ML20010H468
| ML20010H468 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 09/03/1981 |
| From: | Dahlman L, Hansen D, Krumpos P NORTHERN STATES POWER CO. |
| To: | |
| Shared Package | |
| ML20010H459 | List: |
| References | |
| NUDOCS 8109240505 | |
| Download: ML20010H468 (25) | |
Text
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PRAIRIEISLAND NUCLEAR GENERATING PLANT Red Wing, Minnesota UNITS 1 AND 2 I
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f MINNE AP 3Ll5 e 5T. PAUL ~
Penisie essa o
- NW(klag plani l
INSERVICE INSPECTION - EXAMINATION
SUMMARY
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PRAIRIE ISLAND NUCLEAR GENERATING PLANT - UNIT II July'1.to July,13,1981 t
MAINTENANCE OUTAGE INSPECTION PERIOD 2 o
a NORTHERN STATES POWER COMPANY
' MINNF APOLIS, MINNESOTA Report Date: 9-3-81 Commercial Service Date: December 21,1974
> 10v;'40 5 0 5 e:cnie Ds Anocs oScoog
NORTHERN STATES POWER COMPANY PRAIRIE ISLAND NUCLEAR GENERATING PLANT - UNIT II c
i INSERVICE INSPECTION - EXAMINATION
SUMMARY
PRAIRIE ISLAND NUCLEAR GENERATING PLANT - UNIT II July 1 to July 13, 1981 MAINTENANCE OUTAGE INSPECTION PERIOD 2 i
i Report Date: 9-3-81 Prepared by: L C Dahlron, M&SP Specialist D B Hansen Assoc M&SP Engineer Commercial Service Reviewed by: f-ek-
/'A Date: December 21,1974 P M rumporu Superintendent Materials and Special Processes 7
Approved by:
/4 "
,2.%
P,g(WAnde(scn' i
deneral Superintendent Production Plant Maintenance l
INSERVICE INSPECTION - EXAMINATION
SUMMARY
PRAIRIE ISLAND NUCLEAR GENERATING PLANT - UNIT 2
- INDEX -
1.0 Introduction 2.0 Sumary of Results 3.0 Discussion of Examination Appendix A - ASME Class 1 Examination Inservice Inspection - Examination Sunrnary Tables:
)
Table S1.5 - Reactor Coolant Pumps Table II - Baseline Comparison Summary
)
Table III - Isometric' Summary i
Appendix B - ASME Clars 2 Examination No examinations scheduled this outage Appendix C - FSAR Augmented Examination
- No examinations scheduled this outage Appendix D - Seismic Bolting Examination
- No examinations scheduled this outage
)
Appendix E 1
Table I - Personal Listing Table II-Procedure Listing Table III-Equipment and Materials
)
1 Appendix F Form NIS-1, Owners' Data Report for Inservice Inspections j
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Page 1 of 1
INSERVICE INSPECTION - EXAMINATION
SUMMARY
PRAIRIE ISLAND NUCLEAR GENERATING PLANT - UNIT 2 July 1 to July 13, 1981
1.0 INTRODUCTION
This report is a summary of the examinations perfomed during the inservice inspection activities at the Prairie Island Nuclear Generating Plant - Unit 2.
The examinations were additional to the inservice inspections conducted for inspection period two.
The examinations were performed during the plants' reactor coolant pump maintenance outage from July 1 to July 13, 1981. Prairie Island - Unit 2 began commercial operation on December 21, 1974.
This report identifies the examination methods used, the examination report number; and summarizes the results for the examinations performed on reactor coolant pump #21.
2.0
SUMMARY
OF o.ECULTS The evaluation of all the results from the inservice examinations indicated that the integrity of the system has been maintained.
The only anomalies detected were several linear magnetic particle indications on the reactor coolant pump flange bolts. The indications appeared on two of the 24 flange bolts and were all axially oriented and on the bolt shank. One of the bolts had two indications, 3/8" and 1/2" long, that were lightly filed. This area was re-examined with no further indications. The other bolt had several indications ranging from 1/32" to 1/2" long. This bolt was replaced with a new flange bolt.
3.0 DISCUSSION OF EXAMINATION The examination plan focused on reactor coolant pump #21. The pump was disassembled for maintenance and repair and this allowed for a very thorough examination of the pump casing interior pressure retaining boundary, flange bolts, and seal house bolting.
The examination plan was based on the examination requirements of the ASME Boiler and Pressure Vessel Code Section XI,1974 Edition through and including the Summer 1975 Addenda, and com-l plied with Prairie Island's Technical Specification, Section TS 4.2.
The examination is in accordance with the program submitted to the ll-United States Nuclear Regulatory Commission on February 1,1978 entitled, "ASME Code Section XI Inservice Inspection and Testing Program and Information required for NRC Review of Requests for Relief from ASME Code Section XI Requirements."
The examination methods included ultrasonic, magnetic particle, and visual examination techniques. Magnetic particle examinations were performed using either a yoke and/or an A-C coil with wet flourescent Page 1 of 2
magnetic particles. All visual examinations were aided when necessary with artificial lighting and verified for adequacy with an 1M neutral grey card with a 1/32 inch black line. The examination procedures complied with the requirements of the 1974 Edition through and including the Summer 1975 Addenda of ASME Section XI. A listing of the procedures used for the examinations is shown in Table II of Appendix E.
The examination of the flange and seal house bolting utilized all three of the examination techniques. The bolts were cleaned and examined while they were disassembled from the pump. The examination of the reactor coolant pump casing was performed using underwater television cameras, lights, and a variety of manipulating devic'!s.
In conjunction with perfonning the examination of the entire pump casing, 'he underwater equipment was used to investigate c
for the presence of foreign material or loose parts in the cold leg and crossover leg.
Northern States Power Company contracted Westinghouse to perform cortions of the examinations. Hartford Steam Boiler Inspection and Insurance Company, representing ANI, provided the Authorized Inspection, All personnel involved in the performance or evaluation of examinations are listed along with their title, organization, and ASNT Level of certificatir.n in Table i of Appendix E.
Certifications for examination personnel are maintained on file by Northern States Power Company.
All examinations reports and documentation are maintained on file by Northern States Power Company. Table I of Appendices A identifies the examination report aumber(s) for each item examined. Many of the items identify more than one examination report because of the different types of examinations performed on the item.
Table I of Appendix A sumarizes all of the examinations that have been performed to date and identifies the amount that will be examined in the future to complete the ten year examination require-ments.
For retrieval purposes, the prefix of the inspection report number corresponds with the year that the inspection was performed.
The examination report numbers for this outage are prefixed with "81A".
Table II of Appendix A compares the baseline examination results with the results obtained during this examination. Table III of Appendix A identifies the isometric drawings that were used for the examinations. The personnel, procedures, equipment and materials that were used for the inspection are identified in the tables of Appendix E.
Appendix F contains the Form flIS-1, entitled "0wners" Data Report for Inservice Inspections".
Page 2 of 2
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APPENDIX A ASNE CLASS 1 - EIAMDIATION I
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A
NORTHERN STATES POWER CO.
TAILE S1.5 PRAIRIE ISLAND UNIT 2
PAGE 1
OF 3
INSERVICE INSPECTION-EXAMINATION
SUMMARY
MAJOR ITEM:
REACIOR CORE COOIANT PUMPS N ORSY SUB INSP.
R EQ'D.
AMT.
BTEM INSPECTION E.
N DES 9N ITEM PER.
AMT.
EXAM IDENTIFICATION REPORT NO.
GORY ITEM TO BE EXAMINED B5.1 B-G-1 PRESSURE RETAINING BOLTS AND AND STUDS, IN PIACE B5.3 (h 2 IN. DIA.)
8 BOLTS 1 11110 8 76-87 11 O 8
8 BOLTS 9111BU 16 78-67 111REE 8
PUMP B ONE 8
8 BOLTS 1 111RU 8 76-86
%D 8
8 BOLTS 9 'I1110 16 78-68 111REE ITTM B5.2 SEAL 1100SE BOLTING 3
PUMP A ONE 4
4 BOLTS 1 11110 4 76-89 iwo 4
4 BOLis 511110 8 78-69 111REE 4
PUMP B ONE 4
4 BOLTS 1 111RU 4 76-88 1NO 4
4 BOLIS 511110 8 78-70 111REE 4
B5.2 B-G-1 PRESSURE HETAINING BOLTS AND AND STUDS, WlEN REMOVED B5.3 (2 IN. DIA.)
PUMP A SEAL 110USE BOLTING INO 12 12 BOLT 1 1111U 12 81-46,47/81A-4,7 FLANGE BOLTING IWO 24 24 BOLT 1 11110 24 81A-1,2,3,5,6,6R PUMP B FLANGE BOLTING 111REE 24 SEAL llOUSE BOLTING
'I11REE 12 roa g g fin ronu no. ise.neos
NORTHERN STATES POWER CO.
TABLE S1.5 PRA:.73E ISLAND UNIT 2
PAGE 2
OF 3
INSERVICE INSPECTION-EXAMINATION
SUMMARY
M AJOR ITEM:
REACIOR OORE ODOIANT PUMPS E M SUB INSP.
R EQ'D.
AMT.
ITEM INSPECTION C
E.
AND DES I Tl N ITEM PER.
AMT.
EXAM IDENTIFICATION REPORT NO.
GOR)
ITEM TO BE EXAMINED B5.4 B-K-1 INTEGRALLY WEWED SUPPORTS PUMP A
'IND 3
3 SUPPORP A,B,C RELIEF NO. 47 81-129,131,130 POMP B
'IND 3
3 SUPPORP A,B,C 81-132,134,137
'IIIREE 3
B5.5 B-K-2 SUPPORP COMPONENIS*
- COINCIDENT WI'111 SEISMIC BOLTING PLEP A COIDN AND ONE 1
1 00m m 1 77-67,163,158 LATERAL SUPPOPTS
'I.O 1
1 00m m 2 80-181,107,174
'I11REE 1
PUMP B COIDN AND ONE I
1 00wm 1 77-64,162,161 LATERAL SUPPORPS
'IND 1
1 ODIDN 2 80-181,107,108
'111REE 1
B5.6 B-L-1 PUMP CASING _WEWS PUMP A
-NCNE-PUMP B
-NCNE-B5.7 B-L-2 PUMP CASINGS PUMP A or B
'I11REE 1
PUMP A
'IWD 1
1 PUMP CASING 81A-8 B5.8 B-P EXEMPTED COMPONEMIS
-NCNE-B5.9 B-G-2 PRESSURE RETAINING
-NCNE-BOLTING (< 2 IN. DIA )
ronu s 7-a47e e/7s ron u no. ass-s eo s PP9-B-3
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NORTHERN STATES POWER COMPANY TABLE l
PRAIRIE ISLAND UNIT II PACE l
0F 1 BASELINE COMPARISON
SUMMARY
i NSP NDE W BASELINE REPORT BASELINE ISI EXAMINATION COMPONENT /SYST2M ISO MET 110D IDENT.
NO.
INDICATIONS INDICATIONS LIMITATIONS l
REACTOR COOLANT PUMPS B 5.2 PRESSURE RETAINING j
A BOLTS AND STUDS, i
B 5.3 WHEN REMOVED i
Pump A 43 V,MT 12 BOLTS 81A - 7 N/A NONE NONE i
SEAL HOUSE BOLTS UT 12 BOLTS 81A - 4 NONE NONE NONE FLANGE BOLTS 44 V,MT 24 BOLTS 81A -5,6 N/A 2 BOLTS WITH NONE LINEAR INDICA-TIONS 4
l 81A 6R 1 BOLT REPLACED i
AND 1 BOLT WITH l
INDICATIONS FILED OFF j
UT 24 BOLTS 81 A-1,2, NONE NONE NONE
&3 i
B5.7 PUMP CASINGS
)
PUMP A V
INTERIOR 81A-8 N/A NONE NONE S/N 510 SURFACES i
i FORM NO. ISI-1003
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Table III
'NORIllERN STATES PNER 00.
PAGE 1
0F 4
PRAIRIE ISLAND LMIT 2 ISOMETRIC SENARY CLASS 1 REVISIm 00M M ENI' OR SYSTIN IDOP (B R 2-ISI-1 0
SEAL INJECTION (GENERAL VIEW)
A lb"62" A
1" 1 -2VC-21A 1
2-ISI-1A 0
A 2"
2-2VC-21A 3
2-ISI-1B 0
A 2"
2-2VC-21A 3
2-ISI-IC 0
A 2"
2-2RC-10A 3
2-ISI-2 0
CROSSOVER DRAIN 2-2RC-11A 3
A 2"
2-2RC-8A 3
2-ISI-3 0
KTD TAKEOFF COLD LEC A
2" 2-2RC-7A 3
2-131-4 0
RTD TAKEOFF HOT LEG A
2" 2-2SI-35A 3
2-ISI-5 0
SAFETY INJECTION HIGH HEAD A
3" 3-2RC-6A 4
2-ISI-6 0
RTD RETURN A&B 3"
l SPRAY TO PRESSURIZER (GENEPAL VIEW)
A 3"
3-2RC-5 4
2-1SI-7 0
A 3"
3-2RC-5 4
2-ISI-7A 0
2-ISI-7B 0
A 3"
3-2RC-5 4
2-ISI-7C 0
8 3"
3-2RC-5 4
2-ISI-7D 0
A 6"
6-2RC-13B 6
2-ISI-8 0
SAFETY INJECTION HIGH HEAD A
6" 6-2RC-13A 6
2-ISI-9 0
PLO-CAP 8',',
A 2-ISI-10 0
R11R TAKE OFF (GENERAL VIEW) 2-ISI-10A 0
8" 8-2RH-1A 8
2-ISI-10B 0
8"
-2RH-1A 8
2-ISI-10C 0
A 12" 2 - A 2-ISI-11 0
ACCUMULATOR DISCHARGE e
a 9
4 l
Table III NORTIIERN STATES POWER 00.
i PAE 2 0F 4 PRAIRIE ISIAND INIT 2 ISOMETRIC SLENARY NSP ISO LINE LIE
[ff - CAL.
REVISICN OCNPOENT OR SYSIDI IM i
NLNBER SIZE NLNBER STANDARD I
2-ISI-12 0
SEAL INJECTION (CENERAL VIEW)
B 1 "62" 2-ISI-12A 0
B 2"
2-2VC-21B 3
2-ISI-12B 0
B 2"
2-2VC-21B 5
2-ISI-12C 0
B l\\"
lh-2VC-21B 1
2-ISI-13 0
CilARCING LINE (CENERAL VIEW)
B 2"
l 2-ISI-13A 0
B 2"
2-2RC-17 3
2-ISI-135 0
B 2"
2-2VC-5 3
2-ISI-13C 0
B 2"
2-2VC-6 3
1 2-ISI-13D 0
8 2"
2-2VC-6 3
2-1 1-14 0
2" 2-2RC-8B 3
2-ISI-15 0
2" 2-2RC-7B 3
2-ISI-16 0
CROSSOVER DRAIN AND 1.ETDOWN B
2" 2-2RC-10B 3
2-2RC-IIB 3
2-2RC-12 3
2-ISI-17 0
RTD RETURN B
3" 3-2RC-6B 4
2-1S1-18 0
SAFETY INJECTION llICH llEAD B
6" 6-2RC-13D 6
2-ISI-19 0
PLO-CAP B
6" 6-2RC-13C 6
2-ISI-20 0
FilR TAKEOFF (CENERAL VIEW)
B l
2-ISI-20A 0
8 8"
8-2RC-15B 8
2-ISI-20B 0
B 8"
8-2Ril-18 8
2-ISI-20C 0
8 8"
8-2R11-1B 8
2-1S1-21 0
RilR RETURN B
10" 10-2SI-26 10 2-ISI-22 0
ACCUMULATOR DISCllARGE B
12" 12-2RC-16B 11 12-2SI-27B 11
Table III NOR11 TERN STATES POWER CD.
PAGE 3 0F 4 PRAIRIE ISIAND LNIT 2 IUNETRIC SlWARY REVISIO1 00bMNDE OR SYSTDI LOOP IBER 2-1S1-23 0
SAFETY INJECTION 111C11 llEAD B
2" 2-2SI-35B 3
2-ISI-24 0
AUXILIARY SPRAY 2"
2-2RC-19 3
2-2VC-4 3
2-ISI-25 0
REACTOR VESSEL SAFETY INJECTION A
2" 2-2SI-24A 3
2-ISI-26 0
REACTOR VESSEL SAFETY INJECTION B
2" 2-2SI-248 3
2-1S1-27 0
PRESSURIZER RELIEF A&B 3"
3-2RC-21 4
2-ISI-28 0
REACTOR VESSEL SAFETY INJECTION B
4" 4-2RC-148 5
8 6"
6-2RC-14B 6
B 6"
6-2SI-25B 6
2-ISI-29 0
REACTOR VESSEL SAFETY INJECTION A
4" 4-2RC-14A 5
A 6"
6-2RC-14A 6
A 6"
6-2SI-25A 6
2-ISI-30 0
PRESSURIZER SAFETY A
6" 6-2RC-20A 6
B 6"
6-2RC-20B 6
2-151-31 0
PRESSURIZER SURGE B
10" 10-2RC-4 10 2-ISI-32 0
REAC10R COOLANT A
29" 29-2RC-IA 15 A
31" 31-2RC-2A 15 A
27h" 27h-2RC-3A 15 2-ISI-33 0
29" 29-2RC-1B 15 B
31" 31-2RC-2B 15 8
27 "
27 -2RC-3B 15 2-ISI-34 0
REGENERATIVE HEAT EXCHANGER 6
e 2-ISI-35 0
PRESSURIZER SAFETY AND BELIEF EOZZLES e
a o
Table III
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i NORI11ERN STATES PCMER 00.
PAGE 4
OF 4
PRAIRIE IS!AND WIT 2 ISOMETRIC SLM4ARY LINE LINE IIT - CAL.
NSP ISO REVISIW 00MPWENT OR SYSTal IDOP SIZE hu4BER STN#1ARD hu4BER 2-ISI-36 0
PRESSURIZER 25A/16 2-ISI-37 0
STEAM GENERATORS A&B 25A 2-ISI-38 0
REACTOR VESSEL CONOSEAL BOLTING STUDS-17 2-ISI-39 0
REACTOR VESSEL STUDS, NUTS & WASilERS 2-ISI-40 0
REACTOR VESSEL N0ZZLES 2-ISI-41 0
REACTOR VESSEL HEAD WELD 25A 2-ISI-42 0
REACTOR VESSEL SilELL WELDS 1
2-ISI-43 0
RC PUMP SEAL llOllSING BOLTItic A&B 4
2-ISI-44 0
RC PUMP FLANCE BOLTING A&B 2-ISI-45 0
RC PUMP FLYWilEEL A&B 2-ISI-46 o
EXCESS LETDOWN HEAT 6
CL-1 EXCllANCER 2-ISI-47 0
REACTOR VESSEL CLOSURE CL-1 IIEAD CLAD PATCHES 2-ISI-48 0
REACTOR VESSEL CLAD CL-1 PATCH IDENTIFICATION
APPENDII C 75AR AUGMENTED ZZAMDL* ION i
NO EXAMINATIONS SCHEDULED THIS OUTAGE -
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APPENDIX B ASME CLASS 2 EXAMINATION NO EXAMINATIONS SCHEDULED THIS OUTAGE Page 1 of 1
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Ar.'ENDIX D SEISMIC BOLTING EXAMINATION NO EXAMINATIONS SCHEDULED THIS OUTAGE -
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Page 1 of 1
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APPENDIX E TABLE I
- PERSONNEL LISTING TABLE II
- PROCEDURE LISTING l
TABLE III
- EQUIPMENT AND MATERIALS l
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NORTHERN STATES POWER COMPANY APPENDIX E PRAIRIE ISLAND UNIT II TABLE I
PERSONNEL LISTING PAGE 1 of 1 ASNT LEVEL EXAMINER TITLE ORGANIZATION UT PT MT VT L.C.Dahlman M&SP Specialist NSP II II II(1)
D.B.Hansen Assoc.M&SP Engnr.
NSP III III III III (1)
J. Williams ANII Hartford Steam Boiler Insp. &
Insurance Co.
P.E.Bukes Technician W
II II IIA FOOTNOTES:
(1)
Inspection experience and NDE Qualifications were judged to be adequate to perform Visual Examinations in accordance with NSP-VT-1.
(2) Organization:
Westinghouse Nuclear Services Division P.O. Box 2728 Pittsburgh, PA 15230
i NORTilERN STATES POWER COMPANY APPENDIX E
PRAIRIE ISLAND UNIT II TABLE TT PROCEDURE LISTING PAGE 1 0F 1_
PROCEDURE NUMBER FIEi.D PLANT APPROVAL FIELD CllANGE AND REVISION CllANGE PROCEDURE TITLE DATE REMARKS CilANCE DESCRIPTION i
NSP-MT-2, REV. O N/A WET MAGNETIC PARTICLE l-8-81 NONE EXAMINATION NSP-UT-4, REV.1 N/A ULTRASONIC EXAMINATION 1-8-81 NONE i
0F STUDS, BOLTS AND NUTS i
NSP-VT-1, REV. 2 N/A VISUAL EXAMINATION 1-8-81 NONE l
I ISI-8, REV. 7 1
VISUAL EXAMINATION 8-29-80 1
ADDED RECORDING CRITERIA i
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NORTHERN STATES POWER COMPANY APPENDLX F
PRAIRIE ISLAND - UNIT 2 TABLE III EQUIPMENT AND MATERIALS PAGE 10F 1
MATERIAL OR TYPE OR CALIBRATION EQUIPMENT SERIAL NUMBER AT OR BATCH REMARKS ULTRASONIC:
NORTEC 131D S/N 360 CAL. 5-29-81 TRANSDUCERS:
NORTEC S/N - 6807 3/4" 0 2.25 MHZ NORTEC S/N - 6829 1/2" 0 3.5 MHZ MAGNETIC PARTICLE:
MAGNAFLUX YOKE S/N GTL-001 CAL.
7-7-81 ON SITE QUALIFICATION MAGNAFLUX C0IL S/N GTL-2 QUAL. 7-7-81 ON SITE QUALIFICATION BLAK-RAY METER S/N 15544 CAL. 2-27-81 MATERIALS ULTRASONIC LMT GEL BATCH NO.111778 COUPLANT e
_g 6
FO R NIS-1 l
M ORT FOR INSERVICE INSPE C ON i
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FORM NIS-1 OVNERS' DATA REPORT FOR INSERVICE IESPECTIONS (As Required by the Provisions of W : ASME Code Rules) 1.)
Owner NORTHERN STATES DOWFR COMPANY Address 414 NicollFT Mall MTNNFAP01 TS. MINN.
2.)
Piant PRARIE ISLAND NUCLEAR GENERATING PLANT, UNIT II
.ddress WELCH, MINNES0TA 3.)
Plant Unit II 4.)
Owner (Certificate of Authorization) --
5.)
Comercial Service Date 12-21-74 6.)
National Board Number for Unit --
7.)
Components Inspected Manu facturer Component or Manu facturer or Installer State or National Appurtenance or Installer Serial No.
Province No.
Board No.
B5.0 REACTOR CORE COOLANT PUMPS B5.2 & B5.3 PRESSURE RETAINING BOLTS AND STUDS, WHEN REMOVED PUMP A SEAL HOUSE WESTINGHOUSE FLANGE BOLTS WESTINGHOUSE B5.7 PUMP CASINGS PUMP A WESTINGHOUSE 510
+
ISI-1019, Rev. O Page 1 of 2
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FORM NIS-1 (back) 8.)
Examination Dates 7-1 -81 to 7-13-81 9.)
Inspe : tion Int erva11p_p1_74 to19.91_ga 10.) Abstract of Examinations.
Include a list of examinations and a statement concerning s tatus of werk required for current interval.
These examinations were performed durir.g a maintenance outage during the end of the Second Period of the First Ten Year Interval. The examinations completed the requirements for visual examination of the reactor coolant l
pump casings and for the flange and seal house bolting.
I 11.) Abstract of Conditions Noted.
The results of these examinations indicated that the integrity of these systems was maintained. The only anomalies detected were the linear magnetic particle indications ( oriented axially along the bolt shank) of the reactor coolant pump flange bolts.
12.) Abstract of Corrective Measures Recommended and Taken.
All anomalies were corrected. The linear indications on one flange bolt were lightly filed off and the other flange bolt was replaced. The i
new flange bolt and the bolt witn the indications filed off were examined with the same method that located the original indications.
We certify that the statements made in this report are correct and the examinations and corrective measures taken conform to th rules of the ASME Code, Sectio XI.
SM 198/
Signed
[b m B
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Date
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Owner Certificate of Authorization No. (if applicable)
M xpiratfon Date j
CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vecsel Inspectors and/or the Stace or Province of /Gewsefat.
and employed by b e.d t/ge.n dea Leset c d o f h W M df.
have inspected the com-ponents described in this Owner's Data Report during the period 766 L /ff!
to Uk'., // /F#,
i and s ta te tha t 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 tha requ3rements 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 personal injury or property damage or loss of any kind arising from or connected with this inspection.
Da te A v.,es t 20 19 91
/
^
/Tffsoector s Signature _
Commissions /2/8 Edd7, AIN 82/
F National Boar'd, State, Province & No.
ISI-lo20, Rev. o Page 2 of 2
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