ML20082A717

Rev 1 to ISI Rept Unit 1 Catawba 1992 Refueling Outage 6

ML20082A717
Person / Time
Site:	Catawba
Issue date:	03/01/1995
From:	DUKE POWER CO.
To:
Shared Package
ML20082A714	List: ML20082A711 ML20082A717
References
NUDOCS 9504040201
Download: ML20082A717 (20)

Text

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INSERVICEINSPECTION REPORT- l I

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UNIT 1 CATAWBA 1992 REFUELING OUTAGE 6.

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Location: 4800 Concord Road, York, SC 29745 NATIONAL BOARD NO.130 -

COMMERCIAL SERVICE DATE: JUNE 29,1985 .

t Owner: Duke Power Company 422 S. Church St.

Charlotte,NC 28201 Revision 1 l j Op V

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5 Prepared By: .

1-fl (/C Date '2 ~2 7~ k2I Reviewed By / - Date I-II-U

- Appmved By: .<d VM3W Date 3i CIb >

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- Copy No. 4 Assigned To NRC Document Cnritrol Controlled X Uncontrolled  !

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9504040201 950320 PDR ADOCK 05000413 Q PDR t  ;

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. TABLE OF CONTENTS

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4 Section Inic , Revision

1. Summary ofInservice Inspection 1 l ,

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- 2. Status of Required Inspections 1 l

3. Final Inservice Inspection Plan for Outage 6 1- .l

4. Results ofInspections Performed During Outage 6 1 l l l

5. Class 1 Inspection Results 1 l

6. Class 2 Inspection Results 0 .j i

7. Augmented Inspection Results 0

8. Personnel, Equipment, and Material Certifications 0

9. Problem Investigation Reports 0

10. Reference Documents 0

11. Class 1 and 2 Repairs and Replacements 0 I

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(~  ! 1.0 Summarv ofInservice Insnection t

V This report describes the Inservice Inspection of Duke Power Company's Catawba Nuclear Station Unit I during the 1992 Refueling Outage (also referred to as Outage 6, which is in the Third Inspection Period of the First Inspection Interval).

Included in this repon am the final Inservice Inspection Plan, the inspection results for each item, a summary for each category of examination and corrective action taken when unacceptable conditions were found. In addition, there is a section included for repairs and replacements required since June 9,1991.

1.1 Class 1 Insnection The Class 1 Inservice Inspection included examinations on the Reactor Vessel CRD llousing Welds, Steam Generator 1 A Channel Head to Tubesheet Weld and on Pressurizer Safety Nozzle To Safe End Butt Welds. Examinations were performed on Class 1 Dissimilar Metal Butt Welds of the Upper Head Injection System, and on circumferential butt welds in the Reactor Coolant (NC), and Safety Injection (NI) Systems. Also, examinations were performed on Reactor Coolant Pump IC Main Flange Bolting and INC-27 Valve Body Weld.

Visual examinations were performed on the Class 1 Pressure Boundary during System Leakage Tests. Reactor Coolant Pump IC Seal Gland and Seal Housing Bolts, Valves INC-1, INC-2 and INC-3 Studs and Nuts and the internal surfaces of Valves INC-27 and g INI-29 also were examined. In addition, visual examinations were performed on Class 1 Component Suppons of Reactor Coolant (NC), Residual Heat Removal (ND), Safety (V j Injection (NI) Systems and on Pressurizer Support Skin, Support Lugs, Upper Suppon and Lower Support Frame.

The Inconel 600 tubing in Steam Generators I A, IB,1C and ID was inspected by eddy current during Outage 6. The results are shown in the Catawba Unit 1 July 1992 Refueling Outage Eddy Current Examination Report.

Reportable indications were found on the Class 1 Inspections shown in this section. Inspection and evaluation data for each reportable indication is found in the Catawba Unit 1 July 1992 Refueling Outage Eddy Current Examination Repon.

A detailed description of each inspection is found in the final Inservice Inspection Plan in Section 3 of this repon. Results of each examination are found in Section 4.

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. 1 1.2 ' class 2 Insoection O/ The Class 2 Inspections included examinations on RHR Heat Exchanger I A Inlet Nozzle "A," and Outlet Nozzle "B" Nozzle to Shell Welds, Steam Generator 1B Main Steam Nozzle to Upper Head Weld and Steam Generator 1D Auxiliary Feedwater Nozzle to Shell Weld. Examinations were performed on circumferential butt welds of the Auxiliary Feedwater (CA), Main. Steam Supply to Auxiliary Equipment (SA), Main Steam (SM) and Main Steam Vent to Atmosphere (SV), Main Feedwater (CF) and Safety Injection (NI) 3 Systems. Examinations were performed on piping integrally-welded attachments of Main Feedwater (CF) System. .,

Visual examinations wem performed on the Class 2 Pmssure Boundary during System Functional Tests. Also, visual examinations were performed on Class 2 Component Supports of Auxiliary Feedwater (CA), Main Feedwater (CF), Refueling Water (FW),

Safety Injection (NI), Main Steam Supply to Auxiliary Equipment (SA) and Main Steam (SM) Systems.

A detailed description of each inspection is found in the final Inservice Inspection Plan in ,

Section 3 of this report. Results of each examination are found in Section 4.

1.3 Augmented Insnection Augmented Inspections at Catawba 1 consisted of Reactor Coolant Pump Flywheel examinations, Steam Generator Tubing examinations, Pipe rupture Protection examinations, and Thermal Stress Piping examinations. A detailed description of each examination is found in the final Inservice Inspection Plan in Section 3 of this report. l Results of each examination are found in Section 4.

1.4 Alternate insocction No alternate examinations were performed during Outage 6.

1.5 Identification Numbers [

Owner: Duke Power Company,422 S. Church Street, Charlotte, NC 28201 Plant: Catawba Nuclear Statien,4800 Concord Road, York, SC 29745 Plant Unit: 1 OwnerCertification of Authorization: N/A Commemial Service Date: 6/29/85 k

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Manufacturer Manufacturer orInstaller State or National

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Or Installer Serial No. Province No. Board No.

Reactor Vessel Westinghouse Duke Power Co. N/A N/A Pressurizer Westinghouse DCPT-1911 N/A W18589 Steam Generator 1A Westinghouse DCIrI'-1902 N/A Wl1300 Steam Generator 1B Westinghouse DCPT-1901 N/A W11299 Steam Generator IC Westinghouse DCIrl'-1904 N/A W11302 Steam Generator ID Westinghouse DCPT-1903 N/A WI1301 Reactor Coolant System Duke Power Co. NC N/A 126 Residual Heat Removal System Duke Power Co. ND N/A 115 Safety Injection System Duke Power co. NI N/A 128 Chemical and Volume Control System Duke Power Co. NV N/A 127 Auxiliary Feedwater System Duke Power Co. CA N/A 121 Feedwater System Duke Power Co. CF N/A 120 Refueling Water System Duke Power Co. FW N/A 91 Main Steam Supply to Auxiliary Equipment System Duke Power Co. SA N/A 114 Main Steam System Duke Power Co. SM N/A 122 Main Steam Vent to Atmosphere System Duke Power Co. SV N/A 96 Containment Spray A'

i System Duke Power co. NS N/A 118 d Safety Injection Accumulator Tank 1 A Westinghouse 0020 N/A 310 Safety Injection Accumulator Tank 1B Westinghouse 0019 N/A 309 Safety Injection Accumulator Tank 1C Westinghouse 0018 N/A 308 Safety injection Accumulator Tank 1D Westinghouse 0021 N/A 311 Unit 1 Duke Power Co. N/A N/A 130 1.6 The Reactor Vessel, Steam Generators, Pressurizer, Reactor Coolant System Piping, Reactor Coolant Pumps, and Safety Injection Accumulator Tanks were manufactured by Westinghouse electric Corporation, Pittsburgh, PA under purchase agreements from Duke Power Company.

All other systems were fabricated and installed by Duke Power Company,422 S. Church St., Charlotte, NC 28201.

1.7 -

Authorized Name: Nuclear R. N. Inservice McGill Insoector(s)kcb3 D W ",.g ' ; l Employee: The Hartford Steam Boiler Inspection and Insurance Company 200 Ashford Center North, Suite 300 n Atlanta, GA 30338 i i V l Page 3 Revision 1 l February 27,1995

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3 2.0 . Status of Reauired Insoections The completion status ofinspections required by the 1980 ASME Section XI Code,

']~ including addenda through Winter 1981, is sum.marized in this section. The requirements are listed by the ASME Section XI examination category as defined in Table IWB-2500-1 for Class 1 Inspections and in IWC-2500-1 for Class 2 Inspections. Augmented inspections are also included.

Class 1 InspectionsSection XI Inspections- Inspections Percentage Defferal Descriotion Reauired Comoleted Completed Allowed B-A Pressure Retaining 14 Welds 2.5 Welds 17.85 % Yes Weldsin Reactor

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l B-B Pressure Retaining 8 Welds 6 Welds 75 % No l Welds in Vessels Other than Reactor Vessel B-D Full Penetration 36 Inspections 18 Inspections 50 % Partial Welds of Nozzles in Vessels B-E Pressure Retaining 55 Welds 55 Welds 67 % No V Partial Penetration Welds in Vessels Pressure Retaining 46 Welds 32.5 Welds 70.65 % No Dissimilar Metal Welds B-G-1 Pressure Retaining 370 Items 246 Items 66.49 % Yes l Bolting Greater Than 2 Inch Diameter B-G-2 Pressure Retaining *59 Connections 42 Connections 71.18% No Bolting 2 Inches and

'ess in Diameter

• Total connections includes CRDMS that are disasser bled Ol Page1 Revision 1 February 27,1995 l

Qe Class 1 Inspections (Continued)

Section -

l~ Q XI Inspections Inspections Percentage Deferral

('ategory Description Required Completed Completed Allowed BH Integral Attachments 9 Attachments 5 Attachments "55.55 % No for Vessels B-J Pressure Retaining 201 Welds 157 Welds 78.10 % No L Welds in Piping B K-1 Integral Attachments None N/A N/A N/A l for Piping, Pumps and Valves l B L-1 Pressure Retaining None N/A N/A N/A

! Welds in Pump Casings B-L-2 Pump Casings None N/A N/A N/A B-M-1 Pressure Retaining 2 Welds 1 Weld 50 % Yes Welds in Valve Bodies B M-2 Valve Body > 4 in. 7 Valves 5 Valves 71.42 % Yes Nominal Pipe Size 2 Items No O

B-N-1 Interior of Reactor 3 Items 66.66 %

Vessel B-N-2 Integrally Welded Core None N/A N/A N/A Support Structures and Interior Attachments to Reactor Vessels i

B-N-3 Removable Core 1 Item None 0% Yes Support Structures B.O Pressure Retaining 3 Housings 3 Housings 100 % Yes Welds in Control Rod Housings B-P All Pressure Retaining No ,

Components System Leakage Test 160 Components 120 Components 75%

System Hydrostatic Test 20 Components O Components 0%

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Class 1 Inspections (Continued) l

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.Section 1 XI Inspections Inspections Percentage Deferral l Catecorv Descriotion Reauired Comoleted Comoleted Allowed i

B-Q Steam Generator Tubing 100% of Technical Specifications Met N/A Fl .01 Class 1 Component 280 Supports 214 Supports . 76.42 % No Supports l

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Class 2 Inspections U Section XI Inspections Inspections Pemratage Deferral Categorv Description Reauired Comoleted Completed Allowed C-A Pressure Retaining 9 Welds 6 Welds 66.66 % No Welds in Pressure Vessels C-B ' Pressure Retaining 6 Welds . 4 Welds 66.66 % No Nozzle Welds in Vessels C-C Integral Attachments 33 Attachments 25 Attachments 75.75% No for Vessels, Piping, Pumps and Valves C-D Pressure Retaining None N/A N/A N/A Bolting Exceeding 2 Inches in Diameter C-F Pressure Retaining 343 Welds 271 Welds 79 % No Welds in Piping C-G Pressure Retaining 25 Welds 15 Welds 60 % No Welds in Pumps and Valves C-Il All Pressure Retaining No Components System or Component 70 Components 69 Components 98.57%

FunctionalTest System Ilydrostatic Test 90 Components 0 Components 0%

Fl .02 Class 2 Component 568 Supports 437 Supports 76.93 % No Supports ,

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. Augmented Inspections

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ag Descriotion Percentwe Comnlete Reactor Coolant Pump Flywheels: 100% of Technical Specifications met Steam Generator Tubes on Preheater Section 100% of requirement for Outages 1,2 3,4,5 &

6.

Main Steam Pipe Rupture Protection 100% of requirement for Outages 1,2,3,4,5 &

6.

Containment Spray System 100% of requirement for Outages 1,2,3,4,5 &

6.

Thermal Stress Piping 100% of requirement for -

Outage 3. 4,5 & 6 Safety Injection Accumulator Nozzles 100% of requirement for Outages 5 & 6.

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.. , l 3.0'. - Fin'l a Inservice Insnection Plan for Ontwe 6 V The final ISI plan presented in this section lists all examinations credited for Outage 6 at Catawba 1. This includes ASME Section XI Class 1,2 and augmented inspections I

required by the plant technical specifications.

The information shown below is a field description for the reporting format included in this section of the report: ,

1 Item Number = ASME Section XI Tables IWB-2500-1 (Class 1),  !

IWC-2500-1 (Class 2), IWD-2500-1 (Class 3),

IWF-2500-1 (Class 1, Class 2 and Class 3), and Augmented Requirements ID Number = Unique Identification Number I Drawing Number = Location and/or Detail Drawing Locs. = Location Insp. Req. = Examination Technique - Magnetic Panicle,

- Dye Penetrant, etc.

Proc. Numbers = Examination Procedures MaterialType/ Grade = General Description of Material g Diam / Thick = Diameter / Thickness 1 N

Calib. Block - = Calibration Block Comments = General and/or Detail Description l

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PROGRAM : NISIRUNBOAIS102 DUKE POWEsTtXMFANY PAGE 1s [ <*- .

FILE: COO 7133 . QUALITY ASSURANCE DEPARTnENT DATE 2/27/95 .

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PUWT: CATAWBA UNIT 1 PRE-SERVICE AND IN-SERVICE INSPECTION SYSTEM KEY: ITEM NUMBER B06- CATAWBA 1 INSERVICE NSPECTION LISTNG OUTAGE 6 REVISION 1 .

INSP PROC. MATERIAL DIAM 1 CALIB COWENTS '

ITEM NUMBER ID. NUMBER DRAWNG NUMBERS LOCS. REO. NUMBERS TYPEGRADE . THICK BLOCK l

THIS PAGE LEFT BLANK TO AGREE WITH REVISION 1 i

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g 4.0 'Results of Insnections Performed Durine Outane 6 k The results of each inspection shown in the final ISI Plan (Section 3 of this report) are included in this section. The completion date and status for each inspection are shown. All inspections revealing reportable indications are described in further detail in Section 5,6, or 7 as applicable. >

The information shown below is a field description for the reponing format included in this -

section of the report-Item Number = ASME Section XI Tables IWB-2500-1 (Class 1),

IWC-2500-1 (Class 2), IWD-2500-1 (Class 3),

IWF-2500-1 (Class 1, Class 2 and Class 3), and Augmented Requirements ID Number = Unique Identification Number  ;

Inspection Date = Date of Examination  !

Inspection Status CLR = Clear REC = Recordable ,

REP = Reponable Inspection Limited i L = Limited  !

= No Geo. Ref. = Geometric Reflector  ;

I N = No Y = Yes l

Comments = General and/or Detail Description 1

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y DUKE POWER COhPANY PAGE . 3 PROGRAM: NISIRUND43AIS104 OUALITY ASSURANCE DEPARTENT DATE 2/27"15 -

, FEE: OOCM33 , . . .

PLANT: CATAWBA UNIT 1 PRE-SERVICE AND N-SERVICE INSPECTION SYSTEM '

KEY: ITEM NUMBER B06 CATAWBA 1 INSERWE NSPECTION RESULTS OUTAGE 6 REVISION 1 i

NSPECTION INSPECTION INSPECTION GEO. .

ITEM NUMBER ID NUMBER DATE STATUS LIMITED REF. COMENTS B06.180.003 1RCP-1C-F 07/21/92 CLR - N i

e 4 . .**,,.-**ei + e-~.- +-g---- - w - + + - = .+ - + , - - - * * + = + - --e- - 4

-m ---- -----A-__----= * -- w- *-e is--m -------m- ----J

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1 ) 5.0 - Class 1 Insnection Results '

LJ Examinations were perfomied during Outage 6 on the Reactor Vessel, Pressurizer, Steam  !

Generators I A, IB,1C and ID, Piping Welds of Upper Head Injection, Reactor Coolant (NC) and Safety injection (NI) Systems. Examinations were also performed on Reactor Coolant Pump IC, Valves and Supports.

5.1 Reactor Vessel Three (3) Reactor Vessel Control Rod Drive Housing Welds received a dye penetrant examination. No reponable indications were found.

5.2 Pressurizer Three (3) Pressurizer Nozzle to Safe-End butt welds received a dye penetrant examination.

No reponable indications were found.

5.3 Steam Generators Steam Generator l A Channel Head to Tubesheet Weld received an ultrasonic examination. i No reportable indications were found. j 5.4 Pipine

. ,,3 Dissimilar Metal Butt Welds:

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/ Four (4) dissimilar metal butt welds on the UHI Upper to Lower Adapter, nominal pipe size 4 inches and greater received an ultrasonic and a dye penetrant examination. No reponable indications were found.

Similar Metal Butt Welds:  !

Twenty-four (24) circumferential welds, nominal pipe size four inches and greater received ,

an ultrasonic and a dye penetrant examination. No reponable indications were found. l l

Four (4) circumferential welds, nominal pipe size less than four inches, received a dye  !'

penetrant examination. No reportable indications mere found.

5.5 Comoonent Suonorts Thirty (30) Class 1 Component Suppons received a visual examination as required by l ASME Section XI, Article IWF-2500-1. No reponable conditions were found i

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• 5.6 Steam Generator Tubine The Inconel 600 tubing in the four Westinghouse Model D3 recirculating steam generators (RSG's) A, B, C and D at Duke Power Company's Catawba Unit I were examined by eddy current techniques during July / August / September 1992. The tubing in the generators measures 0.750" nominal outside diameter x 0.043" nominal wall thickness. The examinations were perfonned by personnel from Duke Power Company, B&W Nuclear Services (BWNS) Company, Westinghouse, and Zetec, Inc., during the 6th refueling outage.

l One hundred percent (100%) of all tubes were inspected full-length with magnetic bias bobbin coil probes. One hundred percent (100%) of all tubes were also inspected at the  !

inlet and outlet tubesheet secondary face with Zetec's SM-15 Motorized Rotating Pancake l Coil (MRPC). Other areas of interest were also examined with an MRPC probe.

Sleeved portions of tubes were evaluated using a combination of bobbin coil and rotating crosswound techniques. The following is a summary of the results of the bobbin coil, MRPC, and iotating crosswound eddy current examinations for each generator. )

l RSG A.  ;

1 Eddy Current Examinations began in RSG A on 7/24S2 and were completed on 8/24S2.

4,554 tubes were examined full length by bobbin coil; 27 tubes contained ir.dications 40%

thru-wall (TW) or greater; 31 tubes contained indications 20-39% TW.

4,528 hotleg tubesheets and 4,554 coldleg tubesheets were examined with SM-15; 476 hotleg tubes,444 coldleg tubes, and 221 U-Bends were examined using MRPC.

37 hotleg (llL) and 54 coldleg (CL) rolled plugs were examined using MRPC.

26 sleeves were examined using Rotating Crosswound.

86 tubes were removed from service by plugging.

RSG B:

Eddy Current Examinations began in RSG B on 7/23B2 and were completed on 8/24B2.

4,630 tubes were examined full length by bobbin coil; 7 tubes contained indications 40%

TW or greater; 14 tubes contained indications 20-39% TW.

- 4,630 hotleg and coldleg tubesheets were examined by SM-15; 665 hotleg tubes,572 coldleg tubes, and 220 U-Bends were examined using MRPC.

27 hotleg and 34 coldleg rolled plugs were examined using MRPC.

29 tubes were removed from service by plugging.

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Eddy Current Examinations began in RSG C on 7/23B2 and were completed on 9/01S2.

4,480 tubes were examined full length by bobbin coil; 22 tubes contained indications 40%

TW or greater, 25 tubes contained indication 20-39% TW.

4,480 hotleg and coldleg tubesheets were examined by SM-15; 1,125 hotleg tubes,650 coldleg tubes, and 221 U-bends were examined using MRPC.

142 hotleg and 155 coldleg rolled plugs were examined using MRPC.

48 tubes were repaired by sleeving; 85 tubes were removed from service by plugging.

RSG D:

Eddy Current Examinations began in RSG D on 7/24S2 and were completed on 9/5/92.

4,541 tubes were examined full length by bobbin coil; 43 tubes contained indications 40%

TW or greater: 9 tubes contained indications 20-39% TW.

1 4,492 hotleg tubesheets and 4,541 coldleg tubesheets were examined by SM-15; 1,172 hotleg tubes,352 coldleg tubes, and 218 U-Bends were examined using MRPC.

72 hotleg and 89 coldleg rolled plugs were examined using MRPC.

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49 sleeves were examined using rotating crosswound.

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60 tubes were repaired by sleeving; 54 were removed from service by plugging.

1 5.7 Pumps Twenty - four (24) Main Flange Bolts on Reactor Coolant Pump 1C received an ultrasonic examination. No reportable indications were found.

Reactor Coolant Pump IC Seal Gland Bolts and Sealllousing Bolts received visual examinations. No reportable conditions were found. )

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. Twelve (12) Studs and Nuts on' Valves INC-1, INC-2 and INC-3 received a visual '  ;

- examination. No reponable conditions were found. .  !

-l Valve body weld on Valve 1NC-27 receivui an ultrasonic examination. No reponable .f}

indications were found. L; r

The intemal surface of valves INC-27 and INI-129 received a visual examination. No }

mponable conditions were found. .

5.9. Svstem I rakape Test -

The Class 1 Pirssure Bcundary was subjected to a system leakage test as required by. .

- ASME Section XI, Article IWB-5000. - No reponable conditions were found. ,,

5.10 nns 1 Renairs and Replacements ,

4- - Repairs and replacements for work performed from June 10,1991 to October 15,1992 are -

itemized in Section 11 of this repon. l I

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\ ,Y FORM NIS-1 OWNERS' DATA REPORT FOR INSERVICE INSPECTIONS As required by the Provisions of the ASME Code Rules

1. Owner: puke Power Company. 526 S. Church St.. Charlotte. NC 28201-1006 (Name and Address of Owned

2. Plant: Catawba Nuclear Station . 4800 Concord Road. York SC 29745 (Nameand Address of Plano

3. Plant Unit: 1 4. Owner Certificate of Authorization Of required) N/A

5. Commercial Service Date: 6/29/85 6. National Board Number for Unit HQ

7. Components Inspected:

Component or Manufacturer or Manufacturer or State or Natiosul Appurentance Installer Installer Serial Providence No. Board No.

No.

j] See Section 1 Paragraph 1.5 in the AttacE Report O -

l Nale:

I hpplemental shares in farm of hets, shsiches, or drawings rrisy be used prowWed (1) stre s S /g in, a 11 in,(2) Information in mems I thruugh 6 on this data report is included on each sheet, and Q) each sheet as numbered and the number of sheets a recorded at the top of the farrn i

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This NIS-1 Form supersedes the previous NIS 1 Form submitted with Rev. 0 of this report V

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FORM NIS-1 (back)

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8. Examination Dates 06/09/91 to 10/15/92 Inspection Interval from 06M/85 to 06/29/95

10. Abstract of Exarninations. Include a list of examinations and a statement concerning status of work required for cunent interval. See attached recort. i

11. Abstract of Conditions Noted. See attachM reoort. l

12. Abstract of Corrective Measures Recommended and Taken. See attached reoort. [

f We certify that the statements made in this report are correct and the examinations and corrective measures taken conform to be rules of the ASME Code,Section XI [

Date  ! 19 % Signed Duke Power Co. By ( ~ N 5 Owner Certificate of Authorization No.(if applicable) N/A Expiration Date MIA CERTIFICATE OF INSERVICE INSPECTION 1, the undersigned, holding a valid commission issued by the N..lonal Board of Boiler and ,

Pressure Vessel Inspectors and/or the State or Province of b- and employed by i T 'The liSBl&I Co. of have inspected the components described in this Owners Data Report during the period b ~ h * ' / o t/0 -/ 5 . And siaieihaii ihe besi of my knowledge and belief, the Owner has performed examineRons and taken corrective measures t

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 loss of any kind arising from or connected with this inspection.

Date b~/ 19 9 b u, ll'lM N . i Commissions Nb Inspector's Signature National Board, State, Province and No.

'The liartford Steam Doller Inspection & !nsurance Co.

200 Ashford Center North Suite 300 Atlants Ca.,30338  !

k This NIS 1 Form superse:1es the previous NIS-1 Form submitted with Rev.0 of this report

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