electric Company, Castle Hayne Rd., Wilmington, N.C.
us a.e w m c.,nace u.na.c, (b) Manufactured fe, General Electric Company, San Jose, California (NEBG) l us ame wnc eae u.se.,s.r mu.e,
- 2. Identiacation. Certificate Holder's Serial No. of Part A4450 Nu'l Bd. No.
(a) Constructed According to Drawing N= 768E534G001 D. L. Peterson Drawing Prepared by (b) Description of Part laspected NdU/
1361-2 1 (c) Applicable ASM E Code: Section !!!, Edicion , Addesdadace W '75 . Case No.
yga, Standard part for use with Reactor. Hydrostatically tested at 1820 pai.
cm,s., e. rieu ., . w, r., . man o a ... es i
- Total number of sheets - 2 We certify thesche saamasseats made is this : are correct and this vessel part or appartenance as deGaed is the Code coa.
foana ao she sules of construction of une A384E Section 111.
(The appeleable Destsa spectAcaties and Strees Report are not the responsibility of the NFr Certificate Holder far parts. Aa NFF Certit-l icane Heider for appure-- is respaambie for ihraishnes a separase Design Specdicados and Stress Report if the appunemance is not
'-cluded in the component Desten SpectScation and Strees ReportJ i
g Of D 6/ll 19 Ol 3;p,d CE. NEPD-W O 3, i / . h im Q June 16, 1981
<wrr c.,maemee u.se.ri g g ;,,,, ,, ,
NPT N-1151 Cercincue of Anchorisasion Empires CERRRCADON OF DESGN FUR APPURTENANCE (when appilcable) o,,; , i,,,,,,;,, ,, ,;i, ,,
GE, NEPD-WMD-CA, Castle Hayne Rd. Wilminoton. N.C.
22A5556. Rev. 2 Scress analysis report os file as .GE, NEPD, San Jose, Calif.
22A4912, Rev. 2 -
Design specificacions certified by B. N. Sridhar prof Eag.5 si, Calif g,,NoJS345 Stress analysis report certified by B. N. Sridhar p,,,, go,, 3,,, Calif g ,,, 3,,lS 345 CERDRCATE OF SHOP INSPECT 10N 1, the undersigned, holding a valid commission issued by the Nasional Board of Boiler and Pressure Vessel laspectors and/or ebe Scase or Province of North Carolina and employed byDepartment of Labor
,g State of North Carolina beve laspected she part of a pressure vesret described in this bili 19 0.Isad state that to the best of my hiedse l Partial Data Report on and bettet, the NFr Cert 10cate Heider has constructed this part la accordance with the ASMt Code Sectica III.
By sissing this certificace, neither che laspector nor his' employer makes any warreary, expressed or implied, concers.
Ins the part desert bed in this Partial Data Report. Furthermore, neither the inspector not his employer shall be liable in any meaner for may perseast saiury or property damage or a loss of any kind arissag tross or connected with this inspection.
EEC Ull M Due . - - -f 19 g.gg g 4 7 24 n:n v...rs.,.. s.e s C .ss,oas s . . a . s. .. e . e n..
".:*.*C""."ll.:*.*.' /".'C '.'a";.:".*2"*.".2:~.l.*:* :*7."/:::* '~".:.".'.". 'T*.1'T * "~ "' """"'"" " "~ " - ""
'A nnmi m . - w,vm o ., ,,r. ,.,4,,em ,,..c ,n.m m m e om se w. ve,.. N.v. too17 Page 126
j FORM 2 nack) .
leems 4-4 lacl. ee be cosapleted is, seasie wall vessels. .acket s vi nacketed ve ssels. or . hells ed best eschangers, i Nomi..i ce. s. it._ na. L en gth _ It. ...
Alle ace in. Di s
- 4. %elb Wasessel .Thickne.e s_ in.
,_ T.S.c Enne
.p.aatnass .a m s,.eisi s J R.T. _ E ffic;*=cy r. ;
- 1. Seams: Lon g H.T.' !
R.T. No. el Co.r se s Girin H.T.* '
(b) Material T.S.
T.5.
- 6. Heads: ( s) Waerial consees seemaeon.eu.a Ptee s 4. i . p,u j ca e Emmue E staene.a Daem.ew (C.e.. se C e.)
Lama 8 +ea.* A mse Ae.s Amste seates monom. at thaeeeeee Reds.*
(T (a)
(H Other f aseeming If reme.sble, belts used 7.s..saee. s-_
co.unne w ean.....u tas wwa, sees. m
- ...sm.ei.e.e.weie..,..ceae
.. .on..w.W=wsi .. ..
Jacket Closwesto.w .s.. Dvoy Teight Charpy IsApact h-i b
, s; , 575 ep ,,e,,, 7
- 6. Design peessuse _
s 1250 Irees 9 and 10 to be completed for robe secciens Thickness ia. Aasachmens
- 9. Tube Sheets: Samionary. Maseei-' Dia. seese.e. seawei sau.4 a s,.s. x <sen wt to p uw.e Dia. Dickness_ia. Astachsens Flearias. Maserial Type O.D. in. Tliicknes s IYe**.
's Numbee
- 10. Tubes: Meeerial (ser. n in items 11-14 iact to be cosmpleted for inner chambers of incheted vessels. or channels el hees eschamgees.
Nominal Canosion Di n. _ f c._is. Len geh_ is, ia.
T.S. 1%cknees an. Alto asce _ n.
i1. She11: Wmecial .s u.ase s n.twen tunas a sea. no.: tut "
R.T. Efficiency _.
- 42. Seness Long H.T.'
R.T. No, af Cowses Cinds H.T.' T.S.
lg T.S. tM unerial
- 13. Heads (a W acerial w mene.a rim 564e se P, s c, Kavenie aess.e gui,ewu sm c m.. .a a.u A.sie n.es.. si a :c . m c .>
Lesasien thesneu aa t an Top, bestems. etds
'M Chamaet Other f astening if reme.sb6e, bolts
- sed (al (b) (c) p..w w me.en . was Deep veiga . .
4*4 b Charpy leapset _
tp ap ,,,,,,,,,
pse as _
- 14. Dessen pressure' teems wiew to W compieted foe all vessets waeee applacable.
Size Locanon
?. $ siet, V alve Owtet s: Numbee
- 16. Noaales:
- R ed w"**a8 W m enes H ** A*'** ** d Pws... .taaet. *I .n e., 3.a. s, f ase fre. *ueaw.e4 fase sae se 3.siet. semeni 4 ae L ac as soa
- ta spec tion waanoies. No.
Siae L ac asion Openings: H anehele s. N o.
Size L oc ation l Thrv eded. No.
i Lee. Gener Assa.c
<, .- aed ,_ == .e...
- 9. 5.pp+<t s
- Skire .. Lass _
- s. .. s. a. r. .
. 4 s v.e s.
- ., ... .. r_..a.._.e,._.....
I
' O i __-
REPORT NO. NP0059-0005 1B13-010 i
.,,.. Sheet 3 of 3 Sheet 2 of 2 ,/-'/
/"'g
( ,I FORM N-2 NPT CER11FICATE IlOLDERS' DATA REPORT FOR NUCLEAR PART AND APPURTENANCES' As required by the Provision of the ASME Code Rules.Section III. Div. I L (a) Mandaemed by General Electric Coinpany, Castle Rayne Rd. , Wilmington, N.C.
in a.4e w wrr cnune = x en, (b> u m fac w fo, General Electric Company, San Jose, California (NEBG) in e .4e w n c., nee.= w*en en er u A4450 y ,,,3 g g,
- 2. we.uncacco.ceruncate uower's serism or rart 768FM140001 Drawing Prepared by (a) Cansesucced According to Drawing No.
(b) Descripcios of Part taspened Control Rod Drive, Model #7RDB144DG001 N207 (c) Applicable ASM E Codes sectice III. Edision l974 , Addendadme W'75 Ca.e N., 1361-2 Cz a. . - 1
- 1. Cap 166B9274P1 1 (167A2343)
SA182 - F316 Code weld 3/8 thick x 1 1/16 OD P.50YP102 N ; __ ;-
, 1 I 2 I l 6 2. Indicator Pipe 166B9313P1 SA312-TP316 . l 3/4 sch 40-seamless pipe N l \ l 0.113 wall thickness '
1.065 max. dia. Reactor vessel r]
k/
thimble l i
I
- 3. Plug 159A1176P1 I I l
SA182-F304 . _ . .
I L 1/4 thick x 0.812 OD ' l
- 4. Flange 919D610P1 (719E474)
.SA182-F304 Code weld
..B50YP102
)
NN I
i
\
3.37 thick x 3 5/8 OD 'N f neck 1 1/16 thick x 5.0 OD /
/ \
N 2.875 ID :__,
'5. Base 137C5311P1 - -
XM-19 ASitE SA479 3.0 00 x .884 ID -
- 6. Ring Flange 114B5122P2 SA182-F304 Code weld l' thick x 5.0 OD x 1.75 ID P50YP102 MmSW2 hg C0t! TROL ROD DRIVE DWG - 768E534 6 ea.1/2 dia. on 41/8 bolt circle
- 8. Plug 175A7961P1
- 9. W e 137C5934P1 00550 gg_tg 3g479
.30 thick x 2.62 h th r. x 1.307 dia.
,f-m ,A Page 127
.--o_--,,uu-nm w...--u-a.e.-a .m.- -.-- n-=--a -=~-, --.s~a-a- u --. - a s a m n --+ n.mes . ~m s ,+;*.*"a-e~a.,-aser-"-+--ae-.ar-----~.~r. aus ab - - -~ m e as ms n. .- -a-, __a-l 6 j l
l sa a
0 1
l i
1 1
O-I i
l O
REPORT N3. NP0059-0005 IB13-011 ,
l()I NIS-2/NR-1 OVNER'S REPORT POR REPAIRS OR REPIACEMENTS As required by the Provisions of the ASME Code Section XI l
PHP" No. 9308 Rev. 6/93
- 3. Owner: Cleveland Electric Illu:sinating Company Date , 3/27/96 P.O. Box 5000, Cleveland, Ohio 44108 Sheet 1 of 3 i I
- 2. Plant: Perry Nuclear Power Plant Unit one ! :
l l
I 10 Center Road, North Perry, Ohio 44081 W.O. 95-5176 R/0 (Repair Org., P.O. No., etc) I
- 3. Vork Performed By: Cleveland Electric Illuminating Co. Type Code Symbol Stamp NR 10 Center Rd, North Perry, Ohio 44081 Authorization No. 33 Expiration Date 7/18/96
- 4. Identification of System: IB13 Reactor & Internals
- 5. (a) Applicable construction Code: ASME Section III, NB , 1974 Edition Winter 1975 Addenda, code case 1728, 1644-4 7 -272, N E07, a 341-2. WA 5ielp
'b) Applicable Edition of Section II Utilized for Repairs or Replacements: 1983_
Summer 1983 Addenda
( N.,
b
- 6. Identification of Components Repaired, Hodified, or Replacement Components Name of Name of Manufacturer Nat. Other Year Repair ASME Component Manufacturer Serial No. Board ID. Built Replacement Code No. or Hodification Stamped Fiping General '
, 1813 System Electric 1B13 64077 00008 1984 Replacement Yes i
1 l
- 7. Description of Work: Replaced Control Rod Drive Mechanisms (CRDM) and 1" capscrews. See Remarks
- 8. Test Conducted: Hydrostatic- [ ] Pneumatic- [ ] Nominal Operating Pressure- [X]
Other- { } 175 degrees F Pressure 1038 psi Test Temperature
,r
,)
Page 128
j NIS-2/NR-1 OVNER'S REPORT FOR REPAIRS OR REPLACEMENTS
- 9. Remarks: Installed a reolacement CRDM in core location 54-77 S/N A5240 usine (8) capscrews 1"-8x51" I g . ASME SA $40 Gr . B21 (4) Ht# 99896 and (4 ) Ht# 6 f f ' t .
1 NOTE: Attach all applicable Manufacturer's Data Reports. Supplemental sheets such as lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded on the front of this form.
CERTIFICATB OF COMPLIANCE Ve certify that the statements in this report are correct and that allconforms design, to material and workmanship on this Replacement (repair, replacement, or modification) applicable section of the ASME Code.
33 to use the NR stqmp expires 7/18/96 Certifica y of Au,t)opizqtion Jo.
Signed /]mic/-W. /Mmd d:Ma.fi dnW'h
' (Ovner or Owner's Designee,'4'itle)
Date cdB . 19 Q (,
CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the State or Province of OHIO and employed by *ARKVRIGHT MUTUAL INS. CO. of NORV00D, MA. have inspected the repair, modification or replacement described in this report on A geA OS ,s19 91 , and state that to the best of my knowledge and belief, this repair, modification or replacement has been made or constructed in accordance with Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition.
By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the repair, modification or replacement 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 s of any a from or connected with this inspection. 4 Commissions gA 9 % 5 [ em.
?V (Inspector's Signature) 19 c}-
- FACTORY HUTUAL ENG. ASSOC.
Date /hA c?#
9
1 l REPORT NO, NP0059-0005 i l
1813-011- l
'
- i Sheet 2 of 3 Sheet 1 of 2 ;
.~ .
~~ FORM 18 2 Nirf CERTIMCATE HOLDERS
- DATA REPORT FOR NUCLEAR PART AND APPtlRTENANCES* i l ( *
- Is requiared by the Provssoa of the ASME Code Rules.Section III. Div. t l
i
! l 1
- 1. (ap umadactued by General Electric Coinpany, Castle Havna Rd. , Wil
- mington, N.C. i 1
- useam.as.ne w nrr caruseme n ,,
! (g u. % s., General Electric Company, San .Tose, California (NEBG) l anum ausmes, w ac eae.= newnsw _e w., -
A5240 y,,,,,,, i
$ 2. u.a.ia-a- r -naense mader s aserta: No. st ran e o
D. t. r.t r.on i c.> c---eed Acadia s.or im, u 76arssaco01 ,,,,,,,,,,,,,,,,,
._g,,,, control Rod Drive, Model #7EDB144DG001 l g7 .
i M c.U/
8' l co M "- AS8ECodesseedseM.Edidea , Addendadue Case No. * ~ Chas l
4 j 3,,,,,,,,,
Standard part for use irith Rasctor. Bydrostatically tasted at 1820 pai.
- osaw e.2 .4 s .e a - ea
- Total number of sheets - 2 ,
)
I r ..
- i i
T j temaoi c. 6ordfy shesshe sessessees ainde la ele W secdem M.ese cervece sad able .eammi past er appeseeaanse ne deG m fne wa-=essa
.ia.sis.a.e a
Desian d seeem ame -a--an is me esmosamas Demian medemfod se AS4Emiser ter an,anamnac is vs s so . me ori are ama e~so eenes.a.r
- ama serasermininas neoeri.: a weerase ossima spuis. ness and soins sepan it me appene I ~
m_ 4/3 g 83 3;,,, cz, g-uny
- a e-i
.hd .g
!' ce,drs ,e a m a g,,;,,, ***h'e'wfiosa c.,,inase d I^ '- > -- % EFT N-1151
~
i .
! CER*I1FICN!10N OF DESGN R)R APPURTENANCE (when opplicable) t GENERAL ELECTRIC CO.. SAN 00SE, CALIFORMIA l nede ld- <-- ee nte -,
22A5556* Rev. 7. GENERAL ELECTRIC CO.e SAN JOSE, CALIFORNIA
. sarne anyate empen es ate m
- l 22A4912, Rev. 2 -
Daten speelacedene certified by 3. N. Sridhar ' p,g.g s.meCalif me,.ye;L8345 e
smees analysis sepan eenised by 3. N. Sridhar p,g. g.,,3,. ca m' g.,,y.18345 l
CERTIFICATE OF SHOP INSPECTION l
i j 1, she undereissed, holding a entid commisden tested by the Nealosa! Seerd el 541er and Pressare Vesset laspectors
- and/or ske scene er Freelace g North Carolina and emptered byDepart:nent of taber
!
- g State of North Carolina ba*ee laspected she pan d a penom eenset descrbd la shis 1 Partial Data Neoart en 4/30- t6.13and insie that to the ness et air hao.iease and beltet. me Nrf Ceraficate Hoteer has enescructed has panla accordance with me ASME Code Secnea tu.
l By signing this cerdScase, asieber she laspector see his employer sehes any weermany, espressed er *amplied, concera.
- lae the part described Furtheffnete. neither the laspector nor his eenpleref' j shall be liable la any la this Portla! Data Report.--r for any personal imiury er papersy dessage or a tese of eay hand arisia with this Laepeataos.
g 4/3 83
! o= ^ ^ ^
19 - N.C. 723,PA.WOU66, OH10 i
d
]
- [
I..d. , e sien Cam.nissima s ama as sem..r,s... en j *Ul"U**."."**."*."':l'"".".*.":.***".".**"*.'****..O***.'fa.'".*.'*'-T"*'*'- ( O w..
n o,,
tion 7 Tw. va,m csoconoi,n., te een n.o ero,n me o, , o.=t Asus. ses a. e7m si New York. N.Y.10017 1
l l
t l Page 129 1
4
- p .
f *. , .
. ;,. s .
FORM N.2 (bek) esch en gers. ' /
teems 4-8 tact. to be completed fee ainste wall eenseta, jackets of jackeJed eesseta, or shetis of b Nominal Corrosion ja Th la. Allowance _la. Di- f. - in. t.ength fc.
- 4. Sielli Maserial(Kane 4. so.e. :s.T.S.3 pata. 4eeiries; n se s,ickness H.T.' R.T. Efficiency ?.
- 5. Seems: Long 4
H.T.* R.T. No. of Courses
' Ginh T.S. --
- (b) Maaerial T.S. .
- 6. Henda (a) Mascrial Ende to y ees, f Kamase zuwiues Coweal Hemasonecteel Flas Leessae. Cae== <Cese, e, c ea asese Apes A e a, anaam otamusee cte,. == 4.i Twaeamees mem.a nada.e (a) l
. (b)
Other (astening If reseeable botes used coe rine se me.es emewas os.ee ua.s, g 37.s sau. n ,,
- 7. Jacket Closeres(oenense se seee medwees.e .ca. as m., ase. eameeeee . d weise, seserine w emeuas Drop Teight Charpy tapact it.lb s M , ,; ,, 575 ., ,,,,,, 7
- 8. Design peesasse l I
j tress 9 and to so be completed foe tube sections
- 9. Tube Sheets: Sessionasy. M- -d-8 Di - Thicknese_la. Attachsaent (sempest to pree. wet (seeded. Seeses)
(Ehed ab spee. No.)
Flossing. Material Dia. Thickness _ia. Attache ac._
D es*e. Number Type
- 10. Tubes: Material .O.D. in. Thickness a (ser. er to
~
tiene 11-14 imet. no be completed for immer chasabers ei jacketed eessets, or chassels of hens eschangers.
- - - - - - . - - l
. . . _ _ . . . ._ g,,;,,g gg la. A!!awance * . la. Dia._ ft._ta. Leagch ft. sa.
,11. Shetta Material T.S. nickness -
<xand a seu. No.) cute, et a enne speeutee Efficiemey - T.
- 12. Seams: Long H.T.' R.T.
H.T.' R.T. No. of Cwnea Cirth
- T.S.
- 13. Heads (a) Muerial T.S. (b) M amerial seemu,heetant Flas Stee to Prese.
Ca=a namema. , tuwesees Coweea (Come, er Cens.)
natte Apes AAsie fladt e Diameter Lee. sten TMannese. , ,memus- medlee (al Top, honom, ends (b) Chamael (b) (c) other fastraiss _ _
!! remorable. bolsa used (a) soeurs e w eneea emewas Dvop Weishe_
- Charpy impact- - (8-j b
, , F
- 14. Design peessure 8 gi se 'F as semp. og e
leems below to be completed for all eessels where app!(cable.
- 15. Safety Valve Oestets: Number Size Loestion
- 16. Naz=les: neudenemoet Pweee. (lates. 'd ** *"*4 H*****"**
Dem. ee sts, Type Me wtet Thie
- ee o asee.De n> %..w
- 17. laspectica Manhole s. No. Size Loc 3sion Openia sm H andhole s. No. $1== Loc uion
$iae Loc asion Threaded. No-Other - Asisched ,
19 %nnart et Shire Luas _ Less..,, _ ,
O
1 REPORT NO. NP0059-0005
^^~
:-~ . . . . _ . . . . . . .. __
1B13-011 Sheet 3 of 3 >
j Sheet 2 of 2
- " FORM N.: NPT CERTD'ICATE HOLDERS' DATA REPORT FOR NUCLEAR PART AND APPURTEN 1>g l
' '70 h by the Provision of the ASME Code Rules. Sectma III. Div. I General Electric Company, Castle Hayne Rd.. Wilmington, N.C.
4 g, g,3 u.a.,,urd br unnm a n . arr cnese== neem i
1 Genaral Electric Company, San Jose, C=14fornia (NEEG) gg'u,ga 4., onessameame .tne_ - - nesen en -
A5240 y,,.1 ad. No.
2, u--a6 Helder's SerialIdo.of Part _
D. L. Peterson 7dAF91&dS01 Deewiss Prepared by (a) conseracted Acceedies se Daseing k (W Desenyden es Pen tempeesd Control _ Rod Drive. Model #7EDB144DG001 ;
I N207 W'75 C.u Ne, 1361-2 C2 . 1 (c) Appucable AS4ECedenseedenE1.Eduise --1974' . Addendada,.
1
- 1. Cap 16689274P1 (167A2343) Code weld SA182'- F316 N'~
P.50YP102 3/8 thick x 11/16 OD m .
' I
- 2. Indicator Pipe 16689313P1
. 1 SA312-TP316 j N g pg 3/4 sch 40-seamless pipe 0.113 wall thickness
- \
i V 1.065 max. dia.
betor ussel l e I
thimble l i l
- 3. Plug 159A1176FI l :
. SA182-F304
. ,_ , , i L _.
I l
- 1/4 th.ick x 0.812 00 .
g N \
. s.
- 4. Flan '
Code weld 8
.SA18!e -F304 919D610P1 (719E474)-850YP102 g%
3.37 thick x 9 5/8 00 // \
neck 11/16 thick x 5.0 00 *
. 2.875 ID ,
M '
'5. Base 137CS311P1 ~~" "
XH-19 ASNE SA479- -
3.0 00 x .884 10 '
1, -
~ 6. Ring Flange 11485122P2 .
Code weld SA182-F304 1" thick x 5.0 00 x 1.75 ID P50YP102 l
)
,. 7. Ca c 117C4516P2 C0tlTROLh00 DRIVE .;
M - 768E534 6 ea.1/2 dia. on 41/8 bolt' circle
- - - '9.But13hC5934P1
. 8. Plug 175A7961P1 x3_19 gg479 0022- i 1.30 thick x 2.62 dia.
, SA182-F304 i nna n44 v 1 in7 dim Page 130
I REP!RT N3. NP0059-0005 IB13-012 i
(/ I NIS-2/NR-1 OWNER'S REPORT POR REPAIRS OR RRPLACEMENTS As required by the Provisions of the ASME Code Section XI I
l i
PN" No. 9308 Rev. 6/93
. Owner Cleveland Electric Illuminating Company Date 3/77/96 P.O. Box 5000, Cleveland, Ohio 44108 Sheet 1 of 3
- 2. Plant: Perry Nuclear Power Plant Unit One 10 Center Road, North Perry. Ohio 44081 W.O. 95-5177 R/0 (Repair Org., P.O. N<,., etc)
- 3. Vork Performed Dy Cleveland Electric Illuminating Co. Type Code Symbol Stamp NR 10 Center Rd, North Perry, Ohio 44081 Authorization No. 33 Expiration Date 7/18/96
- 4. Identification of Systems 1B13 Reactor & Internals
- 5. (a) Applicable Construction Code: ASME Section III, NB , 1974 Edition Vinter 1975 Addenda, code Case 1728, 1644-4-~W-272 M-zc1,t541-;t W 9e)%
'b) Applicable Edition of Section II Utilized for Repairs or Replacements: 198,3_,
Su - r 1983 Addenda l
- 6. Identification of Components Repaired, Modified, or Replacement Components 4
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 D0008 1984 Replacement Yes System Electric 1813 t
- 7. Description of Vork: Replaced Control Rod Drive Mechanisms (CRDM) and 1" capscrews. See Remarks
- 8. Test Conducted: Hydrostatic- [ ] Pneumatic- [ ] Nominal Operating Pressure- [XI Other- [ ] 175 degrees F Pressure 1038 psi Test Temperature r"
b)
Page 131
j i
NIS-2/NR-1 OVNER'S REPORT FOR REPAIRS OR REPLACEMENTS I
- 9. Remarks: Installed a replacement CRDM in core location (H-il S/N A5580 usinc l
(8) capscrews l"-8x5%" ig. ASME SA 540 Cr B23 (8) Hts 90896.
NOTE: Attach all applicable Manufacturer's Data Reports. Supplemental shrats 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 frcnt of this form.
CERTIFICATE OF COMPLIANCE Ve certify that the statements in this report are correct and that all design, material and workmanship on this Replacement conforms to (repair, replacement, or inodification) applicable section of the ASME Code.
cation 33 to use te NR stamp expires 7/18/96 Certifics3rp of pu 90 u (E4t, GMMcL> Signed A/Ju<l,' , uku
/ (Ovner or Owner's Dehignee, fitle)) ~
Date fluk Z.8, 19 9 (,, CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the State or Provir.ce of OHIO and employed by *ARKVRIGHT MUTUAL INS. CO. of NORV00D, MA. have inspected the repair, modification or replacement described in this report on heh e7A ,s19 9(, _ , and state that to the best of my knowledge and belief, this repair, modification or replacement has been made or constructed in accordance with Section II of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the repair, modification or replacement 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 s of any d from or connected with this inspection. g ,o j mu _ Commissions d 65cy J- cs, ,,, , l l V (Inspector's Signhture)
~
sp 19 ##,
- FACTORY MUTUAL ENG. ASSOC.
Date N ,a _ l 9 l l
REPORT NO. NP0059-0005 1B13-012 .
- N'" Of 2
, . Sheet 2 of 3 i l FORM N.2 NPT CERTIFICATE HOLDERS
- DATA REPORT FOR Ntl CLEAR PART AND APPtlRTENANCES*
As required by the Provision of the ASME Code Rulei. Section lit. Div. I w.%
- 1. (a) Wamulactured by General Electric Cocoany, Castle Hayne Rd. Wilsington N.C.
isnam. ame meewse.t rWT Certae.se se.s.en (bl uamufactured for General Electric Company. San Jose, California OTE3G) in .asaar enenea. nuenen a.a ,e u 0 y ,,,, gg, 3,,
- 2. Idennaeanan-cernficate Holder's Serial No. of Part (a) Constructed Acceeding to Drawiss No. Deswiss Prepared by
} $ Control Rod Drive, & del 47RDB144DGOO1 N Descripeien d Para taspected 4 .UU/ ~ 1974 W'75 *361-2 1 l (c) Applicable ASME Cade: Section !11. E.liria= . Addendadame . Case No. Class Standard part for use with Raactor. Hydrostatically casted at 1520 ps1. 4,
- 3. Raamaskas t-.a.-....a.-.. .
l
- Total ntaber of sheets - 2 ve certify shesthe stes amenta ende is this ano correct and this usset part or app.arresance as densed is the C.ee coe.
fama se she raias of casamection af the ASME Sectice III. (The asedlestae Desasa SpectScauan and Strees Report are not the ressansabtitty of the NPT Certif5 case Hodder for parts. Aa NPT Centf. icane Hender for appurtenneces is ressammeb6e for Aussehens a separass Design t- "- and Strans Raport if the appurtemasse as not tactueet to the cosisement Deense Spec 15cados ame Stress Report.) 4..se 7/23 19 81 S.assed GZ. NEPD-E!D-QA By - - - - uwy cmaa. u.e,a Seetember 15. 1981 M N-1131 Certinesse d Aacherianci Empires c,, tin,ue os e in, 3e. CER'nFICATION OF DESGN FOR WPURTENANCE Men apparable) GZ, NEPD-WG-QA, Castle Hayr.e 3d. Wi1=1sgton, N.C. Design s.a formarios en nie er '
+
22A5556 Rev. 2 Seese analysis report en Ate as G2. NEP%YD-CA. Castle Ravne Rd. ~411misntou. N.C. 22A4912. Rev. 2 Design specincations certwed by 3. N. Sridhar Prol.Eng h eCalif g,,,,M S345 Seese analysis repare certined b, 3. N. Sridhar Ped. Eng. 5e me C'lif Res. No.13343 CER'nFICATE OF SHOP INSPECTION . I. the undersigned, holding a valid commissias lasued ' oy the Nacional Board of Seiler and Pressure Yesset taspectors sad /or the Scare or Premer og North Carolina and employed byDever tent of Labor og State of North Carolina of a peessere nsset described is this Parcal Data Report an havelysyedchep[a i . and state met to the best of sty knowiease and belief. the NPT Ceruncate Hoeder cas construc*.ed this part la accoraance with the ASME Code Seccos III. Sv sagaing this certifiesse, amicher the taspecter mer ais eenployer makes any warreary, espressed or implied, coecern. tes the s trt desert hed ta this Partial Data Report. Furthermore, setther the Inspector nor 'ils employer shai 'se liable in any meaner foe any personal istory or property damage or a less of any hace erasang from or comaceteg
...l isi..,ec :
* ^ " 2' 2'
- I N.C. 723,PA.WCU66, OHIO
. [g'a- eas o,o. s .
~.s. me ,...a..,...... , , ,,, n ,, q
........,.o................n...c...u.....
~ . - . .. .....a-nom > ,,,, ,o, aco.oi , e. wa.a.a ..o c,o c=ot. m.e--8WW en. w w.. v.y ico -
%s d
Page 132
l l FORM N.2 Secu leems 4 4 lact ee be coenplesed fee samale wall ves sels eschess ed n ecketed ve ssels, oe . hells vi liest esd ang.es. f
~. I I
Noonieel Corressem
- 4. Shells Wuerial _
Alle. c e _in. o.- f. ... t.ea gth_ ts. ;,- l i
<snam a se . n.T.S..a c una. .,.Th.o..r.e.a.s_
ms,. e s ia.
- H .T.' R.T. Efficiency %
- 1. Seems: Lee s Cirth H.T.' R.T. No.elCowses i T.S. l
- 6. Hendas (as Waserial T.S. (b) waterial si i. p,.. l c- z u. asiten.. C .a u. ..a .a rim l L.,.u
- a. s. m a i. 4,.s46 som o6 . <e . ., c ., ; l iT .m. e.. Tu. .. .
i. (b) Osher faseeming j If regeevable, bolsa esed co.wne w uan .w..., , casmen.s.s M. T.s sa...se e i I
- 7. jaches Closuresto..en .. .. .....,....u..,s. .. ..., . . .n ...e.,
0 9 we gie Chaspy ide.ct fi-4 b 1250 ,,; , 575 *F as se, es *F
- s. Denisa pees,,e>
teems 9 and 10 se be complaced fee sube sectness Attachemens
- 9. Tube Sheets: $senionary. Masees=3 Dia.
is . se . : c s . . .. ..... Thicknes s _ is. ca.ie.e. se Dia. Thickness sa. Attachmens Flearias. Mas.eial Type
- 10. Tubess Waserial O.D. la. Thickeese IYe'..
s Nwabee tser. se in Isens 11 84 iact. se be cosmpleted fee innwe chambers ed incketed vessels, or chamaets of bens eschangers. Nominal Corrosion is.
- 11. $hett: Waseviel T.S. Th.ckness Ja. Allowance sa. Dia._ f t._ia. Lee sch _ ft.
<snas a se . no.s osa . an. sen.steen R. T. Efficiency ".
- 12. Sesas Less H.T.*
H.T.' R.T. No. of Cowses . Citth de vaserias T.S. t ]. Heads (as WeseriaA T.S. c ..a ne.a rim s6de se P . i c, a sa w. E u u..a as am nees anese n .m.. o s.o.< e sc e.
- C e.s }
Lu.e s Tuesa... n.m n .e. l (a) Togs, bestem, ends i b) Chaamel Otner f asseasag _
!f removstie, bests used (a) *b) (el o.unne w ciwn ..me.,
Drop Teight . Charpy impact (s.46
'F as seme. ed 'F 14 Design pressure' psi as items betow to be comeneted for all .essets *aeve sp,1.cabte, Safet, Val.e Owte< s: Numeev size L x arson l'.
- 16. Ne az.ie s:
Ae..Ww..m.m Puro..e tates. Ts .. w .i .n m M.* aamw8 sis. fe,. wm enm own . or .e M. ci 1 l
** !sspectica M ahoie s. No. 4, se L x se toa Openin g s H aaehele s. N o. Size Lacanoa Th re .eed. No. Site L oc asion ,
Less Waer - 9a as: hed _
'. 9. i.,oces s Shiss v..,..
L es . . . .
. 3.w.wf 2 . m, -' a '4 **
- II e. e. 46 84. d T.W.p.4.
.A b .t .t.. e.
F 4p a.B .y .pg.een - yg.ggy. eg..88.WS W4 6 ie m..$ i 9
REPJRT ND. NP0059-0005 1 1813-012 Sheet 2 of 2 I
. Sheet 3 of 3 ' /% i FORM N.2 NPT CEREF1CATE HOLDERS' DATA REPORT FOR NUCLEAR PART AND APPURTENANCES
- As required by the Provision of the ASME Code Rules, Section til. Div.1 l
. (a) wand.cmed by General Electric Comoany, Castle Rayne Rd. . Wilminstton. N.C. l in e r .enrrc.cose w r General Electric Conpany, San .Tose. California (NE3G) ,
(bi ma.factured to, e meer e n cwesc.w n.4= aw, 2: wwwe - s in A5580 y.e sa, S.
- 2. leeenacauce-Ceruncate Ho& der's Sertal No.af Part
. . e erson 748F9 Mf"001 Drawiss Vrepared by (a) Comeumeted Accordias to Dr==ias W.
(b) Description el Part taspected Control Rod Drive. Model #7RDB144DG001 N207 (c) Appucable ASM E Cade: Section GI. Edition 1974 . Addendadme W'75 , C .e w. 1361-2 Ct.,, 1 l l l Cap 16639274P1 1 1. (167A2343) SA182 - F316 Code weld y N;b;- P50YP102 3/8 thick x 11/16 OD 1 1 l 2 I l
- 2. Indicatcr Pipe 166B9313P1 l 6 SA312-TP316 .
N l ' 3/4 sch 40-seamless pipe O.113 vall thickness l
\ I l
1.065 sax. dia. . Reactor vessel l i I 4
/
- thisible -l , I 1
I l
- 3. Plug 159A1176P1 ; I SA182-F304 ~ ' i
' t ""' '
1/4 thick x 0.812 00
& I N
- 4. Flange 9190610P1 (719E474) Code weld
) !
.SA182-F304 .850YP102
- NN 8 3.37 thick x 9 5/8 OD N /
neck 1 1/16 thick x 5.0 OD , / y 2.875 ID
- 5. Base 137C5311P1 '
N '
/
XM-19 ASME SA479 3.0 00 x .884 ID L
- 6. Ring Flange 11485122P2 SA182-F304 Code weld
. 1" thick x 5.0 00 x 1.75 ID P50YP102
- 7. Cap Screw 117C4516P2 C0f:TRCL ROD ORIVE SA193-86 DWG - 768E53a 6 ea.1/2 dia, on 41/8 bolt circle
- 9. Nut 137C5934P1
- 8. Plug 175A7961P1 IM-19 SA479 SA182 304 1 30 *
- z 2.62 dia.
0.38 thick x 1.307 dia. - 000'G i I O ( Page 133
l REPORT ND. NP0059-0005 IBl3-013 O % NIS-2/NR-1 OWER'S REPORT FOR REPAIRS OR REPLACEMENTS As required by the Provisions of the ASME Code Section XI
)
l l PN" No. 9308 Rev. 6/93
. Owner: Cleveland Electric Illuminating Company Date 3/27/96 P.O. Box 5000, Cleveland, Ohfo 44108 Sheet 1 of 3
- 2. Plents Perry Nuclear Power Plant Unit One 10 Center Road, North Perry, Ohio 44081 W.O. 95-5178 R/0 (Repair Org., P.O. No., etc)
- 3. Vork Performed By: Cleveland Electric Illuminating Co. Type Code Symbol Stamp NR 10 Center Rd, North Perry, Ohio 44081 Authorization No. 33 i Expiration Date 7/18/96
- 4. Identification of Systems 1B13 Reactor & Internals
- 5. (a) Applicable Construction Code: ASME Sect' *>n III, NB , 1974 Edition Vinter 1975 Addenda, Code Case 1728, 1644-4~II-272 Nao? < Se s - 41. DVA-3l2s[4
'b) Applicable Edition of Section XI Utilized for Repairs or Replacements: 19 9 ,
e Summer 1983 Addenda
- 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 Modificatien Stamped Piping General . 1B13 64077 D0008 1984 Replacement Yes System Electric 1B13
- 7. Description of Vork: Replaced Control Rod Drive Mechanisms (CRDM) and 1" capscrevs. See Remarks
- 8. Test Conducted: Hydrostatic- [ ] Pneumatic- [ ] Nominal Operating Pressure- [X]
Other- [ ] 175 degrees F Pressure 1038 psi Test Temperature r v Page 134
NIS-2/NR-1 OVNER'S REPORT FOR REPAIRS OR REPLACEMENTS i
- 9. Remarks: Installed a replacement CRDM in core location 26-31 S/N A2100 using (8) capscrews l"-8x5%" ig. ASME SA 540 Cr. B23 (4) Hti 99896 and (4) Ht# 61811.
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 Ve certify that the statements in this report are correct and that all design, material and workmanship on this Replacement conforms to (repair, replacement, or modification) applicable section of the ASME Code. 33 to use the NR stamp, expires 7/18/96 Certificaty}of Signed Autpp(rjaation RMardr. 1,s la dQu hk Enku.ar)
/ (Ovner or er's Designee, Tijtle) V Date nitL[o 2f 19 CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the State or Province of OBIO and employed by *ARKVRIGHT MUTUAL INS. CO. of NORV00D, MA. have inspected the repair, modification or replacement described
- in this report on A/ue /, 09 ,s19 96 , and state that to the best of my knowledge and belief, this repair, modification or replacement has been made or constructed in accordance with Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the repair, modification or replacement 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 k d from or connected with this inspection. g,, Mh_(Inspector's
= Commissions /Am3 T cc w Signature)
Are 4, .0 6 19 9A
- FACTORY HUTUAL ENG. ASSOC.
Date 9 Y O
REPORT NO. NP0059-0005 IB13-013 Sheet 1 of 2 Sheet 2 of 3 . F0aM N.2 NFT CER*IWICATE HOLDutS' DATA REPORT FOR NUCLEAR PART AND APPURTENANCE 5* As requared by the Provision of the ASME Code Rules. Section !!!. Div.{l fjt/- 44'
.!- ?
L s weemmed by General Electric Company. Castle Hayne Rd., Wilmington, N.C. unemesse ar wierecnes n e= gw u 4w s., . General Electric Company, San Jose. California (NEBG) Uleme ese essess W N Ceresemes neeestsur sensesese maaeser 2 - - eScess Needer's SertalNo. af Past A2100 3,,,g g g g ,. . .
; , %, y 768E534G001 D. L. Peterson -
(u ,_. Control Rod Drive, Model #7EDE144DG001
. - d Passtaspeceed fMU/
W'75 1361-2 1 (et AyrMa AEMECodesSeegina51.Edissee 1974 . Na h yg g% Seavvin d part for use with Reactor. Hydrostae4r =11y caeced at 1820 pai. can.s __ .s m c.e . -.w - _ -
- Total anaher of sheets - 2 l
l Te cerudy shesdie - - made is shie ese eerseet and chie .esent pare er appenmeence as deGaed la se cease een. faame i es rules of - - ei se ASME Seenen15.
===an*=maa Osess e===aa*==*== and seem mesmut arer aos me r==r===*adh of the MPf Cereneses Heider for pests. Am NPF Certif.
Heider sur appureusemens is respea o r =-a* and Screas Repset if the appartmesmos is mes J w==== te ime causamens Dessasireea a.mitte
=en==forans naruishing a sessreae Demos seems nesest.)
12/30 g, 80 CE, 3EPD- WD-QA g,
- c. gg,,,4
_e _.s.m , , - Canitiene ,w w e, June 16, 1981 ,g ,g g NPT N-1151 i I CERURCARON OF DESGN FOR APPURTENANCE (when applicable)
.g,,,Q , ,.;g , GZe NEPD-WD-QA, Castle Hayne Rd., Wilmington, N.C.
22A5556, Rev. 1 Sareas emnersis report am file as GE. NEPD-WD-CA. - Castle Havne Rd. . Vibheton. LC. 22A4912, Rev. 2 oe.s,. :_ -- - congled by B. N. Sem =v- - p,w. Eas.sses. Calif g,,,3.J8345 Saress smalysis repare ceniGed by B. N. Sridhar Ped. Eas. $rese Calif g,,,3 ,13345 l CERTHCATE OF SHOP INSPECTON i
- 1. she undersigned. helating a ve41d comunieeien lemmed by the Nasional Beerd of seiler and Pressure vessel toepeetere l
end/or she scene er Pro,i.ce og North Carolina and employed by Deoart:nent of t. abor i og State of krth Carolina have inspected che pen of a pawsoure veneel described in chia l Pereas omaa neeert am 12/30 is Sand seau that toine best w my m ! aan benet. the NPT CereAcase Heesler aes . _,; ,; lats man la accareance with the ASME Code Seccan III. i By eigmass thse cerealiceae. seisher the taasector not his emelover makes any waaraory, espreseed er implied, concere= [ les the part desertbee is this Perttai Data Report. Furthermore. nettner the inspector nor his emotorer ama&L be linale is any mammer for any persome4 story or properry eenage or a lose of say leane aristn6 from or connected wita dass saepectsen. i a 12/30 ' 80 2 N.C. 687, AWC2711 i
~ /ak $o c-. i l v . s.a
,.e...p.... oc.g e I
i i .- --...--.-.o..........,.-...n....c..r..n.-.-.:.4-...
- ~ . . . - . ._ -
l nami m ,,,,,. - n,,,,. c,,,m:.syaue.:ns. e *.u.. ,,.. u icor I l t Page 135
l l l
. .~
. . . - ~ . . - , . - . . . . - . -
^
F0fBt %2 (bacu leems 4-4 lacl. se be compleeed foe samale all .es set s. iackes s wi iscketed ve ssels, oe ahells of heat eschangees. u i... C - 4
- hells Mas enal _ _T.S.
(E4 e as se .m 3 casi Theckne ss_ ie. Al to.e anc e _ ia. Dia
.a m se s,eeesseep
.i fr ia. Length _ ft. ;.,
')
- 1. Seman.Long H .T.* R.T. Efficiency ?. . . . _ .
Gi,ih H.T.' R.T. No. of Coursea _
- 6. Heada (a) Maserial T.S. (b) Material T.S.
- t ca Eawns. giuene.s cease.4 He.sapheese.& Flas Same se p , .
(T.,.m.s se Twn .e a.ea mesa a m a. A,em Amste mess ca w (c . c (a) (b)
!! renmeeable, botes used Other fastening taimenea, se me T.s..saae,w we goeu,. w i== . en,
. Jacket Closures coewn .. .ee. .eie. w. ne. as n= s .e s. . .. .a e.aees. e .e,.m. .e ....em>
Drop Teight Charpy impace
- 5. Design pressese s 0 ,,; e, SU op ,,,,,,,, (s.l,b tress 9 and to so be completed foe =be sectione
- 9. Tube Sheets: Semiemany. Material Dia. Thickness in. A achmene (zwe as spee. re (s.esas se ore....s (wet ee, a.aees:
Flossin g. Maserial Di a. Thickness _ia. A achenen
- 10. Tebes Maserial O.D. in. Thickness '"sYs'.. Number
- Type (Ser.erUn trees 11-14 iact. to be cosepteted for inner chambers of incketed vessels. or chamaels of hess eschangres.
Noeninal Cerrosion i t. Shetts Maserial T.S. Thackness Ja. A!!awance ia. Dia._ ft. is. Length _ ft. in. ( K&as h seef. N..) thite.ed m ase spessnee)
. 12. Seses: Long H.T.' R. T. Efficiency r.
Girth H.T.' R.T. No. of Coursee
- 13. Heads (al'Maserial T.S. (bs Muerial T.S.
c, Kawas e sineese.a c a. .a He.s.on.nesa Fl.a Shee ts Pee.e. La.ai Thies .. n .e s.. m.de.. a us. Apes Aasse noen.e . Ot etw (ceae. m Cem.) (al Top. betrom, ends (b) Channel If remoesble, belts used f a) (b) (c) Other lassenias sce ne . . t.en em.sens Orop Weight
- Charpy impacs (e.i b 14 Desean pressure' psi as 'F as temp. of 'F leems below to be completed for all .essels where applicable.
- 15. Seleer Yalve Oustees: Number Siae Locassoa
- 16. Neaales:
P.,... #iases, n e.ar ere e.e.e 0*s a. D. as hw Dee. = same ry,e nam ns.a Tneena... w es e es.a M e. Attee*** l i 17 la s pec t ema w annene s. No. 5. a c L oc an on Openin g s: H andhole s. N o. Site Lecanoa i Thee.ded. No. Sese L oc asioa i L S. Supper'e s: Shirt Less i.ess oehee Ars ac hed t sv . = x..._ .m.. . .v ., u. .o. ne. e se nere a ..=*
;,.,..........e...
.....a...e..................
G
l l i REPCRT NO. NP0059-0005 IBl3-013 .
. Sheet 3 of 3 sheet 2 of 2 'Q FORM N-1 NFT CERTIFICATE HOLDE3tS* DATA REPORT FOR NUCLEAR FART AND APPt!RTENANCES*
As required by the Provision of the ASME Code Rules. Secnon 111. Div. I , I
- t. (4 Weesteetweed h General Electric Comoany. Castle Ravne Rd. Wilmington N.C.
.n s ,.w wrc wa n gy w ,a ,,,,4 w General Electric Company. San Jose. California (NEBCf u==. e n m a cnes es.nenen : ,_-
- z. id -naa-a= Mane Hekter's Sestei No.o(Part A2100 y,,.: 34, 3 ,
(e6 Cseenessed Acco dies se Dr ieg No. 76An ucnnt o,ewiss Prepared W D. L. Peterson - f (k r of Pese toepeceed Control Rod Drive. Modal #7RDB14ADG001' i N207
~ (c) Apphenble ASWE Codes senties n!, Edissen 1974 Addende den. W75 Cue we._1361-2 clou 1 I
~ ~
l _
- i. Cap 16639274P1 1 (167A2343)
SA182 - F316 Code weld y 3/8 thick x 11/1600 P.50YP102
, I N _, ,-
i 1 3 m 2. Indicator Pipe 166B9313P1 5A312.TP316 . l 3/4 sch 40-seamless pipe N 0.113 wall thickness
- l
\ I 1.065 max dia. .
Reactor vessel i l . v thimble [ i I
- 3. Plug 159A1176P1 g , l l SA182-F304 i L,- ~
1/4 thick x 0.812 00 l g I
. 4. Flange 9190610P1 (719E474) Code weld S.A182-F304 850YP102
- NN 8 ,
3.37 thick x 9 5/8 OD N h'
/ // K neck 1 1/16 thick x 5.0 OD 2.875 ID
/
\
'5. Base 137C5311P1 1 d
* * * ~
- L'4-19 ASME SA479 4< ~
6 3.0 00 x .884 ID l_. i*-
- 6. Ring Flange 11485122P2 SA182-F304 Code weld a 1" thick x 5.0 00 x 1.75 ID P50YP102
\
. i
- 7. Cap Screw 117C;516P2 I SA193-86 CCf:TRCt. ROD DRIVE '
DE - 768E534 6 ea. 1/2 dia. on 4 1/8 bolt circle
- 8. Plug 175A7961P1
- 9. Itut 137C3924P1
" -" S^' 9 00003 SA182-73C4
** * * * ~ ~' '
0.38 thict x 1.207 dia. . s O Page 136
h REPORT NO. NP0059-0005 m 1B13-014 NIS-2/NR-1 OWNER'S REPORT POR REPAIRS OR REPLACEMENTS As required by the Provisions of the ASME Code Section XI PNPP No. 9308 Rev. 6/93 i
. Owner: Cleveland Electric Illuminating Company Date 3/27/96 P.O. Box 5000, Cleveland, Ohio 44108 Sheet 1 of 3
- 2. Plant Perry Nuclear Power Plant Unit One 10 Center Road, North Perry, Ohio 44081 V.O. 95-5179 R/0 (Repair Org., P.O. No., etc)
- 3. Vork Performed By: Cleveland Electric Illuminating Co. Type Code Symbol Stamp NR 10 Center Rd, North Perry, Ohio 44081 Authorization No. 33 Expiration Date 7/18/96
- 4. Identification of System: IB13 Reactor & Internals 5.'(a) Applicable Construction Code: ASME Section III, NB , 1974 Edition Vinter 1975 Addenda, Code Case 1728, 1644-4 7 -272 .
, N-2td,t%l 2. DM Wl%
M (b) Applicable Edition of Section II Utilized for Repairs or Replacements: 198,3_ Summer 1983 Addenda
- 6. Identification of Components Repaired, Hodified, 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 . 1B13
)
System Electric 1813 64077 D0008 1984 Replacement Yes ; l l a d , 7. Description of Vork: Replaced Control Rod Drive Mechanisms (CRDM) and l" l capscrews. See Remarks J
- 8. Test Conducted flydrostatic- [ ] Pneumatic- [ ] Nominal Operating Pressure- [X]
Other- [ ] Pressure 1038 psi Test Temperature 175 degrees F O Page 137
NIS-2/NR-1 OVNER'S REPORT FOR REPAIRS OR REFIACEMENTS l
)
- 9. Remarks: Installed a replacement CRDH in core location 10-15 S/N A4479 using (8) capscrews 1"-8x5 1/2" Ig. ASME SA 540 Cr. B23 (8) Utt 61811. ,
i l l NOTE: Attach all applicable Manufacturer's Data Reports. Supplemsntal 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 l the front of this form. l CERTIFICATE OF COMPLIANCE Ve certify that the statements in this report are correct and that all design, material and workmanship on this Replacement conforms to (repair, replacement, or modification) applicable section of the ASME Code. Certificat. of A4,thy i ti n N 3 to use the NR stamp expires 7/18/96 l Signed MAM, 62n/gcer } ' Owner o er's Desi'gnee, #fitle) l CERTIFICATE OF INSERVICE INSFECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the State or Province of OHIO and employed by *ARKVRIGHT MUTUAL INS. CO. of NORV00D, MA. have inspected the repair, modification or replacement described l in this report on ne og l . 19 9k. , and state that to the best of my knowledge and belief, this repair, modification or replacement has been made or constructed in accordance with Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor i his employer shall be liable in any manner for any personal injury or property ( damage or ss of any nd from or connected with this inspection. g i /b a _ Commissions g6054 5 _T e,w l V' (Inspector's Signature) i Date phk ,4A 19 et
- FACTORY MUTUAL ENG. ASSOC.
l t O l l
REPORT NO. NP0059-0005 1 B 13-014 Sheet 2 of .' 38*** 1 Cf 2 FORM N 2 NPT CER11FICATE liOLDERS' DATA REPORT FOR .NU1 EAR PART AND APPURTENANCES
- As required by the Proviuon of the ASME Code Rales. Section Ill. Div. I g g g g,,s ,,,,,a w General Electric Company, Castle Rayne Rd., Wilmingten, N.C.
me e m ser c rene.w n.iani gp g ,gg g,, General Electric Company, San Jose, California (NEBC) m e .se n w cma..u ame.r e., : ea., u
- 2. Ideau8casion Cert 1Ac.ase Hekter's Social No. af Part A4479 y,, : ga, g
#N Deewiss Peepared by D. L. hterson (a) Camerameted Accordias ao De ins No.
Control Rod Drive, Model #7EDB144DG001 m Desc% el Pm taw NZU/ 1970 W'75 , c.,3,, N2 cgo, 1 (c) Applicable A5adECades $setianH1.FA=' . Addsadadase Standard part for use with Reactor. Hydrostatically tasted at 1820 psi. L Rwas rwu.e .s =. s . e . o ten.s .
- Total utnaber of sheets - 2 Te coetify chasthe made is chla ene cerveer and this vosset part er appurtenance as densed la de Code coe.
foema se che ruise ed emesssustaen ad the A5 hie 5ecties 111. m ate asencente Desess seeciaeseen and seems neoert are aos the ressoassaalitF of the NM Certtocase Hower for parts. Am NM Certit. scase HaMar for asyurtamaassa is resseenhie for furusseses a separase Deense "; '" tactased la the - C Destsa Specteranos and Stress Resort.) and Saens Raport af the appartemmace as not
, 7/23 g, 81 sg,,,a GZ. NEPD- WD-QA g, , ,
t k m .',
~
Ceninense ed Assheetaania. Espires Scotembe 8 Cartinense ed erizanian % CERT 1 FICA 110N OF DESGN FOR APPURTENANCE Men appliesble) GE. NEPD-WD-4L. Castle Hayne Rd. , W11sington. N.C. De@ 'heam-22A5556, Rev. 2. seress analysis report se file u G2. VEPD-WD-CA. Castle Havne Rd. . Vilminston. N.C. 22A4912. Rev. 2 Desisa specinensiese eartined by 3. N. Sridhar Prol. Eas.ScaseCalif Res.NJS315 s.,e...a.i,sia e,an e,nined 6, 3. N. Sridhar p,.L Eas.sisse Ce ges,3 M M CERTIFICATE OF SHOP INSPECTION
- 1. che undersismed. heidias a valid casamission issued by ee Nerional Seard el Seiler and Pressere Vessel taspectors and/or the 5sase er Provisee d North Carolina and esaptcyed byDeoartment of Labor og State of North Carolina have inspected the part ed a peessure vesset described is chis Parcal Data nesort en 7/23 iSU . and state mas le the W RF Medse and Jelief the NM Cset1Acate Heeder has constructed this part la accareance with the ASME Code Sectice !!!.
. 5, sissies this certinesse, meuhe, che taspector noe his emple.er edes any waarnary, espeessed er impliet esacers.
tas the part desert bed la tais Perttal Data Report. Fe t t-. 9 mert . neither the laspector ser his efapleFer small 'ee liable to say amaser for eey perseest isiery es property e .. er a less of any kind arasses fraes or cannected wica chas inspection. l Due ."e , 7/23 39 81 H.C. 723,pA.wcu66, OH10 C._.... '
< c . sie e.u.a.4 a se .. P a . =e s U, "? 65
":;=~;".::":'.: 2".::1.~=* ~ ~ .::'.:~::.::".::=. "::.::" ' " ""~ '~~ '" ~ ~
eemi n . ecoo.o% c. m.a.: %=,,. c,o- :== r,umC=Ns . s n... o scor r0 V Page 138
F0W N.2 neci) l lsens 4-4 lact, se be completed for siasle wait sessels iaches s el iacketed es set s. or shelle of hese eschassgee s. 1 Co ,es.on l Nom.m. Altom anc e _.a. O, a._ h._ ia. Lengsh _ ft. .a . !
- 4. *Dient s i w es <eveal _ _a T.S. .e m e.h.ckne
.Jscasa sewusees ss_ ia.
Kane a se 3 l H .T.' R.T. Efficiency ". S. se am Leeg H.T.' - R.T. No. of Courses Ginh i T.S. (b) Material T.S.
- 6. Heads: 4 at Masersal C, s.w as. auteue.a C es M maeon ..a Pt ste. . e,.. ., !
g ,me.a on . (c . C .) i ct .a > rwn .. a.m.. a.es a mi. me.. ame se s .44.. t al < 1 (bl ' li reamees6le, boiss seed Othee faseenias iceune. .. n .u.e= os n.a. se... ne T.s s44.. n , Jacke< Closuresto.w,.ei. .. .eu ..+4. . .. is m.e ss es.== .a.. .t a.***e. eewese. w ommens Oreg Teisha chupy id,act h.4 b s 1250 , ,; ,, 575 ep ,,,,,,,,,, e7
- g. Design peessere leems 9 and 10 se be ca.apleted fee sube sections Dia. in. Ass achaeas
- 9. Tebe Sheeses 5 asiosasy. Masevin' a s, . s.a <s ,.e.
uor.,nickness is. e. s Flossia s. Masavial Dia. Thickness _ ia. Astachmeas in. Thickness 1"sYe*e. Nustbee Type to. Tubes: Maserist O.D.
< sw.
- in
. 1 tcess (1 14 iact. se be completed foe imeer chambers ed iacketed vessels, se chamme(s of hees enchassees. Nominal Corrosion la. T.S. Tbickness ia. Allowanc e - .aa. Dia._ fs._la. Len gth _ fs. it. Shetis Waerial numm a se.e. s a ;uin. .s a.ge sonai.e R.T. Efficiency .
- 12. Seses: Lees H.T.'
Cirth H.T.' R.T. No. af Ceases T.S. the uasevisi T.S.
- 15. Hesda (as Waserial sede to P,e.e.
Cs.es Kavesse stisessese Canav.4 Nems.ea.eee.a Ft.: Apes Ans6e meetus 36am.en (C .erC ned Theses.. S ees.. medava mess. I.es se (at Top. hosses, enda b) Chameet tf reme able, boiss used (a) ( b) (c) Other f assenias oewese. w eawn u.<ene Orop Teighs . Charpe laspace f e.( b
'F as<eme. of 'F 14 Design p.e s s.,e' ps. u leems 'Jetos to se campieted ice all vessels enere appiscaste.
5 se L ac aeion ,
- e. S alete v aloe Owt ee s: Number i
- 16. Neazles:
m e.w. rum.as P we.u . Latet , 4.s ees.s M*= aitoeh*4 M.see., Co w s se free um.es.s inseman 3.sn.e. 3r.nas 1* la s peceien Maanose s. No. 'i se Lx snoa
. Loc ation l Openea g s: H amdheie t. N o. Siae L oc ation l Dee ded. No. Sise --
it. Sweport s: Skiri Less i.ess Oener Ge we .se,. s ye a.r
- ses .- e*== m M***
v e. w i ww.. sn e
' 2 e u. .a se. . f . a
'L.i-,.,,.,.......e.
O
REPORT N3. NP0059-0005
~
1B13-014 Sheet 3 of 3 Sheet 2 of 2 j t,;f / ! x,/ FORM N 2 NPT CERT!f1CATE ilOLDERS' DATA REPORT FOR NUCLEAR PART AND APPtlRTENANCES* As required by the Provision of the ASME Code Rules. Section 111. Div. I
- 1. (a) Maavi cewed by General Electric Company, Castle H_ayne Rd., Wilmington, N.C.
u.. .r m c. rune.w w n (b) Manuf actured foc General Electric Company, San Jose, California (NEBC) j sa.aw . e nar .e a cmacaw wee s.,e 4.=e cw., c .u ;
- 2. Identtitcauen-Certificate Holder's Serial No. cd Part A4479 u. t ed. No.
768 m 4C001 Drawing Prepared by . . e enon (a) Constructed According to Drawiss No. (b) Description of Pest taspected Control Rod Drive, Model #7RDB144DG001 N207 (c) Applicable ASM E Code: Sectioa tII. Edicios 1974 . Addeadedme W'75 ; c..e No. 1361-2 C1.s. 1
- 1. Cap 166B9274P1 1 (167A2343)
SA182 - F316 Code weld y 3/8 thick x 1 1/16 00 P50YP102 I N _. ; I I
- 2. Indicator Pipe 166B9313P1 SA312-TP316 . l 3/4 sch 40-seamless pipe 0.113 vall thickness
- l \' g ,
( (')
~J 1.065 max. dia.
Reactor vessel thimble l i 1 l .
- 3. Plug 159All76P1 l :
I l SA182-F304 , I L-1/4 thick x 0.812 00 g
- 4. Flange 9190610P1 (719E474) Code weld
\ ,\\\\ l I
I l
\N X
.SA182-F304 450YP102 '
NN 3.37 thick x 9 5/8 00 N neck 1 1/16 thick x 5.0 00 2.875 ID [/ h' /\
\
q u~. K
- 5. Base 137C5311P1 (6) , ;
7 ' 0 0 .884 ID
- 6. Ring Flange ll485122P2 SA182-F304 Code weld 1" thick x 5.0 00 x 1.75 ID P50YP102
- 7. Cap Screw ll7C4516P2 SA193-B6 C0f!TR01. 800 DRIVE CWG - 768E534 6 ea.1/2 dia. on 41/8 bolt circle
(
~
- 9. Nut 137C5934pl
- 8. Plug 175A7961P1 XM-19 SA479 SA182-F304 0026G 1.30 thick x 2.62 dia.
0.38 thicx x 1.307 dia. t , NJ Page 139
l I REP *RT NO. NP0059-0005 ' j lBl3-015 (V NIS-2/NR-1 OVNER'S REPORT FOR REPAIRS OR REPLACEMENTS As required by the Provisions of the ASME Code Section XI j l PNPD No. 9308 Rev. 6/93 l
. Owners Cleveland Electric Illuminating Company Date 3/27/96 . ,
P.O. Box 5000, Cleveland, Ohio 44108 Sheet 1 of 3
- 2. Plants Perry Nuclear Power Plant Unit One 10 Center Road, North Perry, Ohio 44081 W.O. 95-5180 R/0 (Repair Org., P.O. No., etc)
- 3. Vork Performed By: Cleveland Electric Illuminating Co. Type Code Symbol Stamp NR_
10 Center Rd, North Perry, Ohio 44081 Authorization No. 33 Expiration Date 7/18/96 I
- 4. Identification of Systems IB13 Reactor & Internals l l
- 5. (a) Applicable Construction Code: ASME Section III, NB , 1974 Edition Vinter 1975 Addenda, Code Case 1728, 1644-4~E-272, Nacv] j%l-;L DWA %(xbl%
(b) Applicable Edition of Section XI Utilized for Repairs or Replacements: 1983 Summer 1983 Addenda (3 C l
- 6. Identification of Components Repaired, Hodified, or Replacement Components i
Name of Name of Manufacturer Nat. Other Year Repair ASME Replacement 4 Serial No. Board ID. Built Code Component Manufacturer , No. or Modification Stamped l F1 ping General , IBl3 64077 D0008 1984 Replacement Yes System Electric IB13 I 7. Description of Vork: Replaced Control Rod Drive Mechanisms (CRDM) and I"
- capscrews. See Remarks ,
4
- 8. Test Conducted: Hydrostatic- [ ] Pneumatic- [ ] Nominal Operating Pressure- [X]
Other- l ] 175 degrees F Pressure 1038 psi Test Temperature 4 U Page 140
NIS-2/NR-1 OVNER'S REPORT FOR REPAIRS OR REPLACEMENTS i l
- a
- 9. Remarks: Installed a replacement CRDM i n c or e l oc a t i on 06- 19 S /N t.4 54 5 u s i ng (8) capscrews !"-8x51" 1 Ig. ASME SA 540 Gr . B23 (8) Ht# 99896.
NOTE: Attach all applicable Harufacturer'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 ;tems 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 Ve certify that the statements in this report are correct and that all design, saterial and workmanship on this Replacement conforms to (repair, replacement, or modification) applicable section of the ASME Code. rization No. 33 to use the NR stamp expires 7/18/96 Certificapp of A Signed 1)nad , stAnW OuGL F339meer~ (Ovner or Owner's Designee) Titlb) Date O A 2R 1946, s CERTIFICATE OF INSERVICE IFSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the State or Province of OHIO and employed by *ARKVRIGHT MUTUAL INS. CO. of NORWOOD, MA. have inspected the repair, modification or replacement described in this report on A ct, og ,s19 96 , and state that to the best of my knowledge and belief, this repair, modification or replacement has been made or constructed in accordance with Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any varranty, expressed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property daaage or a of any ki om or connected with this in pection. go Commissions 6 5I,3 7 dw n . (Inspector's Signature) 19 94
- FAcr0RY HUTUAL ENG. ASSOC.
Date h ei 48 O
REPORT NO. NP0059-0005 1B13-015 Sheet 1 of 2 A Sheet 2 of 3 (*) FORM N-2 NPT CERTIFICATE HOLDERS
- DATA REPORT FOR NUCLEAR PART AND APPt'RTENANCES*
As required by the Provisson of the ASME Code Rules. Section !!!. Div. I
- 1. (al Weaulacrured by General Elec t-te Company, Castle Slayne Rd. , Wilnington. N.C.
<name a e . ear w wr cemne u.ien General Electric Cocrpany, San Jose, California (NE3G)
(M Ma faccuned t- <a ame amer < m cneae.ae Hwee en _ :o,o A4545 y,,y g 3.,
- 2. ideoancanon cuancese Holder's Sertal No. of Part Deswing Prepwed by
. . e erson (a) C armeted Accordias no Dr==iss No.
Control Rod Drive, Model #73DB144DCOO1 m Dew des e a Peri tased NZU/ l974 W'75 N2 Class (c) AppHembie ASME Code: Seedo= E1. Edidos . h adme , e,,,3,, g ,, Standard part for use with Raactor. Hydrostatically tested at 1820 psi, ean s a. rwu 4 m.. c . . . e . ...e e .
- Total number of sheets - 2 Te cerdfy chasihe stasemesas made is &ls are correct and dis vessel part se apperassance as defined la se Co se coe.
fosma es che miss ad conseractiam of de ASME Section 111. tThe soonesale Destsn spectacados and Saem P.roort are not the rescenathtlity of the NM Cert 15cate Holder for parts. An NPT Certif. icars Hoeder for appartenances is r aa=.dia fer forussanes a separate Design 3---a- and Scress Report t the a _m is not tactuded to the componens Desten SpectScanoe and Strias Report.)
, 7/23 g 81 3; a CE. NEPD-EfD-QA p C/
im c.r a am.er (,,) ,v C.,drie a An4.tw E ,i,e. September 15. 1981 Certificane ad or.. w N
- 3~1131 CER'I1RCNIl0N OF DESGN FOR APPURTENANCE Men applicable)
GZ, NEPD-EfD-QA, Castia Eayne Rd. . *41 Sington, N.C. Desism infonnenee om fue - 22A3556 Rev. 3 Seesa mmakysis repari am ene n G2. NZFD-WD-CA. Castle Ravne Rd.. Wilminston N.C. 22A4912. Rev. 2 Desisa specificadosa cardlied by 3. N. Seidhar p,4,g g.s...Cali" g,g,3.,18345
$avne analysis report eerdlied by 3* 3* Ifidhaf Prof. Eas. Ss ate C#l Res.No 183 5 CERTIRCATE OF SiOP INSPECTION .
1, che endersigned, holding a eslid commaission issued by the Nacional Board el Boiler and Presmare Vessel '.aspectors and/or the State or Provisee y North Carolina and employed by Deoartment of Labor g State of North Carolina have in ved the past of a peessure vessel described la dis Partial Data Aeoorr on 3 ip,,1. and state that to the nest ct my knowledse ane benef. t24 MM Cer".tacate Hoeder nas constructed tMs part ta accorcance wtta the ASMt Code Section lu.
- Sy signing this certificase, meinher che taapector oor Iris essployer makes any warreary. espressed or iseptiet. concerw.
tas the p a rt desc ribed ta this Partial Da ta Report. Fu rth e rtitore , metther the inspector nor his est foyer shall be liable in say masser for any personal istory er properry damage or a loss et any lune artsang troe or connected
.im . s ... ,e.ooa.
"* ^ 7/23 ' 81 7 N.C. 723,PA.WCl?66, Om0 l
Y$A 6 c .. sic Co.uns ssace s
*=i a si..p . w,)gJN s-.,....w2......
.,..._..n....m.w.n...,......~..
aomi % e,, icoo un ,,, o, ,oo, v.,me,. c,o., :=ct_ .membe,y s,. %m. u scot-U Page 141
FORM N.2 (becU 1 em. 4-a taci. is be c ,6. a fee .iasie .att na set s, iuness # ackeied ussein, on .hetis 4 bem eschmasw ._ N i..s C sien
- 4. htt M u ni.4 _ in. Alte.aace _ ia. o.- fi._ ia. Leasth ft. ;.-
tai . se .n.TA . osi 4 a eens,.c.tri.
. ae .s i S. Seems: Lees H .T.' LT. Elficiency P.
Ginch - H.T.' R.T. No. of Cowses .
- 6. Heads: t al Meserial T1 (b) Material T1 l Lu ca Km u. suse. sees c a..a se..s.,a. .a rt s see. . p,.. l (T . n . Tha. u a.es n.es a.64. A,.s a.es. a.es ca ., (c . c ,3
( al (b) If reme.able, belts used Othev fassemies go.u,ia. ., . a .a. tis we.a.se no T.s sue.n.mawe
*. Jacket Closusett o...n .. .s u ...e. ... .. u n., s. 4 .s a e.e. 4. na. u .as Dr*f 'eisht Charpy idpect is.4b Psi as N *F u semp. of *F
- 8. Desisa Pressue*'
leesse 9 and to ao be compiesed foe sube sections
- 9. Tube Sheets: Semisessy. Maserial Dia. Thickaess ia. Aztecheness asnee a seee. n > <s , se sneuwen tv.se.e. sei Flossias. Meserial Dia. Thickness _la. Arths O.D. in. Thickness 5:Yle. Numibee Type to. Tubees Mesevial (Ser. .e v3 Isees 11-14 iact. to be e.mpleted fee inner chambers e4 jacketed eesseta, er chamaels of bees essbangees.
Nominat Corrosion T1 Thickness J. A!!oesace aa. Dia._ is._Is. Lesadi_fa. la.
- 11. Shett Muevial au.sase .n : ; usa. .a am. sen. stem H.T.' R.T. Efficiency ".
- 12. Seamu Laas Cisth H.T.' R.T. No. of Cowsee T1 sh Muerial T.S.
t 5. Heads (as Wavetial rtas ssme te pv.a. c, x use su eu ca .a M.-..eaw...a (c . , c . L .si Tiu m... n a sa am . as. 4.sie m.ea.. os , (as Top henoa. ends
- bi Chamaet if eemo.sble, belts used (a) ( b) (c) Other lancesin g
.0..er . seena s .e Drop Teighe .
Charpy Impace selb op ,,,,,,,,g op 14 Des gn pressese s ,,; y Isents 'Jetow to se come.eted for all ussels *aeve applicable. M. Safety vain Owtes s: Number $ise Lac acion
- 16. Nessies:
n...e .,u as p .. . . .i.e. M** a"" a** w s s. um .a in na... w m.**.s owi 3, .. un, o. T ,,. 1 i l 1 la spec tion M ana. e s. N.. 4e a e L ee moa Opea 6a g s: H aaehe .e s, N., 5. s e Lae nessa Thee av ed. No. fise - L oc at.oa te. 5.operist Shirt L.se Less Ocnes t -u- a.c 'ned _ . . a n.-.
.. .. % .. . :. .c . ..
*: e. .. .r .
*:-..,,......... l 9
REPORT NO. NP0059-0005 j
~
IBl3-015 - p - - Sheet 3 of 3 Sheet 2 of 2 , d ', g / / () - FORM N-2 NPT CERTIFICATE HOLDERS
- DATA REPORT FOR NUCLEAR PART AND APPURTENANCES
- As required by the Provision of the ASME Code Rules. Section lit. Div. I l
g, g,3 3 ,,r.,,,,ed by General Electric Company, Castle Hayne Rd., Wilmington, N.C. in a eren wartcnua< uii4.n (b) Manuf.ciused to, General Electric Company, San Jose, California (NEBG) ui. e eer e a casac.w umen sw . : <wn e u
- 2. Idenunesuco-Ceruncate Holder s Sertai No. ot Part A4545 g ,e 34, g , j
. . eterson (a) Coeuructed Acceedias to De==ims No. 768 m 4Co01 Drawiss Prepared by (b) Descripsion of Part taspected Control Rod Drive. Model #7RDB1440G001 N207 (c) Applicable ASM E Code: Seedoe 111. Edicion 1974 . Addendadase W'75 . Case No. 1361-2 Class 1 I
- 1. Cap 166B9274P1 1 (167A2343) l SA182 - F316 .
Code held y 3/8 thick x 11/1600 P50YP102
, N _.p )
2 l l m 2. Indicator Pipe 166B9313P1 SA312-TP316 . l 3/4 sch 40-seamless pipe N g y 0.113 Wall thickness
- l
\
p 1.065 max. dia. Reactor vessel . [ thimble l I
- 3. Plug 159A1176P1 I l l
SA182-F304 _ , i L __. _. 1/4 thick x 0.812 00 l l
- 4. Flange 91SD610P1 (719E474) Code weld ' N I
.5A182-F304 ~B50YP102 '
NN 8 4 3.37 thick x 9 5/8 00 '\ neck 1 1/16 thick x 5.0 OD [/
/
g
\
. 2.875 10 _,
N
- 5. Base 137C5311P1 XM-19 ASME SA479 3.0 00 x .884 ID b l s ,%
9
- 6. Ring Flange 11485122P2 SA182-F304 Code weld
, l' thick x 5.0 00 x 1.75 ID P50YP102
# 6P2 skg3,[ C0t! TROL R00 DRIVE DWG - 768E534 6 ea.1/2 dia on 41/8 bolt circle i
- 9. ht 137C5934P1 JU@Uc
- 8. Plug 175A7961P1 19 8*' 9 SA182-F304 . O M x 2. 0 dia.
0.38 thick x 1.307 dia. . A b Page 142
REPORT N3. NP0059-0005 o 1B13-016 (} k_/ NIS-2/NR-1 OVNER'S REPORT FOR REPAIRS OR REPLACEMENTS As required by the Provisions of the ASME Code Section XI ' PNPP No. 9308 Rev. 6/93 l
- 1. Owners Cleveland Electric Illuminating Company Date 3/27/96 ,
P.O. Box 5000, Cleveland, Ohio 44108 Sheet 1 of 3
- 2. Plant: Perry Nuclear Power Plant Unit One l i
10 Center Road, North Perry, Ohio 44081 W.O. 95-518I R/0 (Repair Org., P.O. No., etc) i 3. Work Performed By: Cleveland Electric Illuminating Co. Type Code Symbol Stamp NR 10 Center Rd, North Perry, Ohio 44081 Authorization No. 33 i Expiration Date 7/18/96
- 4. Identification of Systems 1B13 Reactor & Internals
- 5. (a) Applicable construction Code: ASME Section III, NB , 1974_, Edition Vinter 1975 Addenda, Code case 1728, 1644 4, N-272 N-2ri, 8 % g - 2 Do spst%
^
'b) Applicable Edition of Section II Utilized for Repairs or Replacements: 1983_ 3 l
Summer 1983 Addenda ("
' 6. Identification of Components Repaired, Hodified, or Replacement Components Name of Name of Manufacturer Nat. Other Year Repair ASME Serial No. Board ID. Built Replacement Code Component Manufacturer
' No. or Modification Stamped Piping General '
, 1813 . ' System Electric 1B13 64077 D0008 1984 Replacement Yes
- 7. Description of Vork: Replaced Control Rod Drive Mechanisas (CRDM) and 1" capscrews. See Remarks
- 8. Test Conducted: Bydrostatic- ( ] Pneumatic- [ ] Nominal Operating Pressure- [X]
Other- ( ] 175 degrees F Pressure 1038 psi Test Temperature
+
(S
%Y Page 143
NIS-2/NR-1 OVNER'S REPORT FOR REPAIRS OR REPLACEMEfffS O i
- 9. Remarks: Installed a renlacement CRDM in core location 46-31 S/N A3946 usine (8) capscrews I"-8x5%" Ig. ASME SA 540 Cr. B23 (8) He # 99R96 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 Ve certify that the statements in this report are correct and that all design, material and workmanship on this Replacement conforms to (repair, replacement, or modification) g applicable section of the ASME Code. 33 to use the NR stamp expires 7/18/96 Certifica$e of Aut o iration No. 1 Signed N<rtrid / n/af Busfeln &OsMr~ (Ovner or Owner's Designde, Title) Date 14AIA. 2.i 19 % CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the State or Province of OHIO and employed by *ARKVRIGHT MUTUAL INS. CO. of , NORV00D, MA. have inspected the repair, modification or replacement described ; in this report on /w e s, # , s19 9c. , and state that to the best of my knowledge and belief, this repair, modification or replacement has been made or constructed in accordance with Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the repair, modification or j replacement 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 1 ss of any kind from or connected with this inspection. Y'[,, Commissions ,o6 65c y T M ~# - O (Inspector's Sigiiature) Date hc2 d!A 19 9(.,
- FACTORY MUTUAL ENG. ASSOC.
l O
REPORT NO. NP0059-0005 _ _ . . . _ . . _ . . . . . _ _ a m .m. i . . _ _4 . . _ . _ _ . . . ... . -. - - , c lBj3..G.lfrxeA "- = Sheet 2 of 3 Sheet 1 of 2 FORM N.2 NI'T CERUFICATE hot.DERS' DATA REPORT FOR NUCLEAR PART AND APPURTENANCES
- As required by the Provision of the ASME Code Rules. Section !!!, Div. l .
(c, ^; !' g, g ,3 u g .,,,, d by General Electric Company, Castle Hayne Rd., Wilmington, N.C. u.a., ans ase, e avr consem. s. (b) Maedactured to, General Electric Company, San Jose, California (NEBG) imame nas amer.m a a c.,ameme mean en e a.a o
- 2. Idennacessas.Certtacate Holder's Serial No. of Part A3946 y,,.i 34, go, _
* * * *#'UD
. (a) Cosmasesed Accordias to Drawins No. Drawing Prep. red by
. Control Rod Drive, Model #7RDB144DC001 (b) Desca.pues of Part laspected N4U/
.(c) Applicable ASMECode:Section!!!. Edition . Addeadadase . Case No. Class 3, gg,, Standard part for use with Reactor. Hydrostatically tested at 1820 psi.
canw e. su .< . .aa.a . . 4.me e
- Total number of shaats - 2 Wgly shasshe scesaments made la shis are correes and shie vessel part or apparermance as deGaed la che Code cos6 foes she rates of conseraction of she ASME Section III.
can cau. hie ossess spectacanes and seresa neport are aos uw ressoassbitter or tee Nrr Certincase Hoeder for parts. An NFF Ceruf-lass "ider for appertamasces is r c. --ais. tar tweishees a aparue Desisa specdicasion and scnas aspen it she spywiennece is aos nach in the composess oesise spectacauan and sensa nepers. n_ 8/26/ 19 1 sip ed GE' ED""D' on r cnemene umen.
- s. -
.b ^
September 15,.7981 ~l l ceniticue of Ansberiution Expitea Certificase of ortzules No. CER'11 FICA'Il0N OF DESIGN R)R APPURTENANCE (when applicable) p.,1, g.go,,,,g rit, ., GE, NEPD-WMD-0A, Castle Havne Rd. . Wilminaton. N.C. 22A5556, Kev. 2 screu amatyst repen on file a GE, NEPD, San Jose, Calif. 22A4912, Rev. 2 ' Desise specificacions cenified by B. N. Sridhar Prol. Eas. staseCalif g.,,gJ8345 Scress easiysis report cenified by B. N. Sridhar p,,g, g ,,5,,, Calif 33,,, go,18 345 CERTIFICATE OF SHOP INSPEC'T10N
- 1. the madersigsed, holding a valid commissian Isened by rhe Nacional Board of Boiler and Presswe Vessel Inspectors and/or the Sense or Province of North Carolina and employed byDepartment of Labor og State of North Carolina have inspected the part of a pressere vessel described la this Parnai cata neport .a 8/26/ is 83. and state laat so the best or my knowtedse 8"* bettet,the MPT Certincate Holder has constructed this part la accirdance with the ASME Code Section III.
r signing this certificaae. seither the laspector not his employer makes say warraary. espressed or implied. concers. t the part described la this Partial Da ta P.eport. Further:nore netther the Inspector not his employer sh*Il be liable ia any manner foe any personal injury or property damage or e loss of any kind arising from or connected
- chas saspectaca.
Date A 2/M/ 19 M OM83 g y 1 .pl Co.wais sion s N.C. 723,PA.WC1766, OHIO m..- . s .' . . _ . . . _ . . , _ . . . _ . . o = = = = = = = . - = = = = = = U Page 144
a.=........ .
. N FO!BI,N.2 (bacu .
laems 4.-8 lact. so be completed for single wall *essela, ischess of incke. sed vessels, or shells of hees enchangers. Nominal Corrosion
- 4. sheit: Maserial Thi A!! =ance _in. Di- f- in. Length _ ft. ;..
(x1 4 4 spee. n.T.S.(Wi .( Re.se sp.ck ne s s_ ia.
.) s tried) $. Seema: Long H.T.' R.T. Efficiency %
Girth H.T.' R.T. No. of Courses
- 6. Heads: (al Maserial T.S. (b) Material T.S.
t.ami c, x u. Entiene c u.a H a nute.: ri. s44. s. Pe..s.
<T . m.n d. Twen.eu a.m p.eu. a.u. A,.. Aasi. m.44 os u (c . . c 3 (a)
(b) If resmovable, botes used Other fascesing (na enes, s,. ne,,, T.s-, sas., nummer) (o.unne w mi menoien
- 7. Jacket Closures(o un6. u .sn 4. 64, m ,, eie. u n , s eu .. , is n.aus. e.unn. ., .. wni Drop Weight Chupy impace fe,.lh
- 8. Design presse,e n 1250 ps; , 575 og p (ness 9 and 10 to be completed for sube sections
- 9. Tube $beesst Semionary. Macerial Dia. Thickne s s _ in. Assachment (sued a see.. n (s.es c. pr...w.) (u.i4.m. m.ae.e3 Flouisg. Muerial Dia. Tbickness _in. Attachment g
- 10. Tubes: Material O.D. la. Thickness ***T.
s Numbes Type (ser. .e tr> Iness 11-54 iact. so be completed for inner chambers of jackesed vessels, or channels of beas eschangers.
~~~ - ~ ' ' '
Nnal CarrosW .
- 11. Sheit Matesial T.S. Thickness _ im. Allowsace _ . _1.. Dia._ fe._ia. Length ft. is. '
<xand a sea. M..) (nue. .a m ense se..tnes
- 12. Seems: Lang H. T.' R.T. Efficiency %
Girth H.T.' R.T. No. of Courses
- 13. Heads (at Waterial T.S. (b) Macerial T.S.
ce.w. Km.*W e EU6 pen. 4 C. nae 8 H.es.ph.ete 4 rles snee s. Prese. menu n.aw a.u. Ae.s Anste mean on tw (c . ., c s.) L .si Tsuk en (a) Top, bottom, ends (b) Chammet if removable, bones used (a) (b) (c) Ocher f astening coe unne . .n un usen Drop Weight , Charpy impact (e !b op op 14 Design pressure s p,; ,, ,,,,,,,g items below to be completed for all vessets where applicable.
- 15. Safety Valve Omlets: Number Size Loc ation
- 16. Peerzies: -
Pwp.. rinut. Renaderu me.t umen.a Tasenaeu umen. He. Aas.ehed o sta. 0,.., n =* D6 = sin T r,. t* Inspection Manhole s, No. Size L oc ation 1 Loc asion l Openin gs: H andhole s. N o. Size. . j Thre aded, No. Size Loc. tion
- 18. S.pport s: Skirt Lugs Less Other Art ac hed i c.her* 6 How)
Y e. .e M : < M. .e e, cn s.c3 co. u ne p l O
- REPORT NO. NP0059-OOO5
~> 1B13-016 ,
Sheet 3 of 3 Sheet 2 of 2 FOltM N.2 NPT CERTIFICATE HOLDERS' DATA REPORT FOR NUCLEAR PART AND APPURTENANCES
- f , e ' .' I q As requared by the Provision of the ASME Code Rules. Section !!!. Div. t
- t. (e) MandecM by General Electric Company. Castle Havne Rd., Wilmington, N.C.
(b)Meadec w w General Electric Company, San Jose. California (NEBG) , Useems ese address af M carnecess He6eet for emeteet eemoemeep
- 2. AdemeScaean Cerescate Helder's Sorte! No. of Part A3945 W184. Na j (a) Constructed Acceedans se Drevias No. 78 M MC001 Drawing Prepared by D. L. Peterson I
(W Descried.e d Pens tampecesa control Rod Drive, Hodel #7RDB'144DC001 N207 (c) Applicable ASW E Cade: Secuee tti. Edition 1974~ Addende he W'75 CaseN 1361-2 Cleae 1
- 1. Cap 16689274P1 1 1 (167A2343) l SA182 - F316 Code weld y 3/8 thick x 1 1/16 00 P.50YP102
, I N _-
l l 2 l - 6 & Indicator Pipe 166E9313P1 l SA312-TP316 . l 3/4 sch 40-seamless pipe N 0.113 wall thickness
- l
\ I
- V p 1.065 max. dia.
heterMssell e i I thimble l 1
- 3. Plug 159A1176P1 l l l
SA182-F304 I L. 7 l 1/4 thick x 0.812 00 l g I
. 4. Flange 9190610P1(719E474)
.SA182-F304 Code weld ) i 8
- .850YP102 '
NN 3.37 thick x 9 5/8 00 ' N / I neck 1 1/16 thick x 5.0 00
- 2.875 ID /
/ \
4 i _. ,
\
'S. Ba u 137C5311P1 -
i *' XH-19 ASME SA479 - , 3.0 OD x .884 ID - l 1
- 6. Ring Flan 9e 11485122P2 5'I'
- SA182-F304 Code weld
- 1" thick x 5.0 00 x 1.75 ID P50YP102 I i. Cap Screw 117C4516P2 SA193-B6 CONTROL ROD DRIVE DWG - 768E534 j 6 ea.1/2 dia. on 41/8 bolt circle
- 8. Plug 175A7961P1
. Nut 137C393/.P1 ; SA182-F304 0.38 thick x 1.307 dia. .
[ic x 2.62 dia. O
!V Page 145
REPORT NO. NP0059-0005 IBl3-017 (
! 'l NIS-2/NR-1 OVNER'S REPORT POR REPAIRS OR REPLACEMENTS As required by the Provisions of the ASME Code Section XI PHPP No. 9308 Rev. 6/93
- 1. Owners Cleveland Electric Illuminating Company Date 3/27/96 P.O. Box 5000, Cleveland, Ohio 44108 Sheet 1 of 3
- 2. Plant: Perry Nuclear Power Plant Unit One 10 Center Road, North Perry, Ohio 44081 W.O. 95-5182 R/0 l (Repair Org., P.O. No., etc) ,
1 1
- 3. Vork Performed By: Cleveland Electric Illuminating Co. Type Code Symbol Stamp g 10 Center Rd, North Perry, Ohio 44081 Authorization No. 33 Expiration Date 7/18/96
- 4. Identification of Systems 1B13 Reactor & Internals
- 5. (a) Applicable Construction Code: ASME Section III, NB , 1974 Edition
~
Vinter 1975 Addenda, Code Case 1728, 1644-4 "li-272_ _
+J 2o 1 eswa. W 3]upf, (b) Applicable Edition of Section II Utilized for Repairs or Replacements: 1983_
Summer 1983 Addenda zm I i L,)
- 6. Identification of Components Repaired, Hodified, or Replacement Components Name of Name of Manufacturer Nat. Other Year Repair ASME Component Manufacturer Serial No. Board ID. Built Replacement Code No. or Hodification Stamped F1 ping General IBl3 System Electric IB13 64077 D0008 1984 Replacement Yes
- 7. Description of Work: Replaced Control Rod Drive Mechanisms (CRDM) and 1" capscrews. See Remarks
- 8. Test Conducted: Bydrostatic- [ ] Pneumatic- [ ] Nominal Operating Pressure- [X]
Other- [ ] 175 degrees F Pressure 1038 psi Test Temperature
,q %./
Page 146
f NIS-2/NR-1 OVNER'S RRPORT FOR REPAIRS OR REPLACEMENTS l m l
)
l
- 9. Remarks: Instat ted a replacement CRDM in core location 46-11 S/N A452 t usine (8) capscrews !"-8x5%" ig. ASME SA 540 Gr. B23 (8) Hti 99896.
l l NOTE: Attach all applicable Kanufacturer'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. l I CERTIFICATE OF COMPLIANCE l Ve certify that the statements in this report are correct and that all design, material and workmanship on this Replacement conforms to (repair, replacement, or modification) I applicable section of the ASME Code. to use tije N,R, stamp expires 7,18/96 l Certifica M of pu,tJaopir ti o. 33 Signed /Lhot<4 f (R A d k b et W 14-) l (Oyner or gyner's Designee,ITitlW) Date N d N 23' 19 Y6 CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the State or Province of OHIO and employed by *ARKVRIGHT MtffUAL INS. CO. of NORV00D, MA. have inspected the repair, modification or replacement described in this report on &,ce s, 41 9 .s1996. , and state that to the best of my knowledge and belief, this repair,' modification or replacement has,been made or constructed in accordance with Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any varranty, expressed or implied, concerning the repair, modification or replacement 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 1 s of any d from or connected with this inspection. g Commissions d 65r,g _f hoe,o h Date (Inspector's Med a Signhre) 19 p [
- FACTORY MUTUAL ENG. ASSOC.
O
. - - - _ ~ ~ . . - - .. _ . _ - . - - _ - - - . - - - - . ~ _ _ _ _ _ . . _ . - _ _ _ - _-
l - l l l \ ! REPORT NO. NP0059-0005 e
. 1B13-017 Sheec 1 of 2 ]
9 t 2 of 3 - I i rom 64 N.2 NFT CERTU'ICATE ISOLDE3tS DATA REPObOR NUCI.E,Ut FART AND AFPURTENAP.CES* ' I As required by the Provision of the ASME Code Rules. Section Ill. Div, i t s., Messmed br General Electric Costpany. Castle Hayne Rd., Wilmington, N.C. j uneen. meene.- =esercnua. uman, l gg u s ,4 a., General Electric Company. San Jose. California (NEBC)
- eensessesmem-E rnc esee umenen .
- .es
{ r unemassess.caramesse House *s senat No. et runs A4521 ya,,1 ad. No, (ek t - ww es Dres,,,, g., 768E534G001 g,,,,;,, D. L. Peterson - j Control Rod Drive, Hodal #7ED5144DG001 f (b> Deser h et Penta w
- ncut (et App. de A$b4E Cedes $seden H1.h 1974 , W@ W'75 g 1361-2 1 f
f 1,, see,,, Senndard part for use with Reactor. Hydroatardently tested at 1820 pai. cm,.ne _ _.e ,. e. , _ _ e,,,,,, l i
- Total number of sheets - 2 I
l . i ve easdfy seeshe made is side ese cessees and skis ,eemet pare er apparessemee as deemed is she Code can. i asse emiker seine af een-======= ed she Asas Seedse I11. Ther aestlesme Deeens ====en===*== aan Stuen megers ase met the ressenaattlAF et the MPf Cereneses Hewer ter seren. As NPT Caref. HaMar for appartesesses is roepeenhie for Ameeshes a separese Domes se= rase =ana= and Saees Aspart if es apparesseems a ses
- assemea.gr me esmuseems camas ====ui-- ama seems assen.)
. + ! 3, 12/30 g, 80 g,,,g GE, 3EPD-WD- @ ,, . j -
<errceammannessaan <
mengemeeog W w eo June 16, 1981 Cardficase of Aeswisasian No. MPT N-1151 ? CER'I1FICATION OF DESGN FOR APPURTENANCE (when appliemble) i i . Desies. intermanise se file = GE. NEPD-ED- @ , Castia Hayna Rd., Wilmington, 3.C. . I l l 22A5556, Rev. 1 j 5even essaysis r,pers em file as GZ. NEFD-WD-CA. Castle Havne Rd. . W11-heton. M.C. 22A4912. Rev. 2 Dessee speesneensee certified by B. N. Sridhar ' Prof. Eas.ssaee Calif Res.Nej,3345 l Seresa amaaveis repare cervilled by B. N. Sridhar Prof. Eas. senseCalif g,,,3,,18345 CER"!1FICATE OF SiOP INSPECTION i j !. the endersigned, holdies a valid commission isoned by the Marieead 8eerd el Seilee omd Pressure Vessel laspectors
- and/ar che sense er p,ees.ee og North Carolina and employed byDepart
- nant of 1. abor 4 og State of North Carolina hee, inspected the pees ad a paveense venees described in this
} Perna 4 Date neeert as 12/30 3,,80and siste mas to me hese at rar knerwieese a ame bettet. the NPT CeSoeste Meeder ans commenctee rats part in accursance with the ASME Code Sectoe !!I.
- ' Sy signing this ceersficase, messinet the lassector not his eenpleret reakes any wearesty, espressed er iseptied, concers.
tes the eart desett bed to this Perttai Data Aeoort. Furthermore, setther the lassector nor his efe980Fer j sma
..ll.b.e liable is my seemer fee say perseead istury or property domste or a teen of say k. sed artsan6 from or connected s .a_e
,, 12/Jp g, 80
. gdgg C_.. ..i.e . NC T/9,PA.WC2L60, OHl0 - 3 g/ in.e yo i. a se... p . n d .====4==- -
==.:.= : ::, ==r a --- - ~ - - ""
- ! ,, em, s - . _ _ _ ._. c._ v .w e - ~. x . o .
N 4 1 l Page 147 1
+ i I
~
FOfN 2 nacu l l teevne 4 4 tact. so be completed for singte -all vessels, inchet s of iacketed ve ssels. on shells of hesa esch angers.- - *
.q, No minal Coriosion g T Allo-amce _in. Di- f. - in. Leag<b _ fc. ;., 5 ,/
- 4. Shetts Mmevial sse. .S.(mm..e m .Th.ekaa s,.e is teen ns_ ia.
g name n s ,._.. H .T.* R.T. Efficseecy 7 . . . .
- 5. se :. Long H.T.* R.T. No. of Cowses Girsk T.S. (bl Ma<erial T.S.
(s. He. ass (al Maserial $se. se pr.ee. ca e Km.sma. Enlaes.e.4 C onse.6 M.ma.phecie.a Ft.e . g e ne.e a.m n.es a.see apes Ansie mesau. 06 .e (c .ec 3 (T . m enast Thseh .. (si tb) Ocher femenrag If reasovable. boiss used e, (p.weise .e enun . .no
<as n.a. sees. no T.s saa.. n
- 7. Jacker Closuresto.une. .s e..is.o.e. .in.at m.e s. si .. .s n.aaes.o.we.se w mens Drop Teight Chatpy leipacs (e.Ib 375 ,,,,,, op
- 5. Desiga pressese' O psi as 7 1 Items 9 and 10 to be completed fee sube sections Thickness _is. Astachmens i
- 9. Tube Sheess: Stasiosasy. Material Dia. (weie.e. a.se.es tsu.e a se . n (sees,ee i. pr... ree Flossias. Macarlal Dia. - Thickness _im. Astschement O.D. in. Thickness 'I77 s Nember
- Trpe
.10. Tubes: Maserial c .e m 1: ems 11 14 imet. cm be completed for inaee chasabers of incketed vessels. or chammets of bees enchangers.
Nomimal Coerosion is. ia. Din._Is. ia. Lenget Is. Lt. Shetta Muerial T.S. Voickmees _ ia. Allowamee (Kanense .sse. cassa. .a m age se...n.e H.T.' R.T. Efficiency f.
- 12. Senas Leas Girib H.T.* R.T. No. of Cowses T.S. ('ai Muerial T.S.
- 13. Heads (afMuerial saa. se pe.ee.
ca Kaws ma. Eis.,t.een c ..a u n ..a rios eas.e Tnsema... n.m.. a.e. n 4... A sie m esi.e on .., (c . .e c.==.3 s (a) Top bottom ends (b) Channet (c Other f assening il removable, bolts used (a) (b) e o .c . ., .n w n eems b Dvoy Weight Chstpy lepart is.lb
*F as temp. of 'F I4 Design pressure' psi as ltems below to be completed for all vessels where applacable.
l$. Salevy Valve Ouitets: Number Siae Loc anon
- 16. NoazJess R**af e.* * ***e pu ... sina.e.
Tnse ma* ** 4 ""' *8 M*"^"***** M ew D. .e stae 7 v,. nam e** es omaet.o. ni i I? In spec tson W ennote s. N o. , Sise _ L oc ation I Openin g st H anehole s. No. S' ae Lecason Theesded. No. 5 re Loces on Lees Gener AHat hed
- 18. Si.pport s: Sk.ri L.as .o ... e s m.* * **=
3 7 o w.e ; N.a .. .s....
. lr ........ . a t n............w......-.
O l 1 i l l l _.________---_I
REPORT No. NP0059-0005
~
1813-017 Sheet 2 of 2 s Sheet 3 of 3 .
'.. V 2 'O FORM N-1 NFT CERTIFICATE hot.DERS* DATA REPORT FOR NUCLEAR PART AND APPURTENANCES * \ As requered by the Provison of the ASME Cude Rules. Secuan !!! Div. t l
l
,gg u,,,g n,,,a y General Electric Comoany Castle Ravne Rd. , Wilmington, N.C.
in e - - -_ = m c ac n (w u s , 4 g General Electric Company. San Jose California (NEBGi in eac.ree um ,en g --. ,. n-.. u.ae.r.s senat Me. et ran A4521 y,,. ad, k (at Casammewed Acceadams se Deneing E 7/AMMCnot Desuring Prepared W i D. L. Peterson - l (4 n.-- e..- ai Pese t p g Control Red Drive. Model #7RDR14ADC001'
. N207 i
~ (et arr~- ASMECadess.ea ni. Edge 1974 U'75 Ada a.d Co.u _1361-2 c! . 1 T. Cap 16639274P1 I (167A2343)
SA182 - F316 Code weld 3/8 thick x 11/16 OD P.50YP102 I Nh i 2 l -
- 2. Indicator Pipe 166B9313P1 l 6 SA312-TP316 3/4 sch 40-seamless pipe N
l
0.113 vall thickness
- l
\ l 1.065 max. dia. .
t O
- ha w ' vessel l a I
thimble i V 3. Plug 159A1176P1 l g i g I l
. SA182-F304 .
_, , I L_. 1/4 thick x 0.812 00 l I n
. 4. Flange 919D610P1-(719E474)
.SA182-F304 Codeweld\
..B50YP102 NN 8
\
3.37 thick x 9 5/8 00 % l' neck 1 1/16 thick x 5.0 OD
!1
/
/ I
\
. 2.875 ID /_
g \
' 5. '
Base 137C5311P1
*~~ '
XM-19 ASME SA479 i 3.0 CD x .884 ID 4 L [
- 6. Ring Flange 11485122P2 l'
SA182.F304 Code weld a 1" thick x 5.0 0D x 1.75 ID P50YP102 SA$g!#[. CCf: TROL RCD DRIVE l 6 ea.1/2 dia. on 41/8 bole circle DWG - 768E534
- 8. Plug 175A7961P1
- 9. . t 137c3924P1 ZM-19 SA479 5 2f.R x i. m dl.. .
8' 00432 A Page 148
REPORT NO. NP0059-0005 IB13-Ol8
") NIS-2/NR-1 OVNER'S REPORT POR REPAIRS OR REPLACEMENTS As required by the Provisions of the ASME Code Section XI PNPP No. 9308 Rev. 6/93
- 1. Ovner: Cleveland Electric Illuminating Company Date 3/27/96 P.O. Box 5000, Cleveland, Ohio 44108 Sheet 1 of 3
- 2. Plants Perry Nuclear Power Plant Unit One 10 Center Road, North Perry, Ohio 44081 W.O. 95-5183 R/O (Repair Org., P.O. No., etc)
- 3. Vork Performed By: Cleveland Electric Illuminating Co. Type Code Symbol Stamp NR_
10 Center Rd, North Perry, Ohio 44081 Authorization No. 33 Expiration Date 7/18/96
- 4. Identification of Systems 1B13 Reactor & Internals
- 5. (a) Applicable Construction Code: ASME Section III, NB , 1974 Edition Vinter 1975 __ Addenda, Code Case 1728, 1644-4 7 -272, Nauf Mu .2. D M %lr$ N G (b) Applicable Edition of Section II Utilized for Repairs or Replacements: 1981 r~3 Summer 1983 Addenda l i v
- 6. Identification of Components Repaired, Hodified, 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 Paping General '
1B13 System Electric IBl3 64077 D0008 1984 Replacement Yes
- 7. Description of Work: Replaced Control Rod Drive Mechanisms (CRDH) and l" capscrevs. See Remarks
- 8. Test Conducted: Hydrostatic- [ ] Pneumatic- [ ] Nominal Operating Pressure- [X]
Other- [ ] 175 degrees F Pressure 1038 psi Test Temperature fg Page 149
NIS-2/NR-1 OVNER'S REPORT FOR REPAIRS OR REPLACEMENTS
- 9. Remarkr Installed a replacement CRDM in core location 42-4 7 S /N A4 769 usine (8) capscrews l"-8x5%" ig. ASME SA 540 Gr. B23 (4) Htf 99846 and (4) Hr# 61811.
NOTE: Attach all appliccble 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 Ve certify that the statements in this report are correct and that all design, material and workmanship on this Replacement conforms to (repair, replacement, or modification) applicable section of the ASME Code. Certificatp)offut rJgationNo. 33 to use the NR stamp expires 7/18/96 Signed / % d el .. Lu At d Quf& 0Mwsb (Ovner or Ovner's Designee (, Tiqfle) Date M trA1 19 I 19 4/a CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the State or Province of OHIO and employed by *ARKVRIGHT MUTUAL INS. CO. of NORV00D, MA. have inspected the repair, modification or replacement described in this report on pf, sun OG ,s19 94 , and state that to the best of my knowledge and belief, this repair, modification or replacement has been made or constructed in accordance with Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the repair, modification or replacement 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 - s of any k}af from or connected with this inspection. jo
' ~M Commissionsgg g z 3 T ou*,se .
(Inspector's SignaIbre) pf,,,e ,4, oA 19 94
- FACTORY HUTUAL ENG. ASSOC.
Date _.- O\ l h
REPORT NO. NP0059-0005
% 1B13-018 sheet 1 of 2 Sheet 2 of 3 FORM N.2 NPT CER11FICATE hot.DERS* DATA REPORT FOR NUCLEAR PART AND APPt.'RTENANCES*
As required by the Provision of the ASME Code Rules. Sectace !!!. Div. I
- 1. (.3 wemmt crened by General Electric Company, Castle Havne Rd., Wilmington. N.C.
in m. e art c.,en. (b) Mandaceaned fe, General Electric Company, San Jose, California (NEBC) inem. ma ar.m.: a c.rese.w se w me e.es ,.
- 2. idensacamen.Cernecate Heider's sata! .% et Part A4269 M ad. N Deswiss Prepared by
* * "I'#8**
(a) Canamneted Acesse.as se Dreeine W. g ,,p ,,, control Rod Drive Model #7BDB144DGOC1 FMU/ I97' "'73 (c) AppGeeble ASM E Codes smenen n1. Edasans . h&e . Case No. Clase 3, , Standaud part for use with Reactor. Hydrostat1cally tasted at 1820 pai, ten.s . ,wu .s s. wa . __ . ea .
- Total number of sheets - 2 We senify shasshe - made la ehls ese corsect and dnis vecesi pese er apparessance ne defined in the Cees coe.
fanna se she ennes ei cease n ei she ASd1 Section III. The aestiesale Deessa spee.mene.saa a*= and seen Aepset are not the ressenstatitty et the NM Cerapesse Hekter est parts. Aa NM Certti. m- ismas Heider for appartemmaeos sa respeambie for floresshams a separase Desige 5penScesse and Screes Report t the appursentase as est tartuend la she conneesent Oselet e==aa*=an== and Strees ResortJ
, 7/23 g, 81 sipad GZ, NEPD-WD-QA iwr causame umseen 37 [ __, 4 C.,ig; ease a 4.shenanden Empises Sectember 15. 1981 Carnfiemer ei .
h. CER11FICAT10N OF DESGN FOR APPURTENANCE (when mypileable) GZ, NEPD-WfD-QA, Cascia Hayne Rd., Wilmington, N.C. Den, ladosse en fik - 22A5556, lev. 2* Sareas smalysis report so 61e a G2. NEPD-WD-CA. Castle Havne Rd. . Wilminston. N.C. 22A4912, Rev. 2 Design specificad.ma certified by 3. N. Sridhar Prof.Eas Sam,eCalif me,,wJ8345 l s.ees assireis ,v,en ined 6, 3. N. sridhar p,,,,g ,,3,,, Calif ,,,,3Js245 CERTIMCATE OF 5 HOP INSPEC'T10N l
!. the undersigned, holding a entid essmaisaise issued by the Narianal Seard el Boiler and Pressere Vesse! taspectore nad/or che saaee er Pi s.ee og North Carolina ned employed by Depart:nant of t. abor el State of North Carolina bsve inspected the past of a paesense essel des.-ribed is this Pernal Data Resort no 7/M i961.and state east to the best of any knowledse and belief, the MM C eru6 cess Hoeser has egnetructee this part to accorosace with the ASMt Code Section III.
97 saenang than cevuficase, meisher dhe laspector ser n' is employer makes any weareary. espressed or implied. Concer== las the part desert bed to this Partial Da ta Report. Furtherteere. setther the taspector mer his efeaterer t shal
.i l bea.eliable is any meaner for any personal isiery or properry saan.se er a toss of eay Isame arisans from or cannected
,s.,.euen. .
o..e - ,, 7/23 , 81 : KO. H3fAVICU66. OHIO 9MEh Commissina s wn 3.. sie man as m .. e . . ...
, ,(
tw Z*".1":" O* ;. ". "*** " **O** **/.*.'.?'**./***.!'** T ".** * 'P * # ' * "*'"*" ~ ""* **' ** *
- nomi n , .gooo% o. .,e,www c,o,, :not. cuewbors,.. v %. w.v scos-1 Page 150
v i FORM N.2 (bee U lseme 4-8 lacl. se be templeted fee single all vessels. inchess ed tacaeced ve ssels, or shells ei bess eschangees. ~ 1 Neanimal Corrossen l Thickne ss_ ia. Atle.anc e _ ia. Dia. _ is. _ ia. Leagsh st.
- 4. 9 hell W as efial _ _ T.S. i*
cza m a se e. mea (asta. e mense seewareees H .T.' K.T. Efficiency r. ,. 1. Sessim Leas Gian - H.T.' - R.T. No. of Courses T.S. (b) Ma<en al T.S.
- 6. Heedai (at Wesenal a 16,eaees ce.nees M .ae,aenees rim siee i. p,ees.
Lernsee cre== Km mte m Thaenneee ameane meesee a m 6. Apes ansae s eesmo os ee tee .e,c i (Te ne tal (b) If reemeeable betse used Other fas<enies caseeerina, so.e. Me. T.s . san. n _ (peanne e, amie a eee. ens
?. .. .s meesee, sesense er semas Jacket Closurescoeserie. ee es
- eeewe e.== m. ar mer sa-o es ae.
Drog Weight Cha,py tenpace ti.4 b 1250 , ,; ,, 575 ., ,,,, , ,, e,
- 8. Design presen,e s Iness 9 and 10 so be completed fee siabe sections
- 9. Tube Sheess Seassenary. Mase+' Dia. Thickness _ in. Anachmens
<sse, ,,ve wee consees. sessee (Ka.e a se . se. i Flossias. Maserial Dia. Thickness _ia. Anachmess in. Thickness IYe*..
s Number Type
- 10. Tubes: Maserial O.D. (Ser, er v3 teems 11-64 inet. to be cosapleted let inner chambers ei sacketed vesseta, or chanaels of bens eschaagers.
Nominal Carrossen Tbickeess w a. Altomance an. Dia. _ fi. in. Leeg<h _ ft. in.
- 11. Shells Waserial T.S.
tains 6 seee. sea casta. er maase se...tnee H.T.8 R.T. Efficiency .
- 12. Senes: Less C.rth H.T.' R.T. No. of Courses T.S. ibe unserial T.S.
1). Heeds (as Weserial rles Sees to prese. c Kawena, staneeseos Caneena Me eeemenees assaue m esses ameo aees masse messee Dae eer (come. e ceae.: Leem Timeneeee (al Tep, batscm, ends
- bl Chamaet if esseeable, beets used (a) (b) (c) Other f asseeing nee e = este.a samme Orop Weigh .
Charpy Isupact f>4b
'F as seme, el *F 14 Desega pressete' psi as leems seto. to k campseted for all vessels waere applicable.
- . Sasete valve Ovalets: Number $ise Lx sinom
- 16. %es2.les: a..ag eree.ene Pweeee 'In6**. eseeerem desemes, w es e,,ea Me. asteenee Svem. Dee.no s omee, Dee. ee esse Tree 1* In s pec tion Monacie s. No. h ae L x set ea Openings: H amehele s. No. Sise La as son Th te seed. No. Site L ee asica Ovne, {
- 8. See ort s: Sh e r' Less Less 3 e., peec. . , snachse
- - e a ...
( vee wei 3... f
* :s .. .ese ee. f .e.
e..e
% - - - e . . e . ,- ._ - .- .e . l t
l l' O
~ - - -
REPaRT N3. NPOO59-0003 1B13-018 Sheet 2 of 2
.. i Sheet 3 of 3 F
FORM N 2 NFT CERTIFICATE HOLDERS
- DATA REPORT FOR NUCLEAR PART AND APPURTENANCES *
/ [hQ l ). j
( As required by the Provision of the ASME Code Rules. Section 111. Div.1
- 4. (s) Manuf accared by General Electric Company, Castle Hayne Rd., Wilmington, N.C.
<n .as mean .e wrr c.<ancew u.meers General Electric Company, San Jose, California (NEEG)
(b) Mas fscrured fo : encieer . eu j A4269 Nai l ad. No. a
- 2. Identiacation Ceruficate Holder's Sertal No. of Part
. . eterson (a) Can.crucsed According to Drawiss No. 768MMonn1 Drawing Prepared by (b) Descripcios of Par:1a.pecied Control Rod Drive. Model #7RDB144DG001 N207 '
r 1970 W'75 ; c..e No. 1361-2 C1... 1 (c) Applicable ASMECades section t11. Edition . Addenda h e
- 1. Cap 166B9274P1 ]
(167A2343) SA182 - F316 Code weld 3/8 thick x 11/16 OD P50YP102 N_c 2 l l l
- 2. a Pipe 166B9313P1 N
3/4 sch 40-seamless pipe 0.113 vall thickness
! % l 1
1.065 max. dia. Reactor vessel l i . I ( thimble l ' 1 Plug 159A1176P1 l l
- 3. I I i g--
SA182-F304 -- ' i 1/4 thick x 0.812 0D I
- @ l
- 4. Flange 919D610P1 (719E474) Code weld N '
.SA182-F304 850YP102 L
NN 3.37 thick x 9 5/8 OD N' neck 1 1/16 thick x 5.0 OD x 2.875 ID :_,
.CS
- 5. Base 137C5311P1 ' '
XM-19 ASME SA479 3.0 OD x .884 ID 7\' d k---
- 6. Ring Flange 114B5122P2 SA182-F304 Code weld 1" thick x 5.0 00 x 1.75 ID P50YP102
- 7. Cap Screw 117C4516P2 C0f1 TROL ROD DRIVE SA193-B6 DWG - 768E534 6 ea.1/2 dia. on 41/8 bolt circle
- 9. Wt 137C5934 P1
- 8. Plug 175A7961P1 t 2.62 da. MM th ct x 1.307 dia. .
O Page 151
REPORT NO. NP0059-0005 1B13-014 O) ( NIS-2/NR-1 OVNER'S REPORT POR REPAIRS OR REPIACEMENTS As required by the Provisions of the ASME Code Section XI PNPP No. 9308 Rev. 6/93
- 1. Owner: Cleveland Electric Illuminating Company Date 3/27/96 P.O. Box 5000, Cleveland, Ohio 44108 Sheet 1 of 3 4
- 2. Plant Perry Nuclear Power Plant Unit One 10 Center Road, North Perry, Ohio 44081 V.O. 95-5184 R/0 l (Repair Org. , P.O. No. , etc) i
- 3. Vork Performed By: Cleveland Electric Illuminating Co. Type Code Symbol Stamp NR l
10 Center Rd, North Perry, Ohio 44081 AP'horization No. 33 Expiration Date 7/18/96
- 4. Identification of Systems 1B13 Reactor & Internals l
- 5. (a) Applicable Construction Code: ASME Section III, NB , 1974 Edition l Winter 1975 Addenda, Code Case 1728, 1644-4 7 -272 Nao? , /A/4 t4 @[%
6 (b) Applicable Edition of Section II Utilized for Repairs or Replacements: 19 R Summer 1983 Addenda
- 6. Identification of Components Repaired, Hodified, or Replacement Components Name of Name of Manufacturer Nat. Other Year Repair ASME l Component Manufacturer Serial No. Board ID. Built Replacement Code No. or Modification Stamped Piping General ,
- IBl3 l System Electric lB13 64077 D0008 1984 Replacement Yes
- 7. Description of Work: Replaced Control Rod Drive Mechanisms (CRDM) and I" capscrews. See Remarks
- 8. Test Conducted: Hydrostatic- [ ] Pneumatic- [ ] Nominal Operating Pressure- [X]
Other- [ ] Pressure 1038 psi Test Temperature 175 degrees F O Page 152
NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS
- 9. Remarks: Installed a replacement CRDM in core location 42-07 S/N A5586 using (8) capscrews la-8x5 1/2" lg. ASME SA 540 Gr. B23 (8) Ett 61811.
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 Ve certify that the statements in this report are correct and that all design, material and workmanship on this Replacement conforms to (repair, replacement, or modification) applicable section of the ASME Code. Certifica p of Au,gho sption No. 33 to use the NR stamp expires 7/18/96 Signed H ,ual H _t -ft w C A % f L $ .t nu) (Owner or Owner's Designee, T111e'f Date q p(d.4/A-.- cP 7, 19 % CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the State or Province of OBIO and employed by *ARKVRIGHT MUTUAL INS. CO. of NORV00D, MA. have inspected the repair, modification or replacement described in this report on Wm.1, de , 19 % , and state that to the best of my knowledge and belief, this repair, modification or replacement has been made or constructed in accordance with Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any varranty, expressed or implied, concerning the repair, modification or replacement 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 1 sa of any ki from or connected with this inspection. 4 M m.,2m V (Inspector's Signature) Commissions g e m I' homn Date //w ng 19 94
- FACTORY HUTUAL ENG. ASSOC.
O
,~ -- . - . . - - - - .. - . - - _ . - - . . - - - - - . - - - - . . . _ . . . _ - , ~ _ . ? REPORT No. NPOO59-0005
'. . 1B13-019 Sheet 1 of 2 troaM N.2 NFT CERTD1CATE HOLDUtS' DATA RErd bR b PART AND APPURTENANCE 5* i As reqasered by the Provision of the ASME Code Rules.Secuan Ill. Div. t
)/ . .
t General Electric Company, Castle Hayne Itd. , Wilmington, N.C. t (4 wamedeceared by in.m. ens se.m a sert caes somem j gg g,,,g ,,,,,4 g, General Electric Company, San Jose, California (NEBG) emen. ene ese.m a a c m s., :,
- 2. ad==ame d.=.wecase Holder s sortai a ne. or part 6 ,,,,,,,,y,,
(a) Cansasussed Acceeding en Dessing No. 5M1 D. L. Peterson Dre=ias Pmd W (w r- ; - g pe,, g,% Control Rod Drive. Model #7RDR144DGOO1 f14U/ (c) Appuenhie AssECedesseen 31.Ednam. III' ,mw W'75 , c.,, y, 1361-2c ,,,, 1 j g% 5tandard.part for use with Raactor. Bydrostatically tested at 1820 pai. ten. - _ .s e.s .ema __
. a sn .
- Total number of sheets - 2 We eessify abasshe - made la shie ese cesseet and abis vesset pese er apposeseameo as deGmed is she come e femme se she sales of essenees Seetles IIL ffte aselesehte Desten secasa*. ion ei assert aam and seems she AStB ase est tan remm*- et me NPr Carennease Noteer sur parts. As NPr Certif.
-issar usteer sur apparemmmaces ametuses en me emusement osanam is is auraismas a separase Deniss W and seems asport er she appurismenes is aos a-=a.t
= and seress mesert.:
yes, 7/23 g, 81 gg,,g GE. NEPD-WD-QA a f Casuncese d Amaksetansion Empises
.mpye September 15. 1981 s.a. m
,, j CorsiGener d . ' " - No. NPT N-1151 CERTIMCA'110N OF DESGN FDR APPURTENANCE Men applicable)
GE. NEPD-WD-QA, Castle Bayne Rd. , W41mhgton, N.C. p.,;, 3 g ,,,, ,, gg ,, 22A5556, Rev. 2 Seress emalveie ropert en fus es CE. NEPD-WD-GA. Castle Havne Rd. . W41=4a= ton. N.C. > 22A4912, Rev. 2 Design specificesiene certified by B. N. Sridhar si,et,E .s, . Calif a. ,3J8345 Semes analysis separt certified by B. N. Sridhar Psd. Eas. SimeCalif Res. No.18345 j CER11MCATE OF SHOP 1NSPEC110N I. she undersigned. holding a entid coeuriasien lassed by the Nasisesi Seerd of Seiler and Pressure Vessel taspectore sed /or the $sese er Peevance of North Carolina and employed byDepartment of Labor g State of North Carolina have inspected the past ed a psessese vesset described la shis persal asas neeert em 7/23 gg8,1. ase sesee est to see best et my knowkese ,
, and benet.the MPT cerunesse noteur has _ .__ _ a ets part to accaressee wim the AswE coes seeses sat.
1
- Sy signing shie certificase, meisher she laspeveer mer his employer makes any wasreary, espeessed er implied concerna las the part deserthed to this Partial Data Report. Furthermore, netther the laspector not his eenpleFer shall be liable in say meaner der emy peremmat seiery or peeperty des. age er a less of any ksed erasang trem er comoected ,
wi:h this inspection. i o, 7/23 g 81 A4/,8///*M Canumission s E.C. 687,PA.WC2711 l i y Y..v... . si we sa e . m m., e . . .ae N.. ;
?*1**!."il:*l'.*/".'" f.' ".0;."O*." " * '.'.'". *.*O'." ::*.* *".107 ' "
- 1*.* '*'" * """ "'-*"*" " '"-' " *"
4 c.m n v ,o . ceco *. .m .e .. ,. oo., m . cue arm n. a., e... v v 00 3 Page 153
FOIN N-2 (becu . Isens 4-4 lact. ee be cosapleted les single wall vessels ischees of sedesed .e ssels, os . hells of heet enchangers.
~
r s Nominal Coreosion 4 Shetti Atte.ance ,_.... D.- fe._ sa. Le.geh_ g, ;,* .(;3 e (anan..ias.as.The.d
%d at erial _ _.MT.S.(zand sese eassee e ss_ in.
- 1. Seems: Loss H.T.' R.T. E fficienc y r.
Girth H.T.' R.T. No. el Cove se s T.S. (bl M.terial T.S.
- 6. Hesde (m3 Mmetist :
L.em ce st mi. stueue.a c .a H..i.,m. .a rtan sad. e. p,.. cy m.n.m. e. rsum .. a.m a.m a mi. me.e mast. a.es Ota=. a (c . c . ( at (bl _ If reme. ble, boles used Other laseeajag cismwus, se M 7.s.,sau,m n o.u in. ., an m .m.wm
?. Jacke Closveesco.=, ...s.. ..ee.n ..w.umns. . m ..ta= . e. .. wma
- Org Teigh Chaspy leapect ( .4 b 1250 , ,; ,, 575 ., ,,,,,,, .,
- s. Desisa Paes=,,a leeme 9 and 10 se be completed fee tube sectiess
- 9. Tube Sheets: 5:naiseary. Maseri.' Dia. Thickness _ sa. Assachmene sa e a se... n 3 ca.es.a e. pe... wet tu.ame.a.u.c Flearieg. Maserist Dia. Thickness ia. A :achsens O.D. La. Thickness 'f e".'s'. . Number Type to. Tubes: Material tsw. ee un teems 11-54 inct. se be completed for innee chambers of jacketed vessels. or chamaets of beas escheegets.
I Nessimal Coreosion T.S. Thickees s im. Allo.ance _ia. Di a. _ f s. ,.ia. Leesth _ ft. is. St. Shetts Moserian tu6.e a se.e. ne.: inu .eaase se.unee
- 12. Senes: Leeg H.T.' R.T. Efficiency r.
Girth H.T.' R.T. Nc.. of Cour aa T.S. tbe waterial T.S.
- 13. Heads (as Muevial c, sa es. auwiw.s cea.e 4 H .,n ..a rte sies v. pene.
Tween .. s.ei a am me.. aass. a .es.. otemeiee tc m c e.: Laesi (as Top. bestem. ends (bl Chamael If semeeable, belts used (a) (b) - ( c') Other lassening _ sce.eesee .e ses en . wee Deep Teight (~ harpy laepace fe 4b 8 psi sa 'F .c temp. of *T 14 Desigs pressure leems below to be completed for all vessels .nere applicable. ti. $sfety valve Owteis: N. ber fiae Lecesion
' - 16. Nossless p R *iaI ** * * *'**'
Pww..e flates. th ee .ae . . umecies H.* a" wh*e Is.ne Die. sie, f y,e esmwi a o.as ee. Demai l' laspeceson w annoie s, No. 4, , , Loe ss ,o Opensa g s: Hanehele s, W. Size Loc aseon l Thressed ade. $ ige L 3c e e ,og i.ess oenee f
- 18. Supports: Sk ees Less
_ . . . , _ . . . ...v.,. . %st
- a.c .hed . ; _- _ . . ...,
*4.h.$$,?Ome04H..l.1n.m.L
,6L...,...,,,.,...,.,.,,,,..,,,,..,
1 0,
. m REPORT NO. NP0059-0005
~~
1813-019 l l Sheet 3 of 3 Theet 2 of 2 ( . . l FORM N-2 NPT CERTIFICATE HOLDERS' DATA REPORT FOR NUCLEAR PART AND APPURTENANCES
- As required by the Provision of the ASME Code Rules. Section ill. Div. I /Il # Y '
i
~' t l
- 3. (a: Mansacewed by General Electric Cotapany, Castle Hayne Rd., Wilmington. N.c. )
en.aw ase es w arr c.,eacaw nemen (b) Mandacmaed fe, General Electric Comoany, San Jose, California (NEBG) * (ne=e ans ace w a c runeau neeer ser- :==wn au
- 2. Idenuncaden-Ceruncate Holder's $ertal No.of Part AssR6 Nu*!Bd.No.
. . e erson (a) Caneeructed Accoading to Drawing No. 76 D914C001 Drawing Prepared by (b) Descripcios of Par:Imapected Control Rod Drive. Model #7RDB144DG001 N207 (c) Applicable ASMEcode:SecticaEI.Edicion 1974 : Case No. 1361-2 Class I
. Addradadme U'75 s
1
- 1. Cap 166B9274P1 )
- 44 (167A2343)
SA182 - F316 Code v, eld 3/8 thick x 1 1/16 00 ,, P50YP102
, I Na I 2 I l
- 2. Indicator Pipe 16689313P1 SA312-TP316 , l 3/4 seh 40-seamless pipe N ,
0.113 uall thickness + l
% l l O 1.065 max. dia. Reactor vessel l l
d . thimble l 8 l I
- 3. Plug 159A1176P1 l l I 8 SA182-F304 - 8 i
8 g~~ 1/4 thick x 0.812 0D i 8 g
- 4. Flange 91SD610P1 (719E474) Code weld ' N :
1
.SA182-F304 .850YP102 L
NNN 3.37 thick x 9 5/8 OD ' N s l neck 1 1/16 thick x 5.0 OD \ 2.875 ID . s ii
\
A 4
- 5. Base 137C5311P1
.X L XM-19 ASME SA479 3.0 OD x .884 ID 7 1, -
- 6. Ring Flange 11485122P2 SA182-F304 Code weld 1" thick x 5.0 OD x 1.75 ID P50YP102
- 7. Cap Screw 117C4516P2 SA193-B6 C0flTROL ROD DRIVE OWG - 768E534 6 ea 1/2 dia. on 41/8 bolt circle
- 9. Nut 137C5934P1
- 8. Plug 175A7961P1 IM-19 SA'79 SA182-F304 1.30 m x 162 dia.
0.38 thick x 1.307 dia. - 00354 C\ U Page 154
REPCRT NO. NP0059-0005 1B13-020
,/ 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. 6/93
- 5. Owner Cleveland Electric Illuminating Company Date 3/27/96 P.O. Box 5000, Cleveland, Ohio 44108 Sheet 1 of 3
- 2. Plant: Perry Nuclear Power Plant Unit One 10 Center Road, North Perry, Ohio 44081 W.O. 95-5185 R/0 (Repair Org., P.O. No., etc)
- 3. Vork Performed By: Cleveland Electric Illuminating Co. Type Code Symbol Stamp NR 10 Center Rd, North Perry, Ohio 44081 Authorization No. 33 Expiration Date 7/18/96
- 4. Identification of Systems 1B13 Reactor & Internals
- 5. (a) Applicable Construction Codes ASME Section III, NB , 1974 Edition Vinter 1975 Addenda, Code Case 1728, 1644-4 7 -272 N.101 1%/ e1.
'b) Applicable Edition of Section XI Utilized for Repairs or Replacements: 1981 Summer 1983 Addenda
'%l '
- 6. Identification of Components Repaired, Hodified, or Replacement Coaponents Name of Name of Manufacturer Nat. Other Iear Repair A3ME I Component Manufacturer ferial No. Board ID. Built Replacement Code No. or Modification Stamped Piping General '
, IBl3 System Electric IBi3 64077 D0008 1984 Replacement Yes l
- 7. Description of Work: Replaced Control Rod Drive Mechanisms (CRDM) and l" capscrews. See Remarks
- 8. Test Conducted: Hydrostatic- [ ] Pneumatic- [ ] Nominal Operating Pressure- [X]
Other- [ ] 175 degrees F Pressure 1038 psi Test Temperature Page 155
NIS-2/NR-1 OVNER'S REPORT FOR REPAIRS OR REPLACEMEffrS 9 ,
- 9. Remarks: Installed a replacement CRDM in core IOCAtion 46*07 S/N A4302 usion (8) capscrews 1"-8x5%" lg. ASME SA 540 Gr. B23 (8) Ht# 99896.
l 1 l l I NOTE: Attach all applicable Manufacturer's Data Reports. Supplemental sheets such as lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded on the front of this form. CERTIFICATE OF COMPLIANCE Ve certify that the statements in this report are correct and that all design, material and workmanship on this Replacement conforms to (repair, replacement, or modification) applicable section of the ASME Code. Autho o . No 33 NR tamp expires 7/18/96 ~ Certificate Signed w H [/ riza toAluh use the& c;< ant.) (Ovner or Owner's Designee, T/itley Date d 78, 19 Q(o CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the State or Province of OBIO and employed by *ARKVRIGBT MUTUAL INS. CO. of NORV00D, MA. have inspected the repair, modification or replacement described in this report on Nm;, JG ,s19 % , and state that to the best j of my knowledge and belief, this repair, modification or replacement has been ' made or constructed in accordance with Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor ) i his employer shall be liable in any manner for any personal injury or property damage or a loss of any d from or connected with this inspection. go l MM . . -, Commissions ,4d95r.,3 T com
' (Inspector's Signature) hw/, 19 %
- FACIORY HUTUAL ENG. ASSOC.
Date ,0si O
2 REPORT NO. NP0059-0005
. _. . . -y . .. a _ . ..
.- - gg .:_ :.
./j 3 . , Sheet 2 of 3 Sheet 1 of 2 FORM N.2 NPT CERTIFICATE HOLDERS' DATA REPORT FOR NUCLEAR PART AND APPURTENANCES
- As required by the Provision of the ASME Code Rules. Section III. Div. l o _
. g.3 us f.c ,ed by General Electric Company, Castle Hayne Ld., Wilmington, N.C.
in .ma 1.r wrr c. cue <=. w a.,, e (b) Mam&sured fa, General Electric Company, San Jose, California (NEEG) amane ans meer .r a carese.w uwe.,sw e m.cs,we u
- 2. Isle =*ineartes Ceruficate Holder's Sertal No. of Part A4302 g ..: sa, n ,
4 D. L. Peterson
. (a) Caesa.csed Accordias to Dre=ias No. Dre=Las Prepared by (b) Descripcios of Pan taspecad Control Rod Drive, Model #7RDB144DG001 NZU/
(c) Applicable ASMECode:Section!!! Edacaos 1974 , Addendedase 1 W'75 . Case No. 1361-2C1 ass I w ,, Standard part for use with Re.etor. Efdrostatically tested at 1820 pai. l to ,e. wa .< 4.,.u.a. . .. e..iee
- Total number of sheets - 2 We cenify abasebe sensements made la abia are correes and chia eessel part or appersemence as defined la che Code coe.
sules of conseraction of the ASSE e Section 111. foama The =m He as she.Ng Oggggg S$ettOCallGR and Stress llepert are ROC the resposallHilty of the NPT Certificate Was Holder . appurteenaces is esspaamible for insruishies a separase Desigm Specincasion and Stress Report af the appur*==== ss not inesee-d P compement Desten spectacasses see scras neport.:
% 8/26/ _,g 81 siemed CEr NEPD-WD- ,, .f a as r cons use.r.
k Canif; cue .i A. boriassion Espire. Se:rtember 15. T981 c,,,;ft,,, of ,,t,,;,, go, m N-1151 CER'11FICNIlON OF DESGN FUR APPURTENANCE (when applicable) Denism iafor=ation on file - GE, NEPD-WMD-CA, Castle Havne Rd. , Wilminaton. N.C. 22A5556, Rev. 2. siress analysis repon ao file a .GE, NEPD, San Jose Calif. 22A4912, Rev. 2 Desise specifications certified by B. N. Sridhar Prof. Ems.sence Calif ge,,g.18345 Scress emelysis repara cenified by B. N. Sridhar x,g, g.,1834 5 Prof. Eas. St ateCalif CERTIF1CATE OF SHOP INSPECTION
- 1. che undersigned, bolding a valid commission issued by the National Board of Boiler and Pressure Yeseel taspectors and/or the Sense of Province of North Carolina and employed byDepartment of Labor of State of North Carolina be.e laspected the past of a pressure eessei described la shis Partial Data Report on O/26/ 19.01and state that to the best of my knowledse and belief.the NPT Ceruficate Holder has G ;.nW this part la accordance with the ASME Code Section III.
By signing this certificase, meicher the laspector nor his employer makes any warramry, expressed or implied, concero. las the part d escribed in this Partial Data Report. Furthermore. neither the Inspector not his ernployer shall be liable in any meaner for any personst injury or property damage or a loss of any kind erasing from or connected wir6 . bis, inspection. t
'" ' /2 3, al N.C. 723,PA.WC1766, OH10 coramission s
. . . . ~ . . .._.....s.....__._....s
.s.o,.....u.,....,.....,._......m.~....c.,i,m,..i.2..
Page 156
l l
.FOIN N.2 (back) l leems 4-8 lacl. to be completed for single wall cessels. iackets of inche. sed vessels, or shells of heu eschengers.
Nominal Coerosion / l
- 4. Shell: Maseeist _ T.S. Dick ne s s_ ia. Allowance ia. Di a._ fe._ ia. Leesch_ ft. in. i (K&nd a syn. pe.) (mm. of Re.ise specasted)
R.T. Efficisacy 7. >
- 5. Seems: Loas H.T.' l Girch H.T.' R.T. No. of Course s
-T.S. -
(b) Muerial T.S.
- 6. Heads: (a) Ma<erial smaus.: C ee.seea He.se,nectees rami side se Pens.
Leeuse. C, a z.whae Radius Ree6e Apes Angle kodene Otesseau (Came. er Come.) (Top, beteee ende) Thbekness Redame (a) (b) If remoesbie. botes used Other fastesias (nasteeses.s,. we TJ..stse.n meet (Denseine er menn emeten
- 7. Jacket Closures <Dewa* ..eeee and eess.nm.ete. st me ssve sameeseeae. ef heaeed.de sce ne . .=nen:
Deep Weight _ Charpy impact is-lb 575 og ,,,,,,,,, op
- 8. Desige pressu,,a 1250 ps; ,
1 sees 9 and to to be completed for esbe sections
- 9. Tube Sheets: Scus, mary. Wacerid Dia, nic sae ss _ in. Attachmens _
(s.mswa se prenwe (1 rended. seseee (said & s,ee pe.) Dia. ekaess _ ia. Attachment Floacias. Maserial is. Thickness - s;se. Ndebee Type
- 10. Tubes Material O.D.
(see. er tr) leems 11-14 incl. to be completed for incer chambers of jacketed vessels. or channels of heas eschangers.
"~
Nominal Corrosion .~~~' la. Allowance la. Dia._ ft._ia. Length _ ft, in. II. Shell Muerial T.S. Thickness (Khad & spee. MeJ (Min. of Reage spectined H.T.* R.T. Efficiency -%
- 12. Seams: Loss Girth H.T.' R.T. - No. of Causes T.S. (b) Maserial T.S.
- 13. Heads (a) Material _
Centest Heesopherteen Fles side se Press. Csown Kawkle Emsueet Redaw Rme Apes Angse Redan Diametee (Came.erCeas.) Lam ten Twenaeu Radie. (a) Top, bo< tom. ends (b) Chamael Ocher f asseeing l If removable. boiss used (a) (b) (c) a 0. . . e, enan seesemp i Deep Weight- . I (e.lb Ch arpy impact
'F se temp. of *F '
- 14. Design pressure' tai as i
Items below to be completed for all vessels where applicable,
- 15. Safety Valve Outlets: Number Size Loc ation l l
- 16. Naades: R eisd ece, ment Pwpese (Inset. M enesten How Anteched Mumme, D6e. et s&se T ype Mmerset Tateknese Owe t*t. De a n t 1* In spec tion Muncles. No. Size Locacios Opeaangs: Handhole s. N o. Size _ Loc ation Threaded. No. . Sire Loc a tion Legs Ocher Air ac hed
- 16. Suppoets: Shift Legs _ c oe se,.m. gene.e a new, tves e, men < pe. nee,, g ne.,,ee,i 1.- u . . . .v .. . a O
REPORT ND. NP0059-0005
- -p IBl3-020 p .J -. 3 Sheet 3 of 3 Sheet 2 of 2
()
FORM N-2 NPT CERTUICATE IIOLDERS' DATA REPORT FOR NUCLEAR PART AND APPURTENANCES
- As required by the Provision of the ASME Code Rules. Section !!!, Div. t l
i " t g,3 g,,,,,,g i,y General Electric Company, Castle Hayne Rd., Wilmington, N.C. u.a a.c n mwrrc.enec n.e4.n (b) Meaufactured fa, General Electric Company, San Jose, California (NEBG) i
, osaan ama _n er n carna. usa.,sw e wwe aus ,
j u 2, IdentLocanon-Certificate Holder's Sertal No. of Part 04302 ' _N as't Bd. No. l (a) Constructed Accordias to Drawiss No. 768R W C001 Drawiss Prepared by . . Peter' son (b) Description of Per laspected Control Rod Drive. Model #7RDB144DG001 (c) Applicable ASMECode:SecciaoIII.Edicios l974 N207 _, Addenda dare W'75 Ca.e u., _1361-2 Csas. 1 l
.__ , _~, .
- 1. Cap 166B9274P1 1
(167A2343) SA182 .F316 Code weld 3/8 thick x 1 1/16 OD F50YP102 N;r ll l I ^ " " " *""'"
- 2. Indicator Pipe 166B9313P1 2 I l SA312-TP316 .
3/4 sch 40-seamless pipe l () 0.113 vall thickness 1.065 max. dia. lN\ g
' Reactor vessel
- 3. Plug 159A1176P1 thimble l :
I l .
; g l l SA182-F304 I t._ _,,, _
1/4 thick x 0.812 OD . , , _ , l l 4. Flange 91SD610P1 (719E474)
.SA182-F304 3.37 thick x 9 5/8 OD Code weld
..R50YP102
)
N l 8
\
neck 1 1/16 thick x 5.0 OD
. 2.875 ID
\
4
'5. Base 137C5311P1 '
N l
~~ ' '
XM-19 ASME SA479 ' 3.0 0D x .884 ID -
, 6. Ring Flange ll485122P2 -
SA182-F304 Code weld l' thick x 5.0 OD x 1.75 ID P50YP102
. Cap Screw 117C4516P2 ZA193-86 C0f!TR01. ROD DRIVE 6 ea.1/2 dia. on 41/8 bolt circle DWG - 768E534
- 8. Plug 175A7961P1
- 9. Nut 137C5934F1 SA182-F304 IM-19 S*479 0.38 thick x 1.307 dia' -
1.30 thick x 2.62 dia. O OsFlo. (G w/ Page 157
REPORT NO. NP0059-0005 IBl3-021
/^g
( j NIS-2/NR-1 OVNER'S REPORT FOR REPAIRS OR REPLACEMENTS
' ~ '
As required by the Provisions of the ASME Code Section XI PNPP No. 9308 Rev. 6/93
. svner: Cleveland Electric Illuminating Company Date 3/27/46 P.O. Box 5000, Cleveland, Ohio 44108 Sheet 1 of 3
- 2. Plants Perry Nuclear Power Plant Unit One
,, 10 Center Road, North Perry, Ohio 44081 V.O. 45-5186 R/0 (Repair Org., P.O. No., etc)
- 3. Work Performed By: Cleveland Electric Illuminating Co. Type Code Symbol Stamp g 10 Center Rd, North Perry, Ohio 44081 Authorization No. 33 Expiration Date 7/18/96
- 4. Identification of Systems 1B13 Reactor & Internals
- 5. (a) Applicable Construction Code: ASME Section III, NB , 1974 Edition !
Vinter 1975 Addenda, code Case 1728, 1644-4 7 -272
#-241,t % L-> h ^ 1/ns/96 (b) Applicable Edition of Section II Utilized for Repairs or Replacements: 1981 Summer 1983 Addenda
!g J QJ
- 6. Identification of Components Repaired, Modified, or Replacement Components l
Name of Name of Manufacturer Nat. Other Year Repair ASME Component Manufacturer Serial No. Board ID. Built Replacement Code No. or Modification Stamped F1 ping General , 1B13 Replacement System Electric IBl3 64077 D0008 1984 Yes
- 7. Description of Vork: Replaced. Control Rod Drive Mechanisms (CRDM) and l" capscrews. See Remarks
- 8. Test Conducted: flydrostatic- [ ] Pneumatic- [ ] Nominal Operating Pressure- [X]
Other- [ ] degrees F 1038 psi Test Temperature 175 Pressure _ p
! d LJ Page 158
NIS-2/NR-1 O@iER'S REPORT POR REPAIRS OR REPLACEMENTS i
- 9. Remarks: Installed a replacement CRDM in core location SA-27 S/N A5728 usine l
(8) capscrews I"-Rx5%"Ig. ASME SA 540 Cr. B23 (4) Ht# 94896 and (4) Hti 6f8(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 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 Ve certify that the statements in this report are correct and that allconforms design, to material and workmanship on this Replacement (repair, replacement, or modification) applicable section of the ASME Code. 33 to use the NR stamp expires 7/18/96 CertificafgofAutp(rpationNo. Signed A/dtucl K, 64le d d&su fik /!<4/nsed) DateMaAi k 78 (Ovner or 19Owner's 9(p Designee Title)v CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the State or Province of OHIO and employed by *ARKVRIGHT MUTUAL INS. CO. of NORV00D, MA. have inspected the repair, modification or replacement described in this report on /%cs, og ,s1996 , and state that to the best of my knowledge and belief, this repair, modification or replacement has been made or constructed in accordance with Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any varranty, expressed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or proWrty damage or a loss of an kind from or connected with this Commissions inspection.
,cAArt,3 T N.
nY m., _, . (Irispector's STgnature)
- FACTORY MUTUAL ENG. ASSOC. l Date MucA .p s 19 96 O
REPORT NO. NP0059-0005 Sheet 1 of 2 j 4,
~
, \ 1B 13-()21 FORM N-2 N?T CERTIFICATE HOLDERS
- DATA RE NO t BEAR PART AND APPURTENANCES
- V As required by the Provisida of the ASME Code Rules. Section lit. Div. I i
1 I t 9, u,,,g.c .,4 by General Electric Cotrpany, Castle Hayne Rd., Wilmington, N.C. l ue e e, . arr c.,me u se e. gg,) y,,,,g ,,,,,4 go, General Electric Company, San Jose, California (NEBG) ,
<m e amer . a c macai, u e s.e . ci re u ! !
A5728 y ,, , ga, y,,
- 2. see.cacamen-certiacate ficader's serial No.of Part l D. L. Peterson
<., Can uc..d a.rdia. Dr ia, uo. 768zs3' cool or ia, P.,ar%
l
. . Control Rod Drive, Model #7RDB144Dc001 (b) Descripues of Pari taspecsed MU!
(c) Applicable ASMECadet$ectionHI,Edidos
'~
. Addendadare W'75 . Case No. Clus Standard part for use with Reactor. Hydrostatically tested at 1820 pai.
- 5. Remarks teri.e rieu .a..r,w.s.r.asci. e . e
- Total number of sheets - 2 I l
l l i We cenify satshe esasesmenes ende la sinis ese correct end abis vessel para er appartenance as deGaed is abe Code co lessne so abe sales of cesserucaias ei she ASME Secties 111. (The aspilcah4e Design Spectneation and Saees Report are not the responsibility of the NPT Certineate Holdse for parts. An NM Certif-icase ametoded Heider serc=pa-ast in the appuneenacesDestemis . spectScenes and Serges Report.)for forW e separese Design Specsacation and Stress Report if the appartenan 8/29 g, 81 CE, NEPD 6 ,, ,
- o. swed __.__u l
C.nific=e d 4 4.risade. Empire. Sep* ember 15. 1981 c ,gg3,,,, ,g i,,g,, ,,, NPT N-1151 I CER11 FICA 110N OF DESIGN R)R APPURTENANCE (when applicable) De.iss imim== ion es s11. - GE, NEPD-WMD-CA, Castle Hayne Rd. . Wilmincton. N.C. 22A5556, Rev. 2 ' seen .malysis = pori f;te as GE, NEPD, San Jose, Calif. 22A4912, Rev. 2 , j Deslan specificacions certified by B. N. Sridhar p,og ges s,.., Calif g,,,goJ8345 1 Saees smalysis report certified by B. N. Sridhar Prof. Eas. ssue Calif g,,,g ,18345 CER11F1CATE OF SHOP INSPECTION l i I, the undersigned, holdies a valid commission issued by the Nasional Board of Boiler and Pressure Vessel laspectors mad /or the Scece or Province of North Carolina and employed byDepartment of Labor g State of North Carolina beve laspected ebe part of a paeseure vessel described la abis rarnat omaa neport ee 8/29 ,, 8,1, . d ,ta,, tn.i a an, n,,, ,g , no,,,,,,, and beltet,the NPT Cert 1Acate Holder has constructed this part la accordance with the ASME Code Section !!!. By signias abis certificate, meicher the laspector nor his employer makes any warreary, espressed or implied, concere. 1 las the part described to this Partial Data Report. Furthermore, neither the Inspector anr his employer shall be liable is say meanes for any personal injury or property damage or a loss of any kind arising tree or connected with abis sospectica. 8/29 81
- i9 gg N.C. 723,PA.WC1766, OHl0 g C.,...,.
a...ac w. sie w. n.ii n ... n .. e . n..
* .*""1*"'".".i ".E*2." '."1.*.'J.*.".C *T".*. ".!*.*.**. * *.*7,0. *l* * *.?!.*.'f*.*. ' "..*J *. *." '"" * ""' ' '"'*'**"*" " "*"* "' *" ""*
iiomi n vorm tcooo4our.y t= oei.,n.d ,,om ih. oro., o.oi AsME,345 E. 47th St New York., Nh. . - w* 10017 w Page 159
lh
-...a .. -
s .
/ F... - A * *
~"
F N.2 (back) leems 4-4 lacl. so be completed fee single well vessels. jackets of jackied vessels, or shells of heat eschengers. m Nossiaal Corrosion in. ( ")
- 4. 9 ells Maeerial _ T.S. Thickne s s_ la. Atle ance _ia. Dia ft. _ in. Len gth_ is.
(Knad t spee. No.) (Min. ed Range speetf 6ed) H .T.' R.T. Efficiency 7.
- 5. Seams: Loas Girtb H.T.' R.T. No. of Courses
- 6. Heads: (a) Meterial T.S. (b) Material T.S. (
C ona.es He tephutset Fles sade ce Peeee. l g.oe msen
- Cee-. Kauekte Estas 6e es Red &we R odass R m 6e Apes Angle R ed6=e Deemmee (Ceev. er Come.)
(Te,. benem, ende) Th6ehmes e (a) (b) If removable, botes used Other fastening (Meweies.s,ee Me T.s sise.N me,i (o.eertse e, eiseen emeten 7.e, jacket Closures (oeu es osee d.ead.mer.ete. ts s= sa w d4me.= . ar messed.ee n,4me w oneeeni Drop teighs Charpy limpact fa.ib 1250 575 or ,,,,,,, op
- 5. Desisa P' essure s p,3 ,,
tients 9 and 10 so be completed foe sube sections
- 9. Tube Sheets: Sessionary. Materlat -- - Di a,. Dickness_ia. A achmens (Kind a s,ee.me.) (s.impet se preeewei (wended seaiec Flonelag. Maserial Dia. nickness._,_ia. Attachment O.D. la. Thickne s s -a.chee sese . Number Type
- 10. Tubes: Material (sw. ee u) 1 Isema ll_14 incl. se be completed for inner chambers of incketed vessels. or chamaels of heaa eschangees.
~ * ' ~ '
~'
Nominal Corrosion ia. f II. Shell: Material T.S. nickaess Ja. Allowance Ja. Di a. _ f t._ia. Length _ ft. (K tad 6 spee. Me.) (Mia. of Rease speetise4 H.T.8 R.T. Efficiency ?.
- 12. Seams: Leas Girth H.T.' R.T. No. of Courses T.S. (b) Masevial T.S.
- 13. Heads (a) Material gitapeleet Cenical Hemaapheeseet Flee sede se Press.
Crown Kewette Redaus Ree6e Apes Anste R adive Diametee (Cene. er Ceme.) Leese 6en T1dekassa Redlue (a) Top, bottom, ends (b) Channel (b) (c) Ocher fastenies it removable. bole s used (s) coeserne a enan enesen) Drop Teigh . Charpy impace (e.lb op *F
- 14. Design pressvev a p,; ,, ,,,,,,,,g leems below so be completed for all vessels where applicable.
- 15. Safety Valve Outless: Number Size Location
- 16. Noades: .
Reinfereement Purpose Untet. Thfeknees M es ette! He= Aetected Nwntwe Ote, et sise Type ste ersel Owt LM. De ma)
- 17. laspection M anhole s. No. Si te Loc ee son Openin gs: llandhole s. N o. Size Locesion Threaded, No. Size Loc e s.oa Legs O<hes Ae ached
- 88. Supports: Sk ire Lugs < whee. 6 H ewi l avee =e not tre o (n w e,i c o. ..eine s s
l
REPORT NO. NP0059-0005 l
~ 1B13-021 i l,..
Sheet 3 of 3 M'U C L 4 01 - FORM N-2 hl'T CERTIFICATE IIOLDLRS' DATA REPORT FOR NUCLEAR PART AND APPURTENANCES
- As required by the Provision of the ASMR Code Rulen. Section Ill. Div.1 '
l Is
- 1. (.) u...f.ciuted by General Electric Company, Castle Hayne Rd.. Wilminr, ton. N.C.
em.m..w . m warrc.<un<.w w e<> (b) Manuf.ciured fot General Electric Company, San Jose, California (NEBC) ta== m m.n a c ,un<.w me, nor m cw.,c ne.neau
- 2. Idenunctuan-Ceruncate Holder's Sertat No of Part A5728 y ,,., y g,,
(a) Constructed Accordias to Dra=sas No. 768FU4 COOL Drawing Prejared by * ***8 " (b) Description 3 Part laspected Control Rod Drive, P.odel f7RDB144DC001 N207 (c) Applicable ASMECode:Sectientit. Edition - _, AddenAGace W'75 . Case No. 13 61-2_Cj... 1
- 1. Cap 166B9274P1 (167A2343)
SA182 - F316 Code weld 3/8 thick x 1 1/16 00 P50YP102 N_; I I 6 2. Indicator Pipe 166B9313P1 2 l l SA312-TP316 . [ 3/4 sch 40-seamless pipe N l 0.113 uall thickness
.065 m . dia.
a
\ I
(' . Reactor vessel thimble I I l
- 3. Plug 159All76P1 I l g g SA182-F304 1/4 thick x 0.812 00
~ ' I L-l
. g I
, 4. Flange 91SD610P1(719E474)
.SA182-F304 Code weld h 8
*' .850YP102 '
' NN 8 3.37 thick x 9 5/8 OD neck l 1/16 thick x 5.0 OD N h\
. 2.875 ID f g
'5. Base 137C5311P1 -
X14-19 AS!4E SA479 3.0 OD x .884 ID 7
- 6. Ring Flange ll4B5122P2 SA182-F304
- Code weld 1" thick x 5.0 00 x 1.75 ID P50YP102 9
- 7. Cap Screw ll7C4516P2 SA193-06 C0f! TROL R0D DRIVE 6 ea.1/2 dia. on 41/8 bolt circle DWG - 768E534
- 8. Plug 175A7961P1 9. Nut 137C5934P1 SA182-F304 *~19 S*
- 0.38 thick x 1.307 dia. .
1.30 tM ck x 2.62 dia. OM b xd Page 160
REPORT N3. NP0059-0005 1B13-022
/"
b NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REP 1.aCEMENTS As required by the Provisions of the ASME Code Section XI Pt* No. 9308 Rev. 6/93 Owner: Cleveland Electric Illuminating Company Date 3/27/96 P.O. Box 5000, Cleveland, Ohio 44108 Sheet 1 of 3 I
- 2. Plants Perry Nuclear Power Plant Unit One 10 Center Road, North Perry, Ohio 44081 W.O. 95-5187 R/0 (Repair Org., P.O. No., etc)
- 3. Work Performed By: Cleveland Electric Illuminating Co. Type Code Symbol Stamp NR 10 Center Rd, North Perry, Ohio 44081 Authorization No. 33 Expiration Date 7/18/96
- 4. Identification of Systems 1B13 Reactor & Internals
- 5. (a) Applicable Construction Code: ASME Section III, NB , 1974 Edition Vinter 1975 Addenda, Code case 1728, 1644-4 7 -272 NA0=1/Mft5 13W-L W
*b) Applicable Edition of Section II Utilized for Repairs or Replacements: 1981 Addenda p Su==r 1983 V
- 6. Identification of Components Repaired, Hodified, 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 '
- IBl3 System Electric IBl3 64077 D0008 1984 Replacement Yes s a
- 7. Description of Vork: Replaced Control Rod Drive Mechanisms (CRDM) and 1" capscrews. See Remarks
- 8. Test Conducted: Hydrostatic- [ ] Pneumatic- [ ] Nominal Operating Pressure- [Xl Other- [ ] 175 degrees F Pressure 1038 psi Test Temperature Page 161
l 1 NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR BEPLACEMENTS 01 s l I l
- 9. Remarks: Installed a replacement CRDM in core location 42-55 S/N A5725 using j (8) capscrews I"-8x5%" ig. ASME SA 540 Gr. B23 (4) Ht# 99896 and (4) Ht# 61811.
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 I l sheet, and (3) each sheet is numbered and the number of sheets is recorded on the front of this form. CERTIFICATE OF COMPLIANCE Ve certify that the statements in this report are correct and that all design, material and workmanship on this Replacement conforms to (repair, replacement, or modification) applicable section of the ASME Code. 33 to use the NR stamp expires 7/18/96 Certificatepf Signed f AhM AutgrJea31onJv M (2<f h l dOtu/M N<4ew 10vner or Owner's Designee) Tit)Jb) Date 4L '2Y . 1994 CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the State or Province of OHIO and employed by *ARKVRIGHT MUTUAL INS. CO. of NORV00D, MA. have inspected the repair, modification or replacement described in this report on f,9ef t, og ,s1994 , and state that to the best of my knowledge and belief, this repair, modification or replacement has been made or constructed in accordance with Section II of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the repair, modification or replacement 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 1 s of any nd from or connected with this inspection.
m , 1_ Commissions x/d&sn3 r fM, (Inspector's Signature) Date Au4 e7s 19 9f
- FACTORY MITIUAL ENG. ASSOC.
I i e
l REP!RT NO. NP0059-0005
'I~ ' "
1B13-022 Sheet 2 of 3 m FORM N-2 Mi CERTIFICATE IlOLDERS' DATA REPORT FOR NUC1, EAR PART AND APPURTENANCES. v
) As required by the Proviuon of the ASME Code Rules. Section III. Div. I
- 1. ..) Mas.f aceused by General Electric Company, Castle Hayne Rd., Wilmington, N.C.
w.m ea aser,u w nrr cmac u naaen (b) Manufactured foc General Electric Company, San Jose, California (NEBG) m.w ew wa, e n cevone.w n 4,r vor .a w a.cuar. .o
- 2. Idenuncauen-Ceruncate Holder's Serial No. of Part A5728; s u. sa, so, (a) Construered Accoeding to Desva.ng No. 768E534G001 Drawing Prepared by D. L. Peterson (b) Description of Part laspected Control Rod Drive Model #7RDB144DG001 N2U/ Kf6 (c) Applicable ASM E Code: Section III. Edition , Addeadadase ; Case No. Class
- 3. Ressarks: Standard part for use with Reactor. Hydrostatically tested at 1820 psi, ean.r 4...,teu .e . .. v., .w.m . e .. ... a...a e
- Total number of Sheets - 2 We certify thatche stacements made in this report are correct and this vessel part or appurtenance as defined in the Code coa.
ferias to she rules of construction of she ASME Code section !!!. (The appilcable Destsa Specification and Stress Report are not the responsibility of the NM Certincate Holder for parts. An NM Ceruf-icane Holder for appurtensaces is responsible for furushing a separate Design Specificauon and Stress Report af the appurtenance as not included in the cornponent Destel Specincation and Stress ReportJ o 8/31 81 CE, NEPD-EMD ' 19 sisned B. wrr cmaceu namen Certif; ease of A.shorizacion Espires SeMemW M, M Certificate of mahorizacion No.- ()) i. CERTIFICA110N OF DESIGN FDR APPURTENANCE (when applicaMe) Design informuion on file - GE, NEPD-WMD-f)A, Castie Hayne Rd. , Wilminaton. N.C. 22A5556 Rev. 2 seress analysis repo, on file a, GE, NEPD, San Jose, Calif. 22A4912, Rev. 2 Design specificulons certified by B. N. Sridhar Prof. Eas. S**,, Calif Res. No.18 345 Stress analysis report certified by B. N. Sridhar p,,g, g ,,3,,,, Calif g,,, u,,13 34 5 CERTIF1CATE OF SHOP INSPECT 10N I, the undersigned, holding a enlid commission issued by the National Board of Boiler and Pressure Ves sel Inspectors and/or the Scate or Province of North Carolina and employed byDepartment of Labor of State of North Carolina have inspecied she part of a pressure vessel described in chas Partial Data Report on 8 /3 L is Q1 and stai, chai to the se,t of , gno i,4,, and belief the NM Ceruncate Holder has constructed this part in accordance with the ASME Code Secuon Ill. By signing this certificate. neither the laspector aar his employer makes any warranry, espressed ur implied. concern. tas the part d escribed in this Partial Da ta Report. Furthermore, neither the inspector nor his employer shall be liable in any esaner for any personal injury or property damage or a loss of any ks.d stasing from or connected with this inspection.
.e f 8/31 39 81 pl L- 41w/
/f C.mmiesi s RC. 723,PA.WC1766. OHIO
's..e.et., . s y 4G,. s .i i .i n o.... se . . . e ... . . ..a r...
. w .m ,,.. ..
.s.........i..eu......._.....,..a.,,.....m.........,
- . ~ .. . . - . _ . -
.. .i. ,. .
,s ,s-. p.
(10D71 This form IEOCOdolmey be cota ried from the Order D.pt.. ASPJE. 345 E. A 7:n St.. f9.w Yo,6. P..Y. 10017 pg
/ i (x /
Page 162
t l l l
.t I
r e l y.1 FORM N.2 (boek) Isems 4-8 laci. so be co.aplesed for single eall o es sels. jacket e of inckc,ted se ssels, or shells of heat eschaagers. I l Nominal Cweesien -' l Thickne s s_ ia. Alto.aace _ ia. Dia. _ ft. _ ia. L ength_ f t. in. j 4, % ell: Ma4een 1 _ T .S. (Khad a spec. Ne.) (Maa. et Rense SpecW6ee) l H .T.' Pg.T. Efficiency %
- 5. Seems: Leas Girth H.T.' R.T. No. of Cowse s T.S. (b) Material T.S.
- 6. Head s: (a) M aierial -
Cre Kauc h t. Estipete el Ceances He stopheetc al Flet Stde to Peese. a w.iion Redive Radle. R et ae Apee Aaste Rodne. Oteae* *e (Ceae. er ceae.) l (Top. messem ende) Thseka se (a) (b) If semoesble, boles used Other f asceaing (u.ieviet. s, e. N o.. T.S.. Sin. Nueiber) (Describe w ottuh ekeich) 7 Jacket Closure:t oe urtee .. esse sea weid.eee. eie, it me, st ee e..e.. eas. it boaied.4e seeine se eneien Drop Weight Charpy impact it.Ib
- 8. Design peessure a 1250 , ,; ,, 575 op ,,,,,,,,, o r l
Isees 9 and to to be completed for tube sections {
- 9. Tube Sheet s: Semionary. Material Dia. Thickne s s _ in. Ascachmens (Kima a spe., n..) (sunsas se p ee.we) teeteed. Besied)
Floating. Muerial Dia. Thickne s s _in. Attachment O.D. a n. Thickness a sese. Nienbee Type
- 10. Tubes: Material tsw. w in t
teema 11-14 incl. to be completed for inner c.hambers of jacketetl sessels. oc channels of hess enchangers.
~' '" ~'
* ~~
Novainal Corrosion ia. II. Shell: Material T.S. Dickness Ja. Allowance _in. Dia. _ ft. _ ia. Lenstit _ It. ; (K tad & Spes. Me.) (Min. er Rease Spectited) H.T.' R.T. Efficiency % l 12. Seems: Leas Girth H.T.' R.T. No. of Courses T.S. (b) Material T.S.
- 13. Heads i ) Material Ettapeteel C oate el Heseephaessel Flee s6de to Prese.
Creen Kaw rkle Red 6.. neue Apes Aasle R ed6we D6emetu (Cene. or Cone.) Lee se tea Thieknes. R.di.e (a) Top. bottom. cads (b) Chamael (b) (c) Other f astening If remoeable. botse used f a) coesume w eetwa emetent Drop teight . Charpy Impact f'*l b psi at *F at scrap. of *F 14 Design pressure' leems below to be completed for all sessels obere applacable. IS. Safety Valee Outlets: Number Site Loc ation
- 16. No n d e s:
R eind ere ement P wyeee italet. Thiehneee M **e esat How Asise%ed o.iies. pe e.as n enn o3.. = se s e T ype u.e ni .i 1 l 17. In spe c tion Menhole s. No. Size L oc asian i i Opensa g s: H eadhole s, N o. Size Loesoon Thseeded, No. 9e Loc asion _ -.._ l e g s .- - Other Arsached
- 18. Support s: Sh ire Leas _ ( M umiepe r) t De u rs be l d Where a Heet i V ee er Me) ( N umine r s O
REPORT NO. NP0059-0005
.,... 1B13-022 Sheet 3 of 3 Sheet 4 oi 2 FORM N.2 NPT CERTIFICATE 110LDERS' DATA REPORT FOR NUCLEAR PART AND APPURTENANCES
- i As required by the Provision of the AsME Code Rules. Section lit. Div. I ,f f, sjf '
- t. (a) Maa.f aciused by General Electric Company, Castle Hayne Rd., Wilminaten N.C. .
. u.a ene seem.. arr cmne. ween (b) Ms or.ciured foc General Electric Company, San Jose, California (NEBG)
- 2. Idenuncauon-Ceruficate Holder's Sertal No.of Part A5725 y,,,, 34, go, (a) Constructed According to Dsawing No. 768E514C001 Drawing Prepared by . . e ers n (b) Descripcion of Part 1.spected Control Rod Drive, Model #7RDB144DG001 l N207 N295 (c) Applicable ASME Code: Sectioe ll!, Editica 9 , Addenda date W'75 Case No. 1361-2 Clan. 1 1
- 1. Cap 166B9274P1 1 (167A2343)
SA182 - F316 Code t, eld y i 3/8 thick x 1 1/16 00 P50YP102 N ; _. ;-
. ! l 2 l l P'" 2. Indicato'r Pipe 166B9313P1 .
l SA312-TP316 . l 3/4 sch 40-seamless pipe N l l O.ll3 vall thickness * \ I
.065 max. cta. Reactor vessel i h'd ,
thimble l 1 I
- 3. Plug 159All76P1 l g I l SA182-F304 ' I L_ - "'
l ~~ 1/4 thick x 0.812 00 j
- 4. Flange 919D610P1 (719E474) Code weld !
.SA182-F304 ..P,50YP102 '
NN 3.37 thick x 9 5/8 00 neck 1 1/16 thick x 5.0 OD N
/ h\
. 2.875 ID / y
\
l 5. Base 137C5311P1 - ~ ' ' XH-19 ASME SA479 3.0 OD x .884 ID 7 f l , n f 6. Ring Flange 11485122P2 SA182-F304 Code weld l" thick x 5.0 00 x 1.75 ID P50YP102
- 7. Cap Screw ll?C4516P2 SA193-B6 C0flTROL ROD DRIVE DWG - 768E534 6 ca.1/2 dia. on 41/8 bolt circle l
- 8. Plug 175A7961P1
- 9. Nut 137c5934P1 2-19 SA479 ~
SA182-F304 1.30 thick x 2.62 dia,00264 0,38 thick x 1.307 dia. . O Page 163
REPC RT NO. NP0059-0005 1B13-023 h(% NIS-2/NR-1 OVNER'S REPORT FOR kEPAIRS OR REPLACEMENTS As required by the Provisions of the ASME Code Section XI PHPP No. 9308 Rev. 6/93
- 3. Owners Cleveland Electric Illuminating Company Date 3/27/96 P.O. Box 5000, Cleveland, Ohio 44108 Sheet 1 of 3
- 2. Plant Perry Nuclear Power Plant Unit One 10 Center Road, North Perry, Ohio 44081 W.O. 95-5188 R/0 (Repair Org., P.O. No., etc)
- 3. Vork Performed By: Cleveland Electric Illuminating Co. Type Code Symbol Stamp NR 10 Center Rd, North Perry, Ohio 44081 Authorization No. 33 Expiration Date 7/18/96
- 4. Identification of Systems 1B13 Reactor & Internals
- 5. (a) Applicable Construction Code: ASME Section III, NB , 1974 Edition Vinter 1975 Addenda, Code Case 1728, 1644-4 7 -272 13(,l-2 N-Ao7 w p ' x*A '
Wi$ (b) Applicable Edition of Section XI Utilized for Repairs or Replacements: 19 E Su-wr 1983 Addenda l ("] V
- 6. Identification of Components Repaired, Hodified, or Replacement Components 4
Name of Name of Manufacturer Nat. Other Year Repair ASME i Component Manufacturer Serial No. Board ID. Built Replacement Code No. or Modification Stamped I 1813 F1 ping General ' < System Electric IBf3 64077 D0008 1984 Replacement Yes i
- 7. Description of Work: Raplaced Control Rod Drive Mechanisms (CRDM) and 1" capscrews. See Remarks
- 8. Test Conducted: Bydrostatic- [ ] Pneumatic- [ ] Nominal Operating Pressure- [X]
Other- [ ] 175 degrees F Pressure 1038 psi Test Temperature G Page 164
i i l 1 NIS-2/NR-1 OVNER'S REPORT FOR REPAIRS OR RElLACEMENTS
~
J
- 9. Remarks: Installed a replacement CRDM in core locatinn 4 2-3 f S/N A5598 using (8) capscrews l"-8x5f"t Ig. ASME SA 540 Cr. B23 (8) He# 99896. _ ._
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 Ve certify that the statements in this report are correct and that all design, material and workmanship on this Replacement conforms to (repair, replacement, or modification) applicable section of the ASME Code. to use the 7/18/96 Certifica,4e of Auth rizatiojnto. 33 eQu LVu Gy sJamp eacp i resvtfre / Svere, r Signed f(Jn di W i1)n u V
d I
DateDi(LLulo 28(Ovner19 or 9(o Owner's Designe6 Title) CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the State or Province of OHIO and employed by *ARKVRIGHT MUTUAL INS. CO. of NORV00D, MA. have inspected the repair, modification or replacement described in this report on h eu 19 , s19 % , and state that to the best of my knowledge and belief, this repair, modification or replacement has been made or constructed in accordance with Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any varranty, expressed or implied, concerning the repair, modification or replacement 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 from or connected with this inspection. g,, Commissions 46em T coa-s
~/ md u' (Inspector's Signature) pfw es 68 19 %
- FACTORY HUTUAL ENG. ASSOC.
Date O \
REPORT NO. NP0059-0005
.-.--a.... :m --- ~ ~ ~ . -
yyye w.c. : . .. e , . , ,. Sheet 2 of 3 Sheet 1 of 2 I
\
FORM N.2 NPT CER11HCA1T HOLDER $* DATA REPORT FOR NUCLEAR PART AND APPURTENANCE 1* As required by the Provision of the ASME Code Rules. Section !!!, Div. l so j ' - g, (.3 u r.,r.,ed by General Electric Company, Castle Hayne Rd., Wilmington, N.C.
. nam. ans . ear m m c.caacm. ume n gy u a.,,,,,a go, General Electric Con:pany, San Jose, California (NEBG)
<m==. and amerim a a casaca. ame.r en :e.cs.ar = a
- 2. Idenstacauen Certincate Holder's Sertal No. of part A6698 Mes*1 Bd. No.
-(e) Ceneumeted Accordias so Deswiss No. Drawing Prepared by Control Rod Drive, Modal #7RDB144DG001 M D= 4 6 dPersla w d IMUl (c) App!! cable ASM E Codes Section H1. Edidos , Addendadeze W 5 , c ,,g ,, N-2 Cia 1 g, ,, Standard part for use with Reactor. Hydrostatically tested at 1820 pai.
to .t rwu .e , r- .ma.a .: . :.ee v
- Total number of sheets - 2 We cesdfy abacshe stessenesta made la chia are coneet and this eessel part er appareseence as derased la che Code coe.
sales of emeauncties of she ASME 5ection III. m femas ao che.m Denism (TheSpectScaties
===as. and semes liegers are act the rese.=amuty of the MPT Certinesse Holdee for parts. Aa NPT Caettf.
innse Heider for appenemances is respoensbie for forniskies a seperuse Desage P ""-" and Stress Sepast W the appurtensece is not tacta*H la the caesponeet Desism 5pectScattaa and Strums Report.) ru 8/26/ ggg gg,,a GE, NEPD.-M ,, . amar cweasmae umeer Certificase ed Amsberianden Empiree September 15. T981 Cerdficue of 'zulam No.
. CER'11FICAT10N OF DESIGN FOR APPURTENANCE (when oppilcable) o, gam idermaios as nie ., GE, NEPD-WMD-CA, Castle Hayne Rd. . Wilmincton. N.C.
22A5556, Rev. 2. 5 res. aaety.i. repen file n .GE, NEPD, San Jose, Calif. 22A4912, Rev. 2 , Deelse specificulose certified by B. N. Sridhar prol Eas.sta , Calif R,s.Neh830 scress eaalysis report cenified by B. N. Sridhar Ped. Eas. Seme Calif g,,,y,,18345 CER'11FICATE OF SHOP INSPECTION
- 1. she undersigned. holding a enlid comunission issued by the Naiseal Board of Boiler and Pressure Vesnel laspectors and/or the Sense or Proeiace of North Carolina and employed byDepartment of Labor
.g State of North Carolina be,e inspected she pers a a peeseere eesset described in this partial Data Report as 8/28/ tSN. and state that to toe best of my knowledge and belief. the NPT Ceruncate Holster has constructed this part in accordance with the ASME Code Sectica Ill.
By signing this certificase. neither the taspector nor his employer makes any warreary, expressed os implied. concern. les the part described in this Partial Data Report. Fu rthermore, setther the laspector nor his employer shall be liable in any maneet for say personal injun or properry damage or a loss of any kand erasang troen or connected wi' chis laspection. Due - 8/?6/ g9 81
*g Wg- ,
Commissions N.C. 723,PA.WC1766, OHIO MM3 we . s.... n . . si ..r . .- n - ;
".O.*":'l% '.*.*.*.7.".'::*. O*";.:*:"?" "' *"r:*."'. */ ::*/.!".~.;**.* ' " * ". *."./.'" * " ~"" "'*"-"* * "*" "' " ""*
O Page 165
. ,. m .. m. . r x,, . w a. . .. w o ,w. .
, - . ,S~ l FORM N.2 Nek) l
; r laems 4 g tact. so be complesed for single wall vessels inckets of jacke. sed vessels, or shells of hess eschengers.
w) l Nominal Corsosion !
- 4. Shell M at eris! Thi ss ia. Allow anc e _ia. Di- f t._ ia. Length _. fc. in.
(Kaas & Sp.e. N.T.5-.(tsia..i
.) n ige sp.ckne.4) eafa
- 5. Seems: Long H .T.' R.T. Efficiency 7.
Girth H.T.' R.T. No. of Courses *
.T.S. -
(b) Material T.S.
- 6. Heads: (a) Waserial c, Kaw ks. Essa,eae.s c m..a s4..a.,h.es .a ra s sa4. i. P .
L ms (T.p. m.nem. m.) Thien .. a.da.e a.da.. ama. A,.s Aas a. madau. ca m., (c . w c.ne.) (a) (b) If remoemble, bolse used Other fastenias (ns wi.a. Sp ss 7.s..Sim.. m ) (o.u,$m. ., sis n emmen)
- 7. Jackes Closares(p.. m. .. .s.. 4..is.mer. me. u == sa es . .. er m.ai.e. a.weite w . mens Drop Teight Charpy tempact f -lb 1250 ,,; ,, 575 og ,,,,,,,,, op S. Desigs pressere s teema 9 and to so be completed for tube sections
- 9. Tabe Sheets Sessionary. Macerial Dia. Thickness ia. Auschmenc (Kand & Spe.. N ) (S.m).et te pre..te.) (Weld.d. Bessed)
Floadas. Waserial Dia. Thickness _ia. Ascachmens O.D. la. Thickness '** sTs'.. Number Type
- 10. Tubes: Waterial (ser. ., un s Icess 11-14 incl. so be campleted for inner chambers of jacketed vessels, or chamaels of bene eschaagera.
. . . %,3 %,,
T.S. Thickmess _ la. Allownace is. Dia._ ft._la. Length _ft. in.
- 11. Shell Macerial (Kaas 4 59 . N..) (use. ed u.ase Sp.eaned)
- 12. Seems: Long H.T.* R.T. Efficiency %
Girth H.T.' R.T. No. of Courses T.S. (b) Maserial T.S.
- 13. Heads (a) Maserial Ean,ia.. c ac. es.m..,nwee na ram same se re..
ca Kawma. Leema.= Tnsen .. a .es.. . a.4aw a.u. Aees Aasa. anda.. ca meen (c . n ceae.) (a) Top, bottom, ends (b) Chamaet if removable, bois s used (a) (b) (c) Other f asseeiss < o..ene. ., seine n es.wn Orop Weighs . Charpy impace felb
'F me temp. of "F
- 14. Desiga pressuee' psi as isens below so be completed for all vessels where applicable, o
- 15. Safety Valve Outlets: Number Sise Location
- 16. Nessles: .
a.w ... m P we . < sas.t. u.e eetea H.. Act.ches owsm.or as Meine os = sie. T yp. u.ews.a Tsum ..
- 17. la specison M anhole s. No. Se ze Loc ation Openingts: Handhole s, No. Size Loc ation Thegeded, No. Sise Locanon 0 her . ^<* ached Ig. Support s: Sh set Luas Leas < o. .e ri me i 4th. 6 H..I
< y e. M.) a M. .i (n in.,i O l l
1 1 1
REPORT NO. NP0059-0005 l lL., __ _
/) ,
Sheet 3 of 3 Sheet 2 of 2 ( / FORM N 2 NPT CERT 1FICATE HOLDCRS' DATA REPORT FOR NUCLEAR PART AND APPURTENANCES
- As required by the Provision of the ASME Code Rules. Section !!!. thv.1 *
, v ema. !
l
- 1. (a) Man.factured by General Electric Company, Castle Hayne Rd.. Wilmington. N.C. '
theme and addr.as of MPT (se46cate He6 data (b) M-facmsed f, General Electric Company, San Josei California (NEBG) me e 44r .t a cauac = u.w.,an. ..: a.es <ame o
- 2. adeocacanan.cerencate Holder's Serial No. of Part A5598 y : 34, go, (a) Constructed AccoMag to Drawing No. 768 F*i'44 C001 Deswiss Prepared by (b) Descripsien ed Part to pec ,a Control Rod Drive, Model #7RDB144DG001 N207 (c) Applicable ASME Code: Sectica E1. Editios l974' . Addesdadase W'75 C. u 1361-2 C1... 1
- 1. Cap 166B9274P1 1 (167A2343)
SA182 - F316 Code held y N;._ 3/8 thick x 1 1/16 OD P50YP102 r N 2 l I
- 2. Indicator Pipe 166B9313P1 SA312-TP316 . l 7/4 sch 40-seamless pipe N l ;
/' 0.113 wall thickness * \
(S) 1.065 max. dia. Reactor vessel i . I thimble l : 1
- 3. Plug 159A1176P1 ; i l l SA182-F304 _ , i 1_
1/4 thick x 0.812 OD l l
@ l
- 4. Flange 9190610P1 (719E474)
.SA182-F304 Code weld
..B50YP102
)
I
' \
\N / h' 3.37 thick x 9 5/8 OD '
neck 1 1/16 thick x 5.0 OD 2.875 10
/ /\
2 4 g- h 'N
'5. Base 137C5311P1 '~
g 'A ' XM-19 ASME SA479 3.0 00 x .884 ID -
- 6. Ring Flange 114B5122P2 - b-SA182-F304 Code weld l" thick x 5.0 OD x 1.75 ID P50YP102
'. Cap Screw ll7C4516P2 SA193-B6 C0f1 TROL R00 DRIVE DWG - i68E534 6 ea.1/2 dia on 41/8 bolt circle
- 9. Nt 137C5934P1
- 8. Plug 175A7961P1 IM-19 SA479 ()C594 SA182-F304 1.30 thick x 2.62 dia.
g 0.38 thict x 1.307 dia. O Page 166
REPORT N3. NP0059-0005 IBl3-024 b) NIS-2/NR-1 OVNER'S REPORT POR REPAIRS OR REl'LACEMENTS As required by the Provisions of the ASME Code Section XI PNP" No. 9308 Rev. 6/93 Cleveland Electric Illuminating Company Date 3/27/96
- 1. Owners P.O. Box 5000, Cleveland, Ohio 44108 Sheet 1 of 3 I l
Perry Nuclear Power Plant Unit One l
- 2. Plant: l 10 Center Road, North Perry, Ohio 44081 W.O. 95-5189 R/0 l' (
(Repair Org., P.O. No., etc)
- 3. Vork Performed By: Cleveland Electric Illuminating Co. Type Code Symbol Stamp NR l
10 Center Rd, North Perrv, Ohio 44081 Authorization Fo. 33 l I Expiration Date 7/18/96
- 4. Identification of Systems 1B13 Reactor & Internals
- 5. (a) Applicable Construction Code: ASME Section III, NB , 19 1 Edition j Vinter 1975 Addenda, Code Case 1728, 1644 4, N-272 ,
N-2tn, I%l-7 LM+ Bjypt, N 3 "b) Applicable Edition of Section II Utilized for Repairs or Replacements: 1983_ Addenda j
~
Summer 1983 (T L ,l
- 6. Identification of Components Repaired, Hodified, or Replacement Components Name of Hanufacturer Nat. Other Year Repair ASME Name of Replacement Code Component Manufacturer Serial No. Board ID. Built No. or Modification Stamped Piping General - IBl3 IBl3 64077 00008 1984 Replacement Yes System Electric
- 7. Description of Work: Replaced Control Rod Drive Mechanisms (CRDM) and l" capscrews. See Remarks
- 8. Test Conducted: Hydrostatic- [ ] Pneumatic- [ ] Nominal Operating Pressure- [X]
Other- [ ] 175 degrees F Pressure 10 2 psi Test Temperature
,e 'L)
Page 167
l NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REP!ACEMENTS O s.
.h
- 9. Remarks: Installed a replacement CRDM in core location 30-23 S/N A4674 using (8) capscrews I"-8x53" 1 Ig. ASME SA 540 Cr. B23 (8) Hti 61811.
I 1 NOTE: Attach all applicable Hanufacturer'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 COMP 1.IANCE Ve certify that the statements in this report are correct and that all design, material and workmanship on this Replacement conforms to (repair, replacement, or modification) applicable section of the ASME Code. 33 to use the NR stamp expires 7/18/96 CertificateofAutho)pafionNo. r Signed /n 5/suld [(1swmW Guafx& GWtner-- N,, Date )MMt1 2f(Ovac~ 19 or 9Ovner's (o 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 certificate of competency issued by the State or Province of OBIO and employed by *ARKVRIGHT MUTUAL INS. CO. of NORV00D, MA. have inspected the repair, modification or replacement described in this report on Auc4 od , s19 9(., , and state that to the best of my knowledge and belief, this repair, modification or replacement has been made or constructed in accordance with Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any varranty, expressed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage o a1 s of any d from or connected with this inspection.
, Commissions Lf eSca r 2%% ,
(In'spector's Signature) Date ,e/w c t. ,pe 19 94
- FACTORY MUTUAL ENG. ASSOC.
i O1 l
REPORT NO. NP0059-0005 IB M2' Sheet 1 of 2
. Sheet 2 of 3 O) FORM N.2 NPT CERTIFICATE HOLDERS' DATA REPORT FOR NUCLEAR PART AND APPt'RTENA.NCES*
As required by the Provisaon of the ASME Code Rules. Section !!!. Div.1 i General Electric Company, Castle Hayne Rd.. Wilmington. N.C. g, g,3 g,,,g.,,,,,a g m.m..a enrycea..w a g g ,g g g , General Electric Cocoany. San Jose, California ore 2G) us a.e ame,.w w cmnen. a., sw 6 e me ,e u A4674 g ,,1 Bd. No.
- 2. Idenuncattep CaruAcase Holder's Sertal No. cd Part D. L. Peterson Drawing Prepared by (a) Camorrected Accordias em Desen.es No. 768E534G001 Control Rod Drive. Modal 77RDB144DG001 (ba Descripdos 4 para gas % N4V/
1361-2 c,,, 1 (c) Applicable AS4E Code: Saetion Hl. Edicina I974 . Addede das, W'75 , c,,, 3,, g ,, Standard part for use with Reactor. Hydrostatically casted at 1820 psi. tan.s nou w ==. s u.a .- _ : . .e .
- Total number of sheets - 2 Te comfy chas the statsuneata made la sia are correct and chie vessel part or appartenance se defined is che Code coa.
feams se abe rules of conseractima el 6e AS4E Sectica III. (The aeotacabse Dessan Specincanos and stres Repoet are nos the ressoastbtlity of the NPT Certtitcase Hoeder for parts. An NPT Cerut. icass Hoeder for appurtennaces is respoembee for furasshins a separnas Desssa $pecifkasica ami Stress Report af the appurteenacs e act tactuded to the cosioonens Destan Speecanina and Stress Resort.3 7/23 GZ. NEPD-WD-QA g, ,f
,,,, g 81 $;,g mercmonessees n G MMU certificace 4 Aedierizacima Espires September 15. 1981 c,,,ig;,,,, ,4 ,,n ,g2,,;,, 3.,
CER'IIRCNITON OF DESGN FOR APPURTENANCE Men oppilcable) GE. NEPD-WD-QA. Cascia Hayne Rd. . Wilmington. N.C. p ,,; ,;,, , ,, g , 22A5356, Rev. P scress analysis repari oa nta as GZ. NEPD-WD-CA. Castle Ravne Rd.. Wilmington. N.C. 22A4912. Rav. 2 ges,3.J8345 Desism speci!1casimas emitied by 3. N. Sridhar Pvd.Eas.5 casec 411' seese amanysis ;ma emitted by B. N. Sridhar p,a, g,,,3,,,, Calif g,,, 3.,13 34 5 CERTIMCATE OF 5 HOP INSPECTION .
- 1. the vadersissed. holdies a valid coeuniasion issued by the Nacional Board of Boiler and Presmare Vessel taspectors and/or the Senee or Peoetece d North Carolina - and e.aptoyed by0eoarrnant of Labor og State of North Carolina have laspected the part of a peessare eesnt described is chas ParnaJ Date 8tspart ao 7/23 ig31,3 4 state tha to me mes or as knowt eae and beinef. tas MPf Certtacate Hwier itsJ constriscted Lats part la accordance wtth the ASME Code Section III.
By signias chia certificare. eeislier the lasswesor noe liis employer asses any waaramry, espressed or iamplied. concern-tas the p art Gesc ribed la this Partial Da ta Report. Fu rth ertsgre . Seither the f aspector nor lits ersployer ] shall be liable in say mamaev for any personal istury or property daciage or a loss of any had arasang from or ceanected mth chas taspection. Case n . - - 7/23 39 81 N.C. 723,PA.WCU66, OHIO l
, / /
d C.ieumiasion s ,...s...--..- j t . s.v r,..1...~. h<
........._.m......._.........
n, .<, .mo.o% e, m.n ,ome c o,. :.ct .rsue-we@ st. w% u icci-
.can O
! l V' Page 168
FORM 2 Neu items 4-4 las t, ao be completed fee single wall vessels, iaches s of sacketed e ssels. ee heH s of hem eschangees. Nonse64 Caecessen
- 4. Shell: M ueenal _, _. Thickne ss_ in. Alle=ance ia. 04- fi. .a. Leagch _ fe. ;..
(Kame a se _.3
.M.T.S.(tana. 8 R g* seesineet S. Sesem Long H.T.' R. T. Eificiency .
Girik H.T.' R.T. No. of Cowses
- 6. Heada ( s) W esenal T S. (b) Matenat T.S.
L ca a Kawh&e E!!6eucal C oeu.4 H.eusa.nese rise $6de to p,.ea, gt.o. m e se Tu. e. a.es.. m.ea.. e ase 4e.. anew a.esu 06 w gc . . c 3 (al = (b) If renewable. bedes esed Othee f aseeming assa.,ina. se n T.a.. sia.. n e < o.w,sm. au.ea . .no
?. Jacket Closuses t o. ne. .. .. ...e. .e. . 4s mer s. eam .. .. 4 m==.e. a. nn. .r .. ean Oreg Weighs i Chacpy isspect _ fi.ib '
s 1250 ,,; , 375 e, ,,,,,,, e,
- 8. Desi ta Presseee Iseas 9 and 10 se be completed les tube sections
- 9. T.be Sheet s: $sesiemary. Masers =8 Dia. Thickness in. Anachmens cameas, .se.3 cs , s ie s .. co.a ses..e i
Fleeries. Maserial Dia. Thickness _ la. Attachment j
- 10. Tubes: Masen al O.D. in. Thicknes s ""sTle. Number Type (
(Ser. .e VI I Icess 11-44 iact. se be completed for inser ch embers el iacksted vessels, se chamaets of bees eschaagees. Mominal Corvenes sa. Dis. f t._ia. Leesch !. ja. ll. Shell Masetial T.$. nickness J. Allownace l (unas a se e. se.3 (use. es e.g.se .swas l O1
- 12. Seems: Lon g H.T.' R.T. Efficiency -.
Garth H.T.* R.T. No. el Cow se s 1 i T.S. tbs uaserial T.S.
- 13. Heeds (as Weserisk ries swe se P,.ea.
cc u..wme sas .eu can u .en.ne.a ou ., cc . n ceae.> I s es.. Twen .. a a. . am.e me. 4 .. a.saw 1 (as Top. be<som, ends _ ibe Cheesel 1 ( b) (c) Other f assening ( if removable. belas used (al o...n e w ..ea . .no l Deep Teigha . j Charpy impact it.4 b j 8 F u seme. of 'F 14 Desete pre samte' psi as leems wiew to w compieted fee all vessels .nere applicaWo.
- 1. Saies, val e Owstecc Numbee use Lac unea
- 16. Nosaje s:
s ...e ee....no Pwe.ee . lawe, as es ene Me. ast.eaee Dia. .e s6se Tree tasseries Thie nee e s Cisa tee. Demas Nis.ew l* !a s pe c tion M annoie s. N o. 4s s e L ac etion Opensa g s: H andhele s. N o. 5 4e L ac unea Thre see d. No. $.se Lecanoa O'ner suac'ned.
'8. Suppetisi Shire Less Less_ se . . . - -
. m ,s...
v . me w.i w. .. 3. . p., .. _._
.y .
....-....e.
O
REPSRT NO. NP0059-0005
. 1B 13 -024 Sheet 2 of 2 O '
FORM N 2 NPT CERTIFICATE HOLDERS' DATA R Pob ObCLEAR PART AND APPt'RTENANCES* As required by the Provision of the ASME Code Rules. Section Ill. Div. I
- 1. (a) Mandae wed by General Electric Company, Castle Hayne Rd., Wilmington. N.C. l (b) Mamfacewed foe General Electric Company, San Jose. California (NEBG)
- neckere 2
- 2. Idestmcation-Certmcate Holdef's SertalNo.of Part A4674 N an't Bd. No.
76A m 4 con 1 Drawiss Prepared by . . e M son (a) Cassanseced According to Drawing No. (b) Description of Pass taspected Control Rod Drive, Model #7RDB144DG001 N207 (c) Applicable ASME Cadet Section UI. Edition 1974 . Addendedme U'79 . Case No. 1361-2 ca... 1
- 1. Cap 166B9274P1 1 l
(167A2343) SA182 - F316 Code held y 3/8 thick x 1 1/16 00 P50YP102
, N ; ._ ;-
- 2. Indicator Pipe 166B9313P1 @ '
6 SA312-TP316 *
\
l 3/4 sch 40-seamless pipe l 0.113 uali thf ekness - '
\ l 1.065 max. dia. Reactor vessel O e .
- I thimble l I V 3. Plug 159A1176P1 { g i I SA182-F304 ._ , i L __
1/4 thick x 0.812 00 l l
@ l
- 4. Flange 919D610P1 (719E474)
.SA182-F304 Code weld *
..B50YP102 '
)
NN I
' \ l 3.37 thick x 9 5/8 OD \ f 1 neck 1 1/16 thick x 5.0 00 2.875 ID
/ \
_i
\
- 5. Base 137C5311P1 @_u (O , ,
'\ ,
XM-19 ASME SA479 i 3.0 00 x .884 ID '{ , l
-:I
- 6. Ring Flange 11485122P2 SA182-F304 Code weld 1" thick x 5.0 00 x 1.75 ID P50YP102
- 7. Cap Screw 117C4516P2 5A192-B6 CONTROL R00 DRIVE OWG - 768E534 6 ea.1/2 dia. on 41/8 bolt circle
- 8. Plug F 961P1
~
- 9. Wt 137C5934M 5A182-do, 2-19 SA479 1.30 m e x 2.62 da.
0.38 thicx x 1.307 dia. . O Page 169
REPORT NO. NP0059-0005 1B13-025 g NIS-2/NR-1 OVNER'S REPORT FOR REPAIRS OR REPLACEMENTS As required by the Provisions of the ASME Code Section XI PHpo No. 9308 Rev. 6/93
- 5. Owners Cleveland Electric Illuminating Company Date 3/27/96 P.O. Box 5000, Cleveland, Ohio 44108 Sheet 1 of 3
- 2. Plants Perry Nuclear Power Plant Unit One 10 Center Road, North Perry, Ohio 44081 W.O. 95-5190 R/0 (Repair Org., P.O. No., etc)
- 3. Vork Performed By: Cleveland Electric Illuminating Co. Type Code Symbol Stamp NP 10 Center Rd, North Perry, Ohio 44081 Authorization No. 33 Expiration Date 7/18/96
- 4. Identification of Systems 1B13 Reactor & Internals
- 5. (a) Applicable Construction Code: ASME Section III, NB , 1971 Edition Vinter 1975 Addenda, Code Case 1728, 1644-4, N-272 N-7_ch l'e44-3 ht:A 54s/gr.
'b) Applicable Edition of Section II Utilized for Repairs or Replacements: 19 E Summer 1983 Addenda O>
- 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 '
. IBl3 System Electric 1B13 64077 D0008 1984 Replacement Yes 4
- 7. Description of Vork: Replaced Control Rod Drive Mechanisms (CRDH) and 1" capscrews. See Remarks
- 8. Test Conducted: Hydrostatic- [ ] Pneumatic- [ ] Nominal Operatit.g Pressure- [X)
Other- [ ] 175 degrees F Pressure 1038 psi Test Temperature O V , l Page 170
i NIS-2/NR-1 OVNER'S REPORT FOR REPAIRS OR REPIACEMENTS J l
- 9. Remarks: Installed a replacement CRDM in core location 22-51 S/N A4536 usine I
(8) capscrews !"-8x5%" ig. ASME SA 540 Gr. B23 (8) Ht# 618 ll, 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 Ve certify that the statements in this report are correct and that all design, material and workmanship on this Replacement conforms to (repair, replacement, or modification) applicable section of the ASME Code. 33 to use the NR stamp expires 7/18/96 CertificatA of 4ut of zption i No. Signed L{pau',f . &b/ ,Qud h % usa u Q Date Tn2tM k_ ' 8d.(Owner 19'10or Svner's Designed. Title) CERTIFICATE OF INSERVICE DISPECTION i I, the undersigned, holding a valid commission issued by the National Board of l Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the State or Province of OHIO and employed by *ARKVRIGifT MUTUAL INS. CO. of NORV00D, MA. have inspected the repair, modification or replacement described in this report on h e/i G8 ,s19% , and state that to the best of my knowledge and belief, this repair, modification or replacement has been made or constructed in accordance with Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the repair, modification or replacement described in this report. Furthermote, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a sofanykAndfromorconnectedwiththisinspection. g ce,.s
./ U_ Commissions diB E 'I T 7 (Inspector's Signature)
Date awa, c n o 19 M
- FACTORY MUTUAL ENG. ASSOC.
t O
REPORT NO. NP0059-0005 IB13-025 Shee: 1 of 2 Sheet 2 of 3 /64 / ' f O FDRM N 2 NPT CERTD1CATE HOLDERS
- DATA REPORT FOR NUCLEAR PART AND APPt;RTENANCES*
As required by the Provision of'the ASME Code Rules. Secton Ill. Div. l
.=
(. was lacmed by General Electric Coumany. Castle Hayne Rd. . Wi%gton. N.C. m.m. .a m. w art c,rnam. . (g u.a.m,ed f., General Electric Con:nany. San Jose. California (NE3G) ima e =mc.cnnem es.,e n.e ci..r. m
- 2. Idannocamen-Ceritacase Holder's Serial No. ct Part A4536 y ,,g 34, 3, (a) '" T =4 Acceeding to Drawing .%. Deswing Prepared by
* * * *#'"U (4 Desenpa.an el Pan taspected Control Rod Drive Model #7EDB144DG001 d4U/
(c) Appucable ASME Codet Secties W. Edidae 1974
. N adue *# 75 , g,, g,,
N -2 c!,,, 1 gg Standard part for use with Reactor. 'dydrostatically casted at 1820 psi. t an* u . s . . . . ..s > l l
- Total nunber of sheets - 2 Ve certify chescbc sensmensa made in shie rooers ano correct and this vesset part er appurtesance as deis'eed la che Code coe.
fosse se ener tales of -onemuction ed the ASME Code Section !!!. (The asesseneae Desarra Spee Gession and Strees Resort are not the ressensibility of the NP1' Certinesse Holder for parts. An NPT Certif. icasa. Hodder for appurtemasses is rusoeenshie for Aarmaanes a seperuse Desige Specidcasion and Stress Aepart d the appurteenace is act tactuded ta the componens Dessais SpectAcattee ame Stress Report.)
, 12/30 g, 80 $g,4 CE, NEPD-WfD-QA .
37 g ,,,,,c,,,,,,,,. 7, , Carcifiesse of Aacheriassion Empires June 16, 1981 NPT N-1151 Certificace of Ausherizacion No. CERTIFICAt0N OF DESGN FOR APPURTENANCE (when epplicable) _g GE, NEPD-Q'3-QA, Castia Hayne Rd. , Wilmington, N.C. 2215536, Rev. 1 5 re.. analysis report om file u CE. NE?D-Q'D-CA. Castle Eavrie Rd. . Wilminston. N.C. 2h4912, Rev. 2 , Desism specificacioes cenilled by 3. N. Sridhar Peel. Eag. 5:ss eCali' ges.Nej.3343 Scress analysis repen eenified b, 3. N. Sridhar P rol. Ea s. 5: ace Calif 3,,,3.,18345 CERIFICATE OF 5 HOP INSPECTION l
- l. the undersigned. holding a valid co-mission lasued by the Nacional Board of Soiler and Pressure Vessel taspectors I and/or the $ case or pro,ince og North Carolina and employed byDecar nant of La*cor l et State of North Carolina have inspected the part "of a pressure vessel described in this Parttai Data .'tesort ca 12/30 i, _80and state that to me ness ur iny knowiecae l ans bettet. une NFl* Cerencate Hoaaer nas consmacted ws part in accorcance with the ASMt' Code Seenon 111. i By signass this coettficmae. eesehet tae Isspectos not his caelovet maaes any warv.afy. espressed or implied, concern. .
los the p a rt desert bed to t Da Repo ! ta.a,.,, o,r,t.,,,Fu
-y m.aoer ,his Partialoe .a, ,e,,oan u es.e enr,t h .,neither r.more ,a os.othe, ins.pec.
m u . tor .m.no,r,o.'lls-empl0Fe.r
- ->e
.n.a
.. . mw s .u. .,ie.,,o is ;
. ..e l'!/ 30 ., SO 1
N.C. CS7,FAWC2711 . t Canuna s a toe s , i p. .- . s.e ... ,..~a..a....~...,.. .
.n....;.,.... v0130
.~......_-.c.................,.._.....a..,....<.
.....:.,- m -
( . . . . . . .~ . ~ . . Page 171
FORM %2 (beeb leems a4 lac t. se be compteved for s asie = all ves set s, . ackee s of s acketes ve s set s. oe nells of hens eschaage,s. Nomsas! Carrossen T.S. Allem ance ia. Os a. f t. ea. L en gth ,,,,, (c. i.,
- 4. 9 ell: M es een al _ .e a..g.Thic.hae.e.s_
s,. iti s in. y ( Kane s se.e. s. 3 tua R.T. Efficiency a. S. Se sa s: Lea s __ H .T. ' Gi,ih H .T.' R.T. No. of Cow se s T.S. (b) Material T.S.
- 6. Heads: ( al waaerial F t.e s64. e . p, .., .
Ct.we Es.m u. t 846eue.a C.wa el H.ea.ea.et. 4 t, e.o.e m.ein os w gc .. c ,3 l (T.,. m.n . ene t Thsama.u am.e n.sa a 4,. 4.sie i ( si (b) Othee fasicaing If reme.able. bolts esed s. T.s.. saw. N , to. u nn. ., a . ca s u.e.n.a. se. Jacket Clos <et(o.un ...... e.. ...,. ..u==si . .. ...am.a...a. nn. .....m Orog feesh Chaspy Ispect f e.4 b 1230 , ,; , 575 _., ,,,,,,,, o,
- s. cesign pres <,e teems 9 and to to be completed for :=be sections
- 9. Tube Sheees Sessionary. Wasevial Dia. Thickne s s _ in. Ass achmens c u ,... .. ... no so .se e. smi.e tswas,.s Dia. Aus scheese Flossias. Wasevial . Th.i.ckne a s s _ ia.
- in. Thickne s s - ses.. Nwebee Type l
- 10. Tubes: Waterial O.D. tsar, w in I
teems Il-L4 inct. to be coespleted fee inner chambers of iacketed .essels, or channels of hese enchaegets. Nomenal Cearesion is. Dia._ f s._la. Length fs.
- 11. 5hett: Material T.S. Thienness aa. Allow anc e _ a.
cKame a se .s 3 cas6 .a a.ne senstieet R.T. - Efficiency -". I? Sea, ass Leas H.T.' H.T.* R.T. No of Cowses Giach T.S. ibe Materiet - T.S.
!!. Heads ( al Macevial sees to Pt..
E a.eue.i c.= w et n..ea.nese F1.i ci Km.eu. (c . , c ae.) a.no aa i. n .es.. Si iw L .ai Tn. amu a m.a 24. 4.. (as Top, bestem. ends
'biChamaet (c) 0<ner f astening _
if resse.sble. belts esed (al .be o. eine w .n u a ...e e n e Deo, feight Charpy Impact (8-4 b
# 'F t a. De si gn pre s s.te ' psi u F ,as tems. of items ' sele = to se comoieted ies att ves sels =neee applicaele.
s.ae Loc auen M. S eiev, vai.e 0.stes s: N maer M. No az.le s: a .. .v .e. .. 7.re.ee lase. 'w.., rin.. . . . w . ,, u .. anua..
- w. s. , sia, r,,,
sw . s. ..
." la s pe c tion M ennene s, N o. 45 ac L x 6oon Openin g s: ri aaehole s. No. Siae Leenoen Thressee. No. Yise L oc av ion f Lass i egs @ nee - Ass a.c acd .., _ ._ei m a...
.9. 3.pport s: ih e re * . . . g.. 2..e. . -f . - -
v..-w..
*8 :s e. .. .. .. . t . .
m . .. . .e
.s a m . . . s ,. . .. . . .
6 . O
REPORT NO. NP0059-0005 1B13-025 Sheet 3 of 3 Sheet 2 of 2 ,.
/]
V FORM N 2 NPT CER11FICATE HO!.DERS* DATA REPORT FOR NUCLEAR PART AND api'1.!RTENANCES* As required by the Provmon of the ASME Code Rules. Section !!! Div. I
!/#'
g g u ,. lac m ed by General Elecerte Comuany, Castle Havna Rd., Wilmington, N.C.
.- f, (b) w=f-d f c General Electric Ccmoany, San Jose. Califorula (NE3C)'
in e, m c,3saw n c s.,e .wwe ci.., l 2 Maa"Me*Weruncate Holder's Serial No.otPart A4536 y.,, ga,, 3,, (a) Casserneted Acceedias to Drawiss No. 74ATMtennt Dr ; , prep.,ed by . L. Peterson (b) Descried e of Past taspecrea Control Rod Drive. Model #7RDB144DC001 N207
~ (c) Applicable ASM E Cede: Section ni. Edidee 19I0 . Addeedsdace N'75 Cam No. 1361-2 Clu s 1
* ~
T. Cap 16639274P1 1 (167A2343) SA182 - F316 Code weld y 3/8 thick x 1 1/16 OD P.50YP102
, 1 N _,-
I
- 2. Indicator Pipe 166B9313P1 j I 6 SA312-TP316 . g N
l 3/4 sch 40-seamless pipe 0.113 vall thickness
- l \ I 1.065 max. dia. 1 Reactor vessel l i I
f 1 thimble l , I V 3. Plug 159A1176P1 ; , I l SA182-F304 i 1/4 thick x 0.812 00
~
L_ ~ '
- l l
- 4. Flange 91SD610P1 (719E474) Code weld i i !
.SA182-F304 ' '
.850YP102 NN 3.37 thick x 9 5/8 00 neck 1 1/16 thick x 5.0 00 N
\
. 2.875 ID N __'g
/_ ,
Oy d'N
- 5. Base 137C5311P1 M4 XM-19 ASME SA479 /^ ~
3.0 00 x .884 ID 4d '
..j T
- 6. Ring Flange 11485H2P2
~
SA182-F3C4 Code weld a 1" thick x 5.0 00 x 1.75 ID P50YPIC2
- 7. Cap Screw 117C4516P2 SA193-86 CCt:TRCL RCD ORI'/E 6 ea.1/2 dia on 41/8 bol: circle CWG - 768E534
- 8. Plug 175A7951P1
- 9. :tue mc5924P1 U~19 SA'79 SA132-7304
.. 2. W .a.
0.38 thicx x 1.207 dia. . ,
- . 00131
.3 N.
Page 172
REPORT NO. NP0059-0005 h 1B13-026 NIS-2 Met-1 OWNER'S REPORT POR RRPAIRS OR RRPIACEMENTS As required by the Provisions of the ASME Code Section XI Pt'*' No. 9308 Rev. 6/93 ,
- 5. Owner: Cleveland Electric Illuminating Company Date 3/27/96 P.O. Box 5000, Cleveland, Ohio 44108 Sheet 1 of 3 2f Plants Perry Nuclear Power Plant Unit One 10 Center Road, North Perry, Ohio 44081 W.O. 95-5191 R/0 (Repair Org., P.O. No., etc)
- 3. Vork Performed By: Cleveland Electric Illuminating Co. Type Code Symbol Stamp NR 10 Center Rd, North Perry, Ohio 44081 Authorization No. 33 Expiration Date 7/18/96
- 4. Identification of System: 1B13 Reactor & Internals
- 5. (a) Applicable Construction Code: ASME Section III, NB , 1974 Edition Vinter 1975 Addenda, Code case 1728, 1644-4 7 -272.
N.301 / Stat =2. EXA Sf6f% 6
'b) Applicable Edition of Section II Utilized for Repairs or Replacements: 1981 Summer 1983 Addenda
- 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 raping General '
. 1B13 System Electric 1B13 64077 D0008 1984 Replacement Yes
- s
- 7. Description of Vork: Replaced Control Rod Drive Mechanisms (CRDM) and l" capscrews. See Remarks
- 8. Test Conducted: Hydrostatic- [ ] Pneumatic- [ ] Nominal Operating Pressure- [X]
Other- [ ] 175 degrees F Pressure 1038 psi Test Temperature O Page 173
I l NIS-2/NR-1 OVNER'S REPORT FOR REPAIRS OR REPLACEMENTS I T l s# i
- 9. Remarks: Installed a replacement CRDM in core location 46-51 S/N A5225 usine (8) capscrews !"-8x5%" 1R. ASME SA 540 Cr. B23 (8) Ht# 99896.
l l HOTE: 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 Ve certify that the statements in this report are correct and that all design, material and workmanship on this Replacement conforms to ' N (repair, replacement, or modification) applicable section of the ASME Code. 33 to use the NR sjamp. expires 7/18/96 Cer;ificapofAjuhpr4zatio Signed Ahud// (4 h (9mt/ dst det/id fWMMs i Owner or Owner's De/ignee, Title)# Date / 19 T(p CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the State or Province of OHIO and employed by *ARKVRIGIIT HUTUAL INS. CO. of NORV00D, MA. have inspected the repair, modification or replacement described in this report on %6 ;Hy ,s19 % , and state that to the best of my knowledge and belief, this repair, modification or replacement has been made or constructed in accordance with Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the repair, modification or replacement 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 19 gs of any nd from or connected with this inspection. m Commissions /4 6fc3 _r co .nu.
M)/% - Date (Inspector's 4Ar og Signature)Q; 19
- FACTORY MUTUAL ENG. ASSOC.
1 1 I l l 9
REPORT NO. NPOO59-0005 _ ~. . . . ~. IB l 3-02's sh,ee 1 og ;
.
- Sheet 2 of 3 FOR.%f N 2 NFT CERTIFICATE HOLDERS
- DATA REPORT FO4 NUCLE.AR PAR"I* AND APPtlRTENANCFP As required by the Provision of the ASME Code Rules. Section 111. Div. I J l
g General Electric Company, Castle Ha ne Rd., Wilmington. N.C. g, g ,3 y,,,,,,,,,,4 u .es m e c,ea. n General Electric Courpany, San JoJe , California (N'23G) l (bi wasadacmeed tec meaneseese nac.ree. een. ,-_ l 2, heeWortiacate Needer's sortal No. W Part A9 m g, g ag, y,, , (a) Comanessed According en Deseinj No. Deswing Prepared h Control Rod Drive, Model #71DB144DG001 ; g,_ ,_g,, NZU/
~
(c) App!!eshes ASM E Cades Seetsen G1. Edision 1974 . , 444,,4,4,,, W'75' . Case No. Class Standard part for use with Rasctor. Hydrostatically tested at 1820 pai. Ianer 1 - _ - = m ser.e . e . . e e .
- Total number of sheets - 2 l
l ese emmeet and dita eesent peer er appenseence as dedised la she Caes e ! Te eenUy shesche esessenese ende le shie 1 lemma as sh Seedse III. (The -a.e sales ed eenemmeden ed she AStE=aaa Desess seestesamen and saves assen ase ens me el a seserses Denism spendennes sad Serens Report d es appunesamme is nas ismas Needer ter appunemasses is remeessites far tartmese in me casassases cessea *=a-== and assen.a 7/24 3 81 ggy,4 GE. 3EPD- 6 ,, ; . , .
-, c.r.a -
##T ~l 51 .I Consticese ed Anaheriamaism Espines Seotember 15. 1981 Canulcase d . " --." N.,
I CER11 FICA 110N OF DESGN F1)R APPUR11[ NANCE (when applicable) { GE, NEPD-14tD-QA, Castia Hayne Rd., Wilmington, 3.C. Desien iedernesses en file = 22A5556, Rev. & Serese amearete repen se file a GT. NEPD-WMD-CA. Castia Havne Rd. W4 W rton. N.C. 22A4912 Rev. 2 Design speedicadene eersified w B. N. Sridhar ' Pvd. Eas. Same Calif Res.NeJS345 Seese assersie repen eenitied by B. N. Sridhar Pvd. Eas. ss aie Calif g,,,3 ,18343 CER11MCATE OF F*.DP INSPECTION 1 the undersigned he4 ding a entid cesamission leased by the Nasissal Seend el Seiler and Preemme Vessel taspectare and/se che Sense se Province og North Carolina _ ,,g ,,,4,,,4 y Department of I. abor es State of North Carolina b .e ses described la ches Iyee N inspected she pani ed state 19b and a paeseen that to the best at my taowledee permai Osta Resert en and bettet. Se NPT Cereacase Needer tes ceassscled ets eart La accereence wie me A8nsE Code Secues III.
- Sy siensas diis certificase, seisher ee loopeeser see his employer sehes any ensresey. espressed er implies, conceen.
les the eart deserthed Le this perttel Data sepert. Furttermore, settner the lasseetor nor his emonorer ' shall be wish chis }sospectaan.&ehle is any meneer for any personal intasy er property damage er a less et eay knee er) I
"" 7/24
- 81 N.C. 723,PA.WC1766, OHIO
...s.-
r." sei . . s m e. .. r- . w.. g .
.n . . e . m . n . . a .: -.
=
.C. . . . . .
nomi n.. ,o, icooom , e. es a 4, e.c,o, o.oc. .eue-WMs.. w w. v.y scos-Page 174
FORM N.2 f becu teens 4-4 lace, is be co ,seiee fee siaste .ait .e sets. eket s ei susced .e sset s, en .hetis ed bem enchangees.
%=..as Cene..en in. Ane.ance .a. o. _ fe._ ... Leasch fs. .e.
- 4. %48: w u enat _
< aa e a_.a <ui .e se . n.T.5. u.as.Th s . c.han iswo is
- 1. Seems: Long H.T.' R.T. Efficicacy .
H.T.' R.T. No. el Cowses Gint T.S. (b) Waterial T .S.
- 6. Heads: Ial Weserial rios sae. e p,..
c, s=waae attaesse.a c ae.a H. 4.ea. .a Lm mesa Da w (c . c.w.
- e. Thasta... Eses a.es m a a. a, s Anqu cf.e.m.n.m.
( al (b) . If resseeable, boses es4 Other f aseenies to.une. . .. a . e ans n.a. se. m t.s..s6... p mus
..s... ..Isw =4m ..sm c.e.4. ne.w.. .m
?. J ackee Cleomeet<o. n .. .. 0,9 se gh.
r Charpy Isap.cs f 4b n 1250 ,,; , 575 *F as sw of *F
- 4. Desism peesemee taeus 9 and to to be e aplesed fee sube sections
- 9. Tube Shenas 54asionary. Waseeial Dia. Thickne s s _ is. Attachmen te.ee.e. sme.e
<s e a se . s : < s..,me i. e ..,e.e Flearin g. Mesevisa Dia. Thickness ia. Attachmens in. Thickness _ '"s"*s'.. .Wabee Type l
- 10. Tebes: Maseeist 0 D. tver. n vi l Isees 11 t4 incl. te be completed Ice isaee chanisees ei jacketed .essels, er chamaets el bens eschaagees.
we.imai Cene si.e la. it. Sheit Maseeial T.S. Thackeess ia. Atte=aace _ua. Di n. _ f r._ia. L es sca _ ft. cxnas a se.e. no.: Esta .a aans.se...twe H.T.' R.T. Efficaeacy *1
- 12. Seassa Less 1
1 H.T.' R.T. No. el Cear se s Girth T.S. ib) %aseena! T.S.
- 11. Hesda (as Maseeial c w.a .ea.ne.a Fres same ee Pe..
c, s emie su.euen is w (ca . se c s.: sm Ae. 4asse R .m.. 36 Laas Tsues .. m eeve a ssa (at Tee, beeton, ends l
- bl Chemmet (ci canee f asteneng _
il remeeable. botto used (a) (b) o. no,w.n=a en Deep Teight (*hsepy lapset f >4 b sy ,,,,,,,,g sp to. Design pressvee n ,,,,, teems bete
- is be compieted fee all vessels neee appliesete.
!*. Iaiety Val.e Owtet:: %= be, Sise Lx suon IG. Nosale ss m ..e er.. at Pweee .laaet, nes p.se w es teses M astethee 3.na e.3r as 's e.e 3.a. .e sea, Tree ts scsaa l
I. i
*. laspection 54 sanese s, No. 44 L ac saion Openin g s: M amehene s. N o. Site Lec assea Threseed. No. 5.se_ Loc as.ee Lass Less
- nee _ - - -
;9. 5.,, ort sa Sk.ee g. s, .. me :)..ev . s.f98t, a.c
' *4*d * =. m es.e e - . - ve.
b % f ..
* * } ps e. se -s .
u - .. - - ..... .
?
9
REPCRT N3. NP0059-0005 m . 1B13-026 Sheet 2 of 2 / V' >.[' )
/ / Sheet 3 of 3 (j\ FORM N-2 NPT CERTIFICATE hot.DERS' DATA REPORT FOR NUCLEAR PART AND APPORTENANCES*
As required by the Provision of the ASME Code Rules. Section lit. Div. I
- 1. (e) Maadectured by General Electric Company, Castle Hayne Rd., Wilmington, N.C.
(b) Manufactured foc General Electric Company, San Jose, California (NEBC) in ..a .4er .t n casa <.w ewe., en m.*4 co , .
- 2. Identlocation.Ceruncate Holder's Sertal No.of Part A5225 n... sa, y ;
D. L. Peterson (a) Consenseted According to Drawiss No. 769 F53I.cnn1 Drevias Prepared by (b) Descripcios of Part taspected Control Rod Drive, Model #7RDB144DG001 N207 (c) Applicable ASME Codes sectice III. Edition 1974 1
, Addead.das. W'75 . case No. _1361-2 ca...
Cap 166B9274P1 g 1. (167A2343) SA182 - F316 Code held 3/8 thick x 1 1/16 00 P50YP102 N _. ;. I I 2 l l
- 2. Indicator Pipe 166B9313P1 g
SA312-TP316 ' 3/4 sch 40-seamless pipe s 0.113 uall thickness
! % I l
1.065 max. dia. Reactor vessel l i [ t . thimble l I l 8 l l
- 3. Plu9159All76P1 l 8 5A182-F304 - 8 s 1 1/4 thick x 0.812 CD l
@ l
- 4. Flange 9190610P1 (719E474) Code weld !
' 8
.SA182-F304 .850YP102 s 1,_
3.37 thick x 9 5/8 00 '
/
neck 1 1/16 thick x 5.0 00 \ 2.875 10
'X N
i
- 5. Base 137C5311P1
.h '
/
XM-19 ASME SA479 3.0 00 x .884 ID 'f1 L
- 6. Ring Flange 11485122P2 i-1 ic 5.0 00 x 1.75 10 p sng C0t! TROL ROD ORIVE DWG - 768E534 6 ea.1/2 dia on 41/8 bolt circle c
*"1[gA
~ '
- 8. Plug 175A7961P1 gg
.30 m x 24 da.
3 ct x 1.307 dia. - 00625 i Page 175
REPORT NO. NP0059-0005 IBl3-027 (3 NIS-2/NR-1 OVNER'S REPORT FOR REPAIRS OR REPIACEMENTS As required by the Provisions of the ASME Code Section XI PNPP No. 9308 Rev. 6/93 uvners Cleveland Electric Illuminating Company Date 3/27/96 P.O. Box 5000, Clevriand, Ohio 44108 Sheet 1 of 3
- 2. Plants Perry Nuclear Power Plant Unit one 10 Center Road, North Perry, Ohio 44081 W.o. 95-5192 R/0 (Repair Org., P.O. No., etc)
- 3. Vork Performed By: Clereland Electric Illuminating Co. Type Code Symbol Stamp NR q 10 Center Rd, North Perry, Ohio 44081 -Authorization No. 33 Expiration Date 7/18/96
- 4. Identification of System: 1813 Reactor & Internals
- 5. (a) Applicable Construction Coder ASME Section III, NB , 19 1 Edition vinter 1975 Addenda, Code Case 1728, 1644-4, N-272,.
N@o? 4 % I*4L bgd by6Nl.
'b) Applicable Edition of Section XI Utilized for Repairs or Replacements: 1981 Summer 1983 Addenda /
- 6. Identification of Components Repaired, Hodified, or Replacement Components 4.
Name of Name of Manufacturer Nat. Other Year Repair ASME Component Manufacturer Serial No. Board ID. Built Replacement Code No. or Modification Stamped Paping General '
. 1B13 System Electric 1B13 64077 D0008 1984 Replacement Yes
- 7. Description of Vork: Replaced Control Rod Drive Mechanisms (CRDM) and l" capscrews. See Remarks
- 8. Test Conducted: Hydrostatic- [ ] Pneumatic- [ ] Nominal Operating Pressure- [X]
Other- [ ] 175 degrees F Pressure 1038 psi Test Temperature D I Page 176
l I l 1 NIS-2/NR-1 OVNER'S REPORT POR REPAIRS OR REPLACEMENTS
~~ ,
) I
- 9. Remarks: Installed a replacement CRDM in core location 26-59 S/N A4028 usine (8) capscrews I"-8x51" 1 ig. ASME SA 540 Gr. B23 (8) Ht# 99896.
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 Ve certify that the statements in this report are correct and that all design, material and workmanship on this Replacement conforms to (repair, replacement, or modification) applicable section of the ASME Code. Certificatj; of A dzation No. 33 to use the NR stamp expires 7/18/96 Signed A%u/ . u jus _f Nuads C,e eknr> i Title) Date iM1 cd(OvnerorOvner'sDesgnee, 19 E i CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the State or Province of OHIO and employed by *ARKVRIGHT MlTIUAL INS. CO. of NORV000, MA. have inspected the repair, modification or replacement described lit this report on h4 JB ,s19 % , and state that to the best of my knowledge and belief, this repair, modification or replacement has been made or constructed in accordance with Section II of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any varranty, expressed or implied, concerning the repair, modification or replacement 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 kl. from or connected with this inspection. MOR _ _ Commissions N6F5(4) T 8MS . V (Inspector's Signature) Date Nasen as 19#)6
- FACTORY HUTUAL ENG. ASSOC.
O
REPORT NO. NP0059-0005 1813-027 Sheet 1 of 2 Sheet 2 of 3 p
- FORM N.2 N7T CERTU'ICATE 110LDERS* DATA REPORT FOR N1) CLEAR PART AND APPt!RTENANCES*
l l
\
As required by the Provis4 ort of the ASME Code Rules. Sestaoa !!!. Div. t l
- t. (a3 was.fece. red by General Electric Company. Castle Havna Rd. . 'Jilnington. N.C.
in .am .s we c na<me n n. (b) was faceured fu General Electric Cocrpany. San Jose, California (NESC)
.a.a= ==s w a c.,eeem. eemen en . :n
- 2. Idennocattom.Ce'rufLcate Holder's SertalNo.of Part A4028 Nu'l Bd. No.
ES M 01 g ,,,;,,p,,,,,,g gy D. L. Peterson (a) Cassuocted Asnias no Drawiss No. (b) Ducription of Psat taspeceed NZU/ (c) Applicalde ASM E Cadet s ctien tII. Edition 1974 . Addendadme W'75 , c,, 3,, N -2 C; ,, 1 g gg,, Standard part for, use irith Raactor. Hydrostatically cesced at 1S20 ysi. ta.+ u.e.4 .s . a. e . .
- Total nu=ber of sheets - 2 Te certify shes she semesesse made la Ma are correct and Ms vesset part ce appartenance as defined la che Cooe coe.
foama se che rules of construction of die ASME Sectice !!!. (The appisce64e Destsa Specidescos and Stress Report are nos the respoestbults of the NPT Certificate Holder for parts. Aa NPT Certif. icase Maider for appurtenances es respoenst6e for furrasemes a sapenas Dessa Specificanos acd 34rias Esport af the appurtennace is aos tactaded La the component Destas SsueetScados and Stress Report.) 7/23 g9_jl 5 seed CZ' NIPU~ By - "'-- unrceoseem uman,
~
certificue of Aashorianian Empires Seotenber 15. 1981 Certifleme ed 'zanias No. CER*I1FICATION OF DESGN FOR APPURTE.%NCE (*kes applicshle) GZ, NEPD** D-QA, Castle Hayne Rd. , 'Jilaington, N.C. De m.en informe ims au file as 22A5336. Rev. 2 Sans eansysie report a. fite u G2. NE? DAD-CA. Castle Havne Rd.. *4l131nRCon. N.C. 22A4912, lev. 2 Desica specifisatione certified by 3. N. Sridhar p,,,, g ,,3,,, Calif g,,,3.JS345 Scress analysis report eenified by 3. N. Sridhar Prof. Ea s. Same Cali" n ,,g ,13245 g CERTIFICATE OF 5 HOP INSPECTION
- l. the undersigned. heading a valid cosamission isewed by the Naciomat Board of Soiler and Pressere Yesset taspectors mad /or the $ sere se Peoeiece og_ North Carolina and employed byDepar nant of Tabor og 5 tate of North Carolina have inspected the paa of a pressure vesset described is this ;
PurcaJ osta Report on 7/23 is $,J. and state that to the ness W aty knowledsa i
$ sad bedef. the NPf Ceruncate Hoeder nas coa.ttructec : hts part in accortance with the ASME Cade Sectice !!]. .
By signing this certificace, souhee the laspector noe his employee makes any warrearv. espaessed or impliet. Ceecer*. lag th e part described la this Parttal Da ta Report. Furthermore, metther the faspector nor his empleFer shall be listle in any saamer fer any personal ingury or properry damage or a los s et any hand artssag troe or connected
, .nn tas 6s3pec tica.
I I al we 7/2} ,
]4), h, )f)w, ,,
-m.
Y.C. WShO N -
.s w .-
[ va ... %....p..*..
' " ^ * " " ' ~ * ' ' ~ * "
".'*.*C";*;f*.*' 1.f. ' 7_ './ '; ;r".*.* ,;'J:::* * *.O*. " J:*.* "L'? : . ".** *,"' *
- .,._.n.v...._.r.,... ..
.% r. .-r. -
......OO353 (3
O r t l l Page 177
i i i FORM N.2 Nek) tsems 4-8 lact, se be co.npleted fos aimale wall ves sels. omehes s of sacketed ve s sels, os . hells of hest esthangee s. Oi i l l Noenisel Cerrossee 4 %ella M.s ee.al _ _ .3 (hin .d n. Thickne s s im. Allee s c e _ .n. Di a _ f t._ ia. Leasih _ ft.
.. , 1 ,f:
c Kans a se.e. m.T.S. age sounfi.e) l S. Se em s: Long H .T.' R.T. E f f.c ien.: y ". i : 1 Girth - H. T.' R.T. No. of Caerse s T.S. (b) M etersal T.S. , i
- 6. Heads: (as Weseesel ca am ms, s t ue. . .a cea .a M..a. n.. ens rim s 4. se P,n ;
l Laws st , n . en tas. ... ma4 n a.sa.. a.u. ae.s 4asie n.dia ca a.c (c.a.. = c eae. 1 ( at (b) If eemovable, bolas weed Oinee f usemens u .n.s.s,...s T.s..seu,n , co.una.. .. . ...
. Jaches Closuses o. . . . .s . . . . .... . . . . as m., s. . . . e . ., . a.s. ..
- Diog vessh Chaspy laspass fi.lb
- s. Desisa esess=,,e 1250 , ,; , 575 .p ,,,,,,,,,, e7 1: ems 9 and 10 to be completed fee tube sections
- 9. Tube Sheets: Stasionary. Masetial Dia. Thicknes s _ is. Anachment (saa a s, .w cs wis ,,....no to.sa.d. seis.es Floating. Maserial Di a. Thickness ia. Attachmess O.D. in. Thickness 'w"sYe'e. Number Type
- 10. Tubes: Maseenal (sw.
- in teams 68-14 incl. se be completed for insee chambers of pcketed vessels, or channels of beas eschangees.
Nominal Coevosion Ja. Allow ance _an. Di a. fc._ia. Leagch fi. is. ll Shell Waterial (rind T.S. nickness a s,. . n . c uin. .r a.ase s... ti.an 2 2. Se am s: Long H.T.' R.T. Efficiency . Girch H.T.' R.T. No. el Co.e se s T.S. t hi vaserial T.S.
- 83. Heads (as waterial c- Ka mie sis.euui ca H ne.a pia same s eme.
a.es a.o. 4 . 4.si. a.si.e oimmin < c-. c .s Lu=i Tiven .. a.ei (at Top, bouova, ends e b) Chamael (b) (c) Other f assenang
!! semovable. bolt s used (a) . O...nu a usun ..e..a Drop Teighs .
Charpy impact f e.lb 64 Design press.te s ,,,,, op ,,,,,,,,g e r l Items below to be completed for all vessels .nere applicable. ii. $ sfet, Velve Ovelet s: % =ber Siae Loc ation
- 16. Nos aje s: i n .af wo as p.,....s.., He= ^*'*****
o e sin T ree nim ..a T wee .a. . . w = *i .a ( c ic, s, m %. \ I* la s pec eien W eaaoie s. No. As s e L x asion O pv aan g a: H anchole s. No. Siae L x atson Tweeseet. No. 5,se _ L3csooa i.ess Other
>. .e 3 c Su s *u.- hed ..~ _ .== m
- 18. 5.pperi n : Sk i e. Lis a s M.=.
v.. w.. w.... f....
'aP.........t j
. . . . - . . . . . . . . . . ~ . - . . . . . , . . .
O
l l REPORT No. NP0059-0005
. . ..- IB13-027 Sheet 2 of 2 FORM N-2 NFT CERTTF1CATE HOLDERS' DATA R b FOk CLEAR PART AND APPURTENANCES * ,
As required by the Provision of the ASME Coder Rules. Section lit. Div. I g, g ,y ,,,,,, g g General Electric Company. Castle Hayne Rd. Wilmington. N.C. in e eer w m c.,ee. n e gy g,,,,,,,,,,4 g General Electric Company, San .Tose, California OTEBC) sa .es er m n c us. nwenen . :i,
- 2. Idesmacesses<ernaceae Hender's Sertal No. et Port A407R Nes*1 Bd. W.
. L. Peterson (e) Censinacted Acceedias se Dreeles h. 75 AIM 140001 DrawingYrepared h (W Descri, des el Pan tempectea Control Rod Drive. Modal #7RDB144DC001 N207 u' 7 a; 1 (c) Appucewe AsM Ecedes sectien tti. Edkien 1974 , aade. dea e .Ca.e n. 1361-2 cr...
- 1. Cap 166B9274P1 1 (167A2343) l SA182 - F316 Code teld 3/8 thick x 1 1/16 OD P50YP,102 N;_;.
, I I I l
- 2. Pipe 166B9313P1 3/4 sch 40-seamless pipe N 0.113 vall thickness .
! % I t
1.065 max. dia. Reactor vessel l . O 3. Plug 159A1176P1 thimble l I 8 l l I l g~ SA182-F304 - ' i i 1/4 thick x 0.812 00 I '
. 4. Flange 9190610P1 (719E474) Code weld
- ND L
.SA182-F304 ..B50YP102 NN 8 3.37 thick x 9 5/8 00 N T s neck 1 1/16 thick x 5.0 00 -
. 2.875 10 _,
N x
- 5. Base 137C5311P1 .2 L XM-19 ASME SA479 3.0 00 x .884 ID T'
- 6. Ring Flange 11485122P2 SA182-F304 Code weld l' thick x 5.0 00 x 1.75 ID P50YP102
* " " C0f!TR01. ROD DRIVE SA$9- CWG - 768E534 6 ea.1/2 dia. on 41/8 bolt circle
- 9. Nut 137C5934P1
- 8. Plug 175A7961P1 IM-19 SA479 3 t x x 1.307 dia.
- 00054 Page 178
9 REPORT NO. NP0059-0005 1B13-028 h NIS-2/NR-1 OVNER'S REPORT FOR REPAIRS OR REPIACEMENTS As required by the Provisions of the ASHE Code Section XI PNPP No. 9308 Rev. 6/93 5.uwner: Cleveland Electric Illuminating Company Date 3/27/96 P.O. Box 5000, Cleveland, Ohio 44108 Sheet 1 of 3
- 2. Plant Perry Nuclear Povsr Plant Unit One 10 Center Road, North Perry, Ohio 44081 W.O. 95-5194 R/0 (Repair Org., P.O. No., etc)
- 3. Vork Performed By: Cleveland Electric Illuminating Co. Type Code Symbol Stamp NR 10 Center Rd, North Perry, Ohio 44081 Authorization No. 33 Expiration Date 7/18/96
- 4. Identification of Systems 1B13 Reactor & Internals
- 5. (a) Applicable Construction code: ASME Section III, NB , 19 1 Edition Vinter 1975 Addenda, Code Case 1728, 1644-4, N-272 .
NAo? sJ ct s F M 3/26196 tb) Applicable Edition of Section II Utilized for Repairs or Replacements: 19 E Addenda ps Summer 1983
- 6. Identification of Components Repaired, Hodified, or Replacement Components Name of Hase of Manufacturer Nat. Other Year Repair ASME Component Manufacturer Serial No. Board ID. Built Replacement Code No. or Modification Stamped Ptping General '
. 1B13 System Electric IB13 64077 D0008 1984 Replacement Yes
- 7. Description of Vork: Replaced Control Rod Drive Mechanisms (CRDH) and l" capscrews. See Remarks
- 8. Test Conducted: Hydrostatic- [ ] Pneumatic- [ ] Nominal Operating Pressure- [X]
Other- [ ] 175 degrees P Pressure 1038 psi Test Temperature Q V Page 179
NIS-2/NR-1 OVNER'S REPORT FOR REPAIRS OR REPIACEMENTS Od
- 9. Remarks: Installed a replacement CRDM in core location 50-15 S/N A4669 usine (8) capscrews I"-8x54" ig. ASME SA 540 Gr. B23 (8) Hti 6f8ll. ,
NOTE: Attach all applicable Manufacturer's Data Reports. Supplemental sheets such as lists, sketebes, 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. , s CERTIFICATE OF COMPLIANCE Ve certify that the statements in this report are correct and that all design, material and workmanship on this Replacement conforms to (repair, replacement, or modification) applicable section of the ASME Code. 33 to use Cl}e a amp expires 7/18/96 Certificete of A thpyization No. Signed D uk/ . . Gs /ssf Mh 7 N (,Ovner19 or gW er's Designee," Title) Date 4.41$ , CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the State or Province of OBIO and employed by *ARKVRIGffT HUTUAL INS. CO. of NORV00D, MA. have inspected the repair, modification or replacement described in this report on h e t, 06 , s19 C)(, _ , and state that to the best of my knowledge and belief, this repair, modification or replacement has been made or constructed in accordance with Section II of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage o oss of an- ind from or connected with this inspection.ce. go
,_,,_,w__ _
Commissions e /395c.3 7 (Inspector's Signature) 19 9 /.
- FACTORY HUTUAL ENG. ASSOC.
Date // w /i a m i O
m_._.__ . _ . . m-_.__ _ _ _ _ _ . = . . _ - - . . _ _ _ _ . _ _ - _ _ _ . . - - - _ _ _ _ _ _ _ , REPORT NO. NP0059-0005 1813-028 Sheet 2 of 3 Sheet 1 of 2 Foam N-2 NFf CERTIFICATE Hns rinne. DATA REPORT FOR NUCLEAR PART AND APPURTENANCE 5* , As rapired by the Provissue af es ASME Code Rules.Secace III. Div: I ! g gg ,M by General Electric Company, Castle Hayne Rd. , Wilmington, N.C. onua. as.es==m urec us emem (g ie,.w,,,,,,4 a General Electric Company. San Jose, California (NEBC) , memeaussem = =m - ameuren j 2., - '- '- - '-
' useenr ssenessum.wpen a A4669 ,,,,,, g g,,
1 gg ,. . a % es Deusnes h IA**
%wW D. L. Petaceos l
!
- Control Rod Drive, Model #7ED3144DG001 i (to P ad Pas Inspemed i r4(.U/
i (et Aepusehas Astasc.dersessisent.Edisse. 1974 W'75 1361-2 M--- 1 Addsededsse ca eNe. t gm Standard part for uma with Emmetor. Hydroegatically tested at if20 pai. cas.s - .s s l i
- Total asseber of sheets - 1 andein ein we ammier shasshar ese esames and ehie seessi pen er myyssummmmme ne deemed in she c.de ems.
fees as she smise e6 esmemmesism W she ASSE Soesian NL l me se s e se i n.enanmase me w ommen sossesm. ismasess is ime re osamm.s
.e esse.a.n.s.see.m summesamme aus scene assses.a a - om s. e
- a. men ase aus me sumumms.emasse, m-- s n ttae Nrr. carus.m.m u.s.e.s.se,sur sesim. As ee - m m.
, _. 7/7 3 81 y GE HEPD-WD- p b., ,
assecues m j casisassee d Amihamede,e Seo+ M ar- 15. 1981 csissemea! MPT 5-1151
- - No.
g CEEITF1CA110M OF DESGN FOR APPURTENANCE (=6en appisenhie) oogg ;g.,,,, e.ase -- E, NEPD-AMD-CA, Castle Hayne Rd. . 'idf1minaten. N'.C. .' 22A5536, Rev. ?. sesi ee om.are .e ,en e. are . E . MEPD, San Jose, Calif. 22A4912 Rav. 2 oogen -- e.,,igw g, B . B . SrM1* =" Pid Eas.3sse, Calif 3 ,,,, h Seese andress espese cessiSed by B. N. Sridhar Prod. Eas. 5rese Calif g ,,3 ,18345 CER1TFICATE OF SHOT
- INSPECTION
- 1. *e . heidas . ud cemen i.e isomed by de Nasimasi Bead d Seiler and Preamse Vesamt lampsesure and/or time same er p,e,,me, g North Carolina and empiered byDenartment of Labor w State of North Carwlins he,e ' se pen a a mesase wesema Wh d Isi esa ersial Dean assert as 7/7 te$ and mate est to me Wuur N P.ed hatter. the MPT CartIScate Heider = ens haseen te _ wt2 he ASME Case Soestes 01.
By manias abis cer:6Seese aesshier ube t==r.-*.= ear his supeever nahes any wearemsy, espree.ed er impiled. coneers. Ime the e de b R hi
*w he p.niart. i.se.t.t,
.6.s i.e tais m e.d.to, - P,erttaai Data.,e.,eeer,t.
er .e . er e i
,F.u.r.t,h.e.r.m.o.re.
se m wi set.tn.e.r e the,.emd een lase.ec.t.e se.r.ar!
*i. a- ;
' ^ ^ ' 7/7 " 81 i N.C. 723.PA.WCU66, 0$0
* ....6=.
d.
. si c.m.m. s.4- e
- s. a si... p . n
**::" -.. =:*. '_- .? "*r:. . . :::'." .:'_ . .$", :"."' ' " '" " ' " - ' " ' - -
00701 m ie % eorm isooo4cin., t.oom.a.s %= ir o.a., o.m Asue. see a. 47tri .se N.w Yo,s. N.Y.10017 l Page 180
" " ' ~ ' ~ . _ . ~ . ..
4 p! y - ? \.. EeM(M
'=d for single well .eesels. jacbete ed inchgped weseels er ehesto el hees eschengers.
teeme 4-4 tert. se be e
- p ,
c _- . . m ie. Leegh fs. - ia. f T *- Th knese ia. Allegresce isk. Diw f*
- 4. Seela Wesened(sa-saa asea on .s a ee s a.c.arn.e Efficiency 7.
ST.' . it T. S. Sommes Len=
- It.T. No. ed Cearsee Gissin M.T.' T,$,
T.1 --- - - (W he.eenal
- 6. Needes (el a e.nel se es nama rise men se m.o sensese en--a caesena .
s ans. Ca gone. Asse Angde sentes Dtam.m.e (Come. w Caen.3 Themenses Anebue Domese (Ten. tenom. . ment ( =a (H ombeefossesias a
' tt remeenhie, beke esed coeamew on.e-.es. s,.e. m T.s -- - ..
m ., ; wu
- 7. jeekst Cleeusesco mase..o ee e.e u n e Deep *sishs 575 ey %,,
, ,,',*** 7 a 1250 ,,; ,,
- s. Desen m-
!seus9 and to as be -==eA=eed fee eeke sessissa "I^- la.A h mTbd"==es <ene e. amesa.
- f. Tube Sosses5sesseomry. (sama a so.m. pe.4 c .eo Ptenaies unserie& Dia.
to. Thesiesome
]
- emes. % . sabee is. '
77-= ha-=a1 OJL cama. es til to. Tedsman as chosesse ed bene e=-h==,=.e.
"" ime immer casemmese ed jaciareed ==_-.'s. - - ~ ~-
tasma6 L1 t4iert.se he --
.m _
an. OLCfr 1a. LessiA h. - T.5. TMetuneeed A&iewomme
- 11. Sheth aumeamese.ssea " camm..#- _ - ~ -
- R.T.
~ ' *
- FfM- y -.
- 12. Seannet '_- ET.'
A.T. No.edCaersee Ginir _ ST.8 T.S. T.1 (H Maseree!
- 13. Heads (e6 'Wesertes es.m.seen a rs.s 'same i. e.ee.
C, , sewes - enW Canneet Restese Otem e- (Cae e Ceeed Assee Agem Amese P Roween . Rees.m Leesseen (al Top. 6*==. ende ,,,,,,,, (bl Chamael Other f assening (b) -(c) eo. n e., e e (f reumevehde boks seed (a) Deep veighs -. is=4 b Cheryy tempact an ese,. og *F 8 poi as
*F
- 14. Dessas presenre tseme betee se be compdeced for eAl vesseis As applicable.
- 11. Sedecy Veive Oesteta Number
- *: .- 1.ecessen
- 16. Nesatees 8.*d********
M*****"* The.ne em*a*6 www e nosa. m.me., 04 ., same 777.- es series omam.orm e me . Leession
- 17. tespecteen nsenhales. No.
- m. Lerassee '
Openasssa Headhele3. No. Size Lecasion'
- Thmoded. No. An sc hed enwe..
Less som
- 18. Suppests: Eart Legs _
t%- , pe , Other- to. ,se.e iv .e we
' le P w.te 04e f .e.e. wem essa.seens e.e s ee e .ey44..H..
La.e se e ses.some er es un s 9
- . . . . .- . .= -.- .. . - .- - . - - .
1 REPORT NO. NP0059-0005 e' - Sheet 2 of 2 j 3
- Sheet 3 of 3 7
' FORM M.2 NFT CER11FICATE HOtJERS' DATA REFORT FOR NUQ2AR PART AND APPURTENANCI5* h ') ' ,
As required by the Provision of the ASME Code Rules. Sectaas III. Div, t fasser.d by General Electric Company, Castle Hayne Rd., Wilmington. N.C.
- 1. (.3se us.m.. s one .r e c.es same.,,
J (M sams.d e ed a-, General Electric Company, San Jose, California (NEBG)
*an= ==e garg a c es m. mm .,
] 2. -% u.ae r .senes n .ep u.c ad, g., D. L. Peterson (at t --.-.-eed A-_ ; i. D ,ias No. 7AAyA1AtiM1 Drawing Pseposed br
~
(4 f . ' of Pass 8-W Control Rod Drive. Modal #7RDB144DG001 ' N207 (c) ^ ;" - AsaECade:Seedmont.Ediden 1974' Addende u. W'75 C N l ls1.l.Cs . 1 ( l l
- 1. Cap 16689274PT (167A2343)
SA182 - F316 Code weld y 3/8 thick x 11/1600 P.50YP102 I N _, i 1 I m 2. Indicator Pipe 166B9313P1 - l SA312-TP316 . l 3/4 sch 40-seamless pipe N 0.113 wall thicicness
- l
\ I 1.065 max. dia. . '
hCtor vessel . O a I thimble l 1 Plug 159A1176P1 l l
- 3. l ,
SA182-F304 . I L,~ ~ 1/4 thick x 0.812 00 l l
, 4. Flange 919D610P1 (719E474)
.SA182-F304 Coile
..R50YP102 N
\ '
I l 3.37 thick x 9 5/8 OD neck 1 1/16 thick x 5.0 OD \
\
. 2.875 ID i ,_ ,
h N
'5. Base 137C5311P1 M '
~ ~ " '
XM-19 ASME SA479-3.0 OD x .884 ID -
- 6. Ring Flange 114B5122P2 SA182-F304 Code weld 1" thick x 5.0 OD x 1.75 ID P50YP102
- 7. Cap Screw 117C4516P2 CO*tTR0t. ROD DRIVE SA193-86 DWG - 768E534 6 ea.1/2 dia, on 41/8 bolt circle
~ ~ ~ ' " ' 9. Nut 137C5934P1
- 8. Plug 175A7961P1 IM-19 SA479 SA182-F304 1.30 thick x 2.62 dia.
0.38 thick x 1.307 dia. 00702 O Page 181 l
REPORT NO. NP0059-0005 1813-029 NIS-2/MR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As required by the Provisions of the ASME Code Section II PNPP No. 9308 Rev. 6/93
~
- 1. owner: Cleveland Electric Illuminating Company Date 3/27/96 P.O. Box 5000, Cleveland, Ohio 44108 Sheet 1 of 3
- 2. Plant Perry Nuclear Power Plant Unit One 10 Center Road, North Perry, Ohio 44081 W.O. 95-5195 R/0 (Repair Org., P.O. No., etc) l
- 3. Vork Performed By: Cleveland Electric Illuminating Co. Type Code Symbol Stamp NR l 10 Center Rd, North Perry, Ohio 44081 Authorization No. 33 1 Expiration Date 7/18/96
- 4. Identification of Systems 1B13 Reactor & Internals l
- 5. (a) Applicable Construction Code ASME Section III, NB , 1974 Edition Vinter 1975 Addenda, Code Case 1728, 1644-4 7 -272 AJ M lhi-a. EWA$lis (b) Applicable Edition of Section XI Utilized for Repairs or Replacements: 1983_
\
Summer 1983 Addenda i
- 6. Identification of Components Repaired, Modified, or Replacement Components Name of Name of Manufacturer Nat. Other Year Repair ASME l Component Manufacturer Serial No. Board ID. Built Replacement Code No. or Modification Stamped Piping General '
. IBl3 j System Electric IBl3 64077 D0008 1984 Replacement Yes i* Replaced Control Rod Drive Mechanisms (CRDM) and 1" l
- 7. Description of Work:
l capscrews. See Remarks
- 8. Test Conducted: Hydrostatic- [ ] Pneumatic- [ ] Nominal Operating Pressure- [X]
Other- [ ] 175 degrees F Pressure 1038 psi Test Temperature q LJ Page 182
NIS-2/NR-1 OVNER'S REPORT FOR REPAIFS OR REPLACEMENTS O
' )
- 9. Remarks: Installed a replacemsnt CRDM in core location 30-07 S/N A4642 usine (8) capscrews 1"-8x51" 3 Ig. ASME SA %40 Cr. B23 (8) Hti 61811.
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 Ve certify that the statements in this report are correct and that all design, material and workmanship on this Replacement conforms to (repair, replacement, or modification) applicable section of the ASME Code. Certificatejpf Aufh,oy13ation No. a 33 to use the NE stamp expires 7/18/96 Signed L/Aue& W. (J.dhd []uafek Ca95e-t) (Ovner or Owner's Designee, Title) (/ Date Lofd_ / M I 19 Q(o CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the State or Province of OHIO and employed by *ARKVRIGHT MUTUAL INS. CO. of NORV00D, MA. have inspected the repair, modification or replacement described in this report on h e t., de , s19 5E. , and state that to the best of my knowledge and belief, this repair, modification or replacement has been , i made or constructed in accordance with Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any varranty, expressed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damag or Jess of any nd from or connected with this inspection. cgo Commissions a fhsL3 .2' Ccw p, b em _ ~
~
(Inspector's Signature) Of 19 t
- FACTORY HUTUAL ENG. ASSOC.
Date je/ u l, O
r REPORT NO. NP0059-0005 iB13-029 Sheet 2 of 3 Sheet 1 of 2 FORM N.2 NFT CERTIFICATE IIOI.DE25' DATA REPORT FOR NUC1. EAR PA27 AND AFFURTENANC23' As requared by the Provision of the ASME Code Rules. Section IU. Civ. I t, g ., u,,,,,,,,,,,4 w General 11ectric Couroany, Castle Eayce Rd. , Wilmington, N.C. in.-. m mem .e nrr carene.m n n gg g ,g ,,,,,4 r., General Electric Company, San Jose, California OIE3G) usen een mem e n e--uses,me : r m, A4642
- 2. w--=a--a- e uncess nee senaa ne. .t rang g,,g g 3, (a4 Came===ted Ame= dias == Dr==ime No.
01 ,,,,,,,p,,,,,,,,W D. L. Peterseu
- Control Rod Drive, Model #7EDR144DG001 (M P- ;r.:: el Pese leapsesed MUI (c) App &lesh&e A$ hse Cadme Sorman III. Ediaism , Addsededame . Case No. Class l
3, ,, Standard part for use with Rasctor. Hydrostatically testad at 1820 psi. t -
. ..r a . e_.
- Total number of sheets - 2 l Te esvady shesshe - made is ehle ese canese and shis vecess pare er appusasemmae as deGaed la che Code coe, femme e she enses si can h ed she AS4E Sectims III.
tThe ass.ue,ame
- no = - re Denna sseeseenstam an.d e = seems e.ea-D nos the russenemailar et.s A.ssert.e.se ~ the MPr.c.ertenema.
m nd e-N.eeder fo.r perta.. Am NPf C. ag; i
- senemes u. me ceasemens osasa;se -aa-.a.- ans strum nesen.)
7/7 g, 81 sa,*d GE. NEPD-WD- ,, .C [__ . userc - mme c.,,uteme a wanda. Es,ines 5eetember- 15. 1981 c.nir;,,,, e, ,,,;,, 3., m N- 1151 CERI1 FICA'IlON OF DESIGN FDR APPURTENANCE (when sypileable) o.g,g :al g., ,, g;3, _. GE, NEPD-WMD-CA, Castle Hayne Rd. , '411mincton. V.C. 22A5536, Rev. 2 servee smaarois re, t en file .: GE, NEPD, San Jose, Calif. 1114912, Rev. 2 Desism specificasione een:(led W 3. N. Sridhar p,et. Eas.$sereCalif Reg.Nel.3345 Seese maaiyese repers certified b, 3. N. Sridhar Prof. Eas. 5ame Calif g,,,3y.3345 l CERTIF1CATE OF SHOPINSPECTION
- 1. the undereigned, holding a veild commissies issued by the Namassai Beerd el Seiler and Pressure Vesses tampectors nad/.rche 5 e er p - .t North Carolina and sumptered byDepartment of *. abor a State of North Carolina heee inspected the pass d a psussure vessen described is shie pernal Data neomrt om U7 t9.8d and sense mas to me bem W my knowleese and beust, the NFr Cerufleste He6eer has consErected his part la aceWGaare with Se ASME Code Secuas III.
By manias die ceruficaer, mesta.,e the leseector not his emp4=yer makes any wasraney, repressed er implied, concers. las the part desertbed to this pertial Data Report. 'Furtaermore, setther the laspector ser his esepterer sma.ll
- be linale in any manner for any permunal issery or premdamese er a less et emy kind ersusag tree or comaected
*i. i.e,ec s
- " 7/7 t, al N.C. 723,PAwc1766, OWO s . t
_ , ,_I . ., C .iose
....a..-..,
"r=:-" =:*.:'.'2"Jr.: =- - - =.: ." :::'.c=*. ."Jr :'Y * """" -"'- - - - " - -
. 00 E a om> 3. ,, .seco.ci,, to oo e m,. m. cece, c.oe asus. 24s E. 47m se u v ..o N.Y. 20017 Page 183
3 FOlW %2 nacu i ems 4-a s i. .e be c piced fee s.asie . 41...ses s. .actu s vi sade.ed ...sei s e. .n,u s .,# ne e,cm..ge... No .aet Carnos. \
;a. Aue. anc e .__ ... 9. a.
i _ ii . _,_,. . t. . . g.n ,_ li. ...
%usW,.aa _ a e.Th 4.
_TS.on s .s.k.e.m.s_ ira
- 1. Sesam L*.s
< si . se.e. n H.T.' R.T. Efficiency ". i( l l
Cirik H.T.' R.T. No. of Ceveses l I T.S. (b) Maierial T.S.
- 6. Hendas (as Waserial ste. se p .
c, s u. cua .a c s.6 H..a.,n.n. .a rt L. nonen, e ec tm6sm.ees a.m.. sees.e ama. A,.. A.s6 a.44 on .iw (c .. = c 3 47 l (se (b) If tesmovable, boiss used Other f as<eeing o .n.5 se n. T.s. saae.no n <o.un . . . ...
.. .s om..e. .en . ....e u
. Jaches Ctes-n< o..en .. .. .. . ... e.e. u .- .. .
tnog se.ghe Charpy letpace f,.lb 1250 ,a ,, 575 7 ,,,,,,,, e7
- s. Desisa pressure'_
lieeis 9 and to se be completed for sube sections
- 9. Tube Sheess: 5:ecionary. ndaseei 2 Dia. Thickasas is. A achmens (see,.es se pr...we tsetee.sm e ts.e a se... me.3 Flossias. Weserial Dia.
. Th.i.ckness_ia.
n Attachment Type 0.D. in. Thickness -s.... Number
- 10. Tubess Wasevial (se. w in teems 11-14 iact. to be complesed fee inner enesmhers of incketed vessels, or cananels of hesa enchaagees.
Nominal Carrosion is. Thickness ia. Alte. sac e _..a. Dia._ is. ia. Lengsh _ fs. it. Shell: Weseeial T.S. tu 6.s a se . m.. tuin. .# s e e se.. <>.e H.T.' R.T. Efficiency - - .
- 12. Senes Lees H.T.' R.T. .No. of Courses Girth T.S. ibi Waseveal T.S.
- 13. Heads (as Waterial sees se pees Ca M.ma.o ene.a rt.s Cs e Ep.emte Euartae.4 ..s
. a Ceae.)
- a. eave a aees A.ete m enau. Stee.iee (C L.ema.e Ths.sa.es a.es
( al Top. bestem, ends
- b) Chamael ibl (c) Other f assening if removsble, botas used (se ce. n . .nu n . ...e Deep Tenghs .
("h arpy f aipact dealb psa as *F ,as temp. of
'F
- 14. Design presseee' items 'sete. to be compieted 'ee ast vessels neee applicable.
ii. leie<, val.e Oveiev e Number siae Lac ssion --
- 16. No azj e s
. a .. . .
P so e la4**. Tw.e u.e ena Me. act. emes
.e $sse Tree " u.een.a e.
3.aset. De .a M ., D.
'* inspection usanese s, No. 6. a e L x stica Opeaanss: H anehole s. N o. Sese i.ac asson Thre eded. No. Site L oc at eca dene,
' S.
- Sweport s: 5.n et Less Less .3,,,,. :>..v .w . 3444a.c!ned i ,- . . m no..
y e. m., s,. . ,
*:sp. .. u...f
** nw.............
t J O
REPORT NO. NP0059-0005 IB13-029 Sheet 2 of 2 s Sheet 3 of 3 !
/ ) FORM N-2 NFT CERTIFICATE IIOLDERS' DATA REPORT FOR NUCLEAR PART AND APPtJRTENANCES*
-) As required by the Provision of the ASME Code Rules. Secuon !!!. Div. I u g , u w ,,, ,,a 6, General Electric Company, Castle Hayne Rd. . Wilm1ngton. N.C.
m== e.eer.=w wrr cwaae.= uwan. (b) Man.facmd foe General Electric Company, San Jose, California (NEBC) sam. e r.= w n cwone.w umen sw ewwe auca.,-- -- =
- 2. Idenuncassam-ceruncase lioider's Sertal No. at Part A4642 y ,,. g g, 76RE W Cool Drawiss Prep sed by * * * '#8U" (a) Constructed Accandles to Drawing No.
(b) Descripties of Part lasperied Control Rod Drive Model #7RDB144DG001 N207 (c) Applicable ASMECode Section!!!,Edision 74 , Addeada dame W'75 Case No. 1361-2 Class 1 N e e. .,e enem m- m em
- 1. Cap 166B9274P1 1 (167A2343)
SA182 - F316
- Code weld 3/8 thick x 1 1/16 OD P.50YP102 I
N7 I 2 I i
- 2. Indicator Pipe 166B9313P1 6 SA312-TP316 3/4 sch 40-seamless pipe N
l 0.113 wall thickness ' l
\ I 1.065 max. dia. '
Reactor vessel i I ( ) thimble l 1
- 3. Plug 159A1176P1 l , I l SA182-F304 ~ ' i L. -
1/4 thick x 0.812 OD l
.i .
g I
- 4. Flange 9190610P1 (719E474)
.SA182-F304 Code weld
..P,50YP102
)
NN i 8 N 3.37 thick x 9 5/8 OD N / neck 1 1/16 thick x 5.0 00 2.875 ID @ /
/ \
4
'5. Base 137C5311P1 ' "' '
XM-19 ASME 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 P50YP102
- 7. Cap Screw 117C4516P2 SA193-86 CONTROL P00 DRIVE DWG - 768E534 6 ea.1/2 dia. on 41/8 bolt circle
- 9. . Nut 137C5934 P1
- 8. Plug 175A7961P1 *~19 E*' 9 SA182-F304 .30 thick x 2.62 h 0.38 thick x 1.307 dia.
, s'.22G 'v' Page 184
( l REPORT ND. NP0039-0005 1B13-030 l NIS-2/NR-1 OVNER'S REPORT FOR REPAIRS OR REP 1.ACRMENTS l As required by the Provisions of the ASME Code Section XI l PNPP No. 9308 Rev. 6/93 f
- 1. Ovners Cleveland Electric Illuminating Company Date 3/27/96 P.O. Box 5000, Cleveland, Ohio 44108 Sheet 1 of 3 I l
- 2. Plant Perry Nuclear Power Plant Unit One l
10 Center Road, North Perry, Ohio 44081 W.O. 95-5198 R/0 l (Repair Org., P.O. No., etc) I
- 3. Vork Performed By: Cleveland Electric Illuminating Co. Type Code Symbol Stamp g 10 Center Rd, North Perry, Ohio 44081 Authorization No. 33 Expiration Date 7/18/96
- 4. Identification of System: IB13 Reactor & Internals l
- 5. (a) Applicable Construction Codes ASME Section III, NB , 1974 Edition Vinter 1975 Addenda, Code Case 1728, 1644-4 7 -272 N zo't ehe .a. ora a;ppfy, (b) Applicable Edition of Section II Utilized for Repairs or Replacements: 19M_
Summer 1983 Addenda I (v )
- 6. Identification of Components Repaired, Hodified, or Replacement Components Name of Name of Manufacturer Nat. Other Year Repair ASME !
Component Manufacturer Serial No. Board ID. Built Replacement Code or Hodification t No. Stamped Piping General '
, IBl3 System Electric 1B13 64077 D0008 1984 Replacement Yes l
l
- 7. Description of Work: Replaced Control Rod Drive Mechanisms (CRDM) and 1" l
l capscrews. See Remarks
- 8. Test Conducted: Bydrostatic- [ ] Pneumatic- [ ] Nominal Operating Pressure- [X]
l Other- [ ] degrees F Pressure 1038 psi Test Temperature 175 i O Page 185 {
7 I , I NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPIACEMENTS O
+)
- 9. Remarks: Installed a replacement CRDM in core location 34-03 M/N A4264 usine (8) capscrews I"-8x5%" Ig. ASME SA 540 Cr. B23 (8) Htf 99R96 t
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 Ve certify that the statements in this report are correct and that all design, material and workmanship on this Replacement conforms to (repair, replacement, or modification) applicable section of the ASME Code. CertificaAe of Au,t)o,r$ ration No. 33 to use thy NR stamp expires 7/18/96 Signed flewil ~C {As/etf Ahd% lh4cEta) (owner or Owner's Designee, / Title') Date 14ttMlA_. 24 19 @ o CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the State or Province of OHIO and employed by *ARKVRIGHT MUTUAL INS. CO. of NORV00D, MA. have inspected the repair, modification or replacement described in this report on /% u t, .:Id ,s19 94 , and state that to the best of my knowledge and belief, this repair, modification or replacement has been made or constructed in accordance with Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property s of any kind from or connected with this inspection. g, , damage o Commissions,cBdz3 2' 2%
' - - e_ _U (Inspector's mm , t a Signature) 19 9G
- FACTORY HUTUAL ENG. ASSOC.
Date l O l i L
1 REPORT NO. NP0059-0005 IEi3-030 Sheet 2 of 3 Sheet 1 of 2 I
\ l FORM N.2 NFT CERTIFICATE HOLDERS' DATA REPORT FOR NUCLEAR PART AND APPURTENANCES
- As requered by the Provision of the ASME Code Rules. Sectice III. Div.' I g, g 4 g,,g,,,,,,4 6, General Electric Company, Castle Hayne Rd. , Wilmington, N.C.
- taname ens semuss d se"r Casmasmes Nasempo gy s ,,,4 s General Electric Company, San Jose, California (NEBG) ansas aus mamanw n cmansene sessaar ermemessee emsnner
- 2. "---a" -aa .see moeder's serima No. or Pues A4264 ,,,,,,3 ,4, y,, _
gg , % % ,, u 768E534G001 D. L. Peterson gg 7 ___g,,,,._ ,
. Control Rod Drive. Model f71DR144DG001 M4U/
1 W'7b ,CaseNo.
~
l (c) ^7" '- ASMECodesSeesianEt,Edision . Addendadame Cle= g% Standard part for use with Reactor. HydrostaHrally tested at 1820 pai. tone - _ . .s es sen _ es
- Total number of sheets - 2 se essdir desehe made in esa ese essveer and shis vessel pass er appusumesmee as deemed is she Code femme ao es suaes ad - e
- ishe A StE $sedam 111.
a===== a (The
- nom.rasetteeMe, Desse ====
-. ans sene.s.r .ssest h .ase met me.sessammi.ssialty ns.es e D . cy_.a - - et mdthe NPT.CaraSo.n.se.heWe.r see spe. < es - - tsur pens. As NFF C.as smesumes am me sumsament Demar y==aa===== ame seem nesses.)
,m 6/23 ,,
81 CIe EEPD-mD- a Co.,ineme w dash ands. Esp;,.;. SeDtember- 15.1981 C nneme a I " '- ' - No, MPT N-1151 CERTMCA'110N OF DESGN FOR APPURTENANCE (when syylleshle) Dess e m indesinadas se rne -. GE, NEPO-WMD-CA. Castle Hayne Rd. , Wilminaton. N'.C. 22A5556, Rev. Z' serese amareie re,an se rue = GE. NEPD, San Jose, Calif. 22A4912. Rev. 2 ' Design specificassene consfied by B. N. Sridhar Pvd. Eas.ssee. Calif g.,,3J8345 See s emelysis separt eestaned by B. N. Sr1< mar' p,,g, g , s,,,, Calif g.,,3,pl345 CER'ITFICATE OF SHOP INSPECTION 1, the . heiding a valid comunisaism leased by the Neaa Board of Boiler and Pressure Vessel toepecanes i and/or the Sasse er Pseetmee of North Carolina and ensplayed byDepartment of Labor of State of North Carolina he, La ed she pere et a p msne , emet described is chie Partlaa Does seeart am 3 ,,8j,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,, ame tenet.the frPT Cerencase Hoteer hee conseuetes ele een la accordames wie me ASME Code Secuse W. By signing shis eersifiesse, meisher ine Isosometer aar kie employer masses any waerency, empressed er impiled, concere. tas the eart desertbed la this Partial Data Report. Furthermore. seither the inspector nor his empleFer shall be liable in any mammee for any peremmel isiery er properrydesmage or a Lees of any kind erseseg trearer cenaseted wish this inspection.
'" 6/23 '
81
}{A 687 PA.WC2711 Comenieeice s
. , . - .. . ~
w ~ .. . u0865
".= -
- ' =: . .'2" ",: :.:=- - - :: .. '. " .:'.==.l" ": . T " "" -'
~ = - - - " ' - - -
' (10/77) The form (E00040)mov tae ootsm.a t.am the Oets.r Dept.. ASME. 346 L 47tn St New Yorm. N.Y.10017 O
Page 186
~~ ---
~ - . - 3 p
/ y - .
# \.*
FORM N 2 U acid 1 leeme 4-g tact. se be completed 6er single well vessels. inckets ei jachoed eessels or shelle ei hees eschaegers. T.S-Nominal Thickness Coevesima ia. Allowance ia. Oi- ft in. Lengsh_ fs. is. ( -)
- 4. Se(It Meseveal s suas a sees. me. (anne,as messe speeuses)
Efficiency % H.T.' R.T.
- 1. Seemes Long_
- LT. No. of Cowees Ginik H.T.' T.S.
T.S. _ -- (bt Maaeriod
- 6. Headas (a) Meserial -
Plas sue se preen.
- Emesmae e H =-d Cenames _ _ - . .
Lee masse Ceese Apes A*eae aesame Diameser (Case. er Caes.) Thaessneee samee nemen masse (Tee. Deseen. *= del (al (b) Other fassening li remeeable, bedes weed- (o.eerine er essma sweene (aa.neeses.sene.as T.s saae r
- 7. ]acket Closuses<oeese a.en see eme.een. nee, see.as herease en _ .s messee. mewesse er seeeene Drey Weisbs Charpy impact fe.ib 575 og ,,, ,a e7
- 8. Design pressere 8 O pai as
! seas 9 sad 10 as be completed for cabe sectione
' Dh- Thickness _is. Aarachemens (e nees, men een
- 9. Tube Sheece: Sessionary. Mazep-I (semeses is ymouro cause an aves. n.4 Die. Th cheess_la. ?-
Fleasies. Masarial Number Type O.D. la. Thicknese -- sees. (sw. erin
- 10. Tubens Maseria!
teeme 11-14 incl. is be completed for inseccheminers ei jacketed vessels, er chansmis ' ' ~ of heat
" * ~eschangers.
~ ~ ^
. _ . _ ~ . _ .
'Md hh -ia.'
- 11. Shells Weserial T.S. Thicknese n A!!aeance J Dia._ ft._ia. Lessdr_ft.
(same ansees. see. (assa.es mees e,ema e
- F.fficiency 7.
H.T.' A.T.
- 12. Seems: Long A.T. No. of Cownes Girth H.T.' T.S.
P T.S. (b) Maserial
- 13. Hende (an Maserial Fles Sade se Peees.
Etsw w Ceaseet Neumeemerte.d C,ee.e Emusmae Redase DLeessee (Case. se Caes.) Redans Rease Apes Ameae Thaakseee Rad &se-Leesssee (at Top, ho<com ende (b) Chamaet Ocher f assening if eemo ble, bolts used (a) (b) -(c) soeeenee se esteen emosens Drop Weighs _ fs.4b Charpy impact _ op og ,,,,,,,,g
- 14. Dee.gn peces te s p,; ,,
teems below to be completed for all vesseis eteve applicable. I Locados f ti. Sade<y Valee Outleis: Number __ Size l
- 16. Nesties: Reudere =*as How aneehee Thschees. Mewset Pweene sinnes. Tree Wesectaa ousnes. Demee menome Dee. er sase Size Locadan
- 17. Imepection Manhole s. No.
5: - Loc acaen ' Openiass: H andheie s. No. Size _. Loc asion' Threaded. No. Att ac hed = Me-o Legs _ Legs _. O<her __ e aen.
,18. Suppens: Skast t Memeer, c n om.o., io.
svs. men j ..__._._..me.-..e..e..e._e.e.._. 9
REPORT NO. NP0059-0005
.g ., 1B13-030 sheet 2 of 2 O ' FORM N-2 NFT CERTWICATE IBOLDERS' DATA b CLEAR PART AND AFFURTENANCES*
As required by abe Provmos of the ASME Code ihdes. Sectaos HI, Div. I a g, g4 gg,,,ga y General Electric Company, Castle Hayne Rd. . Wilmington. N.C. as e emer w we carensene iman., g4 ,,, General Electric Company, San Jose, California OtEBC) ammen ens v a c=es m une=r er ===a==r A4264 .,,,,,g,,,
,44 m. 76mur an1 0, ing prepared W D. L. Peterson *i g4 c ,dingi,o,
~
(W r . of PassI pecs d Control Rod Drive. Model #7RDR144DG001 (c) A,ptie.68eAsb4EC desseenannt.Edki e I974- Add.ed.2- - W'75 _C w '1361-2 c2 . 1
- 1. Cap 16689274P1 1 (167A2343)
SA182 - F316 Code weld y N; 3/8 thick x 11/16 OD R50YP102 ;' l i I l
- 2. Indicator e 1pe 166B9313P1 6 SA312-TP316 ' .
N I 3/4 sch 40-seamless pipe l l 0.113 wall thickness '
! 1.065 max. dia. Reactor vessel O '
thimble I l - l : V 3. Plug 159A1176P1 t I I SA182-F304 . tl : l L--- 1/4 thick x 0.812 OD - l l
' w
- 4. Flange 9190610P1 (719E474) Code weld
\ x, xxs
- 1 N
.SA182-F304 850YP102 '
NN 8 3.37 thick x 9 5/8 00 % f neck 1 1/16 thick x 5.0 00 . ,
/ \
. 2.875 ID ii
\
'5.
e- N N Base 137C5311P1 ~~ XM-19 ASME 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 P50YP102
- 7. Cap Screw 117C4516P2 CONTR01.f,0DDRIVE SA193-B6 .
DWG - 768E534 6 ea.1/2 dia. on 41/8 bolt circle t - - -
'9. Nut 137C5934P1
- 8. Plug 175A7961P1 IM-19 SA479 SA182-F304 1.30 thick z 2.62 dh.
0.38 thick x 1.307 dia. . 0086G Page 187
i l l REPORT No. NP0059-0005 NIS-2/NR-1 OVNER'S REPORT POR REPAIRS OR REP!ACEMENTS IBl3-03) i As required by the Provisions of the ASME Code Section XI PNPP No. 9308 Rev. 6/93
- 1. Owner: Cleveland Electric Illuminating Company Date 3-27-96 P.O. Box 5000, Cleveland, Ohio 44108 Sheet 1 of 3
- 2. Plants Perry Nuclear Power Plant Unit One 10 Center Road, North Perry, Ohio 44081 W.O. 95-694 R/0 (Repair Org., P.O. No., etc)
- 3. Vork Performed By: Cleveland Electric Illuminating Co. Type Code Symbol Stamp N_R 10 Center Rd, North Perry, Ohio 44081 Authorization No. 33 Expiration Date 7/18/96
- 4. Identification of Systems 1B13 Reactor & Internals
- 5. (a) Applicable Construction Code ASME Section III, NB , 1974 Edition i
Vinter 1975 Addenda, Code case 1728, 1644-4 7 -272 l Nko's j%;.g, y ggg 6 (b) Applicable Edition of Section XI Utilized for Repairs or Replacements: 1983, i l Summer 1983 Addenda b-
- 6. Identification of Components Repaired, Hodified, or Replacement Components Name of Name of Manufacturer Nat. Other Year Repair ASHE l Component Manufacturer Serial No. Board ID. Built Replacement Code No. or Hodification Stamped l
F1 ping General '
, IBl3 l System Electric IBl3 64077 D0008 1984 Replacement Yes l
l I i l 1 l l 7. Description of Work: Replaced Control Rod Drive Mechanisms (CRDM) and 1" capscrews. See Remarks
- 8. Test Conducted: Bydrostatic- [ ] Pneumatic- [ ] Nominal Operating Pressure- [X]
i Other- [ ] degrees F Pressure 1038 psi Test Temperature 175 O LJ i. l Page 188
I l NIS-2/NR-1 OVNER'S REPORT FOR REPAIRS OR REPLACEMENT.
- 9. Remarks: Installed a replacement CRDM in core location 38-3) S/N A4843 usine (R) capscrews l"-8x5%" Ig. ASME SA 540 Cr. B23 (4) Htf 99896 and (4) Htf 61811.
1 NOTE: Attach all applicable Manufacturer's Data Reports. Supplemental sheets such as lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 ! in., (2) information in items 1 through 6 of this report is included on each I sheet, and (3) each sheet is numbered and the number of sheets is recorded on the front of this form. CERTIFICATE OF CONPLIANCE Ve certify that the statements in this report are correct and that allconforms design, to material and workmanship on this Replacement (repair, replacement, or modification) applicable section of the ASME Code. 33 to use the NR stamp expires 7/18/96 o CertificatA Signed of Aut)L u le dAkud/ )(. piz9 stu h No.__ tion h&& aAJ (owner or er's Designed, Titfle) Date Dd GL 19 x i
; CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the State or Province of OHIO and employed by *ARIGTRIGHT HUTUAL INS. CO. of NORV0OD, MA. have inspected the repair, modification or replacement described eel, .x es19% , and state that to the best in thisknowledge of my report onand _@belief, this repair, mo31fication or replacement has been
- made or constructed in accordance with Section II of the ASME Code and the National Board rules as defined in the oublication NB-102, current edition.
By signing this certificate, neither the Inspector nor his employer makes any varranty, expressed or implied, concerning the repair, modification or replacement 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 1 s of any a from or connected with this inspection, yo m . - Commissions af ef67 T en**- V (Inspector's Signature)
- FACTORY HUTUAL ENG. ASSOC.
Date Afe<. OB 19 % r . O
i l l REPORT NO. NP0059-0005
. . . . . - _ _ , . - . . . . _ _ . . _ . _ . ~ . _. _ _ _ _
1B 13-031 Sheet 1 of 2 \
/ g . - y '. . . ,
- M . Sheet 2 of 3
~~
FORM N-2 NPT CERTIFICATE HOLDERS
- DATA REPORT FOR NUCLEAR PART AND CPURTENANCES*
*Es reqilired by the Provision of the ASME Code Rules. See:ios Ill. Div. I l
i l l
- 1. (a) Meadecewed by General Electric Contoany, Castle Hayne Rd. , W41mhgton, N.C. j u e. wwrcreec.=ese=,
l (b) Ma f. cared t- General Electric Courpany, San Jose, California (NEBC)
- ca a.e ma cnusem.noenen.
- 2. lwcanoegerttacase Holder's Sertal No. of past M3 Nac*t ad. No.
(a) Camaracted Acceeding es Drewlas Nm 768E534G001 * * ***#*
- Dr wlas Prepared by i . . Control Rod Drive, Modal f7RDR144DG001 (b) Descripues of Part !aepeceed
. . NZU/
(c) Appilcable ASMECade:SectioeIII,Ediales 1974 W75 1361-2 1
. Addendadace . Case No. Class
- 5. Mas Standard part for use with Reactor. Hydrostatically testad at 1820 pai.
~ m w a. - w m..r. . n .- - :. I
- Total number of sheets - 2 I
1 l
. Te certify chasche seassuments made la chie are cornwet and shis vessel part er appersemence as defined is the Code coa. i fosma se she rules of cesseraction of she ASME Section 111. l (The appucable oesten spectaennen and stress neport are not the responsabatsty et the Nrr certinenee usader for parta. An MPf Certif. 1 icass Hokier for appurtenances is respammible for ihraiskies a separase Deessa Specificacios and Otress Report if the appurtenance is act teetmeed in the compement oeenen specsacanon and stress aeport.) '
l signed O' " 8 6 D.- _19
<mer cneessa. w.sem i
Cardficene of Amihmization Espires "JOn'* 16 1984 Cerdlicase org +8- No. l 6 l i CERTIFICA'IlON OF DESIGN FOR APPURTENANCE (whes appliemble) GENERA'L ELECTRIC CO., SAN JOSE, CALIFORNIA De n.se inforazio. on file - 22A5556' Rev. 2. 5 resa analysis repers on (Ile as GENERAL ELECTRIC CO., SAN JOSE,, CALIFORNIA 22A4912, Rev. 2 . Design specificadoes certified by B. N. Sridhar Prof. Eas.scane Calif ges.goJ8345 t seese analysis report certified by B. N. Sridhar p,og.g g,Sen. Calif Res.No.18345 l CER'11F1CATE OF SHOP INSPECTION I. i I. the undersigned, bolding a valid cosamission las$ed by the Nealoemt Board of Boiler and Pressure Vesse! taspectors l l and/or the $ sate or Province of . North Carolina e and employed byDepartment of I. abor i f og State of North Carolina hive.laspeered the past of a presesre vessel described la this
. Partial Data fleport on 1/2d- 16 a.h.)and state that to the tk.st of my knowledge and belief. the NPT Ceruncate Holder has constructed this part in accordance with the ASME Code Section 111.
By sigr.iag this certificaer, seither the lampector nor his employer makes any warranty, espressed or implied, concern. I I ins the part described la this Partial Data Report. Furthermore nettner the Inspector nor his emotorer shall be liable in any meaner for any personal lajury or property damage or a loss of any kisd arising froaror connected with this taspectica.
, 1/24 83 Dace - - ^ 19
- N.C. 723,PA.WC1766, OHl0 n
an Commissions no.a a.4 re, s n., e tu. e N.. e n m. A. I .t.r . ste.ew.'
., u ... .. .
,.w_.. . -. ..
- m. $ - .
.e . u . m
- i. n- i.: - .
2 i p) L
. _ . _ _ . ____ - - . . . . . . . . , . . . . ._m ... ....,
t Page 189
. b . p . . : n.-
~
FOIN N.2 (bacL) Iseme 4-g imet. to be eagleted for single wait vessels, jackets of incketed sessels. or shells of bees enchaagers. ' Nominal Carmsson b
- 4. Sheila Material T.5- Thickne ss_ ia. Allowance _ia. Di- f. - is. 1,en gth_ ft. in. i (Eind h spee.Ms.) (Wa.ed Reage speettled) 1
- 5. Seamm Leeg H.T.* R.T. Efficiency 5.
Gicth H.T.' R.T. No. of Cowse s l l
- 6. Heads: (a) Muerial T.S. -
(b) Maaerial T.S. Lee ma ceews Emmette rauerseet conaees Heed ,meesses rtes same se phen, rfep.benee,eeden Thaene... Reesmo R da Res. Aees Aass. Rees otenesw gce.e. e, ceae.) (a)
. (b)
If resnoesbie. botes used Other famesing caseaseiea. syse, we T.s..saae, menee , , (o. swine w onesen emeiemp
- 7. J aches Closures (o .unne es se e.e.ead,mee .. u wee sace es-enea s.u measse,s unee er sa mens Drop veight Charpy impact it.lb S. Design pressure s M p,g , 575 ep ,,,,,,,, op l
'leems 9 and to so be coa.ptesed for :=be sections
)
- 9. Tube Sheeses 5 ationary. Muerisi Dia. Thickness _is. Attachmens (same a sese. Me.) (suaeus se presswel (eetaea. seuse>
Flossias. Mmerial Dia. Thickness _la. Atterh=ent
- 10. Tubes: Maserial O.D. la. Thickness ***sYe'.. Number Type (se. ar trs leems 11-14 incl. so be completed foe laaer chambers of jacketed esseels. or chamaels of hens eschengers.
~~~~ ~ ~ ~ ~ ~ ~ '
Nusal %h t1. Sheila Muerial T.S. nickness J Allowance la. Dia._ fc._ia. Length ft. (Kans a spee. Me.) (Mla. ef R eese speetfled) i
- 12. Seems: Long H.T.' R.T. Efficiency 1
Girik H.T.' R.T. No. of Courses l
- 13. Heads (a) Material T.S. (b) Manerial T.S.
Cseen Emmenle Etttettent ceaseel Heeuopherte & Fles Side to Prese. l Lee sten Tidennes*- .Rodius- Redaue Rmse Apes A&ste Redame Diameter (Come. er Come.) l (a) Top, bocios. ends (b) Channel if remoonble. bolsa ased (a) (b) (c) Other f astenias so.eenne w seteen emetent , Drop Teight . i Charpy impace f e.lb
, l L 4. Design pressure' gi as *F as temp. of *F 1
1: ems below so be completed for all sessels where appihable.
- 15. Safety Valee Ouelets: Number Size 1.oension
- 16. Nozzles - '
rwpee. (Intet. Meanteremens ow s.t. ocean, Musisee Die. w sts. Type useertaa Thae neu Wes enea Hee Antoehed
- 17. tespeccion M anhole s. No. Size Location Openin gs: Handhole s. No. 532 Loc asion Taeended. No- Size Location
- 18. Supportas Skirt Lugs Legs Other Azt ec hed
( *h*re 4. Howe tv.s e. noe t we.e .i c m .<> < De eerine s O
REPORT N3. NP0059-0005
~
4 1BF3-03J . Sheet 2 of 2 M.. Sheet 3 of 3 *
' FORM N 2 NPT CERTIFICATE HOLDERS
- DATA REPORT FOR NUCLEAR PART AND APPURTENANCES
- ty -
A's required by the Provision of the ASME Code Rules. Section III. Div.1 . [, t
- 1. (a) Manuf actured by General Electric Company. Castle Hayne Rd.. Wilmington. N.C.
General Electric Conpany, San Jose, Calif'ornia (NEBG) (b) Manufaceuned foc ma=e sad asev= .r a cweseau n.ie.,s., w.we a.ci u = a.au N as*1 Bd. No.
- 2. Ident3Acation Certincate Holder's Serial No.of Part
. . eterson (a) Conserweied According to Dravias No. 768M14 Cool Drawiss Prepared by (b) Descriptica of Part laspecsea Control Rod Drive. Model #7RDB144LC001 N207 .. ..
(c) Applicable ASMEcodessectient!!.Edizion--- 1974 , Addended;f W'75 c.,e N 1361-2 cia.. 1
- 1. Cap 166B9274P1 1 (167A2343)
SA182 - F316 _ ., Code weld P50YP102 N ; ._ ;- 3/8 thick x 11/16 OD 1 I 2 l l
- 2. Indicator Pipe 166B9313P1 -
SA312-TP316 . l N 3/4 sch 40-seamless pipe g 0.113 uall thickness
- l \
p () 1.065 aux, dia. Reactol' vessel thimble i i l , I
*i ~ 1 i l l l
- 3. Plug 159A1176P1 l g SA182-F304
, I t l'
1/4 th,ick x 0.812 00 . I
* . 4. Flange 919D610P1 (719E474)
.SA182-F304 .
' Code weld
.850YP102 s NN I
8
\
N f 7 7 \ 3.37 thick x 9 5/8 OD - neck 1 1/16 thick x 5.0 OD 2.875 ID i_, 4 g- h N
- 5. Base 137C5311P1 ~"-'~ Q6 l N XH-19 ASME SA479 7
3.0 OD x .884 ID - c - - --
- 6. Ring Flange 11485122P2 SA182-F304 Code weld 1 1" thick x 5.0 00 x 1.75 ID P50YP102
- 7. Cap Screw 117C4516P2 C0!! TROL MD DRIVE SA193-86 DHG - 768E534
! 6 ea.1/2 dia. on 41/8 bolt' circle
- l - - -- - 9. Nut 137c5934P1
- 8. Plug 175A7961P1 IM-19 SA479 SA182-F304 1.30 thick x 2.62 6 .
.O'. m j 0.38 thick x 1.307 dia.
l O Page 190
l REPORT N3. NP0059-0005 t iBi3-032
/^\
l V) 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. 6/93
)
l
- 1. owner: Cleveland Electric Illuminating Company Date 3/28/96 )
l P.O. Box 5000, Cleveland, Ohio 44108 Sheet 1 of 3 l
- 2. Plant: Perry Nuclear Power Plant Unit One l 10 Center Road, North Perry, Ohio 44081 V.O. 95-5193 R/0 (Repair Org., P.O. No., etc)
- 3. Work Performed By: Cleveland Electric Illuminating Co. Type Code Symbol Stamp NR_
10 Center Rd, North Perry, Ohio 44081 Authorization No. 33 l Expiration Date 7/18/96 )
- 4. Identification of Systems IB13 Reactor & Internals 1
- 5. (a) Applicable Construction Code: ASME Section III, NB , 19 E Edition I Vinter 1975 Addenda, Code Case 1728, 1644-4, N-272 I N-zo7, # %I- A D*.A r/i Bit.
(b) Applicable Edition of Section II Utilized for Repairs or Replacements: 1981 Summer 1983 Addenda I \.) l
- 6. Identification of Components Repaired, Hodified, or Replacement Components Name of Name of Manufacturer Nat. Other Year Repair ASME Component Manufacturer Serial No. Board ID. Built Replacement Code No. or Hodification Stamped l
Piping General ,
. IBl3 System Electric IB13 64077 D0008 1984 Replacement Yes l
- 7. Description of Work: Replaced Control Rod Drive Mechanisms (CRDH) and 1" capscrews. See Remarks
- 8. Test conducted: Hydrostatic- [ ] Pneumatic- [ ] Nominal Operating Pressure, [X]
Other- [ ] Pressure 1038 psi Test Temperature 175 degrees F e Page 191 l
l l l l l l
- l l
I NIS-2/NR-1 OVNER'S REPORT FOR REPAIRS OR REPLACEMENTS 1.)
- 9. Remarks: Installed a replacement CRDM in core location 50-11 S/N 8620 using (8) capscrews 1"-8x5 1/2" Ig. ASME SA 540 Gr. B23 (8) Htt 99896. ,
1 NOTE: Attach all applicable Manufacturer's Data Reports. Supplemental sheets such as lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded on the front of this form. CERTIFICATE OF COMPLIANCE Ve certify that the statements in this report are correct and that all design, material and workmanship on this Replacement conforms to (repair, replacement, or modification) applicable section of the ASME Code. 7/18/96 CertificajeofA o ization No. 33 to use the NR stamp. expires Signed Mtudd . m Sen & C,< qws - Date 2'10vner
- f. or Qlo 19 Owner's Designee, Title)U J
l CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the State or Province of OBIO and empicyed by *ARKVRIGHT MUTUAL INS. CO. of l NORV00D, MA. have inspected the repair, modification or replacement described in this report on h4 cs. .39 , 49 'M, , and state that to the best of my knowledge and belief, this repair, modification or replacement has been made or constructed in accordance with Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the repair, modification or replacement 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 oss of any, hind from or connected with this inspection. cg/m a_ # _. U Commissions A16&c3 I ce m . l ' Date _ ' (Inspector's h e>, c99 Sfgnature) 19 94,
- FACTORY MUTUAL ENG. ASSOC.
I t l l 1 l i l 1 I r
REPORT No. NPOO59-0005
#M ESGNM M3 OP:Si % EE 8tM ] Sheet 1 of 2
\v} FORM N4 NPT CULTtrtCATE hot.DF.RS' DATA REPORT FOR NUCt. EAR PAAT AND AFFVRTENANCES* As reesired by the Provieson of th ASME Code Rules. Satson lit. Div. I
- g. (el pee fecewed by General Electric Company. Coetle Hayne Rd. , Wilmington. N.C. l ea. e e m aartc -e.e m e 1 (63 u.a.,, yea g , _ General F.loctric Company. San Jose. Celifornia sae-. ese one, w a cwese meim, su e.e e em e, .
- 2. edeseacauen-cevancate nesder e seeten ne. or ru, 8620 g,,. ,4, g ,
(a) censiceewd Acceedie, se D,s. ins No. 68E534C001 n, D. L. Peterecu (bl Dearteelee ei ren supee.e4 Control Rod Drive. Model M RD3144DC001 N201 (et Applicable ASNC Codes gaden tti, g41,ge, 1974 , g4 M' 7 3 . Cue No. ~ Clum 1 g gg,, Standard part for use with Ileactnr. Hydrostatically tested at 1820 psi. an .va v.uen.e. ee .euse
.eesense.e
- Total number of sheets - 2 l
We cently abeethe sensemenee sede la side l ene esseecs and ele vessel part et appeteesence se dedoed le eine Code ces. fases se she selee of eseern. cades of she ASME e Seccles tit. I Ghe icene spotkable Desten Spectneauen for appurtenances is resp and Stress fLesart are not the reseene:Intity of the NPT Certificete Heidet dbr parts. An NPr Certif-a segernae Desige SpectGenteen and Stress t the - in ene somsement Deesen 8,oseW4e _ is met ene eetacensefor Sausshieg one Satene neeeru i o., 11-1 g, 79 sissed '3' IEEPD-WMD-QA Sy inryc.eeem m mn l c edile . ed Aedwrieede sepa,ee June 16. 1981 fv coedneses a wtada n <PT t N-1151 [) (_/ CERUFICARON OF DESGN Ft)R APPURTENANCE (, bee appliemble) De 4 t h h a nie a CE, NEPD-MHD-QA, Castia llayne Rd. Filmingtone N.C. 22A5556, Rev. 1 sene mahete.epwise nae u CL InPD-WD-0A. Cas tle navna hgeliminnton. N.C. 22A4912. Rev. 2 _ Design speelricassou cengsed by B. N. Eridhar Peet. ges. s.e.e Ca lf,f _ Res.NeJ8345 sareae sealysis sepen eentfled by B. N. sridhar p,g, g,,, s,,,, Calif g, g ,18545 CERTmCATE OF SLOP INSPECTION I. de ondeselseed, biding a vel 14 cesaleeles 4seeed by abe Nealeest Beeed of Bella and Pressure Vesselleapectere ese/or the Same er Pseelmee g _ Worth Carolina med eenployed byDepartiment of Labor og State of North Carolina beve toepuied de pas of a pressere eenet deuribed in shie Pardal Data sepan se 11 selbe ousemetuse bee of my knowtedse and te46ef.the NPT Cerutkate He4dee has constreeted this part la eteertance with the ASME Coes Seedse Ill. By elantes shte cenifienee, nelsbee se lupeeser see ble e ployee mehes ear weeraety espressed er lap 11ed. eeeeeen. Ins the sere dentftbed la this Partiel Date Report. Furthersnote, seither the leapettet met ble esmalerer shall able wish be liebte la any menaet fee any pereenet lejecy se peeperty damage et e less of ear kane estales free se esseeceed leapecties.
***--' ^ 11-I $$
7'
!w d
. a.see.- ca deaisee NC 723. PA WCl?66 OHIO
. . .- . a,e.e. . .e . e .
m . :: rt. ':.r r.m. :=:.r:::::.':=1..::'.=:'r.W:e:: " "" ""
. ~ ~ " ' ~
t10/773 Thas form MUOceC) mew tm otetainee feom sne 0 dee Osos ASMs.145 E. e7en si. 74e= Yeek. N.Y. t 0017 n on J v nn nei nr.*. -, -~ / \
\
/
%./
Page 192
000'30Vd 006S549016 iP:51 % 82WW F0fN N.2 (becU 9 tome 4_a snee. be eempie.e4 su e.a ie ..it ...sei., i. eke.e es . 4e.e4 ee e,es er eheu e e# 6.= euh .... () Cwee s
- 4. fa.en, u m u4.a Nemisel Thie 6.e . . ia. Ane..i.en ce _ ;e. Dia._ re. i Leeseh _ fs.-
c a u . _.,__
. se. ne. T,.5.
aum er aease seee.neei .a .
- 1. Seamos Long H .T. ' R.T. Eff.ciency %
Cinh H.T.' R.T. No. el Ceueses
- 6. Needes (al Meeeetal T.S. (b) Wetedal T.S.
Leeeeeee c,e=. st wsae suipaaees Coseest Heeseeeeewei Fles snee te Peese. (Tee. 6m. . esses thus ees acenes ases.e acu aees aeste m eew. Diesiew (ces,. cem.: (al (%) If eemeuble betse used 04 hee foseeeing gueouses.seee. no t.s sim.awee., coe ente se esinen emeums
- 7. Jacbet Cleenvet e..is.o.,e.e.m coeeeram se ese. e ssee 4.= semen .w eeuee.e eenee e. neun, Drop Welske Cha#py impses fe.lb
- s. Desige peessuse s 1250 ,,; e, 575 ep e, ,e.,, ,, op leems 9 and to se be complesed fee embe sectione
- 9. Tebe Sheeses leseiesery. Maeerial Da a- Thietaeae in. Astulumeas assia a seen. pe.) (svesus a pruewn twese e. ses.ec Fleasing. Weseetat Dia. Thicknese la. Aseechneet to. Tuhesi Maeeelai 0.0. la. Thickness '"e"*'e' . Neubn Type -
(see. et un leeme 14-14 &act se be sempleeed fee anaee ebambeen of lecheted geneets et chaneets ed bene enehengers. Nominal Cereesien ll. Shetis Meserial T.S. Thieksesa Ja. Allowamee _sa. Ola._ fe._ia. Leegeh _k. in. tunne a sees.m.. <wie. or p ees e seeetneet
- 12. $eams4 Leeg H.T.' -
- T.
Efficie.cy % Ctesh H.T.' R.T. No.ofCouens
- 15. Heads (al Maseelal T.S. (bp Maeeeial T.S.
cre=a E#wase sis 4ewea cemie se Me eeheewes rees s6ee e. Peese. L.een ie. Twesee.e n es.. a seise me aees aa i. aseise otemeen <ceae. e ceae.i (a) Tep, bestom, ends (b) Chamaet if #emove6te. beise esed (a) (b) _( si oikee esseeeing noe*= ee er eiewn emewn Deep Weight . Cha#py Impses (4 14
- se. Deslaa peesseee' _ psi es 'F avsemp et 'F ltems below to be completed fee att vessels where app;icable.
- 81. Seleer Valve Ow e,es Numbee Slas Locatica -
- 46. Neasless Pesreses stalet, metafees emeas cettet. Deetal frisetee Dia. ee stee Type M es ee.at Th6e hnee s M ese hea New aneenee
- 47. Isopece6ea Maskele s. No. $ se Loc ation Openings H aedhele s. N o. Sise Lee seiea Theesded. N . $4ae Lee st.ea
- 18. Seppenes Skiev _ __ Luse _ Less ochen Aetached ivee Nei en .en s ee wi e od o..me s se e e a me i
'(f Peeteele Meet.Teostee.
Leet e. bee ined.een se e ste. net peeeen.ae esen s e.desseet Ismededet ee whee septeachte. O
r REPORT No. NP0059-0005 IBl3-032 010' m M c29016 Sheet 3 of 3 1>:Si 96. 82 MM V Sheet 2 of 2 FOSM I44 twf CERTtFICATE ItotAtad' OATA REFOEtf FOEL NUC1. EAR FMtf AND APPURTENANCES * ! As reqtaired by the Proneise of the ASME Code Rules. Section III. Div. I I g, g , w,,,,,4 g Ceneral Electric Company Castle Itayne Rd. . Wilminaton. W.C. l es.o. ese ese.e e are c.ee ame=. ' gy %w s General Electric company, Sao Jose. California OrEsc) L Idesaneesee<, euseees es neer's serialsee etfees 8670 M $4. No. (e) Ceessenesed Aseeedaag se Deesieg A 1AAF "Ar' ant presing p,,,e,ed h O' L' E***E808 (4 Deesdyden ei Pae toepeessa Control Rod Drive. Model #7tDR1440C001 N207 (4 Aerilenue AshtECodesSeedseRt,Ediden 1974 ,Addenasa W'75 Cees No. 1341-2 Class I , , _ , Cap 16689274P1
*1.
(167A2343) SA182 - F316 Code weld N 3/8 thick x 1 1/16 00 P.50YP102 _- I i I l
- 2. Indicator Pipe 16689313P1
- I seamless pipe %
0.113 wall thickness e
^
% I 1.065 max. dia. .
l Reactor vessel l . .
*
- I
- 3. Plug 159A1176P1 I
I I l l l 1 . SA182-F304 - ' i '-- i 1/4 thick x 0.812 00
. 4. Fla 9190610P1 (719E474)
Q. %M i M1 F304 3.37 thick x 9 5/8 00
. ~850YP102 L wK 8 neck 11/16 thick x 5.0 00
. 2.875 10 .
/ \ l
.N [
\ <
l 5 Base 132C5311P1 " *
.h b E19 ASHE SA479 3.0 00 x .884 10 -
l
- 6. Ring Flange 11485122P2 ' --
SA182-F304 1" thick x 5.0 00 x 1.75 10 $ph
- 7. Cap Screw 117C4516P2 SA193 86 CONTROL 900 ORIVE 6 ea.1/2 dia. on 41/8 bolt circle DWG - 768ES34
- 8. Plug 175A7961P1
' 8* l'"" 13EC383'Fl
*"'l' 8^'7' SA182-F304 O.38 thick x 1.307 dia. 1.30 chick 2.62 m . l l
l l l O> Page 193
I t s l l l REPORT N3. NP0059-0005 l 1B13-033 O- NIS-2/NR-1 OWNER'S REPORT POR REPAIRS OR REPLACEMENTS As required by the Provisions of the ASME Code Section XI PNPP No. 9308 Rev. 6/93
- 1. Jvner: Cleveland Electric Illuminating Company Date 3/28/96 P.O. Box 5000, Cleveland, Ohio 44108 Sheet 1 of 3
- 2. Plant Perry Nuclear Power Plant Unit One 10 Center Road, North Perry, Ohio 44081- V.O. 95-5196 R/0 (Repair Org., P.O. No., etc)
- 3. Vork Performed By: Cleveland Electric Illuminating Co. Type Code Symbol Stamp NR 10 Center Rd, North Perry, Ohio 44081 Authorization No. 33 Expiration Date 7/18/96
- 4. Identification of Systems 1B13 Reactor & Internals
- 5. ('s) Applicable Construction Code: ASME Section III, NB , 1974 Edition Winter 1975 Addenda, Code case 1728, 1644-4 7 -272, N-207, 1361-2 l (b) Applicable Edition of Section II Utilized for Repairs or Replacements: 19 E
' {
l Summer 1983 Addenda
- 6. Identification of Components Repaired, Modified, or Replacement Components
~ ?
l 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 . IBl3 System Electric 1B13 64077 D0008 1984 Replacement Yes I
- 7. Description of Vork: Replaced Control Rod Drive Mechanisms (CRDM) and l" capscrews. See Remarks
- 8. Test Conducted: Hydrostatic- [ ] Pneumatic- [ ] Nominal Operating Pressure- [I]
Other- [ ] Pressure 1038 psi Test Temperature 175 degrees F Page 194 i i
1 l NIS-2/NR-1 OVNER'S REPORT FOR REPAIRS OR REPLACEMENTS O
- 9. Remarks: Installed a replacement CRDH in core location 02-23 S/N A3519 using (8) capscrews 1"-8x5 1/2" lg. ASME SA 540 Gr. B23 (8) Htt 99896.
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 Ve certify that the statements in this report are correct and that all design, material and workmanship on this Replacement conforms to (repair, replacement, or modification) applicable section of the ASME Code. r satio 33 to use 7/18/96 ) Certificatp of 4u Mlk, the NJ,htounL) stantp expires Signed /Jeut d - bide 6 (Ovner or Owner's Designee 9Titl6) Date Y H l e c99, 19 Q(o CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of f I Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the State or Province of OHIO and employed by *ARKVRIGHT MUTUAL INS. CO. of NORV00D, MA. have inspected the repair, modification or replacement described in this report on Muen 09 , 19 ')6 . , and state that to the best of my knowledge and belief, this repair, modification or replacement has been l made or constructed in accordance with Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the repair, modification or replacement 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 . s of any nd from or connected with this inspection. Commissions,ufBSG T ho , . g
. .m em -
I Date
" '(Inspectords
#/w e;, a:79Signature) 19 c) 6
- FACroRT MUTUAL ENG. ASSOC.
O I
l l REPORT NO. NP0059-0005 IBl3-033 S00 7)tM 606SS/9016 Sheet 2 of 3 6 DST 96. EE W.i
, , sheet 1 of 2 FosLM N.3 NFT CEST1FICATE 8101.DEltS' OATA REPORT FOR Nt)CI. EAR FAa7 AND ApftlRTENANCE3*
As es, seed by she Provimies at the ASME Code aulee. Secti.m itt. Die. I !* 3. gai nsees.e d br_ Ceneral 31ectric Coupesy Castle Royam Rd., Wilmington, N.C. e eem .e are c e e.e - gu se.aw.co.ed s Geomral timetrie campany, san Jose. Californie (NESC) e .se .e .r a c - ee - L assessessen.cmensen semesw a s assess see.arpw, _.A3519 w , p4, g,, g,, % ,,, % ,gg, 4 ,,,,768tS34G401 , , g D. L. Peterson (W Inmeded.e d pess sew Centrol Red Drive. Model #7 ads 144DG001 IUW (es Aseslee6ae AdhitCede$ectiesE1.Edl.ies 1S7k . Addeededere W'75 ,c, ,,,,_ 1361-2c , ,, 1 f 3. aemedio, _8tandard part for use with Reactor. Nydrostatically tested at 1820 pai.
<n.we
.: a s .u.ai. - - _;
- Total esseber of sheete . 2 s
i se seesi made in w eleneue I ' seeme = e#r essaseems enesessene eremmeneseen w ee Ames E seawee eu.med ese enat p = e,pensenese u denud te se coes no. g:The l assim seesesseuse
,, g gg==s , m, meg
, end seem Des. noen me een me nessesam. se = a -iitme t, et me wrf - c.orseneem u,nise ser eeru e
ge,, 7/21 g, 80 % GI MIFD-lBdD-QA
- g . - ,y e c _ me e
,,,,,,,, g w,,g,, g,,,,, June 14, 1981 .
c,,,,,,,, ,,, ,,, MPT N-1131 l CER11 FICA 110N OF DESIGN FOR APPUR1ENANCElesee appliemble) ! peds.i heises se ate a CE. utrD-leID QA. Castle Bayne ad., Wilminston. N.C. (
, 22A3334, Rev. 1 ' ~
same maareteeepen a fueascm. introm. caneia navna na. v41.h con. v.c. 9, a . j.;,Q ,
,,1 22A4912, Rev. 2 ~
Deense speettiendene eenitieg 6, n. M. sem. p.et.see.s.m. Calif . .. see.neAQM
$sese .netrele sepen seedneg g, 3. N. Sridher p,g, g.,, g,,,, celif g.,,,,,1.834 5 CER11f1CATT " SHOP INSPECTION I. se endevolemed, holdies e utid unmisden las the Natu.I Send et seita and preen Va I te pu. ore and/m de $sene a pseelee, g llorth Carolina . emplered byDepartment of t.ebor a state of North Carclins % inepeewd she pen et a penewe euees damned le sie
! perees seen mesen m ! 7 /21 . _Agne amie me, se me nesi eg ., is,s , cas I l ese er een.er.me are cnonsen aaaes ele emiaanse, seismamenenme in mmee en mieesessu,me empiere menee me eenear in eme-se,nse eeeeeeeed -inerme 4.e.a.ns.asy,e impitee, come ee. onese m. l ,,ay, g r
,.t.ee me eart deoe.nbe.e nee- to am.i.e
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- - e mete nevert. Furthe.r.a.we.
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~
!e b Page 195 l l
900*Ildd 606T.69016 6C:SI % 82 2RA4 FORM $4 2 (becu O seema 4 a ta,s. a. h. e apse. d s
.iasi, .au .eswei, .adeen ed iedeud . a s. ee .h tis ei hen enehaasee.., ,
No inst Ceseess.a l 4 soiesti Mmeetal._a 6 se T.1... a #.esaa a .ns. d..e .i
.. ia. Ais aae e _,..a. o.4.-- f s. ia. t.eassh 8<. in.
<m
- 1. Seemm Leas H.T.' - _ R.T. EHieiency "A . . . .
Cinh H.T.* R.T. No elCow ne ,
- 6. Hendee (al Matental T.S. ( b) Mateein! - T.S.
Lueewa ca a um ms. Eis6ee .e coa ..a se. .en.nus Psm side se pen (T*e, **ua. **d.t no.ha..e Red'.. 8
- din a .. ae.a anese m use. Da *..<w (c . m cea..n (a) ,,,
(b) if eemeesbie. belte used Osbee fasemias gu.ewme. sen. se T.s stu. eswas.e3 to.une. .e eum net.he
- 7. jaeket Closwees in... w *e... .. .... J.um.e. . a .a..n .u... ..u ,
Deep veisha Charpy imput fe.lb
- 8. Denism pees e ,e t 1250 ,eg , 315
- __ F es u, e4 'F l l
Seems 9 and 40 se be eemonesed fee e.be seetleas
..w.,Thichaea s in. Aes chmens 1
- 9. Tube Sheetsi Sestlanary. Mmeeia' .. .. a s,... .., 04 a. . .. , o .... e. . n..,
i Fleselag. Maseelal Dia. Thiskeess la. Aisschaeas l
- 10. Tubes M4seeial 0.D. la. Thiekaess _ *7sTe'..
. Nwabee Type items 11- 44 Leet, se be seenpleted dee Lanee chambess of jackened vessels. et eheamelo e4 heae escheesees.
Nomimal Cervo sien 6 ll. Shell Weeestal T.S. Thiemess Ja. Alleesace is. Dia. _ is. ia. Leageb fs. _ _le. tut *4 6 sees.n.,a tui .e ause seusewei 8 2. Seem s: Leag H.T.8 .. - R.T. . . .. Efficiency n Clash H.T.' R.T. No. of Cownses
'^
L). Heads (a) Maseviel ir.5. tbs Mueeial T.S. F, ' ' " < c .a Kamble E44.pe!al C.as.m it.essehnteel Fim e644 M Prese. t.a neena.u messes a.ein m m.. aen Aasi. a us.. one w, scu.. w cea.. (as Top, bones, ends -- (b) Checael _ , . __ if semevable. beh s used (a) (b) (c) Othee facenias _ o.. e e. ee eneen en.une Deep veight Cheepy lepsee _ 8 e-I t
- 14. Desiga preeseve 8 g4. at 'F at semp. of *F leems below te 'ee eempleted fee all vessela where appleeable.
II. Safetr Valve Oueletaz Nuenbee Siae.,, _ Lecnien
- 16. Nessiesa p ..e esasee. *as
,s c.etet. De e.no M.e.t* 9.e. .e stee fece him.*ise thweane R se e.ae.re.*i
*** H.. ausekee d
6 47, laspeetica %4aehele s. No. Se s e L.ec aseen . Opeasa g e: H eadhele s. N o. $ia. Leens. . Thee.ded. No. - $;4e L,e .e i,a __ __ l , (8. $wpperesi Skies __ Lage g.e g s o ge, Avisc he d ! e v e. .e n.i is .. ,n. , 5 0. ... . cem. a.m..i
' te P..e. 44 H. .f *.e.ee.
#L,iet entwe taasent er er e,wi ,,euwe eut esewideve tevened.ee eMe epoiseetle.
l
REPORT NO. NP0059-0005 l 1B13-033 20 '3Wd 606S549016 Sheet 3 of 3 Sheet 2 of 2 FOctM 52 Nrr CERTTFICATE NOE.DERS' OATA REPOstr Fost MICLEAR PART AND APetJRTENANCE3* As seguired by the Frowsica of the ASME Code Rutes. Section 111. Div. I l g g4 g ,g .,g g Ceneral Electric Company. Castle Hayne Rd.. Wilminzcon._N.C. g g,,g g g General Electric Company. San Jose. California (NE30)
.a ac ,
2, ==w.m.c.ninense as.6 der's senas me et Fan A3519 y t s4. pe. (e) Canese.eeed Arceeeng se De==4.s No. 76AF91 lcm 1 D. i.e p p=.4 h D. 1.. Peterson (4 0..eelp.4ee of pas ta.p J Control Rod Drive..Hodel #7RDBl&4DC001 N207
'(o A,,ak.ble A$MECad.e $.ede.51.Edial 197t' - A44 dedue W'75 C.u we,1361-2 ciu. 1 t !
1
*. Cap 16689274P1 (167A2343
$A182 - F 16 Code wld 3/8 thick x 11/1600 R50VP102 N;_;>
. l l I *
- 2. IndtCator Pipe 166BS.113P1 l SA312-TP316 . j M 3/4 sch 40-seamless pipe 0.113 wall thickness
- l N
% I 1.065 max. dia. l
. Reactor vessel l , .
thimble I l 1 I 3. Plu 159A1176P1 8 l l . SA) 2-F304 I I g~~ i 1/4 thick x 0.812 00 q
] .
. 4. Flan
.SA18le9190610P1(719E474)
.F304 Code weld
~B60YP102 ND
- 8
] l I
[ r . -- 3.37 thick x 9 5/8 00 l t neck 1 1/16 thick x 5.0 00 .
. 2.875 10 l .
N N-
*5. Base 137CS311P1
.J b
! Di-19 ASHE 5A479
- l 3.0 DD x .884 10 -
.. y
- 6. Ring Flange 11485122P2 L-SA182 F304 Code weld l 1" thick x 5.0 CD x 1.75 ID P50YP102 l 1 7. Cap Screw 117C4516P2
- er7 w. a_ -
SA193-86 C0flTR01. ROD DRIVE 6 ea. 1/2 dia. on 4 1/8 bolt Circ 1 , DWG - 768E534 j
- 8. Plug 175A7961P1 '9 Hut 137C3934F1 SA182.F304 XM-18 8A479 0.38 thict x 1.307 dia. .
. 1.M .mid z 2.h. . , , .
li l
- i l
I jn a snn nu cc.os ac o, uu. . e ne e n , nn , . , ..
*b Page 196 i
t
i REPORT NO. NP0059-0005 1B 13-034 l NIS-2/NR-1 OWNER *S REPORT FOR REPAIRS OR REPLACEMENTS l As required by the Provisions of the ASME Code Section XI l l PNPP No. 9308 Rev. 6/93 l b ' l i Owner: Cleveland Electric Illuminatino Comoany Date 3/28/96 l
- l. P.O. Box 5000. Cleveland. Ohio 44100 sheet A of 3 l
' l
- 2. Plant: Perry 'rueleg Power Plant Unit One l 1 I 1
10 Center Road. North Perry. Ohio 44081 W.O. 95-5197 R/0 l (Repair Org., P.O. No., etc)l I I l 3. Nork Perforined By: Cleveland Electric Illuminatino Co. Type Code Symbol Stamp EB l l \ 10 Center Rd. North Perrv. Ohio 44081 Authorization No. M j Expiration Date 7/18/96 l l i
- 4. Identification of Systems 1B13 Reactor & Internals l l
l
- 5. (a) Applicable Construction Code: ASME Section III. NB , 1911_ Edition
- Winter 1975 Addenda, Code Case 1728, 1644-4. N-272.
N-207, 1361-2 l l (b) Applicable Edition of Section XI Utilized for Repairs or Replacements: 19).1., r l Summer 1983 Addenda
, 6. Identification of Components Repaired, Modified, or Replacement Components
' i s U. " s-
"' a I
Name of Name of Manufacturer Nat. Other Year Repair ASME l l Component) Manufacturer Serial No.
; Board ID. Built . Replacement Code l Nc. l or Modification Stamped i l
- IBl3 Pigng Sy em l
Gyneral E ectric IBI3 64077 D0008 1984 Replacement Yes i l l l l t t
.O - y ._;,- 1 l' l
- 7. Description of Work: Reclaced Control Rod Drive Mechanisms (CRDM) and la l l l caoscrews. See Remarks l 1
i j 8. Test Conducted: Hydrostatic- [] Pneumatic- () Nominal Operating Pressure- (X) l l Other- [] l l Pressure 1038 psi Test TempSrature 175 degrees F l l I i 1 i T Page 197
e i i e, j HIS 2/NR-1 OWNER
- S REPORT FoR REPAIRS OR REPIJLCEtENTS l l
i
- o I
I l 9. Remarks: InqLa.,11ed a a reolacement CRDM in core location 22-59 S/N A3738 usino l 1 l l (8) caoscrews 1*-9x5 1/2" Ic. ASME S A $ 4 0 Gr. B23 (8) Ht# 61811. l l 1 1 I l l l l l I
! NOTE: Attach all applicable Manufacturer's Data Reports. Supplemental sheets such as l lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 l ll in., (2) information in items 1 through 6 of this report is included on each l lj sheet, and (3) each sheet is numbered and the number of sheets is recorded on l the front of this form. l
' 1 I
,l CERTIFICATE OF COMPLIANCE ll We certify that the statements in this report are correct and that all design, I material and workmanship on this Reolacement conforms to (repair, replacement, or modification) applicable section of the ASME Code, a in d (Owner or owner's Designee, -Tjtle)()
Date A4l b M > 19 @# l r
\
M e ";'M VI.7M ) CERTIFICATE OF INSERVICE INSPECTION
, I ! I, the undersigned. holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by i the State or Province of ggIQ and employed by *ARKWRIGHT MUTUAL INS. CO. of
' NORWOOD. MA. have inspected the repair, modification or replacement described I l in this report on Nm s, 49 '19 % , , and state that to the best of my knowledge and belief, this repair, modification or replacement has been l made or constructed in accordance with Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition.
By signing this certificate, neither the Inspector nor his employer makes any 1 l l warranty, expressed or implied, concerning the repair, modification or j l replacement described in this report. Furthermore, neither the Inspector nor i his employer shall be liable in any manner for any personal injury or property 1 l ,gy ny a % > l damage or a 1,oss of any Yb nd from or connected with this inspection. Commissions /35Bsz3 Joefg
~*
Date hmo '(IIspector's M Signature)19
% + FACTORY MUTUAL ENG. ASSOC. ll
' I, O
REPORT NO. NP0059-0005 1B13-034 200*300d RIGSS&9016 Sheet 2 of 3 4E:ST 96. 82 U.A.i
. . Sheet 1 of 2 rostM N.2 Nrf CEaTtysCAtt seos.otA$' OATA ItDCST FOst MICLEAR PART AND APPtJRTENANCES*
As requered by she Provimos elthe ASMIL code Rimes. Sas;on 111. 06v. I 2 m
- 1. (a) Messieeswed by-- Ceneral Electric Company, Castle Rayne Rd. Wilainston, N.C.
l ane e.em .asers m unem . j gg ageseguensed g., Ceaeral Electric Company. San Jose, California (NEBC) es.=. e see .r a cwese se.ne ,ensemessess mesme, ease.e.eu { j 2. eriencase messer's seriais treet A3738 y ,,.g g ,,, (ep ca emesed Asee,as., se o,eage, g., 768E534C001 g,,,,,,,,,,,,,, D. L. Petersom on r , :_: w pe, % Control tod Drive. Hodel i7aDB144DC001
- ngu/
[ (e) Appliaeble ASMECodes seeden Et,Edleine 1974
. Addoendedese N'II , cm gg 1381*I g 1 3, w ,, standard part for use with Reactor. Hydrostatically tested at 1820 poi, i
comese-____ .s e .es . e. e j j
- Total anseber of sheets - 2 We esselfr sesshe esessommes ende fame es es ensam reine ades aed paesme.s.s.es.e.ls.e.=of AssE 6.is ese E asessen ist.me ensoce end ele ,umi pen w appameenee a essa g ans amass aseen ese est me e --- a== et me art caisneem asesser ser esets. As serr cerew.
ggeg oas6on spesssesswa saress sapen it she appensenew h as
, n. 7/21 g, 80 gg,,,4 M. N a, -
' " ^ ' " ' '
as.rcauseen.asinem l CassiGeese ed Amsbestandes Espiso JUE" 16* 1981 MHesse d sh No. NPT N-1151 l CERTIFICA110N OF DElBCN EUR APPtlRTENANCE (=6es applieeble) 1
..s
# .. s. -
. ~s a Deelen _, _ .. _ es ale - CE, NEPD-4elp-ga, Castle Bayne Rd., Wilmington. N.C.
' ~ 3! 12A5356, Rev. 1
! serese easipeia sapen en Ale as OE. IfEPD-4RfD-CA. Castle Bavna Rd. . W41m4m.com. N.C.
- 22A4912, Rev. 2 __
Doism speettieneseu eenstied by B. N. Sed 8h=" _ ped.Eas.semeE Aes.NeAI.'l'1 i
- j. sseen maalyele sepas eenised br 3. N._Sridhar p, g, g.,,3,,eCalif an.No.18345 i
1,
' CER'!1FICATE OF SHOP INSPECT 10N j t. ** anderetamed. beidies e salad nasmissies l**eed bree Naissai se ,4 et seita and peweene vuee, leepui.e
- and/es she aseos a peeenem a March Carolina e.d empiered byDepartment af Labor j og State of North Caroline hm inspweed she p.n of a peewe eems ducehd la shia l Feettet Gees flopert se
' 7/21 se M, and sente that to the ness et my W 1.. . and hellef. ehe MPt Ceresense eleider hee desseiseted Sta eeet la eeeeroames with the ASME Ceee seesen att.
in Sy signing shie sew & Genes. asisher the laepeeter ses his empleret makes any wasransy, espeessed er leapiled, ee.ceen.
^
,i er
.ehsi li. ..t.e ge.,t.t. desert. hee l.. eeele e,-e la shte .partie.s Furthe.r.m.o.re .D.a... t.a mee.e.r,t_.
n.e,i_ther ee .the.hsn.e.ee.e.to.ee i se..e ats. _esepter.ee c i I oe / A M M 7/21 , 80 l y-d
. a a.,
,,;,, 'NC 779,PA.WC2L60, Offl0
.e._e_..._.....
!, M*.*.*.'"*41.:*l:".'" ""*J'."*.**.[*:':'"* ~ *::L':*," :l';* :**J.:*;*.i*'** * "' * "' ~~~*""' " "*** "' " "
j tiomi n wm icooo oim., oe e u.a m c.e., ef.Wwar.hs slcm s... N.Oem.I..<. soci* j' ~ I' 20*d 100'ON Ef:91 %. R7. NHW ADACC'OATA:df MM' i 1 l i d j Page 198 i i 4
rea 39Ud 006Sst9016 ESSI *E N M FORM N.2 Neu O m lee 4-4 seet. .e he e ptced su ...aie =.48 usuts. autn s .e inavieJ .e..ea.. e *heite of he euw en.s . . -. ' .
,.a
- i.. co sies
- 4. % :: w aniet _ ms la. Alleenace sa. Dia. fa ia. I.ength ft. ie.
<mi.e a se ase u
_ T.S. sui...e .Thi.e.he.e.e
- e. m..
- 9. k *=e: Lema _. H.T.' . . R.T. Efficseney x Cinh H.T.* R.T. No.elComeue
- 6. Headee tal Maseeial T.S. - (b) Masental - T.S.
humiu c..== u 6ae tat.,es..e c eus M.=e em..te.4 Fim time se 9,+. (f.e. e.se e. ?haen .. see a.eu ames Ae.s ane se aus one.mu (c . ceu. (a) (b) If unne shte. betes used Oehee fanemias j tuenn.e.se. me T.s sue,mue i toeouiu e eum .ement t
~~" ~
7 j aek et Cteswa f scenne. ...eu e -ene.....u.u >= e. ei an u.u mus.e.e.u me u.a.nein Deep Weighs Cheepy impses (i.th
- e. Desigapee ouse s U50 ,;, 575 e, e ,e.,,, ,(_ e, teeme 9 and to se be completed fee e=be sectione
- 9. Tiske Skeess: 5sasienney. Mesesi.i Dia. Thieknees in. Auschmene
<s.e a seu. sie.) (s.neue e. . t (we64 4. seuee Fleaetas. Maanlet Dia. Thicknees ie. Anach.sent
- 80. Tebess Maseetal O.D. la. Dickeens ***".*!
e Nesbar Type teesas 11-14 inet. se be eospined fee in.se ebombees ed iseketed vessels. et ebaamata of heaa eschaagess. N ainst Coussion J
%4ekness la. Alleesace ia. Dia. is._la. Leagdi_is. in.
- 14. htti Maeevial<uine n seu. .) cus a.T.S.
ee muse s,u.we
- 12. Seama: Long H.T.' R.T. Uticiency -%
Giuh H.T.' R.T. - No. of Coueses
- e ll. HesJa (s) Maieeial T.$. - (b6 Vue.ial _ T.S.
^ c Km ht. suiedui c em as .em 64.s rios see. se pues. h Ymuk u n.c.. a.eio am Ae. 4 6. m.m.. o. .n sc.u. . c .: Ia) Top, benem, anda _ _ , ,,, - (b) Chseael _ ----_- If reme.atte, belts ased (an (b) ., tgb Othee fuseelag e oeu.se e asus .se .e e
. Deep telgha .
- Chaepy impact (**4 b I4 Design peessnes' psi at _ 'F si semp. .f *F
~
liema bele. se be eempleted fee all vessets ehece applicaWe.
- 15. Sefer Velve 0.sinas N nbu $4ae Leessiea --
\, 66. Sesaleet pe..# ,..
p w,... et n.
, 'a ocaa.o. .. w ... o. . st., r ee. u .e t s u. u m.nas me. au h.e
- 17. taapeeties wanhole s. No. $. ae Leemica - --
Open egst H eadhele s. No, .,. Si4e Lee ssion _ Theesded. No. Siu . Leesteen ..~
- 18. Swopoetsi Skin i.e s s _ Other Au sched Le s s "X.,.. .., ..e so.weib n t e n..*
- M *=*
<v. m.i <m.
- as pee..no <<*..s ~.
- u. *
List eih ,4#1e'*.a ee *di met etees.ee eget teentedaes te.e,e.e..ee ette spyise ette. a- . .aa, e.. **.e. er e. un se t r oc ce 3 MT f . n f (')'),l7 l 0
REPORT NO. NP0059-0005 IBt3-034 l 8'00 '39tM 606ssv3016 Sheet 3 of 3 8tssi 96. 82 tiAl Sheet 2 of 2 FORM M-2 Nrf CERTIFICATE HOLDEas' OATA REPORT FOR NUCLEAR FART AND AFFURTENANCES* As required by the Prowhlon e(she ASME Code Rules. Sec6on 111. Div. l g,g4u g gw General Electric Coonany. Caet.le Lyne Rd. . Wilmington. N.C. (M We ieemse4 L Ceneral Electric Company, $an Jose. California (NEBC) ***** sm .r n c.ea n , air : w.re
- 2. sdeensessen-cernaceae Needee'a sestas me. at ract A3738 %'t R No.
(a) C.am.cie4 Acce,41.s o. ins m,_. 7aArttunn1 o, 4., p, p.,e4 6, 0* La F****'OR (M Descrip4.s of Pan taspee,.4 Control Rod Drive. Hodel J7RD8144DC001 N207 (4 A,,m.m Aswec.44:seede.at. sata.a 19A 444e.4e 4.e W'73 _ C uene. 1361-2 a e i 1
*. Cap 16689274P1 (167A2343)
SA182 - F316 Code wld 3/8 thick x 1 1/16 00 R50YP102 N_" l I I *
- 2. Indicator Pipe 16689313P1 I SA312-TP316 .
l 3/4 sch 40. seamless pipe N l 0.113 vall thickness * % I
. Reactor' vessel .
thimble l g i
- 3. Plug 159A1176P1 .
g , [ [ f^)s . SA182-F304 1/4 thick x 0.812 00
~~ 8 i
L~~ 4, ?
. . 4. Flan
.SA18$e919D610P1
.F304 (719E474)
Coile 850YP102
)Yu L <
\
3.37 thick x 9 5/8 00 neck 1 1/16 thick x 5.0 00 N3
. 2.875 10 @-- / l ss.m I N
' 5. Base 137C5311P1 h \'
Di-19 ASME SA479 . 3.0 00 x .884 10 6 Ring Flange 11485122P2 G"$ SA182-F304 Code weld l' thick x 5.0 00 x 1.75 ID P50YP102 d 7. C 117C4516P2 4 > g C0f! TROL 800 CRIVE 6 ea. 1/2 dia, on 4 1/8 bolt circle DWG - 768(534
- 8. Plug 175A7961P1 9. We 13 C5934P1 SA182 F304
- 18 8^'II 0.38 thics x 1.307 dia. .
. 1. m x1.62h. . , ,
b 00'd 100'oN #9:41 06. A* >lHIJ AAACC)onTA AT tm n i Page 199
REPORT NO. NP0059-0005 1B21-247 fG 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. 6/93
- 1. Owner: Cleveland Electric Illuminating Company Date 3/13/96 P.O. Box 5000, Cleveland, Ohio 44108 Sheet 1 of 1
- 2. Plants Perry Nuclear Power Plant Unit One 10 Center Road, North Perry, Ohio 44081 U.O. 96-770 R/0 (RepaTr Org. , P.O. No. , etc)
- 3. Vork Performed By: Cleveland Electric Illuminating Co. _ Type Code Symbol Stamp _NR 10 Center Rd, North Perry, Ohio 44081 Authorization No. 33 Expiration Date 7/18/96
- 4. Identification of Systems 1B21 Nuclear Boiler (NSSS)
- 5. (a) Applicable Construction Code ASME Section III, NB, NP , 19 4 Edition Vinter 1975 Addenda, Code Case 1644-5, 1728, N-32-4, N-241, N-242, N-272, N-282, N-413 (b) Applicable Edition of Section II Utilized for Repairs or Replacements: 1983_
Summer 1983 Addenda l' t
- 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 System Power IB21 .,109 N/A 1485 Replacement Yes
-a v,_3 4 -fl
- 7. Description of Vork: Replaced installed Phoenix Snubber EP-3 S/N 2067 with Phoenix EP-3 Snubber S/N 2066. MPL# 1B21U445
- 8. Test Conducted: Hydrostatic- [ ] Pneumatic- [ ] Nominal Operating Pressure- [ ]
Other- [ ] Pressure N/A psi Test Temperature N/A degrees F lo 1 Page 200 l
NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS
- 9. Remarks: _ None 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 Ve certify that the statements in this report are correct and that all design, material and workmanship on this Replacement conforms to (repair, replacement, or modification) applicable section of the ASME Code. Certificatpjof Autp9rji atjon Nop 33 to use the stamp expires 7/18/96 Signed JbwW F (febn1 Dud G2hlute (/
/4A/4 - f3(owner 19 or 9Owner's c, Designee, Tifle)
Date
-t - . .H; :Mi CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the State or Province of 08I0 and employed by *ARKVRIGHT MUTUAL INS. CO. of NORV00D, MA. have inspected the. repair, modification or replacement described in this report on MAeru G , 19 % , and state that to the best of my knowledge and belief, this repair, modification or replacement has been made or constructed in accordance with Section II of the ASME Code and the National Board rules as defined in the publication NB-102, current edition.
By signing this certificate, neither the Inspector nor his employer makes any varranty, expressed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property
.s t dan e or a los of any kind from or connected with this inspection.o -.. O RIO "
Commissions 4B433d J. d e cug.
&, p" % 11 (Inspectok's Signature)
Date M Aew t3 19 4(o
- FACTORY MUTUAL ENG. ASSOC.
rec yo(g 9 1 i
REPORT NO. NPOO59-OOO5 1B21-246 l NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS oR REPLACEMENTS l l As required by the Provisions of the ASME Code Section XI l j l PNPP No. 9308 Rev. 6/93 i
! Date 3-26-96 l Cleveland Electric Illuminatino comoany l 1. Owner: l l
P.O. Box 5000. Cleveland. Chio 44108 Sheet 1 of 2 l l 1 Unit One j l Perry Nuclear Power Plant l 2. Plant I I W.O. 95-202 Rev. ,A l l 10 Center Road. North Perrv. Ohir) 44081 (Repair Org., P.O. No., etc)l l , l l 1 1 Cleveland Electric Illuminatina Co. Type Code Symbol Stamp HE l J
- 3. Work Performed By: l
. . 33 l 10 Center' Rd. North Perrv. Ohio 44001 Authorization No. l 1
Expiration Date 7-18-96 l l l l 1B21 Nuclear Boiler (NSSSI l Identification of System
] 4., I 1 l i ASME Section m Class i , 1921. Edition l l S. (a) Applicable Construction code AAAanAm,.C9 d e case 1644-4. 1728. N-272. l winter 1975 l
}
i l N-224-1. N-225. W-249. N-3.N-413. N-71-6. N-71-9. N-71-11 I 19)),_ l (b) Applicable Edition of Section XI Ctilized for Repairs or Replacements: l I I Addenda {
/ Su....cr 1993 l
l l l l
.i l 6. Identification of T ants Repaired, Hodified, or Replacement Components
,l Mh,Mdkb JE.
Repair l ASME l l l Manufacturer l Nat.lOther ;Year l l l Name of l Name of Built l Replacement l Code l l l l component l Manufacturer l Serial No. l Board l ID. lor Modification l Stamped l l ll l l l No. l ' l ' i I l l ll I, l Yes l l Piping Ganaval Electric 1B21 l64084 N/A l 1985l Replaco r t l1 l l l 1 l- system ! , ll l 001 l N/A l '1985l Replau t l Yes l l Piping lJobnson controls l 1821-0070-F ' : I I 1-Syst;= l l l I, I, I, I. I. I..lI I I, I, I, . . l
- l. .
I I i iI 1 I I 1 I I I s I ll 1 f f f f i e a 8 I a e i e e
?. .
's I s
> ~
ll- _l
" ~~-' l 7. Description of Work: R=muod valve S/N 160878 Cm MPL 1B21F0051A. and installed I 1
Retest eerformed eer W.O. 95-2920. (cont. on Line 9)_l refuibished valve S/N 160859 I I 1 I (X) l l 8. Test Conducted: Hydrostatic- [ ] Pneumatic- [ ] Nominal Operating Pressure- l l Other- [ ] 175 _ degrees F l 1038 _ psi Tee Temperature l Pressure Page 201
~~-~
s s l NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEKINTS I l I I l l 9. Remarks: The followino reolacement fasteners were also installed: l 1 1 l Two Inlet Flance Studs (Trace Code ORI) I l l Two Outlet Flance Nuts (Ht# 81617) 1 1 l l l Four 7/16" Air Flance Studs (Heat Code GJ) l l l l Six 7/16" Air Flance Nuts (Ht# 8098740) l l l l 1 1 l NOTE: Attach all applidable Manufacturer's Data Reports. Supplemental sheets such as l l lists, in., sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 l l (2) information in items 1 through 6 of.this report is included on each l l sheet, and (3) each sheet is numbered and the number of sheets is recorded on l the front of this form. l 1 l l l CERTIFICATE OF COMPLIANCE l l We certify that the statements in this rep;,rt are, correct and that all design, l l material and workmanship on this reolacement conforms to l i l (repair, replacement, or modification) l lj applicable section of the ASME Code. l lL l {l Certifi ate of rizat o. 33 to use the NR stamp expires 7-19-96 I l Signed - Mechanical Ouality Encineer l j Date 0 h (Nner or 19 er's Designee, Title) ) i l i I. ll CERTIFICATE OF INSERVICE INSPECTION 0,Mfh[.ha. My ll I, the undersigned, holding a valid commission issued by the National Board of , l l Boiler and Pressure vessel Inspectors, and certificate of competency issued by l the State or Province of QHIQ and employed by *ARKWRIGHT MUTUAL INS. CO. of l NORWOOD, MA. have inspected the repair, modification or replacement described in this report on Mdus M , 19 94 , and state that to the best of my knowledge and belief, this repair, modification or replacement has been j u lj made or constructed in accordance with Section XI of the ASME Code and the l National Board rules as defined in the publication NB-102, current edition. ll By signing this certificate, neither the Inspector nor his employer makes any ll warranty, expressed or implied, concerning the repair, modification or ! ll
,' - replacement described in this report. Furthermore, neither the Inspector nor Lh l his employer shall be liable in any manner for any personal injury or property 'l l. , , , , . l damage o a loss of any kind from or connected with this inspection. ,
G
.a f, 3 l . __ r r N Commissions AA0fTC*3
' &$.) l " D l.. (Inspector's Signature) 2* %W - l l l; Date 774 reA M 19 75-l 1
- FACTORY MOTUAL ENG. ASSOC. ll I'
'l.
G
REPORT NO. NPOO59-0005 l *
- T e i/2., 1B21-246
[ (@l".,/e g ,,-- Shee t 2 of 2
%_/ .;>Q l
FORM NV.1 MANUFACTURCftS* OATA ftEPORT FOR SAFEW AND SAFETY RELICF VALVES *
, (As Required by the Provisions of the ASME Code. Section set. Div.1)
- 1. Manufactured by G. Dikkers (,sa C.o .sau.
. N,V. Hengelo,(e0).
s mae.a. The Netherlands
- 2. Manutacau,wt so, Generia E1ec(ric
- 3. Locasion of instaa.i.un Pe r ry i f"tf6 t'Ytt'Pf*/f Y',*'Ttfito'" "*"""
( Gf.71-6/12DDF*"' to. 33 1978
.casi w... "**'*"'"'
**'"* *"'d"'"8" in.rtI8089 tu.a.n s ryp, a.fety/ relief .
sa tu.a.a.a .,s s.<i.i we.: s emy. y ,aa a orir.c. sue . g ;rei;e Nom.nai wa size 8,, ouna size i o. 6ao. a,
~
- s. see Presure (PS4G) I.lSO Rated Temperature . . .
585 .r stamped Capecay 92h333 some,, g 0 , g o ,p, u,e aumsown ePS4G) 1 .0 5 Hydrossasic Test (PStG) Inssm 2350 975 ,
, ouom _ . l
- 7. Pressure Metaining Pieces Seriet No. or Materiet SpecificeGon identsficauon incl Type or Grade soey 93 95 8 , ,/n 4
. . SA,332 LCB , , , , _,
aonnm or Y* 1.0., $,. 8, s/n 2
. M;352 t.CB _ _ , , , , , , , , _ , , , ,
suppari ned. . . . . . . . . . . . m Nah o.ee A.EU. A52, 53,93.6.4B ., SA J5_0_,L,G, ,_, ,,,, ,,, , SA J5,LCF3A_,,,,,, ,,,_,, _, , , , , , sp,enew h.,. 26 30 95. 5/ri Al 45..Cr Mo V 67__, ,,__ _ , , Adiuaae Screw AEU.957; AFy 085 SA,.182,, FJ,1{,,,,. ,,_ _, tO ***"d'*
- WI- ^ 5%:Lk % S0 F**d* U'90,, - -
(,,/ serias _. . .. . . . , , , , , , _ . , _ _ _ , , _ , . , soning M; AJR; AKA; AJJ; ALR; S.A.,193 ,87/,M ,1,34-7/,M ,13k, ,2!! ooierPiece. AUY.; NtB; AJH; AJL . Liner 56.076 s/n .1' S A 351 CFjA, ., ,,,, ,,, , , , ,, _, ,
, . . , , Cover .61 A6.7 . s/n 6 - SA.351. CESS _.. ~ ^ ' ~ ' '
Vent pipes AFV 025 SA 105 .. _ Flanges AIN 032; AFV 014 SA 105 . . Max. outs 1d'e diarn. valve body: 4 78 anrn ,(18.82") Max. outside length valve : 1642 nati (64.65") R EC F '"~ ' JAN 11 "379 PNPP-S0lDC %M 4 >
- Supplemental sheets ire form of lists, sketches or sJ,awings may be used provided (1) size is 8-1J2* .11*. (2) information en items 12 on this data report is included on each sheet, and Q) each sheet is numbered and number of sheets is recorded at top of this form.
41/76) This Icem (E000421m.y h. uhe .uij I.u. she order 0,pe., ASME,345 E.4 7 St., New York, N.Y.10017 l m i I O Page 202
+ *t ITML LGlb l U~lX FORM NV-1 (Backl D
- CERTIFICATE OF COMPLtANCE We censey that the staaemenas anade in stes repo<t e< cove x:: and that them valve conforms to the rules of construction of the ASME Code for Nucleae Power Pterd Componews. Secs.on Hl. oev.1 Ed.6cn. Addenda Sum. '}6 ,
Coje Case No. 24.11.1978 G. Dikkers E Co.N.V. V.H. Willems oase s.gaed tv
'"******"'* '1 8 0 6 NV Our Asut Cendcate of Ausho,intion No. to use the (NV) wnew expi<es 1st Jul.y,..1980 .
to CERTIFICATION OF oCSIGN ossigninto,nwson an tae st . General Electric and Perry . senss anaeysis repo<t tClass t entyl onfite et . General Electric and Perr.y. .. .. ossion specw.cauons ceror.ed ty' .o._B_r_d_L. e rooks. . . . . _ . . . . . , . , . Pc s== Ga.!1.f9.c.01 a _..__ ... neo. No. '_ . 11655 ..__...__...._ ...... sesees report certised ty' . . Robert .! We.15 7. _ _. .. . . _ . . . eE sesee _ Cal l forni a/ I I I inoi s _ , . .neg.no,,M14S21/62,2524.3 , , , , , , , _ . , . s sienature act required-4st anme on'y. l l CERTIRCATE OF SHOP $NSPECTION l 6 4, she undersigned, holding a wer.d core leeued ty the Naconal aoerd of souw and Pressure vessee inspecsore and she State or Province of Ohio -.. and W try . F*'nne r ins. _ _ . . . . _ of . k9fl9 Itf.9Ye - III- have inspected she pump, or vehe, described in this oata Report on __ _. 2L11 is_2fL and stasm that so the amt of my knoweeds and benef, me uanut.cturw has con. seruced mis pump, or eelve. % .aco. dance wier, the ASME Code for Nah Power Plant C-"- - _ .- - -- ~ -w.r - .r- - he equipment described in mas oata neport.'Fyoiwamo,4, neither me inspector nor his onwaver ehan be nadie in any l manner for any personal injury or property damage'er a loss of any kind e<tsing from or connected with this inspection. A- 'M .g oste signed 2 .hu.19g . I. is._7fL s . Commissions NB 44 %... ._..._. __.. .__ aase=sa.1 vm me. si.ie riev. .no naa
. W.
n j .' " e ' d *N, 4 O
REPORT NO. NP0059-0005 O NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS 1B21-247 l As required by the Provisions of the ASME Code Section XI l l PNPP No. 9308 Rev. 6/93 l
- 1. Owner: Cleveland Electric Illuminatino Comnany Date 3-25-96 l l
1 I l P.O. Box 5000, Cleveland. Ohio 44108 Sheet 1 of 2 l l 1 Perry Nuclear Power Plant Unit One j l 2. Plants l f l 10 Center Road. North Perrv. Ohio 44081 W.O. 95-203 Rev. J ll (Repair Org., P.O. No., etc) l , I I I l 3. Nork Perfomed By: Cleveland Electric Illuminatino Co. Type Code Symbol Stamp MB l 1 . I
' 10 Center Rd North Perry. Ohio 44081 Authorization No. 33 l l '
J l l
,g Expiration Date 7-18-96 l l
i
- 4. Identification of System 1B21 Nuclear Boiler (NSSS) l 5. (a) Applicable Construction Code ASMB Sect 4n III Class 1 , 19 1 Edition
- Winter 1975 Addenda, Code Case 1644-4. 1728. M-272.
l '
\
j l N-224-1. N-225. N-249 N-3. N-413. N-71-6 N-71-9. N-71-11 l , I l l (b) Applicable Edition of Section XI Utilized for Repairs or Replacements: 193)_. l Summer 1903 Addenda l I
.i l
- 6. Identification of Components Repaired, Modified, or Replacement Components )
+ .& , , v ::&:
Name of Manufacturer lNat.fother Year l Repair ASME
, kNameofh Built l Replacement l l Component l Manufacturer Serial No. [ Board ID. Code l l l No. Ior Modification Stamped l' l l '
i l l l Piping General Electric . 1B21 G4084 N/A l 1985 Replacement Yes l l }-- System l l Piping Johnson controls' 1B21-0070-F 001 l N/A 1985 Replacement Yes l i
--8Y8t- .
'I 1'
i l 1 i' i' l
- l l 1
1 l l l
, I 1 ,
l W *
..t. 9 () l l l l, l , .- l
- 7. Description of Nork: Ren.sved valve S/N 160860 from MPL 1B21F0051B. and installed l refu1Lished valve S/N 160802. Retest oerformed Der N.O. 95-2920. (cont. on Line 9) q I
l
. I l
- 8. Test conducted: Hydrostatic- () Pneumatic- [] Nominal Operating Pressure- (X) l l Other- (}
Pressure 1038 psi Test Temperature 175 degrees F l l , I p- I v Page 203
l l l I NIS-2/NR-1 CWNER'S REPORT FOR REPAIRS OR REPLACEMENTS l 1 l l 1 I l l 9. Remarks: The followino replacement fa_pteners were also installed: 1 1 l l Six Outlet Flance Studs (Ht#8094927) I l l l Six outlet Plance Nuts (Ht# 816171 I 1 l l I Sixteen 7/16" Air Plance Nuts (Ht# 809740) i j I i l I I I I I l NOTE: i l Attach all applicable Manu(acturer's Data Reports. Supplemental sheets such as lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 l l in., (2) l l sheet, information in items 1 through 6 of this report is included on each ' J the frontandof(3) each this sheet is numbered and the number of sheets is recorded on form. li CERTIFICATE OF COMPLIANCE l We certify material andthat the statements workmanship on this in this report are correct and that all design, renlacement conforms to (repair, replacement, or modification) l applicable section of the ASHE Code. Certific e of Authprizat No. L to use the NR stamp expires Signed _ __ TN Mechanical cuality En<fineer 7-18-96 l (od er or er's Designee, Title) l' Date 402 19 l l t l
.f *e gas.gj I CERTIFICATE OF INSERVICE INSPECTION 4.
en Aish %AQ MerFw J- l I, the undersigned, holding a valid commission issued by the Nat.ional Board of l l l Boiler and Pressure vessel Inspectors, and certificate of competency issued by the State or Province of QHIQ and employed by *ARKWRIGHT MUTUAL INS. CO. of HgEwooD, MA. l i have inspected the repair, modification or replacement described l
, in this report on Mneck =% , 19 % , and state that to the best i L
of my knowledge and belief, this repair, modification or replacement has been made or constructed in accordance with Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. l By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the repair, modification or ' Ij
\
replacement described in this report. Furthermore, neither the Inspector nor l his employer shall be liable in any manner for any personal injury or property l
.. I damage M M or a--
loss-of ang kind from or connected with this inspection. g, , l l k' { h . . .. z " (Inspector's signature) Commissions /AM%3 f Cew *
- 7. .f_k,jh,ff,jf.fs{[.fM.,,.
g-gv { l 1 Date l #Nc4 04- 19 9<- I i l
- FACTORY MUTUAL ENG. ASSOC. l l A '
I t i l l-i
- 1 G
REPORT NO. NP0059-0005 d 1821-247 Sheet 2 of 2 FORM f.ipf 300O NV-1 N CERTIFICATE if0LDERS' DATA REPORT FOR SAFETY AND SAFETY R
^ * " ** *d 6' '"* "' W n s hhe ASME Code. Seaion all. Ok I
- i. Manuf.ciuved t,y _.S. Dikkprg 4..Qos. Es V, Hengelo_(O_) The Netherlands su see us..~ ee a came.us. ws
- 2. Meaufactured for . . . . General Electric ,_ .
sw d 44o..u os e.,,ch. , e. c
- 1. ____._
- s. toc.i.on ce instam.on . . .
ParU II . . . _ . .__ 4. su _._..e w.~> . .. . _ . . _ (cani _ ._.__ _ c471_4/195 so, . a 4 04 03 rev 6 .. . . _._74 tu.n e,..a.. rr , so.es . , _ _
- 5. Valve Gd"11 tu d.she s Noa
_ __ _ sdenutyino Nos. _I.MI E, Type =_ safety /reli c au.c.i. no < s s.<a.: a 1979_ _ s.w. s.w a.w. c.iot re-., A<s e .d C _._ _. . . .. _,,_.in , _ .
.. . . _ _ . . _ ~ _ . . . . _ . . - - . _
orir.c. She' ~ ~~ .acm " A . 8A " ' ' N'MI Inlet She . Outlet She 10" 8".ncn each
- 6. Set Pressure (PSeG) 1190 Rated wh,mre ~[_" ~ 585 .,
iesa, g 3 g o,,,,,,,,,,e 8'**P*d C***ckV -g _ 92 3{ snowdown (PSic) _46,36 Hydecotetsc Test (PSsG) inset M50 *
- 7. Pressure Retaaning pieces o,,3,, 975 (App'.ceb'. so ve6ves toe ceased syveuns ens,1 Serial No. of Material Specir. cation M* Incl. Type or Grade Body OL 21.8 - 1 SA 352 ICB Bonnet or You O1.33.8 - 2 __
_SA 352 IGB o;e, __SA 350 LF2
- 3A
-' SA 351 UF3A spring washers 2d.30 95 - 82 W Cr Mo V 67 fm Adiasting screw AME 030 AE 013
) sp.ndse A.E 098 SA 182 F316 sw A 564-74 type 630 corui. H1 100 son.no ANY/AJJ/CAI/AYS/II.h7A Ej5"~ ~~ '_~~ ~
f .' ! ew 1 _AJS/APA/AJI/AVR
ye
! Lirier 55.15.8_ - 1
. SA 193-B7/SA 194-7/nA 194.-2H Cover SA 351 CF3A '
55t@.sQ_- 6_ _, ., SA 351 CM3M-Yent nine ..__ 2K5.Q19 .. . .SA 105 Flanges __._. __AKP 067 AKP 005..
. .,_SA 105 Max. outside diam. valve body 480 mm. (18,89)"
Max, outside length valve 1644 mm. (64,72)" +- <
- Sog>plemental sheets in form of tests, sketches or drawings may be used provided (1) she is 81/2" w 11*. (2) infor in hemsat12 eecorded topon thisform.
of this Date Report is included on each sheet, and (3) each sheet is numbesed and numuet . of sheets is i ston r1 in I no,,n stooo42) awy in obi .a.o teoa* the o oe D m A$M(,345 E.L 7th $s.. New Yoak. N.Y. 10017 r l Page 204 6 ___ . , _
)
l s l ronM tN.1 (seck) ggf g CERTIFICATE OF COMPLIANCE . we ce'rtify that the statements made in this report a,e correci and that this vaive confo<ms to the rules of conse,uct.on 1974 Editeon. Addenda num 7[t, of the ASME Code for Nuclear Powe, Plant Components. Sect.on iff. Dev. t.. <Oooel Code Case No. e Signed C. Dikkers & Co N. V. dy _ W. M. Willem : Dase 23-3-1979 <w ceme.uie <s 1806 to use the _ . NV Our ASME Certif.cate of Authorisa. ion No. (NV) symbol expires _ int Juiv. 1980 -
- - - - - _tomf ..
CERTIflCAT10N OF DESIGN Design information on fine at ceneral Eier +ri e amt Pern TT Stress analysis report (Class 1 only) on file at Genern1 Electrit- a mi Pern TT Design specir. cations certir.ed by. Bova P. Brooks PE state California Reg No. 1tX55 Stress report certir.ed by. Robert L. Veiss Ca14 forvi+n /T114 noin Beg. No. M1A491/A9 957AQ PE State
$ 0iges not required- sist name only.
CERDFICATE OF SHOP INSPEC110N t, the undersegned, ho4 ding a valid commission issued by the National Board of Boiler and Pressure Vesset lnspectors Oh4a and employed by Yemper h and the State or Province of have inspected the pump, or valve, described in this Data Report on of _ Tow Ornv8* Oll-93 m wh 19 7.). and state that to the best of my knowledge and belief, the N Certificate Holder has
'" constructed this pump, or valve, in accordance w'ith the ASME Code for Nuclear Power Plant Comm.u.
, ,a
- By signing this certifecate, neither the inspector not his employer makes any warrant expressed or implied, concerning 9tN.d.$f' ,
the equipment described in this Data Report. Furthermore, neither the inspector not 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 inspectiorL Date 91 Erch 49 ' Signed M<t A h,D,'7 4 - - 2 Commissions MB.4456 in.n.ee.si .c. .ne
- p. e-9 9
= I
REPORT No. NP0059-0005 l NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS 1D21-248 l l As required by the Provisions of the ASME Code Section XI l l PNPP No. 9308 Rev. 6/93 l l 1. Owner: Cleveland Electric Illuminatina Company Date 3-23-96 I I l P.O. Box 5000. Cleveland. Ohio 44108 Sheet 1 of 2 l l Perry Nuclear Power Plant 1 l 2. Plant Unit One l l I l 10 Center Road. North Perry, Ohio 44081 W.O. 95-2H Rev. J l l . (Repair Org., P.O. No., etc)l l I i 1 l 3. Work Performed By: Cleveland Electric Illuminatina Co. Type Code Symbol Stamp EB l l 1 1
} l 10 Center Rd. North Perry. Ohio 44001 Authorization No. 33 l l
I l - Expiration Date 7-18-96 j l l 4. Identification of System: 1B21 Nuclear Boiler (NSSS) l l l i 5. (a) Applicable Construction Code: ASME Section III Class 1 , 19 1 Edition Winter 1975 Addenda, Code Case 1644-4. 1728. N-272 (b) Applicable Edition of Section XI Utilized for Repairs or Replacements: 19 E Summer 1983 Addenda w/ ! 1 j 6. Identification of Components Repaired, Modified, or Replacement Components l Name of Name of Manufacturer Nat.lOther Year Repair ASME Compore.t Manufacturer Serial No. : Board] ID. Built Replacement Code l .
, No. l or Modification Stamped l l l Piping I l' l General Electric ! 1B21 l 64084l N/A l 1985 Replacement Yes [
l F System l l l I l ll l i I ; ; ; . I I I i I I i I ; ; ; ; I I I I I I I II _ i l l 1 ! I a l i'
' I I I I I I ' ' ' '
I I I
- 7. Description of Work: Removed valve S/N 160880 from MPL 1B21F00510. and installed l I
l refurbished valve S/N 160861. Retest oerformed ner W.O. 95-2920. (cont. on Line 91 l l I I I l 8. Test Conducted: Hydrostatic- [} Pneumatic- [} Nominal Operating Pressure- [X) l l Other- [] l l Pressure 1038 psi Test Temperature 175 degrees F l i i l n I. (D V Page 205
l l 1 l l i l NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS l l I l l l l 1 l l 9. Remarks: The followino reolacement fasteners were also installed: l 1 I l Three Inlet Plance Studs (Trace Code OEI) l l l l Two outlet Flance Studs (Htfi 8867312) { l I i l Two Outlet Flance Nuts (Ht# 81617) l I i , I I I I I I I' I
- I NOTE: Attach all applicable Manufacturer's Data Reports. Supplemental sheets such as l
lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 l l in., (2) information in items 1 through 6 of this report is included on each l l sheet, and (3) each sheet is numbered and the number of sheets is recorded on l l the front of this form. l
. I l CERTIFICATE OF COMPLIANCE {
! We certify that the statements in this report are correct and that all design, I material and workmanship on this reelacement conforms to (repair, replacement, or modification) l l applicable section of the ASME Code.
Certif cate,of Au rizat No. D __ tc use the NR stamp expires *7'l8A
! Signed . . Mechanical cualitv Encineer (OwFer er's Designee, Title)
.i l u
' ~~ "
J l CERTIFICATE OF INSERVICE INSPECTION l l I, the undersigned, holding a valid commission issued by the National Board of ( l Boiler and Pressure Vessel Inspectors, and certificate of competency issued by 1
,l the State or Province of DHI2 and employed by *ARKWRIGHT MtTrUAL INS. CO. of
'l l NORWOOD. MA. have inspected the repair,' modification or replacement described l in this report on dA4 eat J4 , 19 96 , and state that to the best l l of my knowledge and belief, this repair, modification or replacement has been l l made or constructed in accordance with Section XI of the ASME Code and the ll l
National Board rules as defined in the publication NB-102, current edition. ll l By signing this certificate, neither the Inspector nor his employer makes any ll ll warranty, expressed or implied, concerning the repair, modification or ll ll replacement described in this report. Furthermore, neither the Inspector nor ll ll his employer shall be liable in any manner for any personal injury or property ll ll damage or a oss of an kind from or connected with this inspection. m ll l M Commissions />f 923 f -r ll l ' (Inspector's Signature) l' ll Date M4Ad 83 19 96
- FACTORY MUTUAL ENG. ASSOC. l 5
e i
REPORT NO. NP0059-0005 s'. a s ,t t ns, ; (/ ]; FORM NV.1 MANUf ACTUHCHS' DAT A REPORT FOR SAFCTY AND SAf[1Y H0Uff VALVES *
~
lB21-248 ee
. (As Hequued t,y the Peovis ons of the ASME Code. Sect.on su. Osv. 6) o 2
- i. w.oi so. t o, c . i> i k k.. r ,: 4. c.. . x . v . ii... r.. t ., (i > > Th e :4ci i.c r i mid s 2 w a.,. .. ea n
&TMXW T$OW"~
3 a .a . .a ..t.,nm .
- S CO"I.~.". O am.
M,u . @ a T T D iO 9
--- d f.... --
so o h x-e--. ... .. 4.4 7 mm -4./ i 2 40..
. o.c, .e
.oc
%i twi iv.
li. v,ive g:p ,, ed.nt.ey.no Nos. gg
'"" s ,. s.%'A*.IJ/e(&.3dr.L %.a o,.i.a Sue 5 , y, q a Nom.a. i.wei Sae s a ouuei Sue
.nch once l o " .nch
- 6. Set Pressues (PSIG) . 11 _Q Rated Temperature '385 T
! Stanved Capacity . N lbsthe @ .Q. % Overpressure Blowdown (PSIG) .11,k ,
Hyorostatec Test (PSIGl intet 2 35t) Out'**
- 7. Pressure Retaineng Pieces wwow dlb g Serial No. or Material Specificataon idenufication incl. Type or Grade undy N1 Bonnet or Yone
.bhN 49. [O SU.1 SA 352 14H SA 352 148 l Noul. I SA 350 LF2 oc fd._Qil d - Db SA 351 CF3A Spring Washers M OS 45 Cr Ho V 67 Adsust g Screw Spedie d2- U~ sA 182 F316
.006 A 564-74 type 630 cond. Hil00 S***v
) soeung N sA 193-n7/sA 194-7/SA 194-2H v ,
oo r e-1.i n. r M- _MdhM'/@ni/ euy/nme
.O 1 SA 351 CF3A Cov..r 30.Y Ob M.O sA 351 CF8n V. nr s i p.. S-SA 105 F l .1ni s - b SA 105 M en V . oM st dt di chm. VC:dV C h C3 d y .
- k *A *A l iwv cuba < we vosd' 4ga _
[1E C EIV E D JAN ll1979 PNPP.SOfDC s
- Supple:nwnedi sheets en form of tests. sketches or drawings rnay be used provided (1) she as 8112' k 11*. (2) information en sterns 12 use ilus data report es ,ncluded un each sheet, and (3) each sheet is numtsered and number of sheets is rewed.ed at top of this form.
<usu T.... eu,,o a exm n .. , ,, ,,,,,,,,,,,,, ,,,,,, ,n, o, des Oe.,e . ASME ,345 E . 4 7 $1.. New Yod, N .Y . t 0017 gS !
,Y Page 206
i l p ,f.
.- - u.
. . . wlapuc f'ORM NV.1 (Back)
I i CERTertCATE Of COMPtlANCE we . es.#, eswi uw st.tenwnds made en dus eepo e to...=1.nd new uws ..tv confornes to the tunes of connesuce.un es aw ASME C.=s= s.= %=:le Power Pw.t Coa pu..onis 5.ms wi ut. o., t. 1974 Eda.u.s Adde.wsa sig* 16 3.1 S wwws C. H i kk_e.r_s d. Co, . ?! . V . by N
- t our ASMt Centit.cate of Authoriat.on #6 . 1806 to use the Ngg symbos ensures Ist July, 1960 tomes CERTIFICATION OF DESIGN Design enfornw.on on sde st General Electric and .... ,
stress an.tysis report IClass 1 onM on f.se et Ccnc ral Elec t r ic and ... . Design specificas.ons certif*ed by* Boyd P. Brooks PE Sute Califorola Reg.No- 13655 suess report cent r.ed by' Itobert L. Weiss PE state . Californis/111LnoLa Reg.No. H14921/62-157/#9
- Sigreare not required-4ist name on'v- _.
CERTIRCATE OF SHOP INSPECTION
- t. the undereigned. holding a vetid - - issued by the National Board of Boiter aM Pressure Vessel inepectors and su.e or - oe to and . pioved by idZmper 'dn es .
. have inspected the pump. or velve. desenbod in thie Data Report on 19} . and state that to the best of my knowledge and belief, the Manufacturer has con-etrucInd thes pump. or valve. treaccordance with the ASME Code for Nuclear Power Plant C-:- ; - ---'-
By signing this cartsficate, neither the trW" not Ns employer makes any warrant, expressed or impleed. concerning w equepment descreed in tNs Data Report. Furthermore. neither the inspector not Na employer ehell be fiable in any manner for any personalinjury or y O or a loss of say kind arising from or connected with this inspection. 08'e W. . .M
- ISlV N S % :s b se paee.as= 6 com .s.ons tuasue, basse No4.W stil'
- I
.~ l l
l l l 1 O
REPORT NO. NP0059-0005 i 1 l NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS 1821-249 l As required by the Provisions of the ASME Code Section XI l l PNPP No. 9308 Rev. 6/93 l l l 1. Owner Cleveland Electric Illuminatina Company Date 3-25-96 l 1 I l P.O. Box 5000. Cleveland. Ohio 44100 Sheet 1 of 2 l l l l 2. Plant Perry Nuclear Power Plant Unit .One l 1 l l 10 Center Road. North Perry. Ohio 44001 W.O. 95-205 Rev. J l l , (Repair Org., P.O. No., etc)l 1 I I (
, l 3. Work Perfor1ned By: Cleveland Electric Illuminatina Co. Type Code Symbol Stamp }[B l #
1 I l 10 Center Rd. North Perry. Ohio 44081 Authorization No. 33 l 1
,. Expiration Date 7-18-96 l
- 4. Identification of System: IB21 Nuclear Boiler (NSSS) ,j
- b. (a) Applicable Construction Code: ASME Section III class 1 , 1921 Edition Ninter 1975 Addends, Code Case 1644-4. 1728. N-272.
N-224-1. N-225. N-249. N-3. N-413. N-71-6. N-71-9. N-71-11 (b) Applicable Edition of Section XI Utilized for Repairs or Replacements: 19).],_ Susener 1983 Addenda
, 6. Identification of Components Repaired, Modified, or Replacement Components
, i Name of Name of Manufacturer Nat. Other Year Repair ASMEl G-- +=+nt Manufacturer Serial No. Board ID. Built Replacement Code No. or Modification Stamped Piping General Electric 1B21 64084 N/A 1985 Replacement Yes F System j ll Piping Johnson Controls .
1921-0070-F l 001 N/A 1985 Replacement Yes j l---Syste; l l l
, '3 l
l 7. Description of Nork: Removed valve S/N 160896 from MPL 1B21F0051D. and installed l ,, l refurbished valve S/N 160862. Retest oerformed Der W.O. 95-2920. feont. on Line 9) l l 1 1 I l 8. Test Conducted: Hydrostatic- [] Pneumatic- [ ] Nominal Operating Pressure- [X] l l Other- () l l Pressure 1038 psi Test Temperature 175 degrees F l l l I 1 (
%/
Page 207
l 1 I I i l NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS j i l l
; I l l l l l 9. Remarks: The followina replacement fasteners were also installed: l l 1 l Two Inlet Flance Studs (Trace Code OEI) l l l l l Eicht 7/16" Air F1ance Studs Neat Code GJ) {
i i l l Four 7/16" Air Flance Nuts Wt# 8098740) l 1 1 l l 1 1 I i i I l l l l NOTE: Attach all applicable Manufacturer's Data Reports. Supplemental sheets such as l l lists, sketches, or drawings may be us,ed, provided (1) size is 8 1/2 in. x 11 l l in., (2) information in items 1 through 6 of this report is included on each l l sheet, and (3) each sheet is numbered and the number of sheets is recorded on l l the front of this form. l 1 r- ,, I ll CERTIFICATE OF COMPLIANCE ll.! ll We certify that the statements in this report are correct and that all design, ll material and workmanship on this renlacement conforms to ll (repair, replace::!ent, or modification) ll applicable section of the ASME Code. II ll Certifica e of Auth r zati o._13 to use the NR stamp expires 7-18-96 ' ll Signed - Mechanical cuality Encrineer ll er's Designee, Title) ll Date O b ~4 (ner or 19 gi i I,
' &gstr'MV
_ o. ' ' ll I, CERTIFICATE OF INSERVICE INSPECTION the undersigned, holding a valid comission issued by the National Board of ll ll Boiler and Pressure Vessel Inspectors, and certificate of competency issued by ll the State or Province of OHIO and employed by *ARKWRIGHT MUTUAL INS. CO. of ll NOkWOOD. MA. have inspected the repair, modification or replacement described li ll in this report on M#R
- tsE 19 % , and state that to the best ll of my knowledge and belief, this repair, modification or replacement has been ll made or constructed in accordance with Section XI of the ASME Code and the ll National Board rules as defined in the publication NB-102, current edition. ll ll By signing this certificate, neither the Inspector nor his employer makes any ll ll warranty, expressed or implied, concerning the repair, modification or ll j ll replacement described in this report. Furthermore, neither the Inspector nor ll I ll his employer shall be liable in any manner for any personal injury or property l I ll nd from or connected with this inspection.
,p ['UMAh, ' l l damagehraloeofany A -e Commissions 4d M C7 T bp,,
om i
' M v T
ll (Inspector'sSignature)h ll Date NMcAf o% 19
- FACTORY MUTUAL ENG. ASSOC. l 1' 'lI t
l l e l I l
REPORT NO. NP0059-0005
= _m.+ -
* , - - - ~ ~ - l IB21-249 Sheet 2 of 2 8 ORM NV 8 MANUf"ACTL#tCRS* OATA #1CPORT FOR SAf CTY AND gll7SAf ETY REttLF VA
_ (As Hequired tay tese Provisions of the ASME Code. Section Itt. Div Il .
?c .: t '
- s. Manusmuu ed t.y G.
Dikkens 4. Cas. t!.v. Iteesr.c les ('O Tim httierlanda
- 2. uanusacsua.
d i'td e hwgd vo\ue veave body .
MK % (icf,g ') si it E C ELV E D - ho , g ge J AN 11 1979'
, w.isotDC
- Suppleenental stwets an form of lists, sketches or drawings snay be
, : n: .
sn nems 12 on (fus data sepost is inchaded on each sheet used provided (11 site is 6-1/2* m 11*. (2) information recorded at top of thes form. , and (31 each sheet is numbered and number of sheets is (lN) Thes torns t(00042) niey tse abu.<ms 6,o,n she O der Ocpt ASME 345 E. 4 7 St New York, N.Y. t0017 i 4 Page 208
l l FO61M NV 1 40*CH
- f. .
CEllTWICATE OF COMPLIANCE 4 j we rat.ey ui i che si nents niede in m.s eepo.i . w...o and ihms aus vasoe cu.. sus.n su u.e euse of co...i mi.u..
.. n.e Asut Code for Nwle.se Powee Pim Conipoe .ws, Sco.ues Hl. O.v 1.. 1974 Ed.i.un. Addende a ussi . *76 40.sel e.de g., N. ..
o e h.sgg S.gn o c. niuuer, u.v. i,y W.m.nho
- . ~6 .c.o,..
ASME Cenet case og Aumofuehon No 1806 30 use me N symbos ==p.<ws i s t. July, 1980 tom > , l CERTIFICATION OF DESIGN Design infoe mation on tde at Geocral Electric and .. I Siress .nasysis repo<t (class 1 onsy) on s.se at Ceneral Electric and . ... One.gn speafications certIt.ed by* . Boyd P Broolus California. _ fteg. No. ,1365$ ..
! PE state ,
Stress report certir.ed by* . .. .Rober t ..L. We i s s PE Staae . California /Illinnia Reg. No., IL14921/62:21749. l l ' $4gnature not required-dist name only. 1 1 CERTFtCATE OF SHOP 8NSPECTION t, the undesdgmed, holding a valid cowwnission issued by the National Board of Bauer and Pressesre vessel inspecsors and the State or Province of . Q and employed by ..IWO of M on. have inspected the pump. or valve. described in this Data Repost on
. .M . . y 19 . and state that to the best of my knowtedge and belief. the Manufacturer has con-etructed this pump, or vaiva. en accordance with the ASME Code for Nuclear Power Plant Components.
' Sy signing theo certificate. neither the inspector not les employer makes any warrant, empressed or impeeed. concerning
','
- equepment described in this Data Report. Furthermose. neither the inspecsor not his employer shall be liable in any GEManor for injury or pr damage or a loss of any Imnd arising from or connected with this inspection.
Date -Q. 4
- 19 y' .
% wsb 4
1 Signed
.- . Co,n.n.ss.ons v n me. sea wh MP *
. ._ x ..y '
- n>.t?m : ,
l .'
- Qg, 3 e,s Sf- ,
o b l
. l l O(
l l l
1 i REPORT ND. NP0059-0005 l I l l NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS 1B21-250 l l As required by the Provisions of the ASME Code Section XI l l PNPP No. 9308 Rev. 6/93 l l l l 1. Owner: Cleveland Electric Illuminatina Comoany Date 3-23-96 l 1 l P.O. Box 5000. Cleveland. Ohio 44108 l Sheet A of 2 l l 1
, l 2. Plants Perry Nuclear Power Plant Unit One l I
I l 10 Center Road North Perry. Ohio 44081 W.O. 95-206 Rev. ,,2 l l . (Repair Org., P.O. No., etc)] 1 I I I l 3. Work Performed By: Cleveland Electric Illuminatina Co. Type Code Symbol Stamp HB l 1 I l 10 Center Rd North Perry. Ohio 44081 Authorization No. 33 l l 1 l . Expiration Date 7-18-96 l l l 1
- 4. Identification of System:
l IB21 Nuclear Boiler (NSSS) _' l l 1 I . 1
. l S. (a) Applicable construction Code: ASME Section III Class 1 , 1921,, Edition I Winter 1975 Addenda, Code Case 1644-5. 1728. N-272 (b) Applicable Edition of Section XI Utilized for Repairs or Replacements: 19 E Summer 1983 Addenda L
l 6. Identification of components Repaired, Hodified, or Replacement Components
- , ~ '
Name of Name of Manufacturer Nat. Other Year Repair ASME Component Manufacturer Serial No. Board ID. Built Replacement Code l'
,1 No. or Modification Stamped]
Piping l General Electric 1B21 64084 N/A 1985 Replacement Yes
, F System l
! I I . , 1 i 1 1 I I l
\ \ t Wh ':E l 1 1 I
ll 7. Description of Work: Removed valve S/N 160899 from MPL 1B21P0051G. and installed l l l l refurbished valve S/N 160863. Retest Lerformed Der W.O. 95-2920. (cont. on Line 91 l l 1 I I l 8. Test Conducted: Hydrostatic- [] Pneumatic- [ ] Nominal Operating Pressure- [X] l l Other- [] l l Pressure 1038 psi Test Temperature 175 degrees P l l l t Page 209
l i j NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS it l 1 I i I I l
- 9. Remarks: The followinq replacemant fasteners were also installed: l I
l l Eloht Inlet Flance Studs (six Trace # OCW-3. two Trace # OCW-5) l I 1 l One Outlet Flance Stud (Ht# 88673121 l 1 1 I I I I I I I I I I
- l I
l NOTE: Attach all applicable Manufacturer's Data Reports. Supplemental sheets such as l l lists, sketches, or drawings may be used, provided (1) size is e 1/2 in. x 11 l l in., (2) information in itemo 1 through 6 of this report is included on each l sheet, and (3) each sheet is numbered and the number of sheets is recorded on l the front of this form. l I l CERTIFICATE OF COMPLIANCE l J l We certify that the statements in this report are correct and that all design, material and workmanship on this reolacement conforms to I (repair, replacement, or modification) applicable section of the ASME Code. l
\
\
Certifi ategof Aut pizatio o. to use the NR stamp expires 7'Ih l Signed -- f Mechanical Ouality Encineer l 1 ' (Owne"r' er's Designee, Title) l CERTIFICATE OF INSERVICE INSPECTION l I, the undersigned, holding a valid commission issued by the National Board of l Boiler and Pressure Vessel Inspectors, and certificate of competency issued by l l the State or Province of QHLQ and employed by *ARKWRIGHT MImJAL INS. CO. of l l NORWOOD, MA. have inspected the repair,' modification or replacement described l in this report on M4nk D3 19 4(, , and state that to the best ll l l of my knowledge and belief, this repair, modification or replacement has been ll l ji made or constructed in accordance with Section XI of the ASME Code and the ll ll National Board rules as defined in the publication NB-102, current edition. ll ll By signing this certificate, neither the Inspector nor his employer makes any ll ll warranty, expressed or implied, concerning the repair, modification or ll l replacement described in this report. Furthermore, neither the Inspector nor l l l , his employer shall be liable in any manner for any personal injury or property l l l l damage or a loss of y kind from or connected with this4Ainspection. bge ll r<7 d Commissions FMe.3 T ll ll ll V (Inspector's Signature) l l Date M/4.c4 AM 1995
- FACTORY MUTUAL ENG. ASSOC. ll l
' 'if E
l 0
REPORT NO. NP0059-0005 l J 18211 250 'SheeE"2'of 2 FORM NV 1 MANUFACTUHERS* OATA HEPORT FOR SAFETY AND SAFETY HELitf VALVCS* l (As Required by tioe Provisions of the ASMC Code, Sectiosa lat. Div.1) n j_ p
- 3. SAenuf acewal tsy d. Dikkes's de Ca p . N.V. lla nneln) (f)) 11m %Cist:rlandai
[ 7 g7f,{
- 2. w ut=1urassw - -
m _._ _..... _ --.-- r ~.e-.. etra * % >Oc>wo . 4.-------... sce<m 4:4 71 -6 / l M . ds.4.n. r;4 foe. o we
-- d ---. i 9~
a 1 tve.t swas
- 5. vaave ggl soerney.ng Nos.- ,
'"" Ma.a/,ra.1,id,-
s.t Onice She 4,g4" Nominal enlet Sue 8" Ouuet She encei
, inch 10" inch
- 6. Set Pressure (PStG) _1$- Rated Temperature $g$ 4 Starnyed r,-ay _
N absths @ _O. % Overpressure 84awdown (PS4G) j* Hydrosteoc Test (PS4G) ln8et 2350 Outlet g% g,gg,, '
- 7. Pressure Retaining Pieces .
SerialNo or Material Specification klenutication inct Type or Grade sody Sonnet or Yoke U- M .Y. VIA
.C (L I O.,. SA 352 14n -
M.Li SA 352 IEB
, smas l Nozzle _ b. M _
SA. 350 1.F2-* Disc .511. M E f 4b SA 351 CF3A-sprinowaarmes S M b e6- 1 45 Cr Ho V 67
% screw MMT OM SA 182 F316 8'"'d'* OE- -
A 564-74 type 630 cond. HI100 Sesiao
- I n
V O.er e.ec. m.ra nay/nmkyawx SA 193-87/SA 194-7/SA 194-2H
@*O M W l.inc e- SA 351 CF3A cover 53,5b .M Sn b SA 351 CF8M !
Vent pipe R E A .\ sA 105 s ,..(.-.. . , P l a n:.* n MV SA 10$ 14 ch V. ou\,in d t di cam. ucdv e. body . Q (((f h MM g h cuwas hgW va , . is e _ g ,, it E C ElV E D JAN 113979 PNPP.SOlDC
- Suseplan.sental sheets in form of lists. sketches os diewings nemy be used provided (1) size is 8-1I2"
- 11*. (21 information j
- s. 3%; c.
*- ~
m derneh 1 ? On this data report is encluded on each sheet, and (3) each sheet is numbered and number of sheets is repartent at suo of thes form. { (1N) Tha form (E00042) eewy (see ed><a..es h. .. p., Ostkre thsn., ASME,345 E.4 7 St., New York. N.Y.10017 C')
%s Page 210
. . - . _ - ._ . _ . ~ _ - i 1 l l l f'ORM NV 1 isack) 31 + CERTif'ICATE OF COMPLIANCE We cert.fy shot the stesonients.mmic en this seport ave current and ehme thes valve condurms so the rules of e.one.tnact.on at the ASME Code for Nucleme Puwee Plant Compon.wiss. See:save tal. Div 1, f924 (d i.un, Adde.wl. s e u.e .
- 7 6, Cos's Case No. .... 'U**"'
Date N..ll-IilS.gned G. D i k k.e.r -.s A C.o. . N.V. by . N Our ASME Certifecate of Authorustoon No. l$O6 to uw the NV sovvi symbol eaperes 1stto.J.ui l y , I'd 80 CERTiriCATION OF DESIGN oes.gn information en tde at General Electric and . - .. Stre:a anaeyes report (class oneys on fde at General I:lectric and . .... j ossagn specifications certified tv Boyd P. Brooks PE State Califorula Reg.No. 13655 Strees repont certs.ed te Rober( L. Weiss , PE State California / Illinois Reg.No. H14921/62-25 749
- Sions<ure not veeveree-diet name oney.
CERTIf1CATE OF SHOP INSPECTION 1, the . __p4 holding a v mg- ' --: issued by the National Board ch ^ and Pressure Vesset inspectors and State or of of and empeoved by M* have inspected the pump, or valve, described in this Data Report on 2,,Z P. 19 . . and state that to the best of my knowledge and belief, the Manufacturer has con-servcted Wiis pump, or vahre, accordance with die ASME Code for Nucteer Power Plant Components. DVsigneng thes certificate, neither the inspector nor Ns egyloyer makes any warrarr'. e,imessed :( impleed, concernin0
@ equipment described in this Data Report. Furthermore. eMier the inspeclor nor Na employer shall be tiatdo in any manner for any personal injury or af arn:ge en a loss of any kind arising from or connected with this inspectiort Date @"N'"O O- 19}" . . .j I
i Signed ans,.ciers Com,n,ssions ul % sb art.n me.s.ai. e,bo w fui - 4 4 I D O
REPORT NO. NP0059-0005 i i l NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS 1B21-251 l l As required by the Provisions of the ASME Code Section XI l l PNPP No. 9308 Rev. 6/93 l l 1. Owner: Cleveland Electric Illuminatino Comoany Date 3-25-96 l 1 I l P.O. Box 5000. Clevgland. Ohio 44100 Sheet 1 of 2 l l l l 2. Plant: Perry Nuclear Power Plant Unit One l 1 l l 10 Center Road. North Perry. Ohio 44081 W.O. 95-207 Rev. J j l , (Repair Org., P.O. No., etc)l 1 1 I l l I ! l 3. Work Performed By: . Cleveland Electric Illuminatino Co. Type Code Symbol Stamp }]E l l l l l 10 Center Rd. North Perrv Ohio 44001 Authorization No. 33 l ' I I l ll ,, Expiration Date 7-18-96 l l
- 4. Ident;fication of System: 1B21 Nuclear Boiler (NSSS) l l
1
- 5. (a) Applicable Construction Code: ASME Section III class 1 , 1921,,, Edition l Ninter 1975 Addenda, Code Case 1644-4. 1729. N-272.
N-224-1. N-225. N-249. N-3. N-413. N-71-6. N-71-9. N-71-11 l (b) Applicable Edition of Section XI Utilized for Repairs or Replacements: 193) ,
/9 Susumer 1983 Addenda U
l 6. Identification of Components Repaired, Modified, or Replacement Components
'- ;f Qb Name of Name of Manufacturer Nat. Other Year Repair ASME Component Manufacturer Serial No. Board ID. Built Replacement Code l No. or Modification Stasped
; Piping General Electric 1B21 64084 N/A l 1985 Replacement Yes l-- System Pipng Johnson Controls 1B21-0070-F 001 N/A 1985 Replacement Yes '
i
--Sys te; l l
' y:
-,4
- 7. Description of Nork: Removed valve S/N 160872 from MPL 1B21F0047B. and installed l
refurbished valve S/N 160853. Retest oerformed oer W.O. 95-2920. (cont. on Line 9) l 1 I l l 8. Test Conducted: Hydrostatic- [] Pneumatic- [ ] Nominal Operating Pressure- (X) l l Other- [] l l Pressure 1038 psi Test Temperature 175 degrees F l l l
. i l
O Page 211
i l l NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS oR REPLACEMENTS i I
! l l 1 l 9. Remarks: The followina reolacement f astenergL,,were also installed: l l 1 l Fifteen 7/16* Air Flance Nuts (one Ht# 8098740, fourteen Heat Code GI) l 1
I I i l l I I I
! l 1
I I I i i I l NOTE: Attach all applicable Mandfacturer's Data Reports. Supplemental sheets such as j
, j lista, sketches, or drawings may be used, provided (1) . size is 8 1/2 in. x 11 l l in., (2) infonnation in items 1 thrbugh 6 of this report is included on each l l sheet, and (3) each sheet is numbered and the number of sheets is recorded on l l the front of this fonn. l
- l. I ll CERTIFICATE OF COMPLIANCE l 1; l We certify that the statements in this report are correct and that all design, l material and workmanship on this colacement conforms to (repair, replacement, or modification) applicable section of the ASME Code.
ll Certifica o( o zation No- 13 to use the NR stamp expires "1-19-96 Signed uded Mechanical Ouality Enaineer (Owner or Owner's Designee, Title) Date bb 19 N I
, y Q Ni l CERTIFICATE OF INSERVICE INSPECTION l I, the undersigned, holding a valid commission issued by the National Board of l Boiler and Pressure Vessel Inspectors, and certificate of competency issued by l the State or Province of QlRQ and employed by *ARKWRIGHT MUTUAL INS. CO. of l FORWOOD, MA. have inspected the repair, modification or replacement described ll in this report on MMM d(. , 19 % , and state that to the best l of my knowledge and belief, this repair, modification or replacement has been l made or constructed in accordance with Section XI of the ASMB Code and the l National Board rules as defined in the publication NB-102, current edition. ll l By signing this certificate, neither the Inspector nor his employer makes any l l l warranty, expressed or implied, concerning the repair, modification or l l replacement described in this report. Furthermore, neither the Inspector nor l l l his employer shall be liable in any manner for any personal injury or property l A . o :. '<g,. 8 ll damage or a 1 ss of any p}nd from or connected with this inspection. go l
' " ' ~
"; ll M u~X - Conmissions.#d 8FCJ Y (04, e , l 3
ll [In'shetor's Signature) l li Date AfWeb .34* 1990
- FACTORY MtTTUAL ENG. ASSOC. l l'
t I t I h
m_- , REPORT No. NP0059-0005 11121-251 Sheet 2 of 2 n 9: , UI'tBjy y2g FOHM NV.1 MANUTACTUHERS' DATA REPOHT FOR SAFETY AND SAFETY RFUEF VALVES * (As Required by the Provisions of the ASME Code. Section til. Div. 4) I7
- t. uanufaciured by C. Dikkers & Co. H.V. Hengelo (0) The Netherlands tNamo end nerus on uen.saaw.n
- 2. Maautaceured for Perry I IName.no A44..u.e ewen < or o.aers
- 3. Locanon t.f instauauon North Perry, Otilo eNam.aad Aoa.m.:
4 ----------- 0471-b/125.04.04 acem 25 . ly7e cordwong Noj (Natt Srd. Noj (year Swk)
- 5. Veve G471 su.a.i No s.ria ew : identHying Nos. 160033.a.,taaw tu rs s.i.4
. No i Type safetRosset.y / re l ie f See.ty, sedery .
Pdot; Power Adested Orifice Size . 4. 64'.' Nommel an8et Size . B" iach . inch Ouder Size 10" inch
- 6. Set Pressure (PSIG) .1160 . . Rated To ure Stamped Capacity 9
. ... . . . . . . 565 *F g,lg ebe#w @ .. . o _ % Overpressure Blowdown (PSIG) .110.5 Hydrostane Test (PSao) anset . 2350. .
- 7. Pressure feetaming Pieces Outlet . g n. ,g g.g Serial No. or Material Spedrocation identification inct Type or Grade Body
!O.44.7 s/a.2.. . SA .352-LCB .-
Bonnet or Yoke .03.24.8.s/a..l .... . SA- 352. M" Suppon nods r---_m _...,:.. . . . .
.u..-..
Noute AEU U25. . . - - . Disc
.sA 350 1S -
$5.52,7.s/a.14.
sping wasewes SA 351.CF3A -- 211653.s/n.14. . 45 Cr- 44o-v $? --- - -- Adiusung Screw p AFU 054
- 003 8A- 182 -F31 t Spindie . ..
.AEW.Ol7 --. ..
. Ar .-564-744ype-630-ooe4 < H1100 Spring ,, .na .rn, -
seating
, Onumees AUPr AJRr -AKAr AJJ, ALR, AUY, SA.193-B7/SA -194-#6A--494-2il -
.Aga, .Aag,. Aagg . . - -
Liner .-55.13.8 s/n' 2 4^ ' ' * ' ' Cover SA -351 GF3A- --- 62.04.8 s/a!!' S A -351 -Cf6M--- -- Vent pipe AFW 016 SA 105-- - -- F1anges AFV 070 + 003 SA 105- --- Aax. .>ur side d iasm. v alve body: ,- 476 anm (15.74' inch) Max. outside length valve 1642 aun (64.65 inch) RECEIVED JAN 114979 PNPP.SOjDC
- Suppsemantal sheets m form of arsts, sketches or drawings may be used provided (1) size is 81t2* si t1*. (21 information in nems at recurried 12sop unofthis th.sdata form.report is encluded on each sheet, and (3) each sheet is numbered and number of sheets is tit ?fu Thes tor n (E000478 may be obea..ml froen uw Orrior Dept Asuf. 345 t'. 4 7 St Nevr York, N Y.10017 Page 212
A)R f ORM NV 1 (Backt NS)(SpC g
- CERTiflCATE OF COMPT.AANCE We cerufy that the staiements made in this report a e correct and that this vaeve conforms.co the rules of construction of the ASME Code for Nuclear Powe. Piant Componenas. Sect.on tu. Div.1.. 1974 Eddeon. Addenda a utn, ',7 $
~~~~
Code Case No. w 10-11-78 signed C. Dikkers e . ,v. t,y w.H. willees (ed.a.s ci.e. Our ASME Cerufocate of Authorization No, iDOb to use the 14V symbot evres 1st July, ly8p CCHilFICATION OF DESIGN t Design information on fde at . 98.neya,1. flec t ric and Fe,rry . . . , . _ , , , , , _ , , _
^#' Stress anatvsis report (Claes t enlyt on fite st Gene ral El ec t r te and Fe r ry . ,_ ._ _ ,. ,,, ,,,,,,, , ,.
-- . _ . . . . . . . , . . . . . . . . . . . . _ ., ~ ~ ~ ~ " ~
Design specifecations cert.fied by' ._boyd,P3 Brooks - PE state .ga) i,{o_rtt i a,_ ,, _ ,, , , _ , ,, g ]"g{ ~
~
Strese report certified by* . ___ _.. Robert _b y,ej ss,, ~~* PE Staw Cal i f o rn ia,/,lJ t ino i,s, ,, ,,, , _p.g go, ] ] ] 4}ggg2 2574T _ e Segnature not required- dist name only. s CERTIFICATE OF SHOP INSPECTION 4, the sandersigned, holding a valid -_ _ - !seued by the National Board of Boi6er and Pressure Vesset inspectors and the State or Province of .. Oh19 , and emp:oyed by __ggnener Tna of _ kong, Grov e . .L i t s . have anspeaed the pump, or vaeve, described in this Data Report on ___ . 10- 1.1. 1s 7tL and state that to she been of my wwsedge and besief, the Manufacturer has con-senacted this pump, or valve, in accordance with the ASME Code for Nuc6 ear Power Plant Components.
- 8h eigeting this certificate, neither the inspector nor his emp4 oyer makes any warrant, expreened or implied, concerning he equipment described in this Data Report. Furthermore, neither the inspector not his employer shall be liable in any v,.,.g d $ ~
manner for any personal injury or property damage or a toss of any kind arising from or connected with this inspectiorL Osta 10- 19 78 Signed WC tinspector M C- . s.s . p g . 44 S gPeat*L lid , $4Ble new. SNI reg.) m
- p
- a. t.n .,%
O s
i REPORT NO. NP0059-0005 I s' . , l NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS 1021-252 l ) l As required by the Provisions of the ASME Code Section XI j l PNPP No. 9308 Rev. 6/93 l l l I l 1. Owner: Cleveland Electric Illuminatino Company Date 3-23-96 l l 1 P.O. Box 5000. Cleveland. Ohio 44108 Sheet 1 of 2 l l
- 2. Plant Perry Nuclear Power Plant Unit One l
l l 10 Center Road. North Perry. Ohio 44081 W.O. l 95-208 Rev. _2 l l . (Repair Org., P.O. No., etc)l l 1 1 I l 3. Work Performed By: Cleveland Electric Illuminatino Co. Type Code Symbol Stamp E l l l l 10 Center Rd. North Perrv. Ohio 44081 Authorization No. 33 l l 1 l , Expiration Date 7-19-96 l l
- 4. Identification of System: 1B21 Nuclear Boil 9r (NSES) ll l 5. '(a) Applicable construction Code: ASME Section III c1=== 1 , 1921 Edition.
Winter 1975 aAAmnAm, Code Case 1644-4. 1728. M-272 l (b) Applicable Edition of Section XI Utilized for Repairs or Replacements: 1911. O = ' " " ^-
- 6. Identification of Components Repaired, Modified, or Replacement Components p ,
~ .l s
Name of Name of Manufacturer Nat. Other Year Repair ASME Component Manufacturer Serial No. ' Board ID. Built Replacement Code l No. I or Modification Stamped l Piping General Electric 1B21 64084 N/A 1985 Replacement Yes l l }-- System -l 1 l , I
.l ,
i 1
\ l l ll
- \
_ e l - 7. Description of Work: Removed valve S/N 160895 from MPL 1B21F0047C. and installed j l refurbished valve S/N 160854. Retest Derformed Der W.O. 95-2920. (cont. on Line 9) l 1 l l 8. Test Conducted: Hydrostatic- [] Pneumatic- [ } Nomina - Operating Pressure- [X] l l Other- [] l l Pressure 1038 psi Test Temperature 175 degrees F l l I i Page 213 er
it i l NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS l 1 I l l l l l 9. Remarks: The followina reolacement fasteners were also installed: l l l [ Eicht Outlet Flance Studs (Ht# 8867312) l l 1 l Eicht Outlet Plance Nuts (Ht# 816171 l 1 I I I I I I I l l
! l l
I I
- l l NOTE: Attach all applicable Manu2acturer's Data Reports. Supplemental sheets such as l 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 j sheet, and (3) each sheet is numbered and the number of sheets is recorded on l 1, the front of this form. [
- l. l ll CERTIFICATE OF COMPLIANCE '
l j ll We certify that the statements in this report are correct and that all design, I material and workmanship on this reolacement conforms to 1 m l [ (repair, replacement, or modification) l l applicable section of the ASME Code. ll ll Certif ate o A oriza No. D to use the NR stamp expires W d ll ) Signed a Mechanical cuality Encineer l
'tthner er's Designee, Title)
' ' 'l ll.
u l
.~ ",' q' :>r j CERTIFICATE OF INSERVICE INSPECTION j l l I, the undersigned, holding a valid commission issued by the National Board of i j ll Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the State or Province of QHIQ and employed by *ARKWRIGHT MUTUAL INS. CO. of i NORWOOD. MA. have inspected the repair,' modification or replacement described l1 in this report on N W .TI 19 Q", , and state that to the best ll ll j l of my knowledge and belief, this repair, modification or replacement has been l ll made or constructed in accordance with Section XI of the ASME Code and the l1 ll National Board rules as defined in the publication NB-102, current edition. ll ll By signing this certificate, neither the Inspector nor his employer makes any ll ll warranty, expressed or implied, concerning the repair, modification or ll ll replacement described in this report. Furthermore, neither the Inspector nor ll ll his employer shall be liable in any manner for any personal injury or property l ll damage or a loss of ang kind from or connected with this inspection. l ll 7""5P M ~ V Commissions dlG5T,3 f N, Il
" ll ll (Inspector's Signature)
/'fucA, 19 98,
- FACTORY MUTUAL ENG. ASSOC. ll ll Date o'13 l' "I I f
O
REPORT N3. NP0059-0005 k N 4 1B21-252 Sheet 2 of 2 d O (M ~.- (07YSIlo7 C 19
. FORM NV-1 MANUFACTURERS" DATA REPORT FOR SAFETY AND SAFETY REUEF VAL.VES*
(As Required by the Provisions of the ASME Code. Section 141, Div.1)
- 1. Manufactured by C. Dikkers & Co. N.V. liengelo (0) The Netherlands eNane and Ad@ess of 9denuleaurer)
- 2. Manufactured for Perry 1 (Nerne sad Address of Puechener es Ownert
- 3. t.ocation of instamation #1 orth t'erry Ohio (Nane and Address)
- 4. - .-- ------ G471-6/125.04.04 26 1976 (Dreweng kl (Ned. Bed No.) (Year Suetil
) eCRN)
I 5. Vahre .. . G471. . IdenOfying Nos. 160854 (Wdet No Seeks Ned (Manuteaurers* Serial No.l seimy.'$Mdvs.v,J;",oF u ed orwice SL-e . . _ 4 . 84'.' Nominal intet Size 6" Outlet Sire 10"
- inch im*
inch
- 6. Set Preseues (PSIG) . 11611. . Rated Temperature 585 "F Stamped Capechy .... 9172$3 tbenir @ 0 % overpressure Biowdown (PSIG) 97 9 Set sneem
- Test (PSIG) enlet 2350 . outiet 975
.~ (Apps.cetdo to velwes ser consed systems oneyt
- 7. Piesoure Roteining Pieces
' Mewisi SpecFacation Settet No. or identification inct Type or Grade sody ___.12.DA.B.4/a 1 SA 352 len sonnet or Yo6e !t.'S S s/n 3 SA 352 len
, p1 Support Rode .. d b Nonle 18'f f n12 . % SA 350 LF2 SA 351.CF3A - Dise u ni a s/n lA
, Spring weehers ?11ut =/a 12 45 Cr Ho .V 67
, .. Aquating Screw mr !31/AFU 094 SA .162 E316.. .
.W% >~- ' Spindie _ Ang 034. A 564 74 cype.630 cond. Hl100 z.s..,,r.-s----- - Spring _ r
- Boiting -- AUEe..AJRr AUK, AJJ ALM , SA 193-87/SA 194-7/6A 194-2H Other Pieces J W Mr.AJt.
.l.ine r...- ^0,04.8..s/n-2 -
. 6A 351 4F3A-Cover 58.50..L s/n.1 .- . . SA 351 cF8M.
. Vent. pipe Antn9 , SA 105 -..
.ELang e.s. Arv nio/arv (190. SA 105.
l Max. outside diam. valve body: 4 76 nun (18.74 inch) Max. outside length valve : 1645 mm (64.76 inch) _p _i
- Supplemental sheets in form of lis1s. sketches or drawings may be used provided (1) size is 8-tt2" .11". (2) information in items 17 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.
p i 1 ( Page 214
b
&lM_
UY5. &., - FORM NV.1 (Back) g CERTIFICATE OF COfMLIANCE We umfy that the statements made an this eeport are correct and that this valve conforms to the rules of construct.on of the ASME Code for Nuclear Power Plant Components. Seci.on tit. Div. t.. 1974 Edition. Addenda sum.'7p Code Case No. w 10 7 t1 signed 4. Dikke ras b Co. by W . tt . Willems tuanvt.c.w rs IDU6 to use the IU Our ASME Certsfacate of Authorizatson No. envi symnoi emp.res ist July # !*)tio somes a CERTIFICATION OF DESIGN ossigninformaion on m ei ... pereral,tpectric and Perry _ ,, , _ j stress samysis report Etess onM on a.m . . ..cepral Et ec.t ric .and_Pe r ry_., _._,. i - oesign specir.cmions cert.f.ed by' . .#.95.d. . P , ..Bl q9An_ .... _ . . . . _ . . . . re state . C4I i f9rni A. . _ . . . . _ . . Ra.g. No. .'_.... .. 13155
... [~'
suese report certir.ed te _. __.Xohert L. Vnits-. -_ ._ _ _ . . Pe siste ._...Caliform.isL11.linois.'. . . .. Reg. No. . 314.9.21/h2-2 5749_. ...
- Signature not required-list name only.
CDITIFICATE OF SHOP INSPECTION t, the uredersigned, hokling a valid commission issued ty the National Board of Boller and Pressure Vesset inspectors and the State or Proence of . . ..Ubio . . . . . and employed tv Kemper_ina .. . .. of . Long drove 111... . . . . have inspected the pump. or valve, described in this Data Report on
. 10-11 . 19 liiand state that to the best of my know4 edge and beliet the Manufacturer lias con-structed this pump, or volve. In accordance with the ASME Code for Nuclear Power Plant Components.
By signing this certificate. neither the inspector not Ns employer makes any warrant, expressed or implied, concoming
%e equipment described in this Data Fiepoft. Furthermore, neither the inspector not his employer shall be liable in any manner for any personalinjury or property damage or a loss A any kind arising from or connected with this inspection.
~y
\ Date 10- .. 19 78 Signed .e.e , cu Commiss.ons . .. . . . .. _.Ns .4456 -- - . . . .
tenspecsort tNart. ee. sasse Prov. end NoJ
~
e i O
l REPORT N3. NP0059-0005 l l NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTt; 1821-253 l l As required by the Provisions of the ASME Code Section XI l l PNPP No. 9308 Rev. 6/93 l l l l 1. Owner: Cleveland Electric Illuminatino ComDany Date 3-23-9t l l 1 l P.O. Box 5000. Cleveland. Ohio 44108 Sheet 1 of 2 l l 1 Perry Nuclear Power Plant Unit One l 2. Plants j l l l 10 Center Road. North Perry, Ohio 44001 W.O. 95-209 Rev. J l l
. (Repair Org. , P.O. No. , etc) ]
I I I I l 3. Work Performed By: Cleveland Electric Illuminatina Co. Type Code Symbol Stamp Hg [ ll 10 Center Rd, North Perry, Ohio 44081 Authorization No. 33 ll
, Expiration Date 7-19-96 l
, 4. Identification of System: 1B21 Nuclear Boiler (NSSS) j l
- 5. (a)' Applicable Construction Coder ASME Section III Class 1 , 19 1 Edition l Winter 1975 mAAmnAm, Code Case 1644-4, 1728, N-272 l (b) Applicable Edition of Section XI Utilized for Repairs or Replacements: 1911, Su - r 1983 mAAanAm
- 6. Identification of Components Repaired, Modified, or Replacement Components l lNameof Name of Manufacturer Nat.' Other Year l Repair l ASME l Component' Manufacturer Serial No. Board ID. Built' Replacement Code
- No. or Modification Stamped' l Piping General Electric 1B21 ! 64084. N/A 1985 . Replacement Yes
.l l-- System l l ll l) l I l.
l \ i 7i l l, e
., l l, e i t
- 7. Description of Works nae ved valve S/N 160890 from MPL 1B21F0047D. and installed refurbished valve S/N 160855.
ll Retest Derformed Der W.O. 95-2920. (cont. on Line 9) i I
= ' , j i l 8. Test Conducted: Hydrostatic- () Pneumatic- () Nominal Operating Pressure- (X) l l Other- [] l l Pressure 1038 psi Test Temperature 175 degrees F l l l
)
)
Page 215
l NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS l 1 I l l 1 l l
- 9. Remarks: The followinq reolacement fasteners were also installed: l 1 l l Four Inlet Flance Studs meat Code Z4K) l l l l 1 I I I -
l l 1 1 1 I l
. I I l -
! 1 l NOTE: Attach all applicable Manufacturer's Data Reports. Supplemental sheets such as l l lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 l l in., (2) information in items 1 through 6 of this report is included on each l l sheet, and (3) each sheet is numbered and the number of sheets is recorded on l the front of this form. l l s l l l CERTIFICATE OF COMPLIANCE j l We certify that the statements in this report are correct and that all ' gn, l material and workmanship on this reolacement cc , rms to (repair, replacement, or modification) applicable section of the ASME Code.
I j Certi cate of thori on No. to use the NR stamp expires 7'lb k ll Signed Mechanical Ouality Encineer l % g b ~ 3 Owner or e 's Designee, Title) l l Date f 19 lI
! 'l ...s>. - *~ ^ '
l l CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid connission issued by the National Board of l, Boiler and Pressure Vessel Inspectors, and certificate of competency issued by ll l , the State or Province of QLQQ and employed by *ARKWRIGHT MUTUAL INS. CO. of ll l NORWOOD._MA. have inspected the repair,' modification or replacement described ll l in this report on M4.ue, M 19 M , and state that to the best ll l of my knowledge and belief, this repair, modification or replacement has been ll ll made or constructed in accordance with Section XI of the ASME Code and the ll ll National Board rules as defined in the publication NB-102, current edition. ll ll By signing this certificate, neither the Inspector nor his employer makes any ll ll warranty, expressed or implied, concerning the repair, modification or ll l l replacement described in this report. Furthermore, neither the Inspector nor ll
'.,' ll his employer shall be liable in any manner for any personal injury or property ll ll damage or oss of an ind from or connected with this inspection, ll ll D .
Commissions /)d9St3 C bg1 ll t ll " '(Inspector's Signature) ll l ll Date M.freA M '4 19 %
- FACTORY HUTUAI,ENG. ASSOC. ll l gi i l
l A f k I I l O l I l l _ _ _ _ _ _ _ _ _ _ . _ . _ _ _ . 1
REPORT NO. NP0059-0005 83 A IB21-253 Sheet 2 of 2 l"'%;
> lilyi-(b... ,.
u ._ L.J ;; FORM NV.1 MANUFACTURERS
- DATA REPORT FOR SAFETY AND SAFETY RE1JU' VA1VES*
. (As Required by the Provisions of the ASME Code. Section lat. Div. I) i, %,,,,gy G. Dikkers E Co. N.V. Hengelo. The Netherlands
.a.n.:
,, y,,,m ,,, Gene ra l E I c(N.a.e ctrecaa m. ee u l
- 3. w,,,,, ,, w,,,,, Per ry I [**R$fTh'YlYyMRI'o'" ***'
4, G47 I-6/125. 0M*"""' 31 1978 cmNI tor no No. "*" g
' "" ""tN rt e**lD855 I tuaaes No,safety smuse No.)/ rel i e f ' tuannstectanw( sweat No.3 l
% Aa,..m.d l semy. g ,p ccaan;co ,, ,
Onice Sue Nommet enlet Sue Cunet Sue nach inch .. inch
- 6. Set Pressure (PStG) II . . .. . Rated Temperature $85. . . y Stamped Capacky _0. I. 72 53.. . __. . . aer ta 0 3 o,,,,,,,,,,e s t. s'**"
em teSic) .. 100 7 Hydrostatic Test (f'SIG) inlet . 2.3.5.0 ,,, , o,,,,, 975 (Appiscable to wh. . ... . ,for caosed sysiems onM 7, %, g,, % Serial No. or 8Aaterial C7- " j nden Ecocon incl Type or Grade Body _10.44.7,_s/n,6 , ..SA 352 LCB sonnit or voke _04.14.8 g/,n 2 SA $52 LCB _ _ , , , , , , , , Support nods ~~ 6 Nonte E.057. .. . T ~ .. SA_,.350 t.F2 oise SL.0L B. 461 SA_.J11 QfjA,,_ ,_,
.21.16'n . n/n 11.,
Serias weehers .. 45 gr tio..y 67. Adiusune Sa AEu_.1021 SM 091 SA 18jt ,F316 , _ . , , , . i
g Sp ndie .6DL9.11.. .A_,.564_2_4 tvoe.6_30 cond. H1100 I (V
Senao .. .
, Boama AUP_;._AJh, AKA; AJJ; ALR . . _ .SA]93.-BJ/SA14.-7/SA 194-2H j - OewrF5eose AE;..AtlR; AW; /WL.
U ne r. . .__fild5 r 8 s/ nip . ..$A. 351..?E3A._.
-'a .
s cover . . 55JiQ.7 s/n 77 . SA351 CF8H vent pipe _.A m 039 -5 A,,10L _ , Flanges .AfY.D33; AFV 064- SA 195. .,, Max, outside diam. va'Ive body: 476 mm. (18.74") Max. outside length : 1643 m'm (64.69") RECElVED l JAN 11 1979 PNPP.SOjDC
'h
- SuppiamerHat sheets in form of lists, sketches or drawings may be used provided (1) sue is 81/2" h 11*. (2) information in stems 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.
t1(7GI This term (E00042) may twe obtained f orn the Order Dept ASME,345 E. 47 St., New York. N.Y.10017 e i
\ }
v Page 216
~~ _.
rnL. b'Mi &~Ia s* FORM NV.1 (Back)
- CERTIFICATE OF COMPUANCE we certify that the staternents made in it.is seport see currecs and shot shes valve conforms to the rules of construct.on of the ASME Code for Nuckar Power Plant Components. Section td. Dev.1,. [detson. Addende Surn.
- 76 ,
Code Cam No. 24.11.1978 g n.o G. Dikkers & Co. N.V. by N N W I I I *'"5 w
'"**"'**" 1806 to up the NV Our ASME Cerut cate of Auct.oeksten No. N 1st July 1980 sW expires ~
toaiel , CERTIFICA110N OF DESIGN Design informouon on 64e et . Gericral .Electr.l.c.aod Perry ..
. .,. . ceo.rai.ciectric and.ecrry ;
Suess onetysis report (Class i onsyt on file et . . _ ossagn specincetions ee, tined by. .. _ .. .. .Boyd IL ftr.ooks. . . . . . . _ . . . . . . _ . . _ . . . . . PE State . EaIIforhIa ._. . ..._. ._. ._. Reg.No. . . 13651.. . _ _ _ seess report eertised by' ..-. . .~_ Baber.t I..Welis.. . . . PEState .Callfornlaf.ll.1inclS . . Reg. No. . fl.Id21/.62*28i749 . . _ . . , _
- 6.gnature not required-4st name oney.
l CElmRCATE OF SHOP INSPECT 10N
. e - d.ng .eu .-- - is ed oy e Neuonei .oo.d ce e, and eressure vee ~.
_.. .and employed by E*8mre r Int- _ _ , _ . and the State or Province of ._Dhlo . of ...Long . Grove,.11.1 . how inspected the pump, or we ve, described in this Data Repwt on
. ... . . . 21. 11..,19_78_, and state that to the beet'ei my einowledge and besse(, the Manufacturer has con-eaucsed ins pump, or volve. In accosdence with the ASME Code for Nuclear Power Plant Components.
. ~ . , ,
Oy signing this certHicate. neither the inspector not No employer malies any warrent, eW or impleed. concoming w equipment desenbed in this Data Report. Furthermore, neither the in=& not his employer ehen be ineble in any
.f .rio.omer - w.,tNs _
- se
.y _ ,o, ,,e,sonesi,,mor _ . - o,emo,an, oste . 2A 3 3 t signed .../1. c- $ s.7a_ w . . ._. . . CommisesonetM, M5i _ _ - .. _ __ -
en u. t %. s % i %. I ki 4 s d O
REPORT NO. NP0059-0005 g V) i l NIS-2/NR-1 OWNER'S REPORT POR REPAIRS OR REPLACEMENTS 1B21-254 i l l As required by the Provisions of the ASME Code Section XI l l PNPP No. 9308 Rev. 6/93 l l 1. Owner: . Cleveland Electric Illuminating Company Date 3-23-96 l l l l P.O. Box 5000. Cleveland. Ohio 44108 Sheet 1 of 2 l 1 l l 2. Plant: Perry Nuclear Power Plant Unit One l 1 l 10 Center Road. North Perry. Ohio 44001 W.O. l 95-210 Rev. J l l . (Repair Org., P.O. No., etc)l 1 I I I l 3. Work Performed By: Cleveland Electric Illuminatino Co. Type Code Symbol Stamp gg l I I l 10 Center Rd. North Perrv. Ohio 44081 Authorization No. 33 l l l l Expiration Date 7-18-96 l l l
'4. Identification of System 1921 Nuclear Boiler (NSSS) l l
1 (a) Applicable Construction Code: ASME Section III Class 1 5. Winter 1975 Addenda, Code Case 1644-4. 1728. N-272. 19 1 Edition l l N-413. N-224-1. N-71-9. N-71-6. N-3. N-225. N-249. N-71-11 I (b) Applicable Edition of Section XI Utilized for Repairs or Replacements: 193J , l [mj Summer 1983 Addenda
'G!
l l 6. Identification of Components Repaired, Modified, or Replacement Components l . . i e a i i l l Name of l Name of Manufacturer l Nat. Other! Year l Repair l ASME l l Component l Manufacturer Serial No. l Board ID. i Built l Replacement l Code l 1. l l sl No.
. or Modification Stamped l i l Piping l General Electric l 1B21 64084l N/A 1985 Replacement '
Yes l ll h System l l l , ll l l Piping Johnson Controls l 1B21-0070-F l 001 l N/A l 1985 Replacement l Yes ll l }-Syste: , l l l l ll 1 l l 1 I l iI l l l l l1 I l l I l II . ll l l ! , , ll 11 I. I I I. II l
. . I.
i l I l 7. Description of Work: Removed valve S/N 160873 from MPL 1B21P0047P. and installed l 1 l l refurbished valve S/N 160856. Petest Derformed Der W.O. 95-2920. (cont. on Line 9) l l l l 1 l 8. Test Conducted: Hydrostatic- [] Pneumatic- [ ] Nominal Operating Pressure- [X] l l Other- [] I l Pressure 1038 psi Test Temperature 175 degrees F l I' I I l e ; Qf Page 217
l l NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS oR REPLACEMENTS ie l i 1 ' i , I I l 3. Remarks: The followina replacement fasteners were also installed: l l 1 1 l Eiaht 7/16" Air Flance Studs (Heat Code GJ) l l l l Sixteen 7/16" Air Flance Nuts (Heat Code GI) { I l I i . I I I I I I I I
- l l
l 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 l in., (2) information in items 1 through 6 of this report is included on each l l l sheet, and (3) each sheet is numbered and the number of sheets is recorded on ] l the front of this form. l
' , I CERTIFICATE OF COL.TLIANCE 1 l l ,
l We certify that the statements in this report are correct and that all design, l material and workmanship on this reolacement conforms to l l l (repair, replacement, or modification) l applicable section of the ASME Code. ll ll Certi cate of riza n No. D to use the NR stamp expires l Signed
- Mechanical Ouality Encineer
] 'towner or 19 er's Designee, Title) l 1l Date
'I l l' ,I i i, CERTIFICATE OF INSERVICE INSPECTION ll I ll j l l I, the undersigned, holding a valid commission issued by the National Board of ll Boiler and Pressure Vessel Inspectors, and certificate of competency issued by l the State or Province of pHLQ and employed by *ARKWRIGHT MUTUAL INS. CO. of ll l] NORWOOD. MA. have inspected the repair,' modification or replacement described l l in this report on Mwl. d3 , 1996 , and state that to the best l of my knowledge and belief, this repair, modification or replacement has been Ll l 1 l jl made or constructed in accordance with Section XI of the ASME Code and the
\l National Board rules as defined in the publication NB-102, current edition. l ll By signing this certificate, neither the Inspector nor his employer makes any ,I l
ll warranty, expressed or implied, concerning the repair, modification or ' ll replacement described in this report. Furthermore, neither the Inspector nor l l ll his employer shall be liable in any manner for any personal injury or property damage or a loss of kind from or connected with this inspection. - l ll Commissions zd BTr,4 T $ ] 1 r<7M- - - l l
]l
' (Inspector's Signature) l l ll Date MA A_e4 E 19 M
- FACTORY MUTUAL ENG. ASSOC. l\
l
' l l l '
o 4 l 9
REPORT NO. NP0059-0005 (7 rg IB21-254 Sheet 2 of 2 Q,) I!/*!!!f 3 Q FORM NV.1 MANUFACTURERS
- DATA REPORT FOR SAFETY AND SAFETY REUEF VES.*
(As Required by the Provisions of the ASME Code. Section in, Div.11
- 1. Manutactured tsy G. Dikkers & Co. N.V.en m. aaneu sana.Hesioe l o.a(0) , T he Ne t he r l andii i
.a \
- 2. wovred to, Generaf.aElect r it I su .a4 ama. . .e co,ce ., o o
- a. toca .nn of instaitauon Perry I, North Perry, Ohio G471-6W84^'6T" 30 1978 4.
scn=> cgipg au in.n .. umi n..e e s.vaeve ideni.fying Nos.1y0856 tuoe.i n s.r wo.i '"**"'"' **'"' Tvpe sa fe ty/rel'i e f s ey y R.is.f; Pdos; Power Aawas.d Orince Sue Nominal inlet Size Oudet Siae I M M .M ... al Set Pressure (PS4G) 1180 . hied Temperature 585 ., j Stamped capacity 9172$3, m, g 0 ,,%,,,,,,,,,, 36.7 S^ s= ,,SiG) . 975 Hydrostatic Test (PSIG) inlet 350 , ,, o,, __ _ _ , . .
- 7. Pnes.ute Retaining Pieces Serial No. or Material SpecMcation 6dentification inct Type or Grade sody 10,.04.8 / 1 SA 352 LCB , , _ , , ,
0}.,0.6,{,,sn sonnet er you R, _ 2 SA 352 LC8
'AEd[663 ,,
,SA_}$0,LF2,, _ ,,_,,,, , ,
oi Sh 04 8 3A,. .SA,) M,C_F M , ( Sp,ina washar. .36 30 9 .50 4 5..C r Ho v 6 ,, ,_, __ , _ , j
,SA,,1_82 F}16,7 _ ,,,_._,... ,
Adiu.dna Sae. .AFU 038, AFU 074 fm A. J.6[-B ,tyge 630, Son,d. j,t.11,0p i ( ) Spindia AEV 015. . El Spring
.... 4. . .
somna ...AUP,,,AJR, AKA, AJJ. ALR, ,SA,1}} B,2/SA,_114.. ,7/SA,11,-2H,, , Od,e, P,,ces AUY,,AMR., AJM, AJL , . . , ... , , _ _ , 4 Liner 53 16.,8 g/ri 1 SA J51,,CF3A ,_ _, , . _ Cover. 55.46,7 s/n 2 '
.SA,35.1 CF8N Vent pipe AFW 033 SA,105, ,
Flenges .AF\/ 044, AFV 001 SA,101 , . , _ , , . . . _ ,_, _ , , , Max. outside diam. valve body: 479 nun (18.86") , Max. outside length valve : 1647 mm- (64.84") n.E C ElV E D J AN 11 1979 PNPP.sOlDC
- Supplemental sheets in form of tests, sketches or drawings may t>e used provided (1) size is 81/2" m 11*. (2) information mi stems 12 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.
(117M T he. luem (E00042) nwy tw otn....ed h nen the Orrier Dept., ASME,345 E. 4 7 St., New Yoek, N.Y.10017
.x j
/ 3 LJ Page 218
() . * - U Sf(v7?C
.:tl FORM NV.1 (Back)
CERTirtCATE OF COMPUANCE We artify 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 lit. Div. t.. Edition. Addenda Code Case No. .. .
**3 Date 17.11.78 Signed G. Oikkers & Co. H.V.. - , W.H. Wil leins
. by w..a.e.ca .<>
Our ASME Certeficate of Authorizatson No. 1806 I to tese the N 1st July' 1980 " symbol expires . . Q7y CERT 1FICAT10N OF DESIGN Design information on % st ._General .. , Electric and Perry 1 stress analysis report (Class 1 onlyt on m at ,Generai Electric and Perry 1 e Design spegipjaocygfp by __ Doyd R. . 0. rooks 13655 PE stat.... . .__ ._._ . Rcbert L. We isW " stress PE state repon certined by'i.a/TTT.ii.i_oT.
. ca_.l..I..f.o_.r.n_ ~ .
- s. . Reg. No. M14921/62-25749 t Signature not required- 4ist name only.
CERTIFICATE OF SHOP INSPECTION L the undersigned. holding a g salon issued by t&e National Board of Boiler and Pressure Vesset inspectors
- f. and g tg ' _. .. and employed by . bef0 Der...] ns .
of . have inspected the pump, or valve, described in this Data Report on 19 and state that to the best of my knowledge end belief, the Manu'acturer has con. , Q . .,c;. . _ 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 emplopt makes any warrant, expressed or implied, concoming the equipment described in this Data Report. Furthermore, neither the inspector e.or his employer shall be liable in any menner i personal injury or party damage or a loss of any kind arising from or connected with this inspection. Date . .. 2 - ^ 19 . Signed ha O g __ Commissions , NB 4456 onw.aer mert. sa, sta em .ad Nel
,,' Q u; I
O
REPORT NO. NP0059-0005 i i j NIS-2/NR-1 OWNER'S REPORT POR REPAIRS oR REPLACEMENTS 1B21-255 l l As required by the Provisions of the ASME Code Section XI l l PNPP No. 9308 Rev. 6/93 l l l l 1. Owner: Cleveland Electric Illuminatiner Company Date 3-23-96 l l 1 l P.O. Box 5000. Cleveland. Chio 44108 Sheet 1 of 2 l l 1 l 2. Plant: Perry Nuclear Power Plant Unit One j i i l 10 Center Road. North Perry. Ohio 44081 W.O. 95-211 Rev. J l l . (Repair Org., P.O. No., etc)l l 1 I i 1 l 3. Work Performed By: Cleveland Electric Illuminatina Co. Type Code Symbol Stamp }[g l l 1 I l 10 Center Rd., North Perry. Ohio 44081 Authorization No. 33 l l Expiration Date 7-19-96 l l
- 4. Identification of System: 1B21 Nuclear Boiler (NSSS) l.
l K l 5. (a) Applicable Construction Code: ASME Section III Class 1 , 191{ Edition Winter 1975 AAdanda, Code Case 1644-4. 1728. N-272 L (b) Applicable Edition of Section XI Utilized for Repairs or Replacements: 19 E [ ] S=r 1983 Addenda
- 6. Identification of Components R paired, Modified, or Replacement Components te 4
- Name of Name of Manufacturer Nat. Other Year Repair ASME '
Component Manufacturer Serial No. ; Boardl ID. Built Replacement Code No. , : or Modification St.mped
; Piping General Electric 1B21 64084: N/A 1985l Replacement Yes F System I l ,
I l L L 1 I I I, t g 5 i w- 1 i I, I, i I
- 7. Description of Work: Removed valve S/N 160876 f rom MPL 1B'21F00470, and installed l l
refurbished valve S/ti 160893. Retest Derformed Der W.O. 95-2920. h I l 8. Test Conducted: Hydrostatic- () Pneumatic- () Nominal Operating Pressure- (X] l l Other- () l l Pressure 1038 psi Test Temperature 175 degrees F l l I i Page 219
l I I-l NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS l l 1 l l l l l 9. Remarks: None l l l 1 i l l I I i _. I I I I I I I I l l l l l 1 1 ' i l . l l NOTE: Attach all applicable Manufacturer's Data Reports. Supplemental sheets such as l l l lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 l l l in., (2) information in items 1 through 6 of this report is included on each l l sheet, and (3) each sheet is numbered and the number of sheets is recorded on l l the front of this form. l l l CERTIFICATE OF COMPLIANCE l We certify that the statements in this report are correct and that all design, , l material and wor)rmanahip on this reolacement conforms to l l (repair, replacement, or modification) applicable section of the ASME Code. ll Certifi te of A thoriz on No. D to use the NR stamp expires 7'W M ll Signed "h Mechanical Ouality Engineer l,
% er or Owner's Designee, Title) l l Date N hed 2 19 $ li ll ;
I
- d. .ad, St N t
%W (% * '! '
CERTIFICATE OF INSERVICE INSPECTION I, the smdersigned, holding a valid commission issued by the National Board of i Boilu and Pressure Vessel Inspectors, and certificate of competency issued by l the State or Province of QH.IQ and employed by *ARKWRIGHT MUTUAL INS. CO. of l NORWOOD, MA. have inspected the repair,' modification or replacement described I l in this report on M Acr4 03 1996 , and state that to the best l l of my knowledge and belief, this repair, modification or replacement has been 'l l ll made or constructed in accordance with Gection XI of the ASME Code and the l l ll National Board rules as defined in the publication NB-102, current edition. l l ll By signing this certificate, neither the Inspector nor his employer makes any 'l l ) ll warranty, expressed or implied, concerning the repair, modification or ll l ll replacement described in this report. Furthermore, neither the Inspector nor ll ll his employer shall be liable in any manner for any personal injury or property ll l
. ,6)[# ll damage or loss of y kind from or connected with this inspection, g ll l 5^
ll 4
-e _
Commissions 1)A ho3 C kw ll ll (Inspector's Signature) ll ll Date MMel4 A13 19 9d*
- FACTORY MUTUAL ENG. ASSOC. ll l'
. ' I.
l 0
REPORT NO. NP0059-0005 s / (N v
/ 'IB21-255 sheet 2 of 2 FORM NV 1 N CERTIFICATE HOLDERS' DATA REPORT FOR SAFETY AND ' SAFETY REUEF VALVES
- As Required by the Provisions of the ASME Code. Section 18. Div. t y@ @ gy I. Menutectured t, G, Diktors !. Cou Memmalo (ol L],e i.e.t.be r l aint s 4Name oas Amewse er N ce<imcase s.eaeers
- 2. Manufactured for G0""f*I t'l ec c ric M n Jop , ga 1 i f orgia_
- 3. taceteon of inacenanon l'e r r y i + menw ead Add <e.. .e ruven. , or ownert1 i wnares Norr b t*errv, tHij o (Neme and Asdress)
M/A c47i-6/ z5.n4.03 rev. e ~~~ i Fi 1979 scANI (Orewing No4 (Nerl. Sed NoJ . (Year Buest
- 5. Velve (*47I 4 dent [fpng Nos. _ IN'W3 (Bdeded Na, Germ NoJ * (N Certmcate Moseer's settet Nej Type s:ef eev/re11r f seesty seesty Resef; reet; Power Aausied Ortnce Sise 4 F4~ Nominet' anset size F(Planr.cs) Outlet Size 10" l
'"*" M M i . . _ _
- 6. Set Pmesure (PS4Gl lMU Rated' Temperature 585 y- . c.
Stemped Cepecity 93703 lbsthe @ 3 % Overpressure Slowdown (PSIG) 42.35 Sec. $seem .
",/. M Test (PS6G) inlet 2350' ' Outtet 975 w -w seyeaves for caoned eyeseme eney)
Serial No. or Meneviel Specification 3 ,,y ; identiscetion , , inct Type of Grade-Sedy' 05.19.8 m/n 5 SA 352 ten ,
~'
Sonnet or Yoke 12.?9.8 m/n 2' SA 357 in . Suppoesnode - Nesses
- AJW 113 SA 350 LF2 s ,
06sc 60.07.9 s/n.28 SA'351 CF3A # Spring weehere 26.30.95 s/n 153' 45 Cr No V 67 > [' ] % g, - ASB 081/ASB 009 - J. SA 182 F316- 5 ()) i g,ingi, ., CAD 010 ,A 564-74 type 630.cond. HilOO
.? G ;, % - w. g. . ..:..; g .~ee m ~_.m;; , . ;. w .s. .. :. . ,
~
y goeting ' ANY/ANZ/AVS/AJS/APA/APB/AN7. SA 193-B7/SA 194-7/SA 194-2f f
- Other Pieces \
, .7 . 9r, , .
y , ., q
, g Liner 63.04.09 s/n I SA 351 CF3A< /
Cover 53. 38. H s /n. L. _ ._. _ SA J}l CFre) . Vent til no Akb 04t> SA lit 5 /- 61 antes , ASA 224/ASA 213 . SA 105
/ -
l tax. outaalde dian.. valve 12ody: 478 uun.M'd.62)
- ux. outside length valve : 1648 me..(64.He)
.+.
- Supplementat sheets in form of lists sketches or drawings may be used provided (1) sue is 8112* m 11*. (2) infor stion in hema 12 on this Data fleport is included ori each sheet, and (3) each sheet is numbered and number of s ets is recorded at top of this form.
I10/77) This form (E00042) mey be obteiaed f.om the Ordee Dept. ASME.345 E. 47th St. New Yovk.N.Y.10017 !m V) Page 220
V
. (
't FORM NV 1 (Back) 'mg4 iOWN O
I CERTlf~lCATE OF COMPLIANCE we cenity 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 Plane Components. Section tu. Div.1 IM4 Eddion, Addenda sim .
- 7 6
#"I Code Case No. MIb one, W in11
't / " . I Signed G. Ulkkers a Co.
m cenmem ie.o h, . V . hy 11 j iloue to use the W Our ASME Cenifwate of Authorization No. I Halb tNV) symbol expires Ist JuIy. I 9f,0 tom CERTIFICATION OF-DESIGN Design information on fite at General EITctric and Pe'rrv I + 11 sparen Stress analysis report (Class I ontyl on file at Ceneral Electric and Perry I + ' I I s na re e: .
' Design specificat*ons certified by. Boyd P..Mookn PE M California .
Reg.No. 13655
- a e Stress report certireed by. Nobort 1;. k'eiss- i PE State Ca11fornla/1111nois Reg.No. HI4921/62-25749
-8
. Signature not required-4ist name only. ,
CERTIFICATE OF SHOP INSP.ECT10N I . I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel inspectors and the State or Psovince of Ontario (Canada) ' ande W hy Novn1
- Indcinni ty' Co.
of New Yot'k have' inspected the putnp. .or velve, described h
- this Data ' Report on 17 @Tehe4 _ gg 14 "and state that to the best of my knowledge and belief, the N Certificate Holder has
~
""" ; constructed tNo pump, or valve. In accordance with the ASME Code for Nuclear Power Plant Components.
- 9 .'. s *' By signing this certificate, neither the inspect not his employer makes any warrant, expressed or implie'd conce,rning I s
Tf' the equipment described ir j this Data Report. Furthermore, neither the inspector not.his employer shall be liable in any manner i esonal irjury or rty damage or a loss of any kind arising from or connected with this inspection. ,, TO N ~ Date ! t Sig,,ed L .ay d d 'w= asions s.n. 6653 -
/ f
. per. ym -
, - se. e w. e- ,te h
i O; t
- _ _ _ _ - _ _ _ _ _ - _ _ _ - - . - - _ _ - _ _ _ - - _ - - _ - - _ _ _ _ _ _ . _ ___. _ _ _ _ _ _ _ - _ - _ _ - - _ = _ - _ _ ___-_ - _ - __ _ _ _
REPORT N3. NP0059-0005 O l NIS-2/NR-1 OWNER'S REPCRT FOR REPAIRS OR REPLACEMENTS 1B21-256 l l As required by the Provisions of the ASME Code Section XI l l PNPP No. 9308 Rev. 6/93 l l 1. Owner: Cleveland Electric Illuminatino C w any Date 3-23-96 l l l l P.O. Box 5000. Cleveland Ohio 44108 Sheet L of 2 l l 1
; l 2. Plant Perry Nuclear Power Plant Unit One l l l 10 Center Road North Perry. Ohio 44081 W.O.
l 95-212 Rev. J l l . (Repair Org., P.O. No., etc)] I I I I l 3. Work Performed By: Cleveland Electric Illuminatino Co. Type Code Symbol Stamp I!E l l' l I l 10 Center Rdm North Perry. Ohio 44081 Authorization No. 33 l l l
. Expiration Date 7-18-96
- 4. Identification of Systems 1921 Nuclear Boiler (NSSS)
- 5. (a) App'licable Construction Code: ASME Section III class 1 . , 1921. Edition jl Winter 1975 1ManA = , Code Case 1644-5. 1728. M-272 l (b) Applicable Edition of Section XI Utilized for Repairs or Replacements: 19L1, I sn=-ar 1993 1AAmnAm L
t 6. Identification of Components Repaired, Modified, or Replacement Components l Name of Name of Manufacturer lNat. Other Year l Repair ASME' l Component Manufacturer Serial No. i Board ID. Built l Replacement Code l No. lor Modification Stamped' l Piping General Electric. IB21 64084 N/A ' 1985fReplacement Yes li }- System . l 1
'l I ll 1 l l l
- -.. N.-
) , t g I
l 7. Description of Work: Removed valve S/N 160877 from MPL 1B21F0047H. and installed I l l refurbished valve S/N 160875. Retest nerformed Der W.O. 95-2920. (cont. on Line 9) l 1 1 I I I l 8. Test Conducted: Hydrostatic- [] Pneumatic- [] Nominal Operating Pressure- [X] l l Other- [] l l Prest.ure 1038 psi Test Temperature 175 degrees F l l l a ,
.h Page 221
I l l l NIS-2/NR-1 OWNER *S REPORT FOR REPAIRS OR REPLACEMENTS l l l l l 1 l l 9. Remarks: The followina reolacement fasteners were also installed: l t l l Two Inlet Flanae Studs (Heat Code Z4K) l 1 I l Two Inlet Flapae Nuts (Heat Code X7J) { l l l One Outlet Flance Stud (Ht# 8867312) l 1 l l Cne Outlet Flance Nut (Ht# 81617) l 1 Two Sub-Exhaust Flance Nuts (Heat Code C9N) l I NOTE: Attach all applicable Manufacturer's Data Reports. Supplemental sheets such as l l lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 l l in., (2) information in items 1 through 6 of this report is included on each l l sheet, and (3) each sheet is numbered and the number of sheets is recorded on l l the front of this form. CERTIFICATE OF COMPLIANCE We certify that the statements in this report are correct and that all design, l ll material and workmanship on this rerlacement conforms to (repair, replacement, or modification) applicable section of the ASME Code. l Certif cate* o Au horiza No. 3 1 to use the NR stamp expires % M. Signed . - Mechanical Ouality Encineer
'70wner or Owner
- s Designee, Title) l l Date b1 D 19 k I, .
3 ll CERTIFICATE OF INSERVICE INSPECTION l l l I, the undersigned, holding a valid commission issued by the National Board of l l Boiler and Pressure Vessel Inspectors, and certificate of competency issued by l l the State or Province of QMQ and employed by *AREWRIGHT MITI'UAL INS. CO. of l NORWOOD, MA. have inspected the repair,' modification or replacement described ll in this report on M,44cA C3 , 19 9C , and state that to the best l of my knowledge and belief, this repair, modification or replacement has been l l l made or constructed in accordance with Section XI of the ASME Code and the l! i ll National Board rules as defined in the publication NB-102, current edition. l ll By signing this certificate, neither the Inspector nor his employer makes any l
\l warranty, expressed or implied, concerning the repair, modification or ll ll replacement described in this report. Furthermore, neither the Inspector nor ll ll his employer shall be liable in any manner for any personal injury or property ll damage or a loss of ll ll
,- C M - - kind from or connected with this AAf91'TJ Commissions inspection.
P bp,e.m ll l l (Inspector's Signature) ll l Date M4 33 19 9 S
- FACTORY MUTUAL ENG. ASSOC. ll
'l A A
i [ i e
REPORT No. NP0059-0005 e 1821-256 Sheet 2 of 2 h FORM NV-1 b CERTF8CATE HOLDERS' OATA REPORT FOR SAFETY ANO SAFETY REUEF VAtNES-As Required by the Provisions of the ASME Code. Section alt. Div. I g
- 3, Manut caused by
- c. THkkerg & Co._L.L..llsn/telg (0) The Netherlends
' tNewme and Address of N Certif4eate moedert
- 2. Manufactured for
__ Geneml_E}ggirig,,,_,,,, , (Neme end Add, . of evecAeser or ownw1 Pevry TT '
- 3. Location of eneteRatkm $Norne and Addrosal NO
- 4. C@3bX:OA ~bre
( t 03 Pav .b . _ .(Net't. O Nej . Sad. No.l (Year Suest) (CRN)
' identifying Nos.1SO87'ib, 1979 Od~l I
- 5. Valve ge4edes No Series No. .N cenmcase noider e se<aas me.
ca fatv/rali a f l' Type seesty, seeecy me a c edes; cowe, Assoseed 10" Nominal ante Size -- ----8"--
- - A 8A" Outlet Size
- ortvece Sim dach incn trum .
1180 Rated Temperature 585 y
- 6. Set Pressure (PSIG)
_ in , fg-__ g o,e,p,e,,,,e Blowdown (PSIG) 36.5 Si.mped capeaty 9,17 2 Oudet 975
- , " ; -* Toot (PSaG) lnlet 9%P Meta *4 se ve6tes ser cace.e evstems eatyt
- 7. Pressure Metaineng Pieces Meterial SpecFecation Serial No. ejw Macetic o lack Type or Grade
- 07. '??. 8 SN 9 SA 352 IDB sody SA 352 IRB sonnet or votie _Od.07.8 SN*3 sammeneeede
_ A.7W 017 SA 350 LF2 nonnie SA 351 CF3A oise 54 30.8 SN 1B 45 Cr Mo V67 Spring weehere _94 M 95 m 77 l SA 182 F316
's % Screw AME O28 AMP 010 i T
/ __a.TR oto . A si6A-74 tvoe 630 cond. E1 100
- s,,ndi.
asming ! soning ANJ/AJJ/ ATE /AVS/Amt SA 193-B7/SA 194-7/SA 194-2H
, m.y (.,, comt Pieces _ AW2i. AJi/APA'/AJIl SA 351 CF3A
'l. ' IAner si6."17.8 2 53.23.8 - 5 SA 351 CMM Cover Vent nine AKE.9QQ.,,_. .. I . .. . , _ _ , SA 105 SA 105-nangen AF7128 AKF OM ( .
l .' Max. outside diam. valve body 478 mm. (18,82)" Max. outside length valve ; 1641 mm. (64,60)" I I e
- Supplemental sheets in form of lists, sketches or drawings may be used provided (1) size is 8112" x 11*. (2) information in items 12 on this Data Report is included on each sheet, and Q) each sheet is numbered and number of sheets is recorded at top of this form. 8 l
t
\
i (10/771 This form (E000421may tie otne ned isom the Ovoe< Dept., ASME. 345 E. 47th 54., New York. N.Y.10017 b 1 i i Page 222 l
i a
, /-
FORM NV.1 (Back) CERTIRCATE OF COMPLIANCE l We certify that the statements made en this seport are correct and that th<s walve conforms to the rules of construct.on of the ASME Code for Nuclear Power Plant Components. Sect.on lat. Dev.1 197d Edst.on. Addenda sum '76 , Code Case No. G. Dikkers & Co. i N. V. oate 23-3-1979 Signed by i ceme.c ,3 to use the l Our ASME Certificate of Authorization No. _ ENvl I
,ymboi emp;,es 1st July. 1980 ,
l l tom.: l CERTiftCATION OF DESIGN
' Oesign information on ide at Ctm rn1 Eleetvie nnd Perry II Stress analysis report (Class 1 oney) on fue at General Electric and Perry II Design specifications certir.ed by' hu p ht -
PE State California i geg uo, 13655 Stress report certif.ed by' Enhdrt L. Wei nn PE State en14 fnmi n /T11 ( nn4
- Reg. No. MidQ91M9 937AQ l l
t Signature not required-list name only. ! mumuseaumeau ! CERTIFICATE OF SHOP INSPECTION I t, the undersigned, holding a valid commission issued by the National Board of Soller and Pressure Vessel inspectors and the State or Province of Ohio end e,npaoyed by Kemper Ins. of __ img drove T11- have inspected the pump, or valve, described in this Data Report on 23 March . tg 79 and state that to the best of my knowledge and belief, the N Certifcate Holder has constructed this pump, or valve, in accordance with the ASME Code for Nuclear Power Plant Components.
- Sy signing this certificate, neithet the inspector not his employer makes any warrant, expressed or implied, concerning the equipment described in this Data Report. Furthermore, neither the inspector not his employer shall be liable in any snanner for any personal injury or property damage or a loss of any kind arising from or connected with this inspectiort Date 23_ March ig 79, Segned o e;1 Commissigns E 4456
# an d , .n se si. er .ne u a l
l l l l l l G 9
REPORT,NO. NP0059-0005 O l NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACENENTS 1B21-257 l As required by the Provisions of the ASME Code section XI i l l PNPP No. 9308 Rev.'6/93 l l l 1. Owners Cleveland Electric Illuminatiner Comnany Date 3-23-96 l l 1 l P.O. Box 5000. Cleveland. Ohio 44108 Sheet 1 of 2 l , I i l 2. Plant Perry Nuclear Power Plant Unit One l i J l 10 Center Road. North Perry. Ohio 44081 I l W.O.95-213 Rev. S l l . (Repair Org., P.O. No., etc)l l l l I l 3. Work Performed By: Cleveland Electric Illuminatiner Co. Type Code Symbol Stamp !!E l l l l 10 Center Rd. North Perry. Ohio 44081 Authorization No. 23 l l
. Expiration Date 7-18-96 l l l 4. Identification of System: 1B21 Nuclear Boiler (Mene) i I
- 5. (a) ' Applicable Construction Code: AsME section III M === 1 , 1921 Edition Ninter 19'3 Addenda, Code Case 1644-4, 1728. N-272. l, N-224-1. N-225. M-249. N-3. N-413. N-71-6. N-71-9. N-71-11 l (b) Applicable Edition of Section XI Utilized for Repairs or Replacements: 19 R
;- v 1983 aAAmnA=
] 6. Identification of Components Repaired, Modified, or Replacement Components
,, ^ . _.N R
. Name of Name of Manufacturer Nat. Other Year Repair ASME Ov=t Dianufacturer Serial No. Board ID. Built Replacement Code No. '
or Modification Stamped ,
\
l Piping General Electric 1B21 64084 N/A 1985 Replacement Yes F Systent Piping Johnson Controls IB21-0070-F 001 N/A 1985 Replacement Yes
--Syste l l
l1
/sJ '
l l1 ll
'I I
- 7. Description of Work: Removed valve S/N 160883 from MPL 1B21P0041A. and installed l 1
ll refurbished valve s/N 160046. Retest oerformed oer W.O. 95-2920. (cont. on Line 9) l
- l 1 l
l 8. Test Conducted: Hydrostatic- [] Pneumatic. [] Nominal Operating Pressure- [X) l Other- [] 1 l Pressure 1038 psi Test Temperature 1 75 degrees F l I, j I. O V i I l l Page 223
l i I l NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS ih [ 1 l 1 ' l l 1 l l
- 9. Remarks: The followina replacement fasteners were also installed: l i i
I ) i , l Eixteen 7/16* Air Flance Nuts (Ht#8098740) l ' I I I I I I i i I i I I I I I i
- I l 1 l NOTE: Attach all applicable Manufacturer't; Data Reports. Supplemental sheets such as l l
l lists, sketches, or drawings may be used, provided (1) size is e 1/2 in. x 11 l l in., (2) information in items 1 through 6 of this report is included on each l sheet, and (3) each sheet is numbered and the number of sheets is recorded on j l the front of this form. l
. I CERTIFICATE OF COMPLIANCE ll We certify that the statements in this report are correct and that all design, material and workmanship on this renlacement conforms to I
(repair, replacement, or modification) applicable section of the ASME Code. { h l Certif ri t on No. D to use the NR stamp expires 7'lI3 k l1 Signed Mechanical Ouality Encineer i
._ U (Owner or er's Designee, Title)
Date rk U 19 I e ('hh I\ CERTIFICATE OF INSERVICE INSPECTION l' I, the undersigned, holding a valid commission issued by the National Board of l Boiler and Pressure vessel Inspectors, and certificate of competency issued by l' the State or Province of OHIO and employed by 4RKWRIGHT MtTTUAL INS. CO. of l' j
, lj NORWOOD. MA. have inspected the repair,' modification or replacement described l ll in this report on M 44.eJ+ d3 19 W. , and state that to the best {
l l of my knowledge and belief, this repair, modification or replacement has been l l); made or constructed in accordance with section XI of the ASME Code and the ' l1 National Board rules as defined in the publication ND-102, current edition. 1' ll By signing this certificate, neither the Inspector nor his employer makes any ll ll warranty, expressed or implied, concerning the repair, modification or i l l! r* placement described in this report. Furthermore, neither the Inspector nor l l his employer shall be liable in any manner for any personal injury or property l ! 3 _. damage or a loss of kind from or connected with this inspection. go ( i l l M1- - Commissions MA98Z.*T T cean- l I l l V "(151spector* s ' Signature) l i l1 Date 4Ael4 AT 19 $d
- FACTORY MUTUAL ENG. ASSOC. ll l'
t I , 1 l l e
l l-i l l REPORT NO. NP0059-0005 1821-257 Sheet 2 of 2 l ' s a . L t
- l .Q . .
FORM NV.1 MANuf ACTURERS* DATA REPORT FOR SAFETY AND SAFETY RfilEF VALVES * '
* (As Required by the Provisions of stie ASME Code. Section lit. Div. I) 1 1. Manufactu<ed hy C. silkke.r:6 6 C.. . k . v . a s....g.. l .: (u) Tiw ths t ew r l a nd as
! tNan.e ened Adem et samwtes.wso
- 2. u nutaou< d so, t>erry 1 (Name and Adesm et Puecs. esse em Ownerl
- 3. Locauon of enstauat.on Ute Nor t h Perry , tNan.io ena Asensi l 4. ----- c4 71-b /i n.04.o4 21 1978.
eCRN5 (Orswe**0 No.) (Nat'l See. No.) (Year SuHal l ! 5. Vseve c471 sdensity.ng hos. 160646 l (Model No.,8enes NOJ (Adanutecturers' serial No.) sesey,seedyb.k.*b Amueied Orif.ce She 4.84" 14orrunet intet Si.re $" Outtet She 10"
.inen inca ence 1
l
- 6. Set Pressure (PSIG) !!b$ Rated Temperature - . 585 1 Stamped capacity 905732 tbsmr @ .O % Overpressure Blowdown (PSIG) 98.2.
set steam , ,, Hydrostatac Test (PS4G) inlet ..2350 . Outset - .. .. . . . . .. _. 975 (Appi.cabie so weeves for ceased sysiems'eneyl
- 7. Pressure Retaining Pieces Serial feo. or Material Specifr.ation identiGcation tact Type or Grade l
, sody -..13.45 7 R3 . .S A . 352.J.E n.; . . - . .
sonnet or Yoke . u2.07J .s/a 1 . SA.352..Lca- -. . . j' Support Rods .,m==o--- . - ~ . . . - . - .. .. Nor26e . M,U 050 SA 350.LF2.-.-- .. Oisc ..e5.03,d . 3tt .SA .354..CF3A-- -. - . spring Washers .. 214b53 4/n 29 C r-Ho .V --.. . - .. . Adiusting Screw .AFU 042..* AFU U2b SA.182 F316-.- ..- . . . . . Spindie . AEW U24 .A. 564.746.t.ype 630.cond .H1100
/% Spring r.---..-- .- . . _ . . .. . . _
saeting -. AJZ, . AJR, AAA, AJJ , AIA , .SA 193=d7/SA..lW4=7/SA-494*2tl Other Pieces AUY, AkK, AJM, AJL, -AJJ f- . -- ..-- - . . .
. . Liner. . . . 74.07.8 s/n.2 SA .351 CF3A . - . - - - - . .
Cover. . - . . 58.04.8.s'/n e SA 3')1-CFel4-. -. . - - - . . - a h-- ? 1
* *' *JO Vent, pipe AFW 014. SA 105 ..
I'langeu . . AFV 038 +- 108 SA 105 - - - . - . riax. outside dian. v alve body: 476 tan (18.74 inch)
.* tax. out side length valve : y, 1641 mm (64.61 inch)
I i RECEp/ E D JAli U 1979 l l Pt4PP.sOlDC W. r
- Supplemental sheets in form of tests. sketches or drawings may be used provided (1) Size is 8-112* m 11", (2) information in items 12 on this data report is included on each sheet. and (3) each sheet is numbered and number of sheets is I recorded at top of this form.
l i l ()176) 1hes form (E00042) mov be outa.ned d..an it.e O dee Dept ASME,345 E. 47 St New York. N.Y.10017 i p 4 i Page 224 r
Yn t W!ilb/ m, ~ <- - l FOnM NV.1 (Back) CERTirtCATE Of COMPLIANCE We cettefy that the statements made in thes eeport Ste correct and thal this valve cofiforms to the rules of construction of the ASME Code for Nuclest Power Plant Components. Section lit. Div.1 19 74 Edition, Mdenda s uni .*16
'U#*'
Code Case No. .s... Date ..IU~I I-It$ Signed .G. Oikkers & Co. N.V. by W.H. Willenas tassautow Our ASME Certificate of Authorization No. 1806 to use the NV
.?Q (NV) symbolexpires . _1&f Julye. L960 N - . - -
tomei _j i CERTIFICATION OF DESIGN Design information on file at Geneta1 Electric'and Petry, stress analysis report (Class 1 ontyt on fi6e et _ _Ge ne ra 1 E1 ec( r ic and .Pe rry. Design specificadons certified by' __Boyd E Erooks .. ._ . . . PE State Califorala. . . . . Reg No. 13655 stress report certified by' . Eohert L. Weiss PE State cal i fo rni m / f i l ino is. Heg.No. H14921/62-25749 e signatues not required iist name only. COmFICATE OF SHOP INSPECTION t, the undersigned, hoksing a valid, commission issued by the NaGunal Board of Boiler and Pressure Vessel inspectors and the State or Province of DO and employed by Kem.pe r,_ I n.s,. , of "E ** have inspected the pump, or valve, described in this Data Report on 10 4 . gg,7$_.. and sdte that to the best of my knowledge and tMief, the Manufacturer has con.
< structed this pump, or valve, in accordance with the ASME Code for Nuclear Power Plant Components.
By signing this certificate, neither the inspector not his employer makes any warrant, expressed or implied, concerning the equipment described in this Date Report, Fufthermore, neither the inspector nor his employer shall be liable in any manwr f personal injury or daninge or a loss of any kind ariseng from or connected with this inspection. Signed e- b h1 Commissions .... . _.@ N.b . INerL G4.,5tme Piev. and No.)
't'- i 1
e e i
~ . _ _ _ - . -
REPORT NO. NP0059-0005 O I : V l NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS 1B21-258 i l l As required by the Provisions of the ASME Code Section XI l l PNPP No. 9308 Rev. 6/93 l s
- 1. Owner: Cleveland Electric Illuminatina Comoany Date 3-23-96 l l
l P.O. Box 5000. Cleveland. Ohio 44108 Sheet 1 of 2 l l l l 2. Plants Perry Nuclear Power Plant Unit One
' l I i l 10 Center Road. North Perrv Ohio 44081 W.O. 95-214 Rev. J l l , (Repair Org., P.O. No., etc)l l 1 I i l 3. Work Performed By: Cleveland Electric Illuminatina Co. Type Code Symbol Stamp HE l l l
) 10 Center Rd. North Perry. Ohio 44001 Authorization No. 33 l 1 I Expiration Date 7-18-96 l 1
- 4. Identification of Systems 1B21 Nuclear Boiler (NSSS) l ll S. (a) Applicable Construction Code: ASME Section III class 1 , 19 1 Edition I ' Winter 1975 Addenda, Code Case 1644-4. 17't 8 . N-272 (b) Applicable Edition of Section XI Utilized for Repairs or Replacements: 19),2,,,,
h Summer 1993 Addenda
- 6. Identification of Components Repaired, Modified, or Replacement Components i~ , '- . .; n (
Name of Name of Manufacturer Nat. Other Year Repair ASME Component. Manufacturer Serial No. Board ID. Builtl Replacement Code No. i or Modification Stamped Piping General Electric 1B21 64084 N/A 1985l Replacement Yes
}-- System s.
4,f 7 .y l l
, i t
- 7. Description of Work: Removed valve S/N 160848 from MPL 1B21F0041B. and installed l l
l refurbished valve S/N 160871. Retest Derformed Der W.O. 95-2920. (cont. on Line 9) l l 1 1 I j 8. Test Conducted: Hydrostatic- [} Pneumatic- [] Nominal Operating Pressure- (X) l l Other- [] l l l Pressure 1038 psi Test Temperature 175 degree.s F l l 1
, I
( Page 225 i
m l NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS l y i I d
\
I l l I l l 9. Remarks: The followinq replacement fasteners were also installed: l 1 l l One Inlet Flance Stud Oleat Code Z4K) l 1 I i I l l l l l l I I i i I l j i 1 I I l NOTE: Attach all applicable Manufacturer's Data Reports. Supplemental sheets such as l l lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 l l in., (2) infonnation in items 1 through 6 of this report is included on each l l sheet, and (3) each sheet is numbered and the number of sheets is recorded on l l the front of this form. l l . l
.1 CERTIFICATE OF COMPLIANCE ll :
We certify that the statements in this report are correct and that all design, l l material and workmanship on this reolacement conforms to l l (repair, replacement, or modification) l l applicable, section of the ASME Code. Certif ate riza No. D to use the NR stamp expires W O Signed Mechanical Ouality Engineer l l l l owner or Owner's Designee, Title) l Date brk bg- 19 % ' i
- I, ,
a , CERTIFICATE OF INSERVICE INSPECTION l ll ll I, the undersigned, holding a valid commission issued by the National Board of ll ll Boiler and Pressure Vessel Inspectors, and certificate of competency issued by l l ll the State or Province of 91RQ and employed by *ARFWRIGHT MUTUAL INS. CO. of l ll NOPWOOD, MA. have inspected the repair,' modification or replacement described l ll in this report on Nur4 r03 19 9fr _ , and state that to the best l l ll of my knowledge and belief, this repair, modification or replacement has been il ll made or constructed in accordance with Section XI of the ASME Code and the ll ll National Board rules as defined in the publication NB-102, current edition. ll l l By signing this certificate, neither the Inspector nor his employer makes any l' ll warranty, expressed or implied, concerning the repair, modification or l l ll replacement described in this report. Furthermore, neither the Inspector nor l l
. l his employer shall be liable in any manner for any personal injury or property lL '
l damage or oss of any y d from or connected with this infrpection. gg l1 l ~ uY Commissions,#If#C CF I <w e l\ j j V' (Inspector's signature) ll ll Date # n el. 4 :t 19 90
- FACTORY MUTUAL ENG. ASSOC. ll 1, ' 'I i
l 9
REPERT NO. NP0059-0005 d IB21-25R Sheet 2 of 2 g
.thM NV.1 N CERunCATE HOLDERS
- DATA REPORT FOR SAFETY AND SA As Required by the Proviskms of the ASME Code. Section sa. Div. l ,
- 1. Meauf ctue.d try _. ..C. tfi kkeCi h.CodLy,,_11gsyelo (0) The._te t he r 1'a no s em*w ** ***<ess .e ne camnase meaers
- 2. Manufectused for _ ,s na ral an flect.rL,e,m_
~ oon M e er _, _.,er c -1 1 Location of laetm8ation puffy II sName oas Aster ees ~
4. eCRN) _G471-6/125.04.0L fDe@ hej e g , _ ,,_ _71
- 5. veave C471 g,rt geg. 8hl e N (Yood Seseal 4*****8 "* Sa "*J ed.nsifyia9 Nos' ..160871 R-1979 Type ____ safecy/ relief in c.am e me <.s se<e.e n a
&;. s.eny nu. es. ; . _,. Aa e Orir.c. Siae
___ - _ _ _ _ . 4.84[_ Nomines m 6 . _. 8* Oudd Sif 10"
- m
- 6. Set Pressure PS4G) e 'Y32 Stamped Capocay Rated Temperature 585 .,
lbsAt @- '4
% Overpressure 84owdown (PSAG) A ri %
Hydrosufic Test r$aG) Ins c - 2350 ' y, r,pe net ining Pieces w_ 975
, th'*'*********'******'r"****vi S*tiet No. or
" Mace,ias specif; cation TC. Incl Type or Grade Body _.16. /.L M MM i
_SA M7 1RM sonnet or Yoeie 1111 'il M M8: 2 Sensupocedtods SA M2 fl:B I Nozage .. A.ftf (123 . Disc SA "WIIS2
$.7.2LlL 1.1 .SA.3$1 CF3A Spring Weahors J b.35.90 7 3 _ ., _ -
Adeussing Sm AFU 062 45 Cr Mo V 67 AFU 001 SA 182 F316 g,,n,s. _ A,_JE UUb
,A 5lW$ A 564-74 type 630 cond. H1 100
!. seating
._Af7/.AJE/AVS/ALat/AWZ/AME _
; Other Pieces .AJh/ @ AJ4,,__
j t.iner ,67a }7.,e S.e 2
,,,,,,,,,, . SA 193-is7/SA 194-7/SA 194-211
_ , g ., . @" f _. SA 351.CF3A Q' _. 5J.2:5. 5 Sd_b 8A 351.O Ba " vs, yipe _ Ami 050 , _ _ ,
~~SA 1u5 ila.st
- .fr s.e.s_ . ..... Mt UIJ AtV Uld , _ . . ha lu5 .
NA. uutsiou ciain. VJ1VU Dudy ..
'de7d sh2 (10.52)"
.-i:s h . uutuluu lungtn valve lo44 g,n,t (gg. 72)"
a
- Supplemental sheets P form of lists, sketrJtes or drawings may be used provided (1) size is 8-1/2" = 11* (2) information In itemset 12 recorded onthisthis top of Q forrn. ate fleport is included on each sheet. and (3) each sheet is numbered and number of sheets is s
(10/771 Tbs toem 4E00042) may tw obve.nea geo,n she 0,oe< Oept ASME.345 E. 47en St. New York
. N.Y. 10017 6 %/
Page 226
a f FORM NV.1 (Back) Q yrtraVD om CERTiflCATE OF COMPU4.NCE i 8 sum 76
vve cytify that the statements made in this report IY7' Edition. are Addenda correa accesand that etes waive co of the ASME Code for Nuclear Power Plant Components. Secion af. O v. t _
Code Case No. __ by _ W*h* WI11*"8 Signed _ C. U1kkers a Co. 14.V
- fCV
,e Oase _ t c.nsus. 1606 ._ gn ,, %
(NV) Our ASME Certireeme of Authorhation No. __ bi*' NMR-. . symbol empires _t c r tomel ,
~ ..
CERTIFICATION OF DESIGN Perry 11 GeneralEleecric and Des.gn informnion on rete .: Genersi Electric and Pecry II Stress anaiysis report Class 1 only) on fae at boyd P. Bre.ve Oseign specifications certified by' 13655 Reg.N o PEState _ California ambert L. weiss Suess re;, ort certir.ed te Reg.No._ M t A'n t / . % "h* t . t 4 6. rn t . / < t t < n,, < e pg state _
- SW-e not requi. Cat name only.
CERTIFICATE OF SHOP INSPECTION Vessel laspectors t, the undersegned, holding a valid comrnission issued i and employed by _ by the '"d*' National T"*- Board of Soiler and Pmss Ohio and the State or Provint.4 of have laspected the purno, or valve, described in thes Casa Report on
- f .vava* 111- CertiScote Holder has of .t >'n - end state that to the best of my 1 c _ W and befief, the N
_19 Components. _ constructed this pump, or valve,s. in, accor4ence with the ASME Code ifor il d Nuclear concernere] Power Plant Sy signing this certsfacate, neither the inspector 'nor his employer makes any warrant expressed
- e. Z . s the eovipment desenbod in this Data Report. Fwrthermore, neither fthe inspector connecsed with this inspection.
menner for any personal injury or property damage or a loss of any Lind arising rom or A 3-16 2, NB 4456 Cace _ Signed Y' O '
~'
- Commissions
, smart.se. State Prov.aae No.4 __
v 4 sensaeaert s
\J
> S I
1 4 I O
REPORT No. NP0059-0005 i
\ l NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPI.ACEMENTS IB21-259 l l As required by the Provisions of the ASME Code Section XI l l PNPP No. 9308 Rev. 6/93 l l ;
l 1. Owner: Cleveland Electric Illuminatina ComDany Date 3-23-96 l 1 l l P.O. Box 5000, Cleveland, Ohio 44108 Sheet 1 of 2 l 1 l l 2. Plant Perry Nuclear Power Plant Unit One l l l 10 Center Road, North Perry, Ohio 44081 W.O. 95-215 Rev. ,,g l . (Repair Org., P.O. No., etc), I I I I l 3. Work Performed By: Cleveland Electric Illuminatina Co. Type Code Symbol Stamp }[g 1 ll 10 Center Rd. North Perry. Ohio 44081 Authorization No. 33 l l l
, Expiration Date 7-18-96 l I l
- 4. Identification of System IB21 Nuclear Boiler (NSSS)
- 5. (a) Applicable Construction Code: ASME Section III Class 1 , 1921 Edit. ion Winter 1975 Addenda, Code Case 1644-4, 1728. N-272, N-224-1, N-225, N-249, N-3, N-413. N-71-6, N-71-9, N-71-11 (b) Applicable Edition of Section XI Utilized for Repairs or Replacements: 1913 I Sunumer 1983 Addenda
- 6. Identification of Components Repaired, Modified, or Replacement Components l p ,. q
. Name of Name of Manufacturer Nat.lOther Year l Repair ASME Component Manufacturer Serial No. Board l ID. Built l Replacement Code
' No. l lor Modification! Stamped' ll .
l Piping l General Electric . 1B21 ',64084] N/A 1985l Replacement ' Yes
}-- System l l Piping Johnson Controls 1B21-0070-F 001 l N/A 1985l Replacement l Yes
-Syste 1 l l l l l l l l l l I I' l l I I, I, l
I l 7. Description of Work: Removed valve S/N 160866 from MPL 1B21F0041C. and installed l l l refurbished valve S/N 160845. Retest Derformed Der W.O. 95-2920. (cont. on Line 9) l I I I l 8. Test Conducted: Hydrostatic. [] Pneumatic- [] Nominal Operating Pressure- [X] l l Other- [] l l Pressure 1038 psi Test Temperature 175 degrees F l l l
. i l
O Page 227
I l NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS l l l l ; I I l 9. Remarks: The followino reolacement fasteners were also installed: l 1 l l Ten Inlet Flance Studs (Heat Code Z4K) l l l l Two Outlet Flgnce Studs (Htd 0667312) l l l l Three Outlet Flance Nuts (Ht#81617) l t l l Four 7/16" Air Flance Studs (Heat Code GJ) l 1 I I I I 1 l NOTE: Attach all applicable Manufacturer's Data Reports. Supplemental sheets such as l l lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 l l in., (2) infox1 nation in items 1 through 6 of this report is included on each l l sheet, and (3) each sheet is numbered and the number of sheets is recorded on l l the front of this form. l l< l l l CERTIFICATE OF COMPLIANCE l l We certify that the statements in this report are correct and that all design, l Ll material and workmanship on this reolacement conforms to l l l (repair, replacement, or modification) l l [ applicable section of the ASME Code. ll l ll ll Certif ate of riz on No. M to use the NR stamp expires 74884 ll l ;l Signed - Mechanical Ouality Enoineer l l g M owner or er's Designee, Title) !
,l Date bhr b 19 l' e
gi < * . . . - - li . l ll CERTIFICATE OF INSERVICE INSPECTION l1, I, the undersigned, holding a valid commissica issued by the National Board of l'l Boiler and Pressure Vessel Inspectors, and certificate of competency issued by l l I the State or Province of QH10 and employed by *ARKWRIGHT MUTUAL INS. CO. of ll lh NORWOOD. MA. have inspected the repair,' modification or replacement described ll l in this report on MMeh 43 19 dM- , and state that to the best ll ll of my knowledge and belief, this repair, modification or replacement has been ll l made or constructed in accordance with Section XI of the ASME Code and the ll ll National Board rules as defined in the publication NB-102, current edition. ll l 'l By signing this certificate, neither the Inspector nor his employer makes any ll ll warranty, expressed or implied, concerning the repair, modification or ll ll replacement described in this report. Furthermore, neither the Inspector nor ll ll his employer shall be liable in any manner for any personal injury or property ll
, ll damage or loss of any ind from or connected with this inspection. o ll ll M-CommissionsMSN3 f h ll ll (Inspector's Signature) ll ll Date MA#aA e73 19 9 I
- FACTORY MUTUAL ENG. ASSOC. ll l
e ig I i O
REPORT !!O. NP0059-0005 [ . t t- ~- 1821-259 Sheet 2 of 2 { .
= FORM NV.1 MANUFACTUHERS' OATA REPORT FOR SAFETY AND SAFETY gg REUEF VAI.VES* D '.
(As Required by the Provisions of the ASMC Code. Secsion (11, Div.1)
- 1. Manufacsured by G. Dikke ras .a ,Co .m N. V. flenr .
en- n . e4.n e.ao.,.c o l o (u) The :let.hcriands
- 2. Manufacture 8 for l'erry 1 (N., 4 mJ.ssess of Punen.aer av Owned
- 3. Locanon of instanat.oa tio rt h . l'e rr y ,4=0 1e i.oAad,ese e no
- 4. ---------
4caen C4 71 -b/ 8 2 5 04. 04 22 tor no noa swan e<d.No1 (veer e hf lu 78
- 6. Vaive gi lderwifying Nos. j60 ,
sesay.sesa'h E[dbbed Or.fice Size 4.84" 6nch Nomenal intet Sire 8" Outlet Size indi 10.a'c'h .
,l 6. See Pressure (PSIG) 1165 Rated Temperature I
Stamped Capacity .. .. . . . 5
. gog2 ebser @
O % Overpressure Slowdown (PS G) 49,$ . Nydrostatec Test (PS4G) inlet 2350 Outtet .
- 7. Passsure Retaining Pieces g g.ggg g--.
Serial No. or Materiet SpecFacetion Identifecation inct Type or Grade Body 03.05.8 s/n 5 SA 352 tra Bonnes or Yoke . . 9.2, R.,q_,s,/n ,2 . SA_ 352,1rB, ,. support nods ...- . .. . c. . . . . . . . AEU 056 Nozzle . . _ _ . . . oi.e SA,J50, gjt
. 9.la#L8.a/.n..I85 . SA,,})L QE)A sprino wnshers 211653 nr 23 41,Cr No V M,,
44 iing screw AFU 132-089 . , ._ ,. spindie tyL 1,pj y)M._, _ _, _, _,._ .. , ,
... ME .90.3. . A h!4.-71.upt.MQ. E9sd_r H4100 m s eriaa . . - . . . - - . . .=.---
d' Soning Oei.r e,eces
. MEs @.a..Ms .AJ.I e A.LM e UA I9dINI9dIENkM
' .. ML. AP,1s ^)M. AJL -
Liper. 7 hqt 4 s./n i . . . . . . . . . . . . . . . . . .
.C9 ver .... h&7.pfsi tt SA.15 LCf3A.. --..
. 36.35L CEdM.
.c Vent piPe . ....A W.. M 4 . - . . . - - . . . . .
11 anghrt. _. . .. AEY Q97. .UM .SA.105 ... SA 105 . ... . -.. .- . Max. outside diars. valve body: nax. outside length valve : 476 ewa (13.74 inch)
,- 1643 cua (64.89 inch) flECEIVED JAN 11 1979 PNPP-SojoC
- Supplementat sheets in form of lists sketches or
- swings may be used provided (1) size isn ortna6on .
8112 m 11- (2) i f in itemsat12 reentded topon thisform. of this data report is included on each sheet, and (3) each sheet is numbered and number of sheets is (t(76) i Th.s form (E00042) may be chia.ned feo.u she Oeder Deus ASME,345 E. 47 St., New York N Y.10017 . ,f% l L Page 228
fr ' O \f' FORM NV.1 (Back) MQ,., ,
- CERTiflCATE OF COMPT.tANCE We certify that the statements made en thes report are Correct and that this valve conforms to the rules of construction of the ASME Code for Nuclear Power Plant Componenes. Section Itt. O.v.1., IN Edit on. Addenda 8"* D,
', e~i c Ca , %.
y ,10-11-76 Signed C. Dikkiars 6 Co. N.V. W.H. Wi l'l em s (adanutsouvert 15Ub to use the NV Our ASME Cert #ficate of Authorizatson No. 8 N (NV) symbol expires 1 s c ,.!u, l y,g 1960 hw -- somes CERTIFICATION OF DEStGN Et ecc ric and Ferry Design inferrnation on fde at .'.".nnal Cenera1 , Elect ric and Perry Stress analysis report (Class 1 only) on file et Design spedfications certifjed by* .. 60yd P. Brooks. . . . ,_ PE State CaLiforuaa .. . . . . Reg. m. ._ Ibfk__... .. Strees report certified by' __ _ Eobe.rt..h.Wej a s .._ , . . _ . . . . _ _ _ ,,, PE State Ca1iforoia]J11inois , .. .. Reg. No. , .. _.M)49.2.lf 62-2 5749 _ __,,,, , . 8 Segnature not required-list name only. CERTFICATE OF SHOP SNSPECTION L the underegned, holding a valid 6... .- 7 issued by the National Board of Soiler and Pressure Vessel inspectors and the State or Province of..._0hi.o . ... .. . . and employed by h-r Y r%. of GI.2Vt.111.... . .. . . . have inspected the pump, or valve, described in this Data Report on
.19-11. .-. 19 2L and state that to the best of my knowledge and boGef. the Manufacturer has an.
etnacaed this pump, or valve, in accordance with the ASME Code for Nuclear Power Plant Components. Oy signing this certificate, neither the inspector nor his eMoyer makes any warrant. expressed or irnpleed, concerning he equipment desenbed in this Data Report.Turthermore, neither the inspector rior his employer shau be liable try any rnanner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection. , , ~ Date . E U '\1 9.J.i . Signed h # #. Commsssions - AIB.e456 . . _ . speaert ..tNan te. same Prev. sae No.) 9
\
I O
REPORT NO. NP0059-0005 l NIS-2/NR-1 ONNER'S REPORT FOR REPAIRS OR REPLACEMENTS 1821-260 l l As required by the Provisions of the ASME Code Section XI l j l PNPP No. 9308 Rev. 6/93 l l l 1. Owner: Cleveland Electric Illuminatino Comnany Date 3-23-96 l l l l P.O. Box 5000. Cleveland. Ohio 44108 Sheet L of 2 l l l l 2. Plant Perry Nuclear Power Plant Unit One ] I i 1 l 10 Center Road. North Perry. Ohio 44081 W.O. 95-216 Rev. .J l ! l = (Repair Org., P.O. No., etc)l I I I l l 1 l 3. Work Performed By: Cleveland Electric Illuminatino Co. Type Code Syml n " imp }!E l l l 10 Center Rd. North Perry. Ohio 44081 Authorization No. 33 l 1
. Expiration Date 7-18-96 l
- 4. Identification of Systems 1B21 Nuclear Boiler (NSSS) l
. l S. (a) Applicable Construction Code: ASME Section III Class 1 , 19 1 Edition I Winter 1975 m M mmia, Code Case 1644-4, 1728. N-272 l
(b) Applicable Edition of Section XI Utilized for Repairs or Replacements: 19)) ,. Summer 1983 AMamin
- 6. Identification of Components Repaired, Modified, or Replacement Components )
, 9% N i \\
Nr.me of Name of . Manufacturer Nat. LOther Year Repair . ASME l l Component Manufacturer [ Serial No. Board ID. Built Replacement ' Code l ! I No. or Modification Stamped l , l Piping General Electric i 1B21 64084l N/A l 1985L Replacement Yes I h System j 'l I I l l lh l I I i 1l l .
; lI s l, 1, 1, I. Ii i a iI
- t" "'e i
s I i 1, I, I I, I, II ii I
, 7. Description of Work: Removed valve S/N 160886 from MPL 1B21F0041D. and installed l 1
refurbished valve S/N 160849. Retest Derformed Der W.O. 95-2920. (cont. on Line 9) l
, I I I l 8. Test Conducted: Hydrostatic- [] Pneumatic- () Nominal Operating Pressure- [X) l l Other- [] l l Pressure 1038 psi Test Temperature 175 degrees F l 1 I i i i Page 229 L __ _ _ _ _ _ _ _ _ _ . . ___ __
- 1 1
)
)
i l 1 NIS-2/NR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS e l l l l I l l 9. Remarks: The followino renlacement fasteners were also installed: l 1 l l One Inlet Plance Stud (Heat Code Z4K) j l I l Three Inlet Flance Nuts (Heat Code X7J) l l l l Four Sub-Exhaust Plance Nuts (Heat Code C4N) l 1 1 I I I i i 1
- - 1 1
l NOTE: Attach all applicable Manufacturer's Data Reports. Supplemental sheets such as l l lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 l l in . , (2) information in items 1 through 6 of this report is included on each l l sheet, and (3) each sheet is numbered and the number of sheets is recorded on ) l the front of this form. l, I . l . CERTIFICATE OF COMPLIANCE l l We certify that the statements in this report are correct and that all design, l material and workmanship on this renlacemer.t confozus to l (repair, replacement, or modification) lll applicable section of the ASME Code. l l 1 ll Certificate of Author tion No. M to use the NR sf. amp expires 7 86 % ll Signed M % / Mechanical Ouality h car ll , D (Owner or er's Designee, Titlt) ll Date ub 19 b l l l' y.n "
. 1 l CERTIFICATE OF INSERVICE INSPECTION l l I, the undersigned, holding a valid commission issued by the l~ational Board of l ll Boiler and Pressure Vessel Inspectors, and certificate of compttency issued by l ll the State or Province of Q!ilg and employed by *ARKWRIGHT MtJrUAL INS. CO. of l ll NORWOOD. MA. have inspected the repair,' modification or replace 0ent described ll in this report on /14L-4 34 19 96 , and state tlut to the best ll of my knowledge and belief, this repair, modification or replacemnt has been ll made or constructed in accordance with Section XI of the ASME Code and the ll National Board rules as defined in the publication NB-102, current edition.
ll By signing this certificate, neither the Inspector nor his employer makes any !;'l ll warranty, expressed or implied, concerning the repair, modification or l ll replacement described in this report. Furthermore, neither the Inspector nor l
.,P "l ll his employer shall be liable in any manner for any personal injury or property l ll damage or g oss of any ind from or connected with this inspection. p(<w,+1.
I ll d/D _ Commissions /M<M r lj V' ~(Inspector's Signature) i ll Date NA uh *
,23 19 M
- FACTORY MUTUAL ENG. ASSOC. 1l l gi ig '
1 i O
REPORT NO. NPOO59-0005 f n .t.
- w 'C fo ~sn ,'~
1B21-260 Sheet. 2 of 2 y (G
- FORM NV.1 MANUFACTUHERS' DATA REPOf1T FOR SAFETY ANO SAFEW REUEF VALVES *
(As Required by the Provisions of the ASME Code, Section set. Div. 81 - '
- t. Manut.ctured by . C. Dikkers & Co. N.V. Hengelo (0) The riccherlands tm m. .ad Adm ~ ,
- 2. Manufactured lo, Ferry 1 es u.aut.csur.r(
eName ad Ade et cura a er o ri NO rIIl P.e f ff e Oh, to,,.
.h 3. t.ocation of instaNation
* (Nanw and Ad&ees)
- 4. -. .
=-
6471-b/125.04.04 24 1978 acett torme - (N.rt e,4. mi nom,own E Valve . . . ...
..% 74. . .. .eNo.:
th%d No., senes No.3 .. _. 4dentifying Nos. j 6,0,649, , ,,,,,ls's,._iad Nef* r. quan dmaure Type j s.*. .r.. s o,fsd n.w.g; .e Me e ,adt . . ___ ._ .. . ...__._ ..__..._ ..._ l Orifice Sin 48.' Nominal sniet *Size D" 10"_ each nam
. .__._ _. Oudet Sire _
inca
- 6. Set Pressure (PSIG I I.N ._ . . . . --- - . Rated Temperature . 555. . . . .,
Siamped Casacity 19323 4. .. . ib. air e_o 5, overp,e ure esowdown (eSici 96.2 l sei. steem
! Hydrostatic Test (PSIG) inlet _23511 - om m:r
,, p,_ .
l
% . . . r 4 v'/.U ene v i l
~
Series No. or . . Maurial Spectrecation identification . Inct Type or Grade Body L3d L 2 2/n 5' ._$A 352 IfB , Sonnet or Yohe i11 Sh M .a/n._1.
._SA,_351 If R Support Rods _
.- L. -
Nonle .. AELLDIL
' __SA.350. IF7 oisc .
, ..53.ua.d s/a 9a sA 311;cr1A Spring washers . siinst =/a 11 - ._fel.Cr Ma V 67 Adiusting Scroin Spendte
.. AF11.043/ Arf 8 <mt . . . .' sA 1d2 MI6 .
Spring
.ADl.001' A 564-7I. ryne 630 cand.111100 eosiing Ata ,..AJv. an are at o A r o'aereiec - -.m m. ~
- ; ._f.yl lG3_R7/$A 144-7/$A 144-714 V \ 1.Inar -- _. b4,04,M "!a 9 ,..
.SA.358 cr1A Cover. 58,46 A s/.a.7 . - . _ . u '49 ' e5* l l
. Vent pipu __ _ . AN.030 . i .' . . . . . . _.S A.1Di. -
..b< _ .+p
* ]{ F1anges .. ..AFV.022/AFV 091 . . . . % L.105 .._ ._
tiax, outside diam. . valve. body: 476 :m.(18.74 inch) 1 tiax.. outside length valve . 1645 era (64.76 inch)
- RECEIVED JAN 111979
,.. PNPP.SOfDC a:+ ."
- Suppiernental sheets in form of lists. sketches or drawings may be used provided (1) size is 8-112* x 11*g (2) information in items 12 on this data report is included on each sheet, and (3) each sh'est is.nuanbered and number of sheets la recorded at top of this form. .
, , ,. s.,y," I
~ ",,-.
(l176) This form (E00042) eney be obteia.d lanm the Order Dept ASME. 345 E. 47 St., New York. N.Y.10017 l I A b Page 230
g) 'it .'.: S *g '"-,-~ FORM NV.1 (Bad) 10 CERWlCATE OF COMPT.tANCE i We wetafy that the statements enade in this report a<e correct and that this vasve conferens,to the rules of consouct.on ' susa.*74 c ethe ASME Code for Nuclear Power Plant Components. Section its. O v. l (5f 74 Ed seon. Addenda tou Code Case No. ..... H.V. by nl.M. Willents
.) ate 10 -l l *73 . Signed C. Oikke.rs a &, ,i 150b to use the NV Our ASME Certificate of Authoruassun No. .
C- (NV) symbos experes ..._1sc. July . 1St10 tou ,-- # CERTIFICATION OF DESIGN oesign information on r.ie at . Gueral.t:lesrJic. erid Pstry ._ _.._.. .. .. suess anasysis report ictass t oneylon nie nt Genecal .Elec r cic ao43c try .__ . ... . . j . . . . . . . - . . .....
. . . . .certired oesign specir.cenons . . . . .by'. . lay.d.18 arodks.._ . ..
PE Stati . ...CA1.if0 Inia . .. .. Reg.No. . . . .llh55 ; We,Lut.. y .. ;_ _. ._.. . Stress report certised by: _..., . Robe.rr t.. Reg. No. ._ 1114S2 r /^1-7 U49 _ PE State _ . cal I fn rnla/1llinals._ . t S.onature not required-sist narr4 on#y. CERTIFICATE OF SHOP INSPECDON
- 1. the undersigned, holding a valid commission issued by the National#*-a- Board ofra,n_ Soi6er end Pressure Vessel inspectors and empioved by .
and the State or Prodnce of . Utlio .. . ..... .. of _l&Ag Gretc lli- have inspected the pump. or valve, described in this Geta Report on
.. 1.0-11... . ... 197tl._, and state that to the best of my knowdedge and belief, the Manufacturer has con.
structed this pump, or valve. in accortlance wdth the ASME Code for Nuclear Power Plant Components. t i (* manner Sy signing this cer'tificate, neither the inspector not his ernpaoyer makes any for any person.slinjury or property damage or e loss of any kind arising from or connected with this inspectiort}}