ML20024C437
| ML20024C437 | |
| Person / Time | |
|---|---|
| Site: | Maine Yankee |
| Issue date: | 02/24/1983 |
| From: | Maine Yankee |
| To: | |
| Shared Package | |
| ML20024C428 | List: |
| References | |
| NUDOCS 8307120626 | |
| Download: ML20024C437 (99) | |
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INSERVICE INSPECTION EXAMINATION REPORT MAINE YANKEE ATOMIC POWER STATION JULY 11, 1982 through FEBRUARY 24, 1983 O
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PREFACE Enclosed is a NIS-1 Summary report prepared by Maine Yankee Atomic Power Company. We complete most of our inspections during refueling outages. A few inspections are performed during power operation and unscheduled shutdowns.
This report includes abstract and detailed information on the examinations performed, the as found conditions, and the corrective actions taken.
It includes those inspections performed since the end of the 1981 refueling outage, through the 1982 refueling outage, and including those inspections performed during the four week unscheduled outage ending in February 1983.
This concludes the last inspection period of the first inspection interval for safety class 1 components. This inspection completes all safety class 1 inspection requirements excluding those for which relief requests are currently under staff review. Safety class 2 and 3 components have only been in the ISI program since 1979, therefore, this concludes only the first period of the safety class 2 and 3 inspection interval. We hope to start our second inspection interval with the inclusion of all three safety classes in order to eliminate the three year interval offset of our safety class 1 components from our safety class 2 and 3 components. This would not affect the overall number of components required to be inspected during the next interval.
The examinations referred to in this report were performed primarily by Magnaflux Quality Services of Hartford, Connecticut, with a limited number of inspections performed by Maine Yankee and Yankee Atomic Electric Co.
personnel. A supplement to this report is the NIS-1 report prepared by Combustion Engineering, Inc., summarizing their inspections of Maine Yankee's Q
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1346L - AJC
j TABLE OF CONTENTS SECTION
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() NIS-1 OWNER'S DATA REPORT l-9 NIS-1 form 10 Abstract of Exams 11 Abstract of Conditions Noted 12 Abstract of Corrective Measures Recommended and Taken III
SUMMARY
REPORT
1.0 INTRODUCTION
1.1 Examination Methods 1.2 Evaluation of Data 1.3 Examination results 2.0 SLNMARY OF EXAMINATIONS 2.1 P.eactor Vessel l
2.2 Pressurizer 2.3 Steam Generator E-1-1 2.4 Steam Generator E-1-2 2.5 Steam Generator E-1-3 2.6 Reactor Coolant Pump P-1-1
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2.7 Reactor Coolant Pump P-1-2 2.8 Reactor Coolant Pump P-1-3 2.9 RHR Heat Exchanger 2.10 HP Drain Cooler 2.11 Plping l
3.0 SYSTEM PRESSURE / LEAK TESTS 4.0 STEAM GENERATOR EDDY CURRENT l
5.0 DEFERRED EXAMINATIONS EACTOR PRESSURE VESSEL INSERVICE EXAMINATION REPORT IV r
1.0 ABSTRACT 2.0 NIS-1 OWNER'S DATA REPORT 3.0
SUMMARY
AND CONCLUSIONS 4.0 EXAMINATION REPORT 5.0 EXAMINATION PROCEDURES 6.0 CALIBRATION STANDARDS
_pG 7.0 EXCLUSIONS AND EXCEPTIONS 8.0 EXAMINATION DETAILS AND RESULTS 9.0 EXAMINATION SLNMARY DEFINITIONS 1
FORM NIS 1 OWNERS' DATA REPORT FOR INSERVICE INSPECTIONS As required by the Provisions of the ASME Code Rules n'O
Maine Yankee Atcmic Pwer Cmpany, Wiscasset, Maine
- 2. Plant _ __
(Name and Address cf Plant)
II
- 4. Owner Certificate of Authorization (if required)
IFR-36
- 3. Plant Unit
- 5. Commercial Service Date 12/29/72
- 6. National Board Number for Unit Reactor Vessel 20865
- 7. Components Inspected Manufacturer Component or Manufacturer or Installer State or National Appurtenance or installer Serial No.
Province No.
Board No.
R.P. Vessel C.E.
67106 NA 20865 R.P. Head C.E.
67206 NA 20865 Pressurizer C.E.
67601 NA 20858 Stm. Gen. #1 C.E.
67501 NA 20919 Stm. Gen. #2 C.E.
67502 NA 20920 f(Q N
Stm. Gen. #3 C.E.
67503 NA 20921 RCP #1 Byrcn - Jackscn 681-N-0421 NA' NA RCP #2 Byrcn - Jackson 681-N-0422 NA NA RCP #3 Byrcn - Jackson 681-N-0423 NA NA Piping Stone & Webster I&
NA
'NA Note: Supplemental sheets in form of lists, sketches, or drawings may be used provided (1) size is 8% in. x 11 in.,
(2) information in items 1 through 6 on this data report is included on each sheet, and (3) each sheet is numbered j
O and the number of sheets is recorded at the top of this form.
I This form (E00029) may be obtained from the Order Dept., ASME,345 L 47th St., New York, N.Y.10017 4
FORM NIS 1 (back) 2/24/83
- 9. Ir<pection interval from 12/29/72 to 12 /29 /A2
- 8. Examination Dates 7/11/81 to
- 10. Abstract of Examinations. Include a list of examinations and a statement concerning status of work required for current interval.
- 11. Abstract of Conditions Noted
- 12. Abstract of Corrective Measures Recommended and Taken We certify that the statements made in this report are correct and the examinations and corrective mea-sures taken conform to the rules of the ASME Code,Section XI.
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19 G Signed MMNE YANKEE By q__
Date_
Owner Certificate of Authorization No. (if applicable)
N/A Expiration Date N/A CERTIFICATE OF INSERVICE INSPECTION 1, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel ins cciors and/or the State or Province of ggligfNvSE775and employed by M. A A. E.I[. do of M. dI have inspected the components described in this Owners' Data Report during the period ghfdffl to II A /983
. and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owners' Data Report in accordance with the requirements of the ASME Code,Section XI.
By signing this certificate neither the inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owners' Data 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.
Date WC /[
19 83 Commissions lY8 ~7Sd.S NA /2,2 A inyfector's signature National' Board, State. Province and No.
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0WNER Maine Yankee Atomic Power Company, Wicasset, Maine 2.
PLANT Maine Yankee Atomic Power Company, Wicasset, Maine 3.
PLANT UNIT
- 1 4.
OWNER CERTIFICATE OF AUTHORIZATION DPR-36 5.
COMERCIAL SERVICE DATE 12-29-72 6.
NATIONAL BOARD Nt.NBER FOR UNIT Reactor Vessel 20865
- 10. ABSTRACT OF EXAMINATIONS COMP 0ENT CATEGORY MJMBER EXAMIED ETHOD Reactor Vessel B-G-1 100% of 27 Head Studs UT,MP,VT B-G-2 1004 of 20 Head Nuts UT,W 100% of 8 Instrument Nozzle Studs VT 100% of 8 Instrument Nozzle Nuts VT Pressurizer B-G-2 1004 of 19 Manway Studs W,VT 100% of 19 Manway Nuts VT 1004 of 20 Manway Studs UT Steam Generators E-1-1 B-B 24" of 1 Circumferential Weld UT B-G-2 36 Manway Studs MP,VT 40 Manway Studs UT C-A 100% of 1 Circumferential Weld UT C-B 100% of 2 Nozzle-to-Shell Welds UT 1
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OWNER Maine Yankee Atomic Power Company, Wicasset, Maine 2.
PLANT Maine Yankee Atomic Power Company, Wicasset, Maine 3.
PLANT UNIT
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OWNER CERTIFICATE OF AUTHORIZATION DPR-36 5.
COMMERCIAL SERVICE DATE 12-29-72 6.
NATIONAL BOARD NLNBER FOR UNIT Reactor Vessel 20865 10.
ABSTRACT OF EXAMINATIONS COWONENT CATEGORY NUMBER EXAMIED ETH00
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C-C 100% of 7 AttaciYnent Welds MP C-E-2 100% of 8 S @ ports' Components VT Tech Specs 468 Generator Tubes EC E-1-2 B-B 24" of 2 Circumferential Welds UT 4" of 3 Circumferential Welds UT 12" of 5 Meridional Welds UT B-H 24" of 1 Support Weld UT B-G-2 36 Manway Studs VT,W 35 Manway Studs UT 36 Manway Nuts VT C-E-2 100% of 8 Supports' Components VT Tech. Specs.
849 Generator Tubes EC 4
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OWNER Maine Yankee Atomic Power Company, Wicasset, Maine 2.
PLANT Maine Yankee Atomic Power Company, Wicasset, Maine 3.
PLANT UNIT
- 1 4.
OWER ERTIFICATE OF AUTHORIZATION DPR-36 5.
COMERCIAL SERVIE DATE 12-29-72 6.
NATIONAL BOARD NLNBER FOR UNIT Reactor Vessel 20865
- 10. ABSTRACT OF EXAMINATIONS COMP 0ENT CATEGORY NUMBER EXAMIED ETHOD E-1-3 B-B 24" of 1 Circumferential Weld UT B-G-2 38 Manway Studs W, VT 40 Manway Studs UT C-E-2 100% of 8 Supports' Components VT Tech. Specs.
825 Generator Tubes EC r
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Rractor Coolant Pumps P-1-1 B-G-2 11 Seal Studs VT 9 Seal Studs W
11 Washers W
s P-1-2 B-G-2 16 Seal Studs VT,MP 16 Washers W
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OWNER Maine Yankee Atomic Power Company, Wicasset, Maine 2.
PLANT Maine Yankee Atomic Power Company, Wicasset, Maine 1
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PLANT UNIT
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0WNER CERTIFICATE OF AUTHORIZATION DPR-36 i
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COMMERCIAL SERVICE DATE 12-29-72 i
6.
NATIONAL BOARD NLNER FOR UNIT Reactor Vessel 20865 i
- 10. ABSTRACT OF EXAMINATIONS j
i COMPONENT CATEGORY NUMER EXAMIED ETHOD j
P-1-3 B-G-2 16 Seal Studs VT,MP 16 Washers VT t
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RHR HX E3B C-D 100% of 16 Studs and 32 Nuts VT j
C_F, C-G 100% of 2 Nozzle-to-Pipe Welds UT (RT installation acceptance) 3 (Preservice) 1 k
HP Drain Cooler C-D 100% of 5 Studs and 5 Nuts VT i
j Piping B-J 100% of 2 Socket Welds LP B-F 100% of 8 Safe-End Welds UT (C.S. Side Only) 100% of 7 Safe-End Welds LP i
f 100% of 1 Safe-End Weld VT l
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OWNER Maine Yankee Atomic Power Company, Wicasset, Maine 2.
PLANT Maine Yankee Atomic Power Company, Wicasset, Maine 3.
PLANT UNIT
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OWNER CERTIFICATE OF AUTHORIZATION DPR-36 5.
COMERCIAL SERVICE DATE 12-29-72 6.
NATIONAL BOARD NLNBER FOR UNIT Reactor Vessel 20865
- 10. ABSTRACT OF EXAMINATIONS COMP 0ENT CATEGORY NUMBER EXAMIED ETHOD Piping B-K-1 100% of 14 Pressure Boundary LP Support Welds 8-K-2 100% of 103 Supports" Components Vf
.B-G-2 Pressure Retaining Bolting on VT 20 Valves C-D Pressure Retaining Bolting on VT 6 Valves i
Internals of 4 Valves VT D
C-E-1 10L of 8 Pressure Boundary
'If Support Welds 100% of 2 Pressure Boundary LP Support Welds C-E-2 1005 of 154 Supports' Components VT
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OWNER Maine Yankee Atomic Power Company, Wicasset, Maine 2.
PLANT Maine Yankee Atomic Power Company, Wicasset, Maine
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PLANT UNIT
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OWER CERTIFICATE OF AUTHORIZATION OPR-36 s.
5.
COMERCIAL SERVICE DATE 12-29-72 6.
NATIONAL BOARD NLNBER FOR UNIT Reactor Vessel 20865
- 10. ABSTRACT OF EXAMINATIONS COMP 0ENT CATEGORY NUMBER EXAMIED ETH00 Fiping C-E-2 100% of 1 Supports' Components VT (Preservice)
C-F, C-G 1004 of 3 Circumferential Butt MP Welds 100% of 3 Circumferential Butt RT,LP Welds 100% of 17 Circumferential Butt RT Welds C-F, C-G 1004 of 5 Circumfarential Butt RT (Preservice)
Welds 100% of 9 Circumferential Butt RT,LP,UT, Welds VT Hydrostatic C-H (1980) 3 Main Steam and Feedwater VT Tests Systems, SC-2 RCP Seal Water Header VT 10
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OWNER Maine Yankee Atomic Power Company, Wicasset, Maine 2.
PLANT Maine Yankee Atomic Power Company, Wicasset, Maine 1
3.
PLANT UNIT
- 1 4.
OWNER CERTIFICATE OF AUTHORIZATION DPR-36 5.
COMMERCIAL SERVICE DATE 12-29-72 6.
NATIONAL BOARD Nt.NBER FOR UNIT Reactor Vessel 20865
- 10. ABSTRACT OF EXAMINATIONS COMPONENT CATEGORY NUMBER EXAMINED METHOD Hydrostatic C-H (1980)
HPSI Suction Lines VT Tests LPSI an CS Pump Vent VT Header RHR HX E3B (RHR Side)
VT i
Isolation Valves I
c' LPSI Pump P-128 to First VT Isolation Valves B-P Reactor Coolant System VT SC-1 Boundaries Deferrals B-F 1 Safe End Weld LP 3 Safe End Welds UT,LP
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OWNER Maine Yankee Atomic Power Comoany, Wicasset, Maine 2.
PLANT Maine Yankee Atomic Power Company, Wicasset, Maine 3.
PLANT UNIT
- 1 4.
OWNER CERTIFICATE OF AUTHORIZATION DPR-36 5.
COMMERCIAL SERVICE DATE 12-29-72 6.
NATIONAL BOARD NUMBER FOR UNIT Reactor Vessel 20865
- 11. ABSTRACT OF CONDITIONS NOTED COMPONENT CATEGORY NLN3ER EXAMINED METHOD Reactor Vessel B-G-1 2 Linear Indications on Nut 54 MP Head Nut 54 Pressurizer B-G-2 4 Manway Studs not initially VT accepted due to pitting and corrosion Steam Generators E-1-1 B-G-2 2 Manway Studs had small surface MP indications
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C-C Surface Indications were found MP on 2 Attachment Welds E-1-2 B-G-2 4 Manway Studs were cracked UT E '.-3 B-G-2 4 Manway Studs were found to have MP surface indications Reactor Coolant Pumps P-1-1 B-G-2 2 Seal Studs rejected for VT corrosion P-1-2 B-G-2 1 Seal Stud rejected MP
1.
OWNER Maine Yankee Atomic Power Company, Wicasset, Maine 2.
PLANT Maine Yankee Atomic Power Company, Wicasset, Maine 3.
PLANT UNIT
- 1 4.
O WER CERTIFICATE OF AUTHORIZATION DPR-36 5.
COMMERCIAL SERVICE DATE 12-29-72 6.
NATIONAL BOARD NUMBER FOR UNIT Reactor Vessel 20865
- 11. ABSTRACT OF CONDITIONS NOTED COMPONENT CATEGORY
_NUMER EXAMIED METHOD Piping B-G-2 1 Relief Valve Stud had excessive VT gouging Bolting on Valve PR-M-17 failed VT due to galling B-J Surface indications were found on LP Socket Welds 72 and 82 on Line l
SIH-33 B-K-2 PS-7, PS-6, PS-5, and PS-3 on VT Line SIH-22 were rejected due to missing pads under pipe PS-2 on Line SIH-22 had a missing VT nut and bolt C-E-2 CS-SH-93 on Line CS-22 was found VT to have a loose nut and bolt LSS-203, 204, and 206 on Line VT WFPD-8 had loose rod eye bushings l
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OWrER Maine Yankee Atomic Power Company, Wicasset, Maine 2.
PLANT Maine Yankee Atomic Power Company, Wicasset, Maine 3.
PLANT UNIT
- 1 4.
OWNER CERTIFICATE OF AUTHORIZATION DPR-36 5.
COMERCIAL SERVICE DATE 12-29-72 6.
NATIONAL BOARD NtNER FOR UNIT Reactor Vessel 20865
- 11. ABSTRACT OF CONDITIONS NOTED COMP 0 TENT CATEGORY MM3ER EXAMIED ETHOD Piping C-E-2 LSS-207 and 209 had a broken VT bushing and bent rod, respectively H-9, LSS-211, and H-13 on Line VT WFPD-10 were found to have concrete damage Supports H-14 and H-15 on line VT WFPD-10 had loose nuts and a plate pulling away from the wall, respecitvely Feedwater Supports SH-20, 21, 31, VT 32, 41, and 42 were found to have various problems with spring can settings and loose components Hydrostatic Test B-P During the RCS Leak Test, several VT leaks from valves and gaskets were found I
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OWNER Maine Yankee Atomic Power Company, Wicasset, Maine
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PLANT Maine Yankee Atomic Power Company, Wicasset, Maine 3.
PLANT UNIT
- 1 4.
OWNER CERTIFICATE OF AUTHORIZATION DPR-36 5.
COMMERCIAL SERVICE DATE 12-29-72 6.
NATIONAL BOARD NUMBER FOR UNIT Reactor Vessel 20865
- 12. ABSTRACT OF CORRECTIVE MEASURES RECOMMENDED AND TAKEN COMPGNENT CORRECTIVE ACTIONS TAKEN Reactor Vessel The surface indications were removed by filing.
Head Nut 54 Four Pressurizer The studs were wire brushed and evaluated as being acceptable.
Manway Studs Steam Generators E-1-1 Manway stud surface indications were removed by filing.
D Indications on attachment welds were removed by grinding.
E-1-2 Four manway studs replaced.
Twelve generator tubes plugged.
E-1-3 Manway stud indications were removed.
Reactor Coolant Pumps P-1-1 Degraded seal studs were replaced.
P-1-2 Degraded seal studs were replaced.
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OWNER Maine Yankee Atomic Power Company, Wicasset, Maine (2.
PLANT Maine Yankee Atomic Power Company, Wicasset, Maine h PLANT UNIT
- 1 4.
OWNER CERTIFICATE OF AUTHORIZATION DPR-36 5.
COMMERCIAL SERVICE DATE 12-29-72
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6.
NATIONAL BOARD NLNBER FOR UNIT Reactor Vessel 20865 l
- 12. ABSTRACT OF CORRECTIVE MEASURES RECOMfENDED AND TAKEN COMPONENT CORRECTIVE ACTIONS TAKEN PIPING Bolting 1 relief valve stud replaced.
All bolting replaced on valve PR-M-17.
SIH-33 3
i Socket Welds 77, 82 Surface indications removed by filing.
SIH-22 Supports rO es->. 5. 6. e 7 eees ere imete11ee emeer nine.
SIH-22 Support PS-2 Installed nut and bolt.
1 1
i WFPD-8 Supports 1
LSS-203, 204 and 206 Rod eyes were shimmed.
CS-22 Support CS-SH-93 Bolting was tightened per maintenance request.
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OWNER Maine Yankee Atomic Power Company, Wicasset, Maine 2.
PLANT Maine Yankee Atomic Power Company, Wicasset, Maine 3.
PLANT UNIT
- 1 4.
0WNER CERTIFICATE OF AUTHORIZATION DPR-36 5.
COMMPlCIAL SERVICE DATE 12-29-72 6.
NATIONAL BOARD NWBER FOR UNIT _ Reactor Vessel 20865
- 12. ABSTRACT OF CORRECTIVE MEASURES RECOMfENDED AND TAKEN
_ COMPONENT CORRECTI'/E ACTIONS TAKEN WFPD-10 Support LSS-207, LSS-209 Bushing replaced; bent rod replaced.
WFPD-10 Supports H-9, LSS Oll, and H-13 Concrete damage was patched.
l WFPD-10 Support l
H-14, H-15 Nuts were made tight, support tightened to wall.
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Feedwater Supports L
SH-20,21,31,32,41 and 42 These supports were corrected in accordance with Yankee Atomic's recommendations.
Reactor Crolant System Leak Test All leaks were brought to an acceptable condition.
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1.0 INTRODUCTION
f This report describes the inservice inspections performed since the 1981 refueling outage up to and including those inspections performed during the unscheduled outage of January,1983, at the Maine Yankee Atomic Power Station, tiiscasset, Maine. The non-destructive examination procedures used for inservice inspection were in accordance with the 1974 edition of the ASE Boiler and Pressure Vessel Code,Section XI, " Rules for Inservice Inspection of Nuclear Power Plant Components," up to and including the Summer 1975 addenda; except that piping 1
examinations and acceptance criteria for piping examinations were in accordance with the Summer 1976 addenda. Additional examinations were as delineated by Plant Technical Specifications. Inspections were conducted to the extent allowed by system l
design and the non-destructive testing technology employed.
This report summarizes the areas examined, the type of examinations, test data results, evaluations and repairs.
i 1.1 Examination Methods Manual ultrasonic testing techniques were employed in conjunction with visual, i
liquid penetrant and radiographic examinations. These non-destructive examinations j
were performed in accordance with Yankee Atomic Electric Company procedures found in Engineering Guidelines Book III, " Inservice Inspection POE Procedures." The examination procedures were reviewed and approved by personnel qualified to SNT-TC-1A, Level III; and conform to the requirements of ASE Section XI (5/75 to 5/76) and applicable portions of ASE Section V (5/75). Additional inservice inspections as l
f required by Plant Technical Specifications were performed in accordance to approved 4
Combustion Engineering procedures. All examinations were performed and evaluated by j
personnel qualified to SNT-TC-1A.
The following procedums were utilized for the examinations:
Procedure Number Revision Title I'
YA-UT-1 2
Ultrasonic Examination - General l
Requirements YA-UT-2 1
Ultrasonic Examination - Circumferential, Longitudinal, Meridional, and Flange Welds YA-UT-4 1
Ultrasonic Examinations of Vessels -
Nozzle to Vessel Welds YA-UT-7 1
- Ultrasonic Examination of Bolting YA-UT-11 2
Ultrasonic Examination of Piping -
Dissimilar Metals Welds l
YA-PE-2 3
Liquid Penetrant Examination YA-W-1 1
Magnetic Particle Examination O
y YA-RT-1 1
Radiographic Examination YA-VT-1 4
Visual Examination
Combustion Engineering Procedures f..
00000-SIS-012 1
Procedure for Multi-Frequency Eddy Current Examination of Non-Ferromagnetic Steam Generator Tubing in Accordance with NRC Regulatory Guide 1.83.
0000(MESS-07(M)2 2
Procedure for Control of Eddy Current Examination Data 1.2 Evaluation of Data The examination results were reviewed by personnel qualified to SNT-TC-1A Levels II and III.
Indications were evaluated to the acceptance standards in the 1974 edition of the AS W Boiler and Pressure Vessel Code Section XI, up to an including Summer 1975 addenda, except that the acceptance standards for piping examinations are in accordance with the Summer 1976 addenda. The additional l
inspectic.ns performed in accordance with Plant Technical Specifications were evaluated to the acceptance standards of these specifications.
1.3 ' Examination Results Summaries of all examinations that were performed are contained in Section 2.0 of this report. All detailed data, calibration records, material and equipment g-certifications, personnel qualifications, and procedures are maintained at the
.H Plant Site as part of the permanent records.
Details of iceportable indications and corrective measures can be found in the l
applicable part of Section 2.0.
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2.0 SLM4ARY OF EXAMINATIONS f5 2.1 Reactor Vessel V
B-G-1 Pressure Retaining Bolting Greater Than 2 Inches Twenty-seven reactor head closure studs; 1-S, 2-S, 4-S, 5-S, 6, 11-S, 12-S, 13-S, 14-S, 15-S, 17-5, 20-S, 23, 24-S, 25-S, 27-S, 29, 31, 33, 36, 38, 39 42,46,49,51and53wereexaminedultrasonically,visuallyandbymagnet1c particle. No significant indications were found.
Twenty reactor head closure nuts; 4, 6, 8, 10, 12, 14, 16, 18, 20, 22, 26, 30, 36, 38, 42, 44, 46, 48, 50 and 54 were examined ultrasonically and by magnetic particle. Two surface indications were found on nut 54 and were removed by filing. The nut passed inspection.
Eight nuts and bolts on instrument nozzle 67 were examined visually. No unacceptable conditions found.
2.2 Pressurizer 6-G-2 Pressure Retaining Bolting Less Than 2 Inches in Diameter Nineteen manway studs were examined visually and by magnetic particle.
Twenty manway studs were examined ultrasonically. Nineteen manway nuts were examined visually. Four manway studs were deemed unacceptable because of surface pitting and corrosion.
This unacceptable condition was tended with wire brushing and the studs were considered acceptable for further use.
2.3 Steam Generator E-1-1 8-B Vessel Welds Two feet of one circumferential weld was examined ultrasonically with no V
observable. indications.
B-G-2 Pressure Retaining Bolting Less Than 2 Inches in Diameter Thirty-six manway studs were examined visually and by magnetic particle.
forty manway studs were examined ultrasonically.
Two studs had small surface indications which were removed by filing. Further inspection revealed no indications.
C-A Circumferential Shell Welds One nuncred percent of circumferential weld 1-C-ll was examined ultrasonically. No indications were found.
C-B Nozzle-to-Shell Welds One nundred percent of two nozzle-to-shell welds 1-N-1, 1-N-2 were examined ultrasonically. There were no significant indications.
C-C Integrally Welded Attachments Seven integrally welded attachments were examined by the magnetic particle method. Surface indications were found on two of the attachment welds.
These indications were removed by grinding. The repaired welds were reinspected and deemed acceptable.
C-E-2 Support Components The componuts of snock suppressors 1-SS-1, 1-SS-2, 1-SS-3, 1-SS-4, 1-SS-5, 1-SS-6, 1-SS-7 and 1-SS-8 were examined visually. No indications were found.
U Technical Specifications Four hundred sixty-eight generator tubes were eddy current tested. Six tube wall degradation indications less than twenty percenty were found.
These indications are acceptable.
2.4 Steam Generator E-1-2 B-B vessel Welds Two feet of two circumferential welds 2-C-1 and 2-C-3 were examined ultrasonically. Four inches of three circumferential welds 2-C-4, 2-C-5 and 2-C-6 were examined ultrasonically. One foot of five meridional welds 2-M-1, 2-M-2, 2-M-3, 2-M-4 and 2-M-5 were examined ultrasonically. No reportable indications were foend.
B-H Vessel Support Welds Two feet of support weld 2-C-7 was examined ultrasonically with no recordable indications.
B-G-2 Pressure Retaining Bolting Less Than 2 Inches in Diameter Thirty-six manway studs were examined visually and by magnetic particle.
Thirty-five manway studs were examined ultrasonically.
Thirty-six manway l
nuts were examined visually. Ultrasonic testing found four cracked studs.
Tnese studs were replaced.
C-E-2 Support Components Components to snock suppressors 2-SS-1, 2-SS-2, 2-SS-3, 2-SS-4, 2-SS-5, 2-SS-6, 2-SS-7 and 2-SS-8 were examined visually. No indications found.
Technical Specifications Eignt nunorea forty-nine generator tubes were eddy current tested.
Twenty-three of these tubes show wall degradation indications and twelve of
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the indications were over twenty percent. The tubes with greater than twenty f~
percent wall degradation were plugged.
I 2.5 Steam Generator E-1-3 B-B Vessel Welos Two feet of one circumferential weld 3-C-1 was examined ultrasonically revealing no significant indications.
B-G-2 Pressure Retaining Boltir., _ess Than 2 Inches in Diameter Thirty-eight manway studs weIl examined visually and by magnetic particle.
Forty manway studs were examined ultrasonically. Four studs were found to have surface indications which were removed.
The studs were then acceptable for use.
C-E-2 Support Components Support components of shock suppressors 3-SS-1, 3-SS-2, 3-SS-3, 3-S5-4, l
3-SS-5, 3-SS-6, 3-SS-7, 3-SS-8 were examined visually. No significant i
indications were found.
Technical Specifications Eignt nundred twenty-five generator tubes were eddy current tested. Nine tubes had wall degradation indications less than 20% which is acceptable.
2.6 Reactor Coolant Pump P-1-1 B-G-2 Pressure Retaining Bolting Less Than 2 Inches in Diameter Eleven seal stuas were examined visually. Nine seal studs and eleven washers p
were examined.by magnetic particle testing. Two seal studs were rejected due Q
to corrosion. These seal studs were replaced.
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2.7 Reactor Coolant Pump P-1-2 l
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B-G-2 Pressure Retaining Bolting Less Than 2 Inches in Diameter s
Sixteen seal studs were examined visually and oy magnetic particle. Sixteen unacceptable during magnetic particle examin(tion.
washers were examined by magnetic particle. One seal stud was found a
This seal stud was replaced.
N 2.8 Reactor Coolant Pump P-1-3 B-G-2 Pressure Retaining Bolting Less Than 2 Inches in Diameter Sixteen seal studs were examined visually and oy magnetic particle. Sixteen washers were examined visually. No significant indications were observed.
2.9 RHR Heat Exchanger E3B C-D Pressure Retaining Bolting on Vessels Sixteen studs and thirty-two nuts were visually inspected with no recordable indications.
C-F, C-G Nozzle-to-Pipe Welds Two nozzle-to-pipe welds, N1 N2 JT3 and N1 N2 JT4, were examined ultrasonically.
These were preservice inspections and no indications were found. Radiography was used for installation acceptance.
2.10 HP Drain Cooler C-D Pressure Retaining Bolting on Vessels Five studs and five nuts were examined visually. No recordable indicatons were observed.
2.11 Piping B-J Socket Welds Welds 77 and 82 on line SIH-33 were examined by the liquid penetrant method. Both welds had one surface indication which was removed by filing.
li The welds were reinspected and deemed acceptable.
B-F Pressure Retaining Dissimilar Metal Welds Tne following welos were examined ultrasonically:
Line RC-1 welds SE-I and SE-J c/s side only and SE-6 Line RC-3 weld SE-B c/s side only Line RC-7 weld SE-7 c/s side only Line RC-12 welds SE-I and SE-J c/s side only Line RC-8 welds SE-5 i
The following welds were liquid penetrant tested:
i Line RC-1 SE-I and SE-6 Line RC-3 SE-B i
Line RC-7 SE-J Line RC-8 SE-S Line RC-12 SE-I and SE-J Weld SE-J was unable to be LP tested, but was visually inspected instead.
O1 (See Section 5.0) No significant indications were observed from the above examinations.
B-K-1 Integrally Welded Supports O
The following supports were examined by the liquid penetrant method:
U Line CH-61 CH-HSS-603 and CH-HSS-604 Line DRH-2 DRH-2-4(W) and DRH-2-5(W)
Line DRH-1 DRH-1-8(W) and DRH-1-ll(W)
Line RC-52 RC-HSS-108(W)
Line RC-50 RC-HSS-103, RC-HSS-104A, RC-HSS-104B and RC-HSS-105 Line RC-26 RC-SH-29, RC-SH-28 and RC-R-10 No significant indications were observed.
B-K-2 Support Components The following one hundred three supports were examined visually:
line RC-15 BP-SH-7 line RC-20 RC-SH-34 BP-SH-9 line RC-21 RC-SH-35 line RC-4 BP-SH-1 BP-SH-3 line RC-22 RC-SH-36 line RC-10 BP-SH-4 line RC-26 RC-H-10 BP-S-5 RC-SH-28 BP-SH-6 RC-SH-29 m
line RC-6 SL-SH-12 line RC-28 RC-SH-30 L,)
SL-SH-ll SL-SH-10 line RC-29 RH-HSS-102 line RC-ll RC-SH-501 line RC-46 RC-HSS-291 RC-SH-502 i: 169 RC-SS-601 H-168 RC-SS-602 RC-S-28 line RC-48 RC-HSS-101 RC-HSS-102
'line RC-16 RC-SH-506 line RC-50 RC-HSS-105 line RC-18 RC-R-16 RC-HSS-104A RC-A-1 RC-HSS-104B RC-SS-18A RC-HSS-103 RC-R-19 line RC-52 RC-HSS-108 line 2" RC-19 CH-48-1 (SH)
RC-HSS-107 RC-HSS-106 line 4" RC-19 RC-HSS-101-RC-SS-30 RC-SH-23 RC-SH-22 line DRH-1 DRH-1-11 DRH-1-8 DRH-1-6 9
B-K-2 continued line DRH-2 DRH-2-1 line SH-22 PS-4 b
DRH-2-4 PS-3 V
DRH-2-5 (SH)
PS-2 PS-1 line DRH-4 DRH-4-1 (SH)
H-50 H-51 line DRH-5 DRH-5-1 (SH)
H-52 H-53 line CH-45 CH-A-166 H-54 H-55 line CH-46 CH-SH-295 CH-HSS-601 line SIH-30 PS-5 CH-HSS-602 PS-4 PS-3 line CH-58 CH-PS-1 PS-2 CH-PS-2 PS-1 CH-PS-3 CH-PS-4 line SIH-31 SIH-SH-24 CH-PS-37 line SIH-41 SIH-PS-1 line CH-61 CH-SH-296 SIH-PS-3 CH-HSS-603 SIH-PS-2 CH-HSS-604 SIH-PS-4 SIH-PS-5 line CH-126 PS-5 SIH-HS-6 PS-4 PS-3 line SIH-42 SIH-SH-29 1
PS-2 SIH-SH-28 PS1
%5 PS-1 line CH-128 PS-35 PS-2 PS-3 line SIH-22 PS-7 PS-4 PS-6 PS-5 Pipe supports PS-3, PS-5, PS-6 and PS-7 on line SIH-22 were found with rr.issing pads under the pipe. Pads were installed and the supports passed inspection.
Support PS-2 on line SIH-22 had a missing lut and bolt. A nut and bolt was installed and the support passed inspectica.
B-G-2 Pressure Retaining Bolting Less Than 2 Inches-in Diameter The bolting of the following twenty valve! were visually examined in place.
Line Ntsnber Valve Number Line-Nu ter Valve Number RC-5 RC-17 RC-45 LD-1 RC-S-18 RC-79 RH-M-1 RC-ll RC-27 CH-66 CH-46 RC-16 RC-37 CH-68 CH-M-52 RC-17 PR-4 CH-51 CH-51 PR-8 SIL-22 HSI-61 RC-18 PR-3 LSI-12 PR-7 SJH-31 HSI-62 RC-26 PR-M-16 S'.H-42 HSI-63 PR-M-17 Prrssurizer PR-S-ll
One stud on valve PR-S-ll failed due to gouging. This stud was replaced.
Excessive galling was found on the studs on valve PR-M-17.
The studs were J
replaced on both PR-M-16 and PR-M-17.
Both valves passed visual inspection.
C-D Pressure Retaining Bolting The bolting of the following valves was examined visually.
Line Number Valve Number RH-44 LSI-44 RH-3 LSI-47 RH-4 LSI-46 RH-12 LSI-50 WFPD-8 FW-F-207 WFPD-4 MS-11 The internals of the following valves were examined visually:
Line WFPD-4 FW-131 Line WFPD-8 FW-231 Line WFPD-10 FW-331 Line CS-13 CS-94 No significant indications were observed.
C-E-1 Integrally Welded Supports The following eight supports were tested by the method of magnetic particle:
. (Q j
Line WFPD-4 Penetration 53 Line WFPCk-8 Penetration 54 Line WFPD-10 Penetration 55, LSS-207, LSS-209, H-13, H-14, H-15 No significant indications were found. LSS-207 and LSS-209 were liquid penetrant tested on line WFPD-10 with no significant Indications observed.
C-E-2 Support Components one hundred fifty-four support were examined visually; Line Support Line Support RH-1 RH-SH-45 CS-1 CS-SH-99 RH-SH-42 CS-4 CS-SH-100 RH-SH-43 CS-16 CS-SH-79 RH-SH-44 CS-15 CS-SH-82 RH-ll RH-SH-32 SHP-1 SH-1 RH-SH-33 SH-20 RH-13 RH-SH-52' SHP-HSS-lll' j
RH-25 RH-SH-26 SP SH-2 RH-27 RH-SH-37 SH-3 CS-13 CS-SH-76 SH-4 CS-SH-74A SH-27 CS-SH-748 SP-3 SH-5 CS-22 CS-SH-93 SH-6 CS-8 CS-SH-97 SH-7 CS-3 CS-SH-98 SH-8 SH-9
t C-E-2 continued Line Support Line Support WAPD-21 H-324 WAPD-23 H-311 H-325 H-300 H-326 H-369 SH-326 H-303 H-315 H-302 H-316 H-304 H-305 WFPD-8 SH-327 H-306 LSS-203 H-307 SH-2 H-308 LSS-204 H-309 SS-3 H-310 SS-4 LSS-205 WFPD-10 H-7 LSS-206 LSS-207 H-5 H-8 SH-6 LSS-208 SH-40 SS-9 SH-41 LSS-209 SH-42 LSS-210 SH-43 SS-10 S-44 SS-ll SH-45 LSS-211 I,!
SS-12 WAPD-23 H-320 LSS-212 SH-320 H-13 H-321 H-14 H-322 LSS-213 SH-322 LSS-214 H-312 SS-15 H-313 SS-16 H-314 LSS-215 H-365 LSS-216 SH-365 SS-17 H-367 SH-18 SH-367 SH-30 WFPD-10 SH-31 WFFD-4 HSS-201 SH-32 HSS-202
-SS-33 SS-329 SS-34 SH-329 WAPD-25 H-317 SH-328 H-318 SH-19 H-319 SH-20 H-302 SH-21 H-301 SH-22 H-300 SH-23 H-314 SH-24 H-369 SH-25 by H-366 CH-3 CH-SH-202 l
H-368 CH-4 CH-SH-201 CH-5 CH-SH-200 l
Hanger H-13 on line WFPD-10 was visually examined for preserve acceptability
[C}
after a hanger modification.
L; CkSH-93onlineCS022hadaloosenutandbolt.
The bolting was tightened perxNR 1419-83.
LSS-203, 204 and 206 on line WFPD-8 had sliding rod eye bushings. These supports were shimmed to correct this condition.
This condition was noted after the feedwater transient in January 1983.
LSS-207 and LSS-209 on line WFPD-10 had a broken rod eye bushing and bent rod, respectively. These conditions were related to the feedwater transient of January 1983.
Both the bushing and rod were replaced to correct these conditions.
The feedwater transient caused concrete dsmage on supports H-9, LSS-211 and H-13 on line WFPD-10.
This damage was corrected by patching damaged areas.
Supports H-14 and H-15 on line WFPD-10 had loose nuts and were pulled out from the wall. The supports were tightened to an acceptable condition.
Feudwater supports SH-20, 21, 31, 32, 41 and 42 were found to have various problems with spring can settings and loose clamps. These problems were evaluated by Yankee Atomic's analysis group and the problems were corrected following their recommendations.
C-F, C-G Pipe Welds
/3 (V
Weld numoer six on lines WFPD-4, 8 and 10 were examined by the magnetic particle method with not recordable indications observed.
Weld number one on lines WFPd-4, 8 and 10 were examined radiographically and by liquid penetrant. No indications were found.
Seventeen welds were examined radiographically with not significant indications observed; 3, 4, 4A, 5, 7, 7A and 8 on line WFPD-4; 3, 4, 5 and 7 on line WFPD-8; and 3, 4, 5, 5A, 7 and 13 on line WFPD-10.
Welds 13, 14, 15, 16 and 17 were examined radiographically for preservice acceptability on a non-return valve vacuum line.
No indications observed.
Welds lA,1B and 2 on lines WFPD-4, 8 and 10 were examined radiographically by liquid penetrant, ultrasonically and visually for preservice acceptability. No recordaole indications were observed.
3.0 SYSTEM PRESSURE LEAK TESTS (b
w The following is a list of ASE Section XI system pressure tests performed during the last inspection period. No unacceptable leakage found.
System Boundary Main Steam and Feedwater Steam Generator up to - Feed Reg. Valves all three systems
- First Blordown Iso. Valves
- MS Nonreturn Valves
- First Aux. Feed Iso. Valves RCP Seal Water Header PCV Bypass Valves PCV Inlet Stop Valves Filter Bypass Valve Filter Outlet Iso. Valves HPSI Pump Suction Lines (See attached sketch)
LPSI and CS pump vent header Containment spray and LPSI pumps vent line check valve to containment RHR Heat Exchanger E3-B First isolation valves RHR side Valve LSI-67 LPSI pump P-12A to First iso. valves
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Valve LSI-68 LPSI pump P-128 to First iso. valves The Reactor Coolant System leak test was performed in accordance with ASE Section XI at the terminatjon of the 1982 refueling outage. The following conditions were found.
Loop 1 Valve RC-16 had a body to bonnet leak. The hot let primary manway was leaking past the gasket.
Loop 2 Blank flange downstream of primary sample valve RC-227 was leaking.
Loop 3 Valve RC-345 was leaking past its seat.
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Valve.PR-A-1 leaks at the body to bonnet seal. -
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,.,.. g This sytem was pressurized to 1.05 times the system operating pressure of"-
2235 psig at 350oF. All noted unacceptable leaks were corrected and reinspected during plant operation. All conditions were acceptable.
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COMBUSTION ENGINEERING, INC.
NUCLEAR POWER SYSTEMS SYSTEMS INTEGRITY SERVICES- - - - - - -
WINDSOR, CONNECTICUT h.o REPORT OF EDDY CURRENT EXAMINATION OF MAINE YANKEE STEAM GENERATOR NO.1, 2, & 3 i
MAINE YANKEE ATOMIC POWER COMPANY WISCASSET, MAINE OCTOBER, 1982 j
Prepared By: /
Date:
j H. Labieniec SIS En'gineer Approved By:
- 0. 4/+,o _
Date:
a.7-33 NP.Lareau ASNT-TC-1A Level III Examiner Date: 2 d1 Approved
_a
.P. O'Les Superv sor, Component Examination Services
>k-Date: A D3 Approved B q
H.D. Goddard Acting Manager, Systems Integrity Services DOCUMENT NO.
TR-SIS-029 Date:
2/2/83 6
0 ABSTRACT f
fO An inse'rvice eddy current inspection and dent assessment program was performed in a selected sample of tubes in all three steam generators of the Maine Yankee Atomic Power Station during the period of October 9,1982 through October 20, 1982.
Approximately 8.2% (468 tubes) of the tubes in No. I steam generator were inspected, 15% (849 tubes) of the tubes in No. 2 steam generator and 14.4%
(825 tubes) of the tubes in No. 3 steam generator were inspected from the hot side, over the "U" bend and partially down the cold side to the No. 7 drilled support plate. Both dent and defect data was obtained simultaneously (one probe pass) by use of multi-frequency testing. Tube wall degradation indications were observed during the analysis of the data for all three generators.
Six less than 20% indications were observed in steam generator No.1. Twenty three indications were observed in steam generator No. 2.
Twelve were greater than 20% and eleven were observed less than 20%.
Nine tube wall degradation indications were observed in steam generator No. 3, all were less than 20%. Dent like indications were observed at the No. 7 and No. 9 drilled support plates, and at various locations throughout the eggerate support areas and horizontal run of the "U" bend.
Sludge depth measurement data indicated a maximum of 8.0" accumulation of sludge on the secondary side of the hot side tube sheet of Nr 2 steam generator and 14.0" in No. 3 steam generator.
All other indications will be listed in Table 1, 2, and 3.
A This report provides an analysis of the examination including pertinent infor-((f 3) mation on the conduct of the test, test procedures, personnel and equipment certifications.
C
-i-
1
SUMMARY
)
An inservice eddy current inspection was performed on a selected sample of tubes in the Maine Tanicee Atomic Power Station No.1, 2, and 3 steam generators during the period of Oc:tober 9,1982 through October 20, 1982.
The inspection program satisfied the requirements of the USNRC Regulatory Guide 1.83, Revision 1, (July 1975), " Inservice Inspection of Pressurized Water Reactor Steam Generator Tubes". The inspection program was conducted in accordance with Combust-ion Engineering Procedure No. 00000-SIS-012. " Procedure for Multi-Frequency Eddy Current Examination of Non-Ferromagnetic Steam Generator Tubing in Accordance with USNRC Regulatory Guide 1.83", and the Maine Yankee Technical Specification. All inspection data was controlled in accordance with Combustion Engineering Procedure No. 00000-ESS-070-02, " Procedure for Control of Eddy Current Examination Data".
The inspection program consisted of utilizing multi-frequency eddy current techniques to collect steam generator tube dent and defect data and a 25 KHz test to measure the accumulation of sludge on the secondary side of the hot and cold side tube sheets.
Table 1 details the results for steam generator No. 1.
Table 2 details the results for steam generator No. 2 and Table 3 details the results for steam generator No. 3.
Selection of the tubes to be examined was based on an evaluation of data taken during May 1977, July 1978, May 1981 and March 1982 inspections.
{
The data from the inspection program was recorded on magnetic tape and on. strip charts. These recordings were analyzed to evaluate the extent of tube wall anomalies. The results were recorded on the eddy current examination report sheets contained in Section V of this report.
Maine Yankee Power Station is currently maintaining the magnetic tape and strip chart reccrds.
O e
S e
e
,a e
i
RESULTS OF EXAMINATION I(
Upon completion of the testing, the strip chart and tape recorded data were
()
reviewed by a Data Analyst to evaluate for dent and defect indications. The tubes that were inspected in all three steam generators are indicated on the tube sheet maps Figures 1, 2, and.3.
Figure 8 shows the tubing supports arrangement (eggerate, drilled support). A complete set of eddy current exam-ination report sheets for the multi-frequency eddy current testing are included in Section V of this report.
Tube wall degradation indications were observed during the analysis of the data. For all three generators no indications such as pitting in the sludge pile region were observed.
However, degradation in the "U" bend region of l
Rows 3 thru 12 was found. A listing of degradation indications for each steam generator is shown in Table 6.
Dent indications were observed at the No. 7 and No. 9 drilled support plates on the hot and cold sides. Additionally, dent indications appeared throughout the eggerate region and also the hat side batwing area. The No. 7 and No. 9 drilled support plates are partial supports while all other supports are the eggerate type.
The number and magnitude of dents at the drilled support plates are listed in Tables 1,2, and 3.
Comparison of similar data obtained during previous inspections of steam generators No. 2 and No. 3 is presented in Tables 4 and 5.
Testing in steam generator No. 1 was limited to Rows 3 thru 12 and a comparison of support plate data is not available. Testing in steam generator No.
2 indicated a shrinkage of dent values as compared to the March 1982 inspection (Average shrink value of.94 mils for No. 7 support and.60 mils shrink value
((' ' )
for No. 9 ssupport). Testing in steam generator No. 3 indicated an increase of dent values when compared to February 1980 inspection.
(Average growth value of 2.15 mils for No. 7 support and 3.95 mils for No. 9 support).
The overall results indicate an average decrease of.77 mils in the drilled support plates denting in steam generator No. 2 and an average increase of 3.05 mils in steam generator No. 3 dent values.
The indications listed as dents at the "U" bends on the eddy current examination report sheets are dents in the tubes at the vertical support straps in the hori-zontal section of the tubing between the hot and ' cold sides These dents appear to occur at the edge of the support strap'where the. tubes intersect the seclloped bars.
i To obtain a representative sample of data on the cold leg, a portion of the program (63 tubes in both the No. 2 and No. 3 steam generators) was performed full length.
The 25 KHz sludge testing indicates up to 11 inches of sludge on the secondary side of the cold side tube sheet in No. 2 steam generator, and up to 8 inches on the hot side tube sheet.
In No. 3 steam generator 10.8 inches of sludge was detected on the secondary side of the cold side tube sheet and up to 14 inches on the hot side tube sheet.
The tubes that were tested for sludge depth and the C"~)
depths detected during testing are indicated on the tube sheet maps included as Figures 4.5,6 and 7 of this report.
No sludge depth measurements were taken for
!{
the No. I steam generator. -.. _ -
EQUIPMENT
\\ f.(
Q The complete eddy current inspection system can be broken down into two categories; inspection equipment and probe positioning equipment.
)
The eddy current inspection equipment consists of:
- 2etec MIZ-12 Multi-Frequency Eddy Current Tester with dual mixers. ~ ~
- Two - two channel strip chart recorders (Brush MK 220) or equivalent.
A specially modified stereo tape recorder (Hewlett-Packard 8-channel).
Eddy current test probes (A56DSF) or equivalent.
Calibration standards (defect standard per ASME Section XI plus dent standard).
A supply of magnetic tape and strip chart paper.
2etec Model-2 Vector Analyzer.
The pertinent certification sheets for the above equipment are included.
in Section IV of this report.
The probe positioning and drive system consists of:
' - A CE Mark 'III Finger Walker., including remote controller.
- A closed circuit television system.
- A probe drive mechanism.
- A comunication system.
The MII-12 multi-frequency eddy current tester uses eddy currents as the probing media to measure variations in effective conductivity and/or permeability of the tube being tested.
In non-magnetic materials..such as inconel, conductivity is usually the only significant variable. When the effective conductivity decreases due to a discontinuity in the tube wall, the test coil voltage increases in direct relationship with the effective conductivity change. Thus, the amount of increase in coil voltage is related to the size of the discontinuity. The coil voltage is sinusoidal, thus it can be described with a single vector having magnitude and phase. The MIZ-12 system provides a method for reading out two quadrature components of the test coil voltage vector. In
.e addition, the MIZ-12 multi-frequency eddy current tester is a highly versatile and compact eddy current inspection system.
Utilizing a
" Time-Sharing" technique, the operator may test at up to four (4) frequencies simultaneously. The MIZ-12 contains two mixing circuits.
giving the operator the ability to subtract out most undesirable data
, {'
1 (i.e., noise, support signals, etc.).
The CRT display allows the operator to view the mixer output as well as the test signals.
b.
.. J
The response from the eddy current tester is fed through the memory f4 oscilloscope to the tape recorder and then to the strip chart recorder. Audio input (microphone) is also provided to record the O
identity of the tube under test at the start of each test. The recorded data can then be analyzed with the aid of the eddy current wector analyzers. = _=--
2.
Special sensing probes fabricated for the specific tubing to be tested and designed to negotiate the bends in the tubing are use.f.
The probes are attached to nylon tubing which is used to insert and with-draw the probe. The instrument leads and a stainless steel safety wire pass through the nylon tube.
The defect calibration standard is a length of Inconel-600 tubing 3/4" OD by 0.048" wall thickness (similar to that used in the Maine Yankee Steam Generators) in which artificial (machined) defects have been introduced. This standard was made in accordance with the ASME Code,Section XI, " Description".
A dent standard is also used for the assessment of dent sizes at the '
support plate intersections. This dent standard has several zones in which the tube radius is reduced approximately uniformally around the circumference. Measured dent signal voltages are compamd directly to an empirical curve n1ating signal voltage to radius reduction obtained from scanning the dent standard.
The minor denting observed in the steam generators is assumed to be reasonably uniform around the circumference.
The Mark III Finger Walker is used for remote positioning of the probe at the desind tube location. The CCTV system is used.to observe the movement of the Finger Walker and facilitates position verification.
The probe insertion and withdrawal mechanism is' a device which ensures a constant probe speed when recording the eddy current test results.
This is important in that accurate location of any addy current indication is dependent on constant probe speed since tube length is correlated with strip chart speed.
_ CONDUCT OF TEST After calibration, a typical sequence of operations to inspect a selected tube was:
1.
Mechanically drive probe in selected tube and push through tube. >
},~'
at " fast" speed.
2.
Note on brush recorder chart the coordinates of tube under' test at start of test.
1 3.
Clear oscilloscope scnen.
. O 4.
Energize tape recorder. Using microphone, voice record coordinates of tibe under test. Energize brush recorder.
! ?,
_ =.
5.
Withdraw probe at " slow" speed.
Observe all instrumentation for
['
proper operation.
(Probe withdrawal at slow speed = ~12 inches /
)
second).
6.
Stop brush recorder and' tape recorder when probe exits from tube.
7.
Advise probe positioner operator to change coordinates.
1 8.
Repeat operations for next set of coordinates.
Calibration check on the eddy current test instrumentation were per-formed at the beginning and end of each reel of tape.
Position verification.was continuos 1y monitored on the Finger Walker controller and TV monitor; video taping of positon verification was perfonned.
Periodically througheut the inspection. The video tape position verification record is being retained by Maine Yankee Atomic Power CompatW.
o 9
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e I
- 6 ?-
.1
TABLE 1
(\\
STEAM GENERATOR NO. 1 5,70 "If' Tubes Total Tubes 1,673,T29.4%)
Tubes Through No. 7 Drilled Support Plate 779 (12.7%)
Tubes Through No. 9 Drilled Support Plate I
TUBES INSPECTED (OCTOBER 1982)
NUMBER INSPECTED REMARKS l
.6 Tube Wall Degradati l
Total, Defect Detection 468 (8.2%)
IndicationsListedTg Total, Hot Side Dent Detection 468 (8.2%)
117 Dent Indications f
Hot Side Sludge Depth Heasurenent '
Sludge Measurements Not Taken Sludge Measurements Not Taken Cold Side Sludge Depth Measurement PERCENT
'IOTAL '
AVERAGE MAX f.
NUMBER OF PLATE DEhT
. DENT DEhT
' ' - IN3PECTED INSPECTED INDICATIONS (MILS)
(MILS)
I
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- 9 Drilled hupport Plate:
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Bot Side Not TeitSd
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Cold Side Not Tested
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- 7DrilledSupportP$ ate: Y4
- Hot Side
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Not Tented
^
c Cold Side Not Tested, s
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N
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Dent maFnitude based on, comparison'pf signal' aNp1Itudes with signals ~
NOTE:
j from denn\\ etandard (see. Dent Standard Certification Section IV).
s Average [entimbnained by talcing aveEage of dent indidatIons excluding zero dent indications.. i s
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TABLE 2 j
r STEAM CENERATOR No. 2 Total Tubes 5,703 "U" Tubes Tubes Through No. 7 Drilled Support Plate 1,673 (29.4%)
Tubes Through No. 9 trilled Support Plate 779 (13.7%)
TUBES INSPECTED (OCTOBER 1982).
NUMBER INSPECTED REMARKS Total, Defect Detection 849 (15%)
23 Tube Wall Degrada; Indications Listed Tz Total, Hot Side Dent Detection (All Elev.)
849 (15%).
416 Dent Indications
/'
Bot Side Sludge Depth Measurement 112 (1.96%)
Max. 8 Inches Cold Side Sludge Depth Measurement 18 (0.32%)
Max. 11.0 Inches PERCENT TOTAL AVERAGE MAX IN INSP IND CA IONS (MI )
(M
)
- 9 Drilled Support Plate:
Hot Side 148 18.9 141 7.27 13.0 Cold Side 148 18.9 143 8.10 14.0
- 7 Drilled Support Place:
Hot Side 90 5.'3 46 3.02 7.5 Cold Side 90 5.3 86 5.26 11.0 t
j-NOTE: Dent magnitude based on comparison of signal amplitudes with signals from dent standard (see Dent Standard Certification Section IV).
4 Average dent obtained by taking average of dent indications excluding e
zero dent indications.
s 7
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TABLE 3 '
STEAM CENERATCR NO.3
[
5,703 "U" Tubes Total Tubas Tubes Through No. 7 Drilled Support Plate 1,673 (29.4%)
Tubes Through No. 9 Drilled Support Plate 779 (13.7%)
TUBES INSPECTED (OCTOBER 1982) g i
INSPECTED REMARKS
. S Tube Wall Degradati' Total, Defect Detection 825 (14.4%)
Indications Listed To Total, Hot Side Dent Detection 825 (14.4%)
377 Dent Indications E
Hot Side Sludge Depth Measurement 130 (2.3%)
Max. 14 Inches cold Side Sludge Depth Measurement 7 (0.01%)
Max. 10.8 Inches PERCENT TOIAL AVERAGE MAI NUMBER OF PLATE DENT DENT DENT i.
INSPECTED INSPECTED INDICATIONS (MILS)
(MILS)
- 9 Drilled Support Plate:
Hot Side 144 18.4 115 4.66 10.0 Cold Side 143 18.3 121 5.31 10.0
- 7 Drilled Support Plate:
Hot Side 119 7.1 52 2.82 6.5 Cold Side 119 7.1 89 4.19 11.0 NOTE: Dent asguitude based on comparison of signal amplitudes vith signals from dent standard (see Dent Standard Certifiestion Sectibn IV).
Average dent obtained by taking average of dent indications excluding zero dent indications.
TABLE 4 D
MAINE YANKEE DENT INSPECTION COMPARISON STEAM CENERA11)R NO. 2 MAY JULY MAY MARCH OCTOBER LOCATION
_1977 1978 1981 1982 1982 No. 7 S/P Hot Number Inspected 100 260 295 Not Tested 90
% Occurrence 21 63 62 51 Indications 21 155 162 46 Average Dent 0.5-1 3.1 2.79 3.02 No. 9 S/P Hot Number Inspected 31 273 204 154 148
% Occurrence 0
31 92 100 95 Indications 0,
84 188 154 141 Average Dent 0'
2.8 7.90 7.97 7.27 No. 9 S/P Cold Number Inspected 68 273 204 135 148
% Occurrence 0
0 92 99 96 Indications 0
0 189 134 143
?N Average Dent 0-0 bd 9.09 8.60 8.10 No. 7 S/P Cold Number Inspected 152 260 259 Not Tested 90
% Occurrence 6
11 85 95 Indications 1
29 220 86 Average Dent 1
2.8 6.38 5.26 i
i NOTE:
Percent occurrence indicates number of dent indications to number of tubes tested that pass through the location specified.
i 4
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TABLE 5
)
{
)
MAINE YANKEE DENT INSPECTION COMPARISON STEAM CENEP.ATOR NO. 3 l
FEBRUARY
---OCTOBER 1980 1982 1ACATION No. 7 S/P Hot
~
Number Inspected 350 119
% occurrence 41 43.7 Indications 144 52 Average Dent 1.6 2.82 No. 9 S/P Hot l
Number Inspected 278 144 i
% Occurrence 63 79.9 Indications 176 115 Average Dent 1.4 4.66 No. 9 S/P Cold Number Inspected 278 143
% Occurrence 3.6 84.6 Indications 1.0 121 Average yent
.75 5.31 4
No. 7 S/P Cold Number Inspected 350 119
% occurrence 14.5 74.7 Indications 51 89 Average Dent 1.1 4.19 NOTE: Percent occurrence indicates number of dent indications to number
- I of tubes tested that pass through the location specified...
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TABLE 6 TUBE WALL DEGRADAT1_0N INDICATIONS
\\
S/G #1 S/G #2 S/G #3 LINE ROW LINE RDW 5,
LINE R0W_
8 7
<20 132 5
<20 25 8
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<20 139 10
<20 99 8
100 7
<20 135 8
<20 1 01 8
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<20 124 7
<20 103 8
118 7
<20 120l 5
<20 104 7
<20 19 8
<20 105 8
<20 30 7
<20 107 8
<20 31 8
<20 41 8
<20
'39 8
57 37 8
33 105 8
33 135 6
90 110 5
47
^
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49 99 8
56 99 6
52 1 01 8
31 127 B
42 x
31 6 -
<20
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98
'107'
< 20 ' ' '
+
t>:
NOTE: L86 R87 Plugged Due to Non-Removal of Camlock.
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- OCTOBER, 7
FICURE N.,-
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- --..I.GU.RE #3 F
5.0 DEFERRED EXAMINATIONS
(
)
Safe-end weld SE-J cn lir.e RC-1 was unaole to be liquid penetrant tested, as s
required, due to a persistent oild residue which could not be removed. Several cleaning attemots were made with spotcheck cleaner, demineralized water and soap, and dry rags; all being unsuccessful. Further attempts were taken with a wire brush and a flapperwheel; these too being unsuccessful.
Because this is a high radiation area and the number of cleansers allowed to be used on the pressure boundary is limited, this problem is being investigated further ar.d an attempt to liquid penetrant test this weld will take place during the next refueling outage.
Safe-end welds SE-D on lines RC-2, RC-8 and RC-13 were unaule to be NDE tested due to inaccessibility. These welds are located in an area just large enough to get a hand and possiole a forearm into. They are also about ten feet above the floor. This location makes cleaning and examining next to impossible.
A method of automatic examination needs to be investigated before attempting to examing these welds during the next refueling outage.
U e
4 1
4
REACTOR PRESSURE VESSEL INSERVICE EXAMINATION REPORT for MAINE YANKEE ATOMIC POWER COMPANY WISCASSET, MAINE C'O DOCUMENT No.
IR-IS1-014 issue Date:
5/12/83 M
Originator: ~ Project Engineer '
fj 1
Approvals:
G
' t L.
- .. I ion v
nager, inWsdection Prepared By:
INSERVICE INSPECTION DEVELOPMENT DEPARTMENT DAWED COMBUSTION ENGINEERING,INC.
F V WW b81 wne.Cenecut SYSTEMS
/
M==nt No.: IR-ISI-014 Revision No.:
0 g(.-.'N
\\ V AsSTancr The Inservice Inspection Program examinations were conducted in accordance with tne American Society of Mechanical Engineers Eoiler and Pressure Ves-sel Code,Section XI 1974 Edition including addandas through the Summer of 1975 and USNRC Regulatory Guide 1.150.
In the performance of these avaminntions, h hnetion Engineering, Inc.
(C-E) acted as the prime contractor and supplied the examiners and the evamination system. Hartford Steam Boiler (HSB) s'erved as the Authorized Inspection Agency. By this arrangement, the HSB Inspector reviewed the
. applicable procedures and examiner's qualifications, witnessed the exam-inations and checked for general code compliance as specified in Ika-2120 of Section XI.
The Inservice Woion report is presented in two (2) Volumes.
Volume I.......
. Report Volume II........ Examination Data
' 1 '
O i
1 i
2 y
I-l m
FORM NIS-1 OWNERS' DATA REPORT-FOR INSERVICE INSPECTIONS As required by the Provisions of the ASME Code Ru* les Page 1 of i
- 1. Owner Maine Yankee Atomic Power Company, Wiseasset, Maine Maine Yankee Atomic.Po(wer Station, RFD #2, Name and Address of Owner)
J., Plant Box 240, Bailey Point - Ferry Road. Wiscasset. Maine 04578 (Name and Address of Plant)
- 3. Plant Unit iI
- 4. Owner Certificate of Authorizanon (if requard) VPR -36
- 5. C~ =m.al Service Date 12-29-72
- 6. National Board Nurnber for Unit
?ORF;
- 7. Components 14;M Manufacturer Component or Manufacturer or Installer State or National Appurtenance or installer Sena! No.
Province No.
Board No.
Reactor Vessel M - CE. Inc.
67106 NA 70R69 Reactor Vessel Closure Head M - CE. Inc.
67206 WA 70RA9 Pressurizer M - EE. Tne.
67601 MA 90RER Primary (3)
Pinine(Hotteesl M - ER. Tnn.
511-09 NA NA 1 O
.N N
N N N N N N N N l
l l
Note: Supplemental sheets in form of lists, sketches, or drawings may be used p.e/M (1) size is 3% in.x 11 in.,
(2) information in items 1 through 6 on this data report is included on each sheet,and (3) each sheet is numbered jy and the number of sheets is recorded at the top of this form.
This form (200029) rrey be obtained from the W Dept., ASME,345 L 47th St., New York, N.Y.1C017
Pcg2 I of 1 (Beck)
FORM NIS-1 (back) j T
Il-12-82 9. Inspection Interval from 12-29-72 o 12-29-82
'c (V. Examination Dates
\\
10-Il-82 to t
8
- 10. Abstract of Examinations. Include a list of examinations and a statement concerning status of work required for currentintewal. One hundred and thirty-six ( 136) items were examined and the first interval is now complete.
j
- 11. Abstract of Conditions Noted.
Below
- 12. Abstract of Corrective Measures Recommended and Taken The thermal shield support system be inspected during the next refueling outage.
- 13. Capacity:
2630 Mw(t) 825 MWE We certify that the statements made in this report are correct and the examinations and corrective mes-sures taken conform to the rules of the ASME Code,Section XI.
Y l' Y/
19 0 Signed N!A r l!)n M
er-By Dare
/ /
ner' c'
Certificate of Authorization No. (if applicable)
NA Expiration Date CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and/or the State or Provmee of 8Hf4C#uf677Y and employed by MS. 8. //f 6 of
//M r/o r h, ("7" have inspected the components described in this Owners' Data Report during the period
~
durucr /9522 to ##A /949 and state that to the best of my knowledge and belief, the Owner
(
) has performed examinations and taken correctree measures described in this Owners' Data Report in accordance with the requirements of the ASME Code,Section XI.
By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and correenve measures described in this Owners' Data Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.
Date uw
/Y 19 # 3
, YY b Commissions A/S 7 son
/V9/,32 2 Insp/ctor's Signature National Board, State, Province and No.
I1.
Of the 55 welds in the reactor vessel and closure head that were ultrasenically examined, 13 welds had no indications and 42 welds had indications caused by either component geometry or real reflectors in the WRV.
All reflectors were sized and found acceptable.
Eighty-one (81) areas of the reactor vessel and internals (upper guide structure and core support barrel) were examined by visual techniques, with 80 areas having no indications and I area having a reportable condition. The reportable condition was 3 of the top 9 thermal shield pins were dislodged, one pin was protruding 1.5".
All pins were retrieved prior to plant startup and based on the CE report, CEN-232 (m)
Maine Yankee Thermal Shield Support System Failed Positioning Pin Evaluation, the pins were deemed unnecessary to normal plant operation.
I VRV - Weld Required Volume l
CE, Inc. - Combustion Engineering, Inc.
l 1
iLJ
Document No.: IR-ISI-014 Revision No.: 0 3
Q
SUMMARY
AND CONCLUSIONS The Reactor Pressure Vessel ISI examinations of the Maine Yankee Atomic.
Power Station were conducted from October, 1982, through November, 1982.
The purpose of the ISI was to fulfill the requirements of the 1974 Edition of Section XI of the ASME Boiler and Pressure Vessel Code, and the USNRC Regulatory Guide 1.150.
Selection of RPV weld areas to be inspected was in accordance with the 1974 Edition of Section II including Addendas through the Summer of 1975.
There were two types of examinations perfomed: ultrasonic and visual.
These examinations were conducted by qualified personnel from Combustion Engineering, Inc. Written procedures wera developed by Combustion Engineering and reviewed by the Hartford Steam Boiler Company and reviewed and approved by Maine Yankee Atomic Power Company.
Overall supervisory control of the program was supplied from the Nuclear Power Systems Development and Services Department, Inservice Inspection Group of Combustion Engineering, Inc.
~
9 e
e e
L III-1 9
)
~
Document No.:
IR-ISI-014 Revision No.: 0 IEERVICE EXN4INATION SUPf1ARY ASME Section Code Ntanber of XI Examination Near Surface Voltane Category Welds Requirement Examination Completed B-A 7
1004 Yes/1001, 1D0%
B-B 13 RPV
$t each cite.
WA 5% of each ciretunferential weld 6 Clohuth Hebd 10% bach long.
WA 10% of each longitudinal weld B-C 1
100%
WA 100% (Parallel) 50% (Perpendicular) A B-D 6
100%
WA 1004 (including 6 I/R Areas)
B-G-1 1
100%
N/A 18 flgaments (38 through 1)
B-I-1 6
100%
WA 100t B-I-2 1
1004 N/A loot B,7 9
'100t N/A 100t B-N-1 36 RPV 100% **
N/A 100% **
5 Closure head 100% **
WA 1004 **
B-N-3 34 100% **
N/A 1004 **
Pressurizer 5
None N/A 1006 **
- For the remaining length of teld, see previoud Maine Yankee IS1 neports.
- Accessible Areas -
III-2
Dr =nt No. : E-ISI-014 Revision No.: 0 REFCr0R PRESSURE VESSEL INSERVICE EXAKIN#JrION REPORT Em following pages present a listing of each examination item.
The plan sheets identify each weld or item by designation ntaber, provide a verbal description of the eramination area, identify the ISI reference number and the code examination category. They also identify the exam-ination method (s) to be used and the procedures to be followed.
All of the above information has been provided to enable the users and qualified examiners to guickly identify the various examination items and perform the examinations in an efficient manner and in keeping with ALN R concerns.
Additionally, all of the required IJr calibration blocks lave been Identi-fled on the plan sheets thus enabling Maine l'ankee Atomic Power Company to provide those blocks which will be used, prior to the start of the eraminations.
~
4
'e t
o.
f IV-1
1 S
MS couoOSHON ENGWEENHO. WC ZONE 1
CLAssi IR-1SI-014 DOCUMENT No.:
PROGRAM PLAN E-234-112 REAC'IUR PRESSURE VESSEL HEFERtNCE DRAWING No.t TITLh:
E$
yO Ewe lQ8@
EXAMINATION ARtA EXTENT l
l AREA DESCRIPTION OF EXAMINATION QgE 3[m.4 gd E
PROC $ DURE OttloNAttoN 3
E NtJMBER 0
3 5
a 5"
RPV-A utter Shell course 6 Plange 100s B-c trr 92882-Ist-001
'IB-52 Ciretanferential (Parallel)
RPV-A Opper Shell course to Flange 50%
B-c trr 92882--1S1-004
'IB-35 circumferential From 180 Degrees (Perpendicular) to 360 Degrees RPV-B Hiddle Shell codrse to Upper shell 54 B-B tir 92882-1S1-001 TB-52 Course '- Ciretaferential r
RPV-c Middle Shell course to twer Shell 1006 B-A trr 92882-1S1-001 TB-52 Course - Circumferential i
RPV-b Bottoni Head Assembly to tower Shell -
51 B-B trr 92882-1S1-001 TB-52 Circumferential RPV-A-1 Upper Shell course tongitudinal Weld 104 B-b trr 92882-1S1-001 TB-52 at 60 Degrees Orientation l
RPV-A-2 Upper Shell course tongitudinal Weld 101 B-b ttf 92882-181-001 TB-52 at 180 Degrees Orientation RPV-A-3 Upper Shell course tongitudinal Weld 104 B-B trr 92882-1S1-001 TB-52 at 300 Degress Orientation RPV-B-1 Middle Shell course tongitudinal Weld 1004 B-A ttr 92882-1S1-001 TB-52 l
at 30 Degrees Orientation 0
I/A Not APPLICABLE REVISION:
II) DURING HYDROTEST IY
- PAGE:
L--______-
b
'/WOUSilON ENGH4EEFWNG. H4C ZONE 1
CLASS 1 IR-IS1-014 90cOMtNT No.:
Ph0 GRAM PLAN E-234-112 m a l PRESSURE VESSEL 1EFERENCE bhAWING No.:
tlTLt-5>
5 5
AREA-EXTENT h$E h
EXAMINATION PO
$"gl REA DESCRIPTION ES E
g PnOCEDURE y
DESIGNATION OF EXAMINATION E
$g NUMBER 3g 5
5 5"
RPV-B-2 Middle shell Course tangituditial Weld
- 1001, B-A ttr 92882-1S1-001
'IB-52 at 150 Degrees Orientation RPV-B-3 Middle shell Course tongitudinal Weld 100%
B-A IJr 92882-1S1-001 TB-52 st 270 Degrees Orientation RPV-C-1 Lower Shell Course longitudinal Weld 100%
B2A (fr 92882-1SI-001 TB-52 at 90 Degrees orientation RPV-C-2 Lower Ehell Course longitudinal Weld 100%
B-A ttr 92882-181-001 TB-52 at 210 Degrees orientation RPV-C-3 Lower Shell course longlLudinal Weld 100%
B-A (fr 92882-ISI-001 TB-52 at 330 Degrees orientation fut-FL Flange. Ligaments around stud Holes 100%
B-G-1 UT 92882-ISI-005 TB-35 38 through 1 4
6 l
! /A NOt APPLICAhtE REVISION:
il DURING HYDROTESt y_g l
PAGE:
GOMOUSTION ENOBNEERNG. INC ZONE-1 class 1 DocOMhNT No.:
PROGRAM PLAN REFERENCE DRAWING No.:
E-23b113 REACIVR PRESSURE VESSEL TITLE:
5>
5 5
AHtA EXTENT
@"8 h
EXAMINATION PO lhg!
AREA bESCRIPTION 2
2 PROCEDURE IM DESIGNAlloN OF 5
El(ARINATION NUMBER 8
a=
5
. RPV-D-1 Peel Segment to Peel Segment at 66 10%
B-B trr 92882-IS1-001 1B-52 Degrees Orientation hPV-D-2 Peel Segment to Peel Segment at 117 10%
B-B (Tr 92882-ISI-001 TB-52 Degrees Orientation RPV-D-3 Peel Segment to Peel Segment at 168 104 B-B (fr 92882-ISI-001 TB-52 Degrees Orientablon RPV-D-4 Peel Segment to Peel Segment at 219 Idt B-B (Tr 92882-ISI-001 10-52 Degrees Orientation RPV-D-5 Pedl Segment to Peel Segment at 270 lbt B-B (fr 92882-1S1-001 1B-52 Degrees Orientation RPV-D-6 Peel Segment to Peel Segment at 312 101 B-B trr 92882-151-001 1B-52 Degrees Orientablon RPV-D-7 Peel Begment to Peel Segment et 1$
lut B-b (tr 92882-1S1-001
.TB-52 Degrees Otlentation i
RPV-E Bottom Head to Peel Segment Torus 5%
B-B trr 92882-IS1-tici TB-52 l
i I
i c '/A NOT APPLICABLE HEVISION:
0
'fl DORING HYDROTEST l
PA9tt
-I'
i,oMetEDoN ENOBHEERNG. INC 20NE 1
CLASS 1 IR-ISI-014
)ocOMENT No.:
PROGRAM PLAN E-2n-lu REACER PRESSURE VESSEL 1EFtRENct DhAwlNo No.t TITLt:
l EXTENT 8 El$
E '*' !
E EXAMINATION PE AREA DESCRIPTION 2
PROCEDURE E
OF EXAMINATION
{gE M
NUMBEn
- O 3
Y 0*
IR-AA-1 Inner Radius of Inlet Nozzle at 0 1004 B-b UT 92882-ISI-007 1B-52 Degrees Orientation IR-BB-1 '
Inner Radius of Outlet Nozzle at 60 100%
B-D trr 92882-Isi-007 18-52 Degrees Orientation IR-CC-1 inner hadlus of inlet Notzle at 120 1001 B-b UT 92882-ISI-007 TB-52 Degrees Orientation IR-DD-1 inner Radius of Outlet Nozzle at 180 100%
b-D (Tr 92882-181-007 TB-52 Degrees Orientation IR-Ek-1 inner hadius of Inlet Nozzle at 240 1001 B-D UT 92882-I51-007 TB-52 begrees Orientation IR-ft-1 inner radius of. Outlet Nozzle et 300 1004 B-D LTr 92882-ISI-007-TB-52 Degrees Orientation RPV-AA-1 Inlet Nozzle to Shell Weld at 0 100%
B-b UT 92882-ISI-006 1B-52 Degrees Orientation 1004 B-D (Tr 92882-1S1-001 1B-52 RPV-BB-1 Outlet Nozzle to Shell Weld at 60 100%
b-D UT 92882-181-006 TB-52 Degrees Orientation
~
100%
B-D tTP 92882-ISI-001 TB " I RPV-cC-1.
Inlet Nozzle to Shell Weld et 120 100%
B-D OT 92882-191-006 TB-52 Degrees Orientation 100%
B-D Ifr 92882-ISI-001 1U-52
/A Not APPtl caste 0
ntvisioN:
!! DURING HYDROTEST IV-I*4 l'Act:
WeUSION ENGhEERNG. 04C ZONE 1
cLAssi IR-181-ble oocuMENT No.:
PROGHAM PLAN E-234-1H f1EFERENet DMAWING No.:
TITLh:
5>
5
=
Ewe lEll E "'
EXAMINATION 5
A EXTENT AREA DESCRIPTION OF E
PROCEDURE 5
3gg EXAMINAit0N-
{gE sE NUMBER
- 0, 5
5" RPV-DD-1 Outlet Nozzle.to Shell Weld at 180 1001 B-D trr 92882-ISI-006 1B-52 Degrees Orientation 100%
B-D UT 92882-ISI-001 TB-52 RPV-EE-1 Inlet Hozzle to Shell Weld et 240 100%
b-D UT 92882-1S1-006 1B-52 begrees Orientation 100%
B-D UT 92882-1S1-001 1B-52 RPV-FF-1 Outlet Nozzle to Shell Weid at 300 1004 B-D tir 92882-1S1-006 TB-52
- Degrees Orientation 100%
B-D trr 92882-ISI-001 TB 2 11PV-AA-2 Inlet Nozzle to Extension Piece at 0 100%
B-D lir 92882-1S1-006 1B-52 begrees Orientation RPV-BB-2 Outlet Nozzle to Extenslon Piece at 60 100%
B-D UT 92882-1S1-006 TB-52 Degrees Orientation RPV-CC-2 Inlet Notzte to txtenslod blece at 120 1001 B-D OT 92882-181-006 TB-52 Degre6s Orientation RPV-IJD-2 Oublet Nozzle to Extension Plece at 180 100%
B-D UT 92882-181-006 TB-52 Degrees Orientation RPV-Et-2 inlet Notzle to " Extension Piece at 240 100%
Degrees Orientation RPV-17-2 Outlet Nozzle to extension piece at 300 100s B-D trr 92882-1S1-006 19-52 Degrees Orientallon
/A NOT APPtlCAbtE 0
REVitl0N:
- 1) DURING HYDRotEst IY-1*$
PAGE:
s COMBUSTION tNONEEftNO. INC 20NE 1
class 1
~
DocOMtNT No.:
PROGR/M PLAN REFERENCE bMAWING No.t E-234-114, E-233-518 TITLE.
REACIVR PRESSURE VESSEL 5>
g.
5 AREA DESCRIPTION DESIONAtloN OF E
g E
PROCEDURE a: y EXAHINAT10N gE $gE NumeER 33 5
6"
=
RPV-BB-3 Extension Plece to Primary Piping at 60 100%
B,J bT 92882-ISI-006
'IB-11 Degre&s Orientation M-tD-j txtension Plece to Primary Piping at 180 1001 B,1 UT 92882-1S1-006 TB-11 begrees Orlehtation RPV-W-3 kttension blece to Primary biping at 300 1004 B,1 UT 92882-1SI-006
'Is-11 Degrees Orientation l
t/A NOt APPLICABLE REVltlON:
0
'll DURING HYbHOTEst PAGE:
IV-1.6
S MS COMBUSTION ENGINEERNG. INC ZONE I
CLASS 1 gg_gg DOCUMENT NO.:
PROGRAM PLAN E-233-526 REFERENCE bhAWING NO.:
TITLE:
5>
5 5
8 exAMINATioid PO
{E l
E"h AHEA EXTENT AntA otscWT!oN E
PROCEDURE Em DESIGNATION OF EXAMINATION
{gE
- s E NUMBER 3 0 U
U 0"
RW-BB-4 P1pe longitudinal Weld 12" B-J trr 92882-ISI-006
'IB-11 RW-BB-5 Pipe tongitudinal Weld 12" EN trr 92882-ISI-006 Trs-11 RW-DD-4 Pipe tongitudAnal Weld 12" B-J trr 92B?2gSI-006'
'IB-11 RW-CD-5 Pipe tongitiudinal Weld 12" B-O UT 92E82-ISI-00if, I,TB11_
l 1
RW-h-4 P1pd tungItudir.a1 Weld 12" B-J trr 92882-ISI-005
'IB-11 f
RW-h-S Pipe tongitudinal Weld 12" th)
UT 37882-1Si-006 '
TB-11 r
a 1
i, p
I l
1/A Not APPLICABLE nEVISION:
II) DURING HYDh0 Test
COMBUSitOf4 D40fedEEFUNO. lHC 2ONt I
class i IR-IS1-014 DocuMtNt No.:
PROGRAA4 Pt AN REFEhENct bHAWING No.1 E-234-113, E-234-117 REACIUt PRESSURE VESSEL
. TITLE:
5>
5 5
LXTENT.
G88
@8@
txAMINATioN Q E ARtA ARtA DESCRIPTdON 2@2 P'tOCEDURE ce $
OF 2
jme
$ig NbMBER yO EXAMINAT10ii gE U
6" w
CP-1 Clad Patch at 0 tbgree and 25" Below loot b-I-1 vr 92882-1S1-065 N/A Co'e Support Flange
/
CP-2 Clad Patch at 60 Degrees and 25" Below 100%
B-I-1 VT 92882-ISI-065 N/A Cote Support Flange cP-3 clad Patch it 120 Degrees and 25 Below 100%
B-I-1 VT 92882-1SI-065 N/A d
Core Support Flange CP-4 C16d Patch at 180 Degreen and 25" Below loot B-1-1 VT 92882-1E1-065 N/A Cote Support Flange -
CP-5 Clod Patch at 240 Degrees and 25" Below 1004 B-1-1 VT 92882-1S1-055 N/A Core Sophort Flange CP-6 clad Patch et 300 Degrees and 25" Below loot B-1-1 VT 92882-ISI-065 N/A Core Support Flange G-1 cote Stabilizer it 20 Degrees 1001 L B-N-1 VT 92882-1S1-065 N/A cS-2 tore Stabilizer at 80 Degrees 1004 B-N-1 VT 92882-ISI-065 N/A CS-3
'Cofe 8thbilizer at 140 begrees loot B-N-1 VT 92882-ISI-065 N/A CS-4
~ dote Blsbilizer dt 200 begreen loot B-N-1 VT 92882-151-065 N/A i
N/A NOT APPLicAtit.t htVisloN:
iIil DURING NYbHOTE$t IV-I'8 PAut:
b S
COM00 silon D40lNEEfuNG. ItaC 20Nh 1
CLASS 1 I ~ U ~ 14 DOcOMtNT No.:
PROGRAM PLAN REFEntNet bRAWING No.:
E-234-113, E-234-117 TITLg.
hEACHR PRESSURE VESSEL AREA EXTENT EE8 E
EXAMINATION PO AREA DESCRIPT10N OF 2S h 2
PROctDURE NM btSIGNAtioN E
fgI EXAMINATION NUMBER 6*
l m
CS-5 Core stebilizer at 260 Degrees 100%
B-N-1 VI 92882-1SI-065 N/A CS-6 Core stabilizer at 320 Degrees 100%
B-N-1 VT 92882-ISI-065 N/A CSL-1 Core Stop Lug at 8 Degrees 100%
B-N-1 Vr 92882-151-065 N/A C5tr-2 Core Stop Lug at 53 Degrees 1004 B-N-1 Vr 92882-ISI-065 N/A CSL-3 Cord B' top Lug et 93 Degrees 1001 B-N-1 Vr 92882-151-065 N/A CSted Core stop Lug.at 128 Degre5s 100%
b-N-1 VT 92882-1S1-065 N/A CSL-$
Core stop tug at 173 Degrees 1004 B-N-1 Vr 92882-1SI-065 N/A CSic6 Core Stop Lug at 213 Degrees 100%
B-N-1 Vr 92882-1S1-065 N/A CSL-7 Cath stop Lug at 248 Degrees 1004
'B-N-1 Vr 92882-1S1-065 N/A CStc8 Core St6p Ltkj et 293 Degtees 100%_
B-N-1 Vr 9288d-181-065 N/A CSte9 Core Stop Lug at 333 Degrses
- 100%
B-N-1 Vr 92882-181-065 N/A BHN Bottom liedd,iCI Nozzles All B-N-1 Vr 92882-181-065 N/A 1/A NOT APPLicA8LE hEVISION:
0 4
III DuntNo NYDROTEST PAGE:
IY~1*9
KMRBs Po 6
.OMBUSDON ENGWEEFuNG. WC 20NE 1
CLASS 1 IR-IS1-014
)OCUMENT No.:
PRDGRAM PLAN IEFEHENCE bhAWING No.:
E-134-133, E-234-113 REACER PRESSURE VESSEL tiTLt:
Ebel E*
E el-2 GXAMINAT10N P!
- " ^
EXTENT AREA DESCRIPTION op,,gNAtlON OF PROCEDURE f
EXAMINATION QgE
$Ig NUMBER
- 0, U
U 0"
MG-1 Plos Baffle Skirl Welds Accessible Areas B-N-1 VT 92882-1S1-065 N/A KW-1 Rey Way Il et d Degrees 100%
B-N-1 VT 92882-ISI-065 N/A KW-2 Kef Way $2 at 90 Degrees 100%
b-N-1 VT 92882-ISI-065 N/A KW-3 Rey Way $3 at 180 Degrees 100%
B-N-1 VT 92882-ISI-065 N/A KW-4 key wap 14 at 270 Degrees loot B-N-1 VT 92882-1S1--065 N/A ONB-1 Outlet Nozzle Boss at 60 Degrees 1001 B-N-1 VT 92882-ISI-065 N/A ONB-2 Outlet Nozzle Bohs et 180 Degrees 100%
B-N-1 Vr 92882-181-065 h/A ONB-3 Outlet Nozzle Boss at 300 Degrees 100%
B-N-1 VT 92882-181-065 N/A SC-1 Butvel11ance Capsules at 83 Degrees 1001 s-N-1 VF 92882-ISI-065 N/A SC-2 Surveillance capsules at 157 Degrees 100%
B-N-1 VT 92882.16I-065 N/A SC-3 Surveillance capsules at 253 Degrees 1001 B-N-1 VT 92882-1S1-065 N/A SC-4 Butvel11ance Capsules at 263 Degrees 1001 B-N-1 VT 92882-ISI-065 N/A SC-5 Survblilence Capsules at 343 Degrees.
100%
B-N-1 Vr 92882-ISI-065 N/A SC-6 Butvelliance Capsules at 353 Degrees 1001 B-N-1 VT 92882-1SI-065 N/A
'A NOT APPLICAhlt 0
REVistoN:
') DUhlNG HYbh01Est PAGE:
i
h M
g d
msim onsme e
zone I class i
~
cuMENt No.:
PROGRAM PLAN
'~ ' # ~ "
nsAm as vessel FEftENCE DitAWING No.:
TITLE:
5>
A"EA EXTENT E5l Q8g tXAMINATION Q O AliEA DtSCRIPTION 2
2 I".
PROCEDURE sed DESIGNATION OF Ef$
Eh_E EMHIMTM NUMBEn 33 8
a-5 CBAK-1 Core Bartel Alignment Key at 0 Degree 100%
B-N-3 vr 92882-151-065 N/A CBAK-2 Core Barrel Alignment Key at 90 begrees 100%
B-N-3 Vr 92882-1S1-065 N/A CBAK-3 Cote Barrel Alignment Key at 180 Degrees 100%
B-N-3 Vr 92882-1S1-065 N/A CBAK-4 Cord Barrel Alignment Key at 270 Degrees 100%
B-N-3 VT 92882-181-065 N/A CBGL-1 Core Barrel Guide Lug at 25 Degrees 100%
b-N-3 Vr 92882-151-065 N/A CBGL-2 Cote Barrel Guide Lug at 115 Degrees 100%
B-N-3 vr 92882-1S1-065 N/A CBGL-3 Core Barrel Guide Lug at 205 Degrees 1004 B-N-3 Vr 92882-181-065 N/A CBGL-4 Core Barrel Guide Lug at 195 begrees 100%
B-N-j vr 92882-181-065 N/A CEMs-1 Cdre Barrel Hating Surface (Top and 100%
B-N-3 Vr-92882-181-06S N/A 4
Bottom)
ONP-1 Outlet ibzzle Projections at 60 begrees 1004 B-N-3 Vr 92882-1S1-065 N/A ONP-2 Outlet Nozzle Projections et 180 Degrees 100%
B-N-3 Vr 92882-151-065 N/A ONP-j Outlet Noztle Projections at 300 Degrees 100%
B-N-3 Vr 92882-181-065 N/A CSB Core Shrobd Bolting (8) 100%
B-N-3 Vr 92882-1S1-065 N/A i
10T APPLICAbtg litVibloN:
0
'UnlNo HYbHOTEtT IV-I*II PAGE:
.I
.Q uuswmu nuttn uc zone
- 1. CLAssi IR-151-014 COMENT No.:
PROGRAM PLAN
"~# "
REACIU1 PRESSURE VESSEL FERENcE DHAWING No.:
. title:
5>
5 5
I EwalEyh E5 EXAMINATION Q 5 AREA EXTENT REA DE8CRIPTION Eg2 PROCEDURE gd DEslGNATioN OF EXAMINATION
$gE 8sg
-, 3 2
NUMBER 6
6=
'ISP
%ermal Shield Pins Accessible B-N-3 VT 92882-1S1-065 N/A Areas IISS fxAmr Core Support Struct6te Accessible B-N-3 vr 92882-ISI-065 N/A Areas CBGW Cote Bupport Battel Girth Welds (.i)
Sampled B-N-3 VT 92882-151-065 N/A Welds CSW Core Shroud Welds Sampled B-N-3 VT 92882-151-065 N/A Welds CSA
' Core Shroud Anhulus Ared Accessible B-N-3 Vr 92882-181-065 N/A Areas IISP IAAmt Cote Support Plate (OD)
Accessible b-N-3 Vf 92882-1S1-065 N/A Areas
'f IOT APPLicAhtt 0
HEvitioN:
URING NYDROTtst IV-1.12
- pggg,
JL o
6 IR-181-014 E
1 Mass 1 CUMENT NO.:
PRDGRAM PLAN I ' *~
~
FERENch DMAWING No.:
tiTLh-G 5
E=gl
@ l E5 EXAMINATION PO AntA
. EXTENT REA bESCRIPTioN k
DE88GNATION OF E
g PROCEDURE 3o$
EXANINATION aF a
g NUueER B8g 8
a-SB-1 Snubber Block at 20 Degrees 100%
B-N-3 Vr 92882-1S1-065 N/A SB-2 Bnubber block at 80 Degrees 1004 B-N-3 VT 92882-ISI-065 N/A SB-3 Bnubber Block at 140 Degrees 100%
B-N-3 VT 92882-ISI-065 N/A SB-4 Snubber Block at 200 Degrees 100%
B-N-3 VT 92882-1S1-065 N/A l
SB-5 Snubber Block at 260 Degrees 100%
B-N-3 VT 92882-1S1-065 N/A SB-6 Snubber Block at 320 Degrees 100%
B-N-3 VT 92882-1S1-065 N/A i
UGHR-1 Ul4;et Guide Hold Down klug 1004 B-N-3 VT 92882-1S1-065 N/A ins-1 Upper Guide Hating Surf &ce 1001 B-N-3 VT 92882-181-065 N/A UGKW-1 Uppet Guide key Way at 0 Degrees-100%
B-N-3 VT
, 92882-1S1-065 N/A UGKW-2
~
Upper Guide Rey Way at 90 Degrees 100%
B-N-3 VT 92882-1S1-065 N/A j
UGKh-3 Upper Guide Key by at 180 Degrees 100%
B-N-3 VT 92882-ISI-065 H/A 1
UGKW-4 Ugaer Guide key b y at 270 Degrees 1004 D-N-3 VT 92882-1SI-065 N/A i
Ug4;et Guide Puel Alignment Plate w 100%
B-N-3 Vt 92882-181-065 N/A
{
UGFAP-1 l
' 1oT APPLICABLt U
hEVlSloN:
i URIMG HYDHOTkST IV-1.13 p
'O S
G) cusnon twsutta uc 20NE 1 CLAssi In-ist-014 icuMENt No.t PROGRAM PLAN E-1 W 11# E-164-003 REAC10R PRESSURE VESSEL FERENCh DitAWING NO.:
g (g, 5 >-
E AREA EXTENT E"l Egg l
@8 EXAMINATION I~O AR A DESCRIPTION Pn0CEDURE
$d E
DESIGNATION OF glg EXAMINAit0N 3g Nuustn 33 2
g 3
a=
PCid Periphtital Control Element Shrouds Accessibib-B-N-3 Vr 92882-151-065 N/A (Adjacent to outlet Nozzles)
Areas 1GT-1
. instrumentation Guide Tubes Accessible B-N-3 VT 92882-ISI-065 N/A Areas i
NOT APPLICAbl G 0
hEViSl0N:
)URING HYbHOTeti IY-I'I4 PAGE:
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PROGRAM PLAN E-234-122, E-234-121 RW CNRE HN FERtNCE DhAWING No.:
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B-N-1 Vr 92882-ISI-065 N/A CHKW-1 Closure Head Key Way at 0 Degrees 100%
B-N-1 VT 92882-ISI-065 N/A CHKW-2 Closure Head key Way at 90 Degrees 100%
B-N-1 VT 92882-ISI-065 N/A CHKW-3 Closure Head Key Way at 180 Degrees 100%
B-N-1 VT 92882-1SI-065 N/A
. CIEW-4 Closure Head Key Way at 270 Degrees 1004 B-N-1 VT 92882-1S1-065 N/A JOT APPLICABLE ttEVisioN:
0 TIRING HYDh0 TEST IY-2*I PAGE:
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- UMENT No.:
PROGRAM PLAN E-234-118 m C M RE HEAD
- ERENCE bhAWING No.:
TITLE:
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CHPS-1 Cicsure Head Peel Segment to Peel 10%
B-B LTP 92882-1S1-008 TB-16 Segment at 0 Degrees CHPS-2 Closure llead Peel Segment to Peel 10%
B-B (TF 92882-ISI-008 iB-16 Segment at 60 Degrees CHPS-3 Closure Head Peel Segment to Peel 104 B-B UT 92882-ISI-008 TB-16 Segment at 120 Degrees CHPS-4 Closurd llead Peel Segment to Peel 10%
B-B (Tr 92882-1SI-008 TB-16 Segment at 180 Degrees CHPS Closur6 Head Peel Segment to Peel 10% ;
B-B (Tr 92882-1S1-008 TB-16 Begment et 240 Degrees CHPS-6 Cidsur6 Head Peel Segment to Peel 10%
B-b (Tr 92882-15I-008 TB-16 Begment et 300 begrees t
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'1 PAGE:
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Accessible N/A-VT A92882-ISI-065 N/A Areas
- IIP 11 eater Penetrations Accessible N/A Vr 492882-ISI-065 N/A Areas llSPA fleater Support Plate Assembly Accessible.
N/A Vr A92882-ISI-065 N/A Areas E
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- 92882-ISI-065 N/A Areas SS Burge acteen Accessible N/A Vr
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- Use Appendix A to Procedure 92882-ISI-065 HEVihlON:
O l URINGilYDHOTEST Wen Wrforminj this examination.
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Document No.: IR-ISI-014 Revision No.: O j
EXAMINATION PROCEDURES The Maine Yankee Inservice Inspection examinations were conducted to written procedures prepared in accordance with Section XI of the ASME Boiler and Pressare Vessel Code, Paragraph IWA-1400.
The ult,rasonic and visual procedures were developed by Combustion Engineering, approved by CE, MYAPC and reviewed by HSB.
j Table I of this section contains a complete listing of all procedures used during this outage.
There were four (4) Engineering Notices writte:, during this outage.
They are listed in Table II.
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1)ocument No.: IR-ISI-014 Revision No.: 0 1
2 BIE I Procedure Applicable Number Revision Title Type 92882-ISI-001 1
Automated Ultrasonic hamination Complere Procedures for Reactor Vessel helds 92882-ISI-004 0
Ultrasonic hamination Procedures Specific
- for Reactor Vessel to Elange Weld 92882-ISI-005 0
Ultrasonic hamination Procedures Specific
- for Reactor Vessel Flange ligament Areas 92882-ISI-006 2
Automated Ultrasonic 5' - ination Complete
. Procedures for Reactor Vessel Nozzle Welds and Extension Piece Welds from the Nozzle Bore 92882-ISI-007 1
Automated Ultrasonic hamination Complete p)
Procedures.for Reactor Vessel Nozzle Inner Radii S2882-ISI-008 0
Ultrasonic hamination Procedures Specific
- for Closure Read Meridional, Circumferential. Dome and E1ange Welds 00000-ISI-029 3
Generic Manual Ultrasonic Examina-Generic 1
tion Procedure
\\
S2882-ISI-053 0
Procedure for the ID Surface Exam-Complete ination of the RPV for Maine, Yankee Atomic Power m y e
S2882-ISI-065 1
Procedure'for the Remote Interior Complete Visual Examination of Reactor Pres-sure Vessel ax! Closure. Band Areas 92882-ISI-065 0
Appendix A to Procedure Omoplete j
Appendix A S2882-ISI-065
\\
l 00000-ISI-069 0
Procedure for the Orientation and Complete l
Set up of the ISI Positioning System l
for the Inside' Surface Examination i
p of Reactor Pressure Veamm1m
- 2 bis procedure shall be used with 00000-ISI-029 in order to : form a complete procedure.
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Document No.: IR-ISI-014 Revision No.: O TABLE II LIST OF ENGINEERING NOTICES EN Number Affected Document Number Issue Date M-001 92882-ISI-001 Rev. 1 10/15/82 E-002 92882-ISI-004 Rev. 0 11/11/82 E-003 92882-ISI-005 Rev. 0 11/11/82 E-004 92882-ISI-053 Rev. 0 12/14/82
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Document No.: IR-ISI-014 Revision No.: 0 CALIBRATION STANDARDS This section lists all of the calibration standards utilized during the examination. Copics of all calibration standards drawings have also been included within this section.
Block No.
Drawing and Revision TB-11 ISI-8-78 1
7B-16 ISI-13-78 4
TB-35 ISI-25-78 2
7B-52 re-FIST-501-092 0 Q
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l I)ocument No.: IR-ISI-014 Revision No.: 0 C6 EXCLUSIONS AND EXCEPTIONS Ihe examinations cont'ained in this program plan will comply with the ASME Boiler and Pressure Vessel Code,Section II, 1974 Edition to and including i
the Summer of 1975 Addenda and USNRC Regulatory Guide 1.150.
However, the items listed below are exceptions.
1.
Code Category B-I-2 examinations will not be conducted. The closure head clad patch examinations cannot be perfomed due to surface oxidation in the closure head-In addition, the Sumer 1976 Addenda to Section II deleted the requirement to perfom this namination.
2.
The closure head circumferential weld examination, Code Category B-B, will not be perfomed. This is due to block insulation covering the entire weld. Also, access to this weld is highly restricted because of the closure head support shroud and air vents.
3.
Articles I-4110 and I-4120 of Sect: on II were not perfomed daily as required. Instead linearities were perfomed in 'accordance with the USNRC Regulatory Guide 1.150.
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Document No.: IR-ISI-014 Revision No.:
-0 EXAMINATION DETAILS AND RESULTS The following section outlines the evamination details and results.
Examination items are listed by zone.
A.
1)iscussion The examinations of the Maine Yankee Atomic Power Station were con-ducted to fb1 fill the requirements of the 1st 10 year Inservice Inspection Interval.
B.
. General Examination Techniques The nondestructive testing was performed using ultrasonic and visual techniques in accordance with written procedures required by IWA-1400 of Section II.
Visual Framinations The visual examinations were conducted on subject welds and components in accordance with Procedure No. 92882-ISI-065, Rev. 1 and Appendix A.
)
Ultrasonic Evaminations All UT avamination techniques that were used are. described in detail in Appendix 1.
C.
Evamination Personnel CE examination personnel performing the Inservice Ev==inations were certified in accordance with CE Procedures 00000-ESS-127 and 00000-ISI-037 These certification procedures are in accordance with SNT-TC-1A, 1975 Edition. Copies of personnel certifications for each individual are contained in Appendix 4 of this report.
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M==nt No. : IR-ISI-014 Revision No.: 0
(
EXAMINATION S199tARY.DEEINITIONS There are four coltans under the general heading Ev=% tion Results".
These columns are titled (1) No Indications, (2) Insignificant Indica-tions, (3) Significant Indications, Geometrical and (4) Significant Indications, Other.
l For this listing, all trr indications with amplitude equal to or greater than reporting response w re recorded, evaluated and reported in the tables. The term "No Indications" was used when the amplitude was less than the recording response or when no indications were observed. All recorded indications are considered significant -with those caused by component geometry listed as " Geometrical" and true indications listed as'"Other".
'Ibe term " Insignificant Indications" was used for visual indications such as surface scratches, sling marks, weld spatter, etc.
5 4
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Docunent No.t IR-ISI-014 Revision No.2 0 ZONE 1 RDC10R VESSEL NON-DESTRUCTIVE EXAMINATION SU W RY Examination Results I"he(
Exa atton Exam oh No Inst nificent indications Ind$ cationsSlanificant Indications N'*8 N8 Htder Geometrical Other RPV-A trr 001-11 X
Acceptable, Spot Indication tri 004-1 X
kPV-B Ur 001-8 X
.hPV-C tir 001-2 X
Sized, Acceptable trr 001-6 X
Sized, Acceptable tre 001-7 X
Acceptable, Sgnt Indicatioh hPV-D tr?
001-6 X
hPV-A-1 trr r 001-4 X
l RPV-A-2 trt 001-4 X
RPV-A-3 tir b01-4 X
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kPV-h-1 UT 001-1 k
Blzed, Acceptable trr 001-5 X
RPV-B-2 UT 001-1 X
elzed Acceptable tir 001-$
X hPV-B-3 Ut 001-1 X,
Dr 001-5 X
l' RPV-c-1 trr 001-3 X
trr 001-$
X RPV-c-2 trr 001-3 X
trr 001-6 x
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O Docunent No.t IR-ISI-014 Revision No.t 0 2@E 1 REACTOR VESSEt, NON-DESTRUCTIVE EXAMINATION SUMMRY txaminallon Examination Results Exa ation Exam no on Data sheet No insignificant Stanificant Indications Rem &rb Hun 6er Indications Indications Geometrical Other RPv-C-3 UT 001-3 X
trr 001-6 X
RPV-FL trr 005-1 X,
HPv-D-1 tre 001-8 x
hPV-D-2 UT 001-9 X
X Acceptable, spot Indication hPV-D-3 tir 001-8 X
NPV-D-4 ttf 001-9 X
hPV-D-B Uf 001-9 X
RPV-D-6 trr 001-9 X
i hPV-D-7 UT 001-9 X
RPV-E trr 001-9 X
j 1R-AA-1 trr 007-1 X-kvaluateda Clad Noise th-hs-1 trr 001-1 X
IR-cc-1 trr 007-1 X
1R-to-1 tre 007-1 X
j 1h-EE-1 (ft.
007-1 X
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Doctanent ka.t IR-ISI-014 Hevision No.: 0 ZONE 1 REACIQt VEBSEt.
NON-DtSTRUCTIVE LXAMINATION SUWARY Examination Examination kxamination Examination Results Aiea htW Data Sheet No Insignificant Significant Indications Remarks Number thdications Ihdicatiohs Geometrical Other IR-W-1 UT 007-1 X
RW-AA-1 trr 001-10 X
Irr -
006-6 X
X Acceptable, Spot Indication kW-Be-1 trt bol-10 X
trr -
006-3 X
RW-Od-1
.ttf 001-10 X
trf ;
006-4 X
X Bited, Acceptable hW-bb-1 trf 001-10 k
1Tf 006-4 X
hPV-kt-1 t/t 1 001-10 X
i ttf 006-4 X
ttt 0
i RW-W-1 001-10
.X tit J 006-4 X
Acceptable # Spot
- t indication RW-AA-2 ttt.i 006-1 X
i kW-bb-2 ttf 006-1 X
hPV-Od-2 (ft 006-1 X
kPV-bp-2 ttt 006-2 X
nW-kE-2
,tff 006-1 X
kW-M-2 trf 006-2 X
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.e Document No t IR-ISI-014 Revision No.t 0 TONE 1 REACTOR VBSSEL
, NON-DESTRUCTIVE EXAMINATION SUMMRY Examination Results e
No Insi nificant lHdications Ind$ cationsStanificantIndications Remarks humber Geometrical Other RW-BB-3 UT 006-1 X
RP'!-CD-3 Of 006-2 k
RW-h-3 Ut 006-2 X
RW-BB-4,5 Vf 006-1 X
RW-ID-4,5 Ut 006-2 X
RW-FF-4,5 Vf 006-2 X
cP-1 VT 065-32 k
w CP-2 Vf 065-32 X
X t
cP-4 Vf 065-32 X
CP-t vt 065-32 X
i-CP-6 W
065-32 X
CS-1 VT 065-30 X
CS-2 Vf 065-30 X
cs-3 W
065-30 x
CS-4 Vf D65-30 X
CS-5 VT D65-30 x
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Doctcwnt No.4 IR-ISI-014 Hevision No.: 0 ZONE 1 81EACIUt ML N081-DESTRUCTIVE EXAMINATION SUMARY Examination Examination Results Exa tion Exam a on g
Data Sheet No Insignificant Stanificant Indicdtfons Rendrks Humber indications Indications Geometrical Other CS-6 Vr 065-30 X
cstel VT 065-27
.X t
cste2 VT 065 X CSte3 yr 065-27 X
CSic4 VT 065-27 X
cst,-b VT 065-27 X
cst 4 Vt 065-27 X
cstc7 W
065-27 X
p cstra vt d 065-27 k
catc9 Vf.
065-27 X
I BHN VF 065-29 X
FBs-1 Vf 065-28 X
KW-1 VT 065-31 X
%2 Vf 065-31 X
kw-3 VT 065-31 X
$4 vt 065-31 X
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i lbecaenL Noei 1R-ISI-014 Revision No.t 0 20NE 1 RE M FOR VESSEL NON-DESTRtFTIVE EXAMINATION SUMARY Examination Examination Results Exa ellon Exa a on Data Sheet No Number thdlcellohs Ind$ cationsStanificant Indications Rem 6rks Insi nificant Geometrical Other CNB-1 W
065-34 X
i CNB-2 vt 065-34 x
1 ONB-3 W..
065-34 X
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j sc-1 W-065-33 X
BC-2 W
065-33 X
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ac-3 Wf 065-33 X
ac-4 W
065-33 X
Y I
DC-5 W3 065-33 X
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065L33 X
1 GAK-1 W
065-1 X
- c CBAK-2 W~
06B-2 X
i.
CBAR-3 W
06$-3 X
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CBAK-4 W
065-4 X
jl
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l 03GL-1 W
OlGL-2 W
065-11 X
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065-12 X
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QiGtc4 W
065-13 X
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v IA>ctaient No.: 111-ISI-014 lievision No.: 0 ZONE 1 ItEAC'Iul VESSEL NON-DESTRUCTIVE EXAMINATION SUFfMRY Examination Results l
E e$
Exa nation Eka a on No Inst nificent Sidnificant Indication Remads Number thdications Ind$ cationsGeometrical Othe~r CBMS-1 vr 065-22 X
CNP-1 VT
'065-5 X
Vr 065-21 X
CNP-2 Vf d65-6 X
ONP-3 Vr 065-7 X
CSB Vr 065-14 X
'IEP (10P)
Vf C65-19 X
3 Pins Pohitioned incorrectly
'ISP Vr 065-17 X
12 of the 17 pins (B01161)
W te exahithed due I
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065-16 X
Vt 065-35 X
l LISP (00)
Vt 065-15 X
CBGW Vt 065-20 X
Upper h ld Only CSW VT 065-9 X
Sampled helds CSA VT 065-8 X
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- 0. -. --.- - u Doc' Rent No.t IR-ISI-014 Hevision No.t 0
2me1 h WsssL NON-bESTRUCTIVE EXAMINATION SONIMRY
~
Examinatioh Examination Results Exa tion Ex4 ch Data Sheet No Insignificant SidnificantIndications Remarks Number thdtcations indications Geometrical other SB-1 W
None Unable to examine due to clearance between core barrel and refuel pool wall Bb-2 W
Noran Unable to examine que to clearance between core barrel and teruel pool wall SB-3 VT 065-18 X
SB-4 Vf 065-18 X
SB-5 W
065-18 X
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BB-6 W
065-18 X
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LDHR-1 W
06$-24 X
N1 yr None I
Unable to examine due to upper guide structure matirvj surface resting on stax) in refuel pool UGKW-1
' VT 065-23 X
UGRW-2 VT 065-23 x
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Doctanent No.t lH-ISI-014 hevision No t 0 ZONE 1 REEIUt VE:SSEL NON-btSTRUCTIVE LXAMINATION $0kMRY Examination Results ha Lion Exam oh h
MWW MWWh Re e ks Humber lnd{cstjons lnd cations Geometrical Other UGKW-3 VT 06$-23 X
UGgw-4 W
065-23 X
UGFAp-1 Vt.
-065-25 X
Limited examina-tion due to loca-tion of bpper guide structure in refuel px)1
- W 065-26 X
Accessible areas
.1GT-1 W'
065-27 X
Accessible areas W
D65-25 X
Acce9sible areas A
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- Revision No.t 0 ZONE 2 CIDSURE HEAD NON-DESTRUCTIVE EXAMINATION
SUMMARY
Examlhallon Examination Results Examination Examlha on Area Mh Date Sheet No Inst nf ficant StanificantIndications Remargs Number thdicallons lnd cations Geometrical Other CHMs-1 VT 065-40 x'
CHKW-1 Vf 065-41 X
CHkW-2 VT 065-41 X
OlKW-3 W
'065-41 X
CHKW-4 Vt 065-41 k
CHtt-1 tit 008-1,2 X
UT 008-3 X
CHPS-2 tir 008-1,2 X
lft 008-3 CHPS-3 lft i D08-1,2 X
(ft 008-3 X
CHPS-4 (ft 008-1,2 X
tre 008-3 X
CHPS-3 ttt 008-1,2 X,
4 008-3 X
OIPS-8 ttr 008-1,2 X
r 008-3 X
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NON-DtSTRUCTIVE EXAkINATION SU h kY Exa lion ha a gon Examination Examination Results Dati Sheet No insignificant slanificant Indicatioh<
R'"8 08 Number Indications Indications Geometrical Other SNA VF 065-36 X
hP Vf 065-37 X
i HSPA Vf 065-37 X
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'Vt 06$-38 Unaccessible
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