ML20217J169
| ML20217J169 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 03/24/1998 |
| From: | Barbour J, Cherry J, Hogge A DUKE POWER CO. |
| To: | |
| Shared Package | |
| ML20217J160 | List: |
| References | |
| NUDOCS 9804060213 | |
| Download: ML20217J169 (544) | |
Text
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~l 537 Pages FORM NIS-1 OWNER'S DATA REPORT FOR INSERVICE INSPECTIONS As required by the Provisions of the ASME Code Rules ,
- 1. Owner: Duke Enerav Corooration. 526 S. Church St.. Charlotte. NC 28201-1006 (Name and Address of Owner)
- 2. Plant: Catawba Nuclear Station. 4800 Concord Road. York. SC 29745 !
(Name and Address of Plant)
- 3. Plant Unit: 1 4. Owner Certificate of Authorization (if required) N/A
- 5. Commercial Service Date: 6/29/85 6. National Board Number for Unit lag
- 7. Components inspected:
Component or Manufacturer Manufacturer State or National Appurtenance Installer Installer Serial Province No. Board No. No. Section 1.1 in the attached report lists the Manufacturer / Installer Serial [' s - Number; State or Providence Number; and National Board Number for _ the systems and the NSSS Components. Detailed listings of the components inspected are contained in Sections 4 and 11. Note: Supplemental sheets in form of lists, sketches, or drawings may be used provided (1) size is 81 /2 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 and the number of sheets is recorded at the top of this form. O
{ } FORM NIS-1 (Back)
- 8. Examination Dates October 4,1996 to January 5,1998
- 9. Inspection Period identification: First Period of the Second interval
- 10. Inspection Interval identification: Second inservice inspection Interval
- 11. Applicable Edition of Section XI 1989 Addenda None
- 12. Date/ Revision of Inspection Plan: February 13,1996 / Revision 1
- 13. Abstract of Examinations and Test. Include a list of examinations and tests and a statement concerning status of work required for the inspection Plan. See Sections 3.0,4.0 and 11.0
- 14. Abstract of Results of Examination and Tests. See Sections 5.0 and 11.0
- 15. Abstract of Corrective Measures. See Section 8.0 We certify that a) the statements made in this report are correct b) the examinations and tests meet the inspection Plan as required by the ASME Code, Section XI, and c) corrective measures taken conform to the rules of the ASME Code, Section XI.
Certificate of Authorization No. (if applicable) N/A Expiration Date N/A l { } Date '3 N 19Q Signed Duke Energy Corp. By w Owner & CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel inspectors and the State of Province of NC employed by
- The HSBl&l Co.
of have inspected the components described in this Owners' Report g during the period October 4.1996 to March 23.1998. and state that to the best of my knowledge and l belief, the Owner has performed examinations and tests and taken corrective measures described in the l Owners' Report in accordance with the Inspection Plan and as required by the ASME Code, Section XI. By signing this certificato neither the inspector nor his employer makes any warranty, expressed or implied, concerning the examinations, test, and corrective measures described in this Owners' 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 n dMM Commissions NC 978 National Board, State, Province, and Endorsements hrligpector's Signature' l Date N-2$ 19997 !
- The Hartford Steam Boiler inspection & Insurance Co.
200 Ashford Center North Suite 300 l Atlanta, GA. 30338 I l
O INSERVICE INSPECTION REPORT UNIT 1 CATAWBA 1997 REFUELING OUTAGE 10 Location: 4800 Concord Road, York, South Carolina 29745 NRC Docket No. 50-413 NATIONAL BOARD NO.130
) Commercial Service Date: June 29,1985 Owner: Duke Energy Corporation 526 S. Church St.
Charlotte, N. C. 28201-1006 Revision 0 Date 3 28 Prepared By: ! > j Reviewed By: 2 Date 2 3 / 98 Approved By: hlL Date 3 ' 24 Cl8 , D Copy No. 2 Assigned To NRC Docueent Control Controlled X Uncontrolled
) CONTROLLED DISTRIBUTION Copy No. Assigned To Original Duke Power Company Ouality Assurance Technical Services 1 Catawba Work Control 2 NRC Document Control i UNCONTROLLED DISTRIBUTION 3 Hartford Steam Boiler Inspection and insurance Company (AIA) O
f-O TABLE OF CONTENTS Section - Title Revision 1.. GeneralInformation 0 L
- 2. Summary of Inservice inspections 0
- 3. Second Ten Year Interval Inspection Status 0 l 4. Final inservice inspection Plan 0
- 5. Results of Inspections Performed 0 l-
- 6. Reportable Indications O L
l .7. Personnel, Equipment, and Material Certifications 0
- 8. Corrective Action 0
- 9. Reference Documents 0
- l. .10. - Class 1 and 2 Repairs and Replacements 0
- 11. . Pressure Testing 0 t
l L> J l l O l L
O 1.0 GeneralInformation .
~ This report describes the Inservice Inspection of Duke Energy Corporation's Catawba Nuclear Station Unit 1 during the 1997 Refueling Outage (also referred.
.to as Outage 10), which is the last outage in the First Inspection Period of the Second Ten Year interval.
Included in'this report are the final inservice inspection Plan, the inspection results for each item, a summary for each category of examination and corrective 1 action taken when unacceptable conditions were found, in addition, there is a section included for repairs and replacements required since October 4,1996. 1.1 ' Identification Numbers Manufacturer State ore National item Manufacturer or Installer Province Board or Installer Serial No. No. No. Reactor Vessel Westinghouse Duke Power N/A N/A Co. Pressurizer Westinghouse DCPT-1911 N/A W18589 Steam Generator Babcock and O' 1A- Wilcox, Inc. 770101 N/A 151 Steam Generator Babcock and 769304 N/A 150-1B Wilcox, Inc. Steam Generator Babcock and 769302 N/A 147 1C Wilcox, Inc. Steam Generator Babcock and 769303 .N/A 149 1D Wilcox, Inc. Reactor Coolant - lonics, Inc. 1S-86P764 N/A 584 Pump 1A Reactor Coolant lonics, Inc. 2S-86P764 N/A 585 Pump 1B Reactor Coolant lonics, Inc. 3S-86P764 N/A 330 Pump' 1C Reactor Coolant lonics, Inc. 4S-86P764 N/A 331 Pump 1D O Refueling Outage Report EOC 10 Catawba Unit 1 ' Page 1 of 4 Revision 0 Section 1 March 23,1998
3 Identification Numbers Continued Manufacturer Manufacturer State or National
! tem or installer ' or Installer Province Board Serial No. No. No.
Reactor Coolant Duke Power Co. C-1NC N/A 126 System Safety injection Duke Power Co. C-1NI N/A 128 System Chemical and Duke Power Co. C-1NV N/A 127 .i Volume Control _ System Auxiliary Duke Power Co. C-1CA N/A 121 Feedwater System Feedwater Duke Power Co. C-1CF N/A 120 System Refueling Water Duke Power Co. C-1FW N/A 91 System Main Steam Duke Power Co. C-1SA - N/A 114 Supply to Auxiliary Equipment System Main Steam Duke Power Co. C-1SM N/A 122 System Main Steam Vent Duke Power Co. C -1SV N/A 96 to Atmosphere System Containment Spray Duke Power Co. C-1NS N/A 118 Systern Steam Generator Duke Power CO. C-1BB ~~N/A~- 111 Blowdown System L Steam Generator Duke Power Co. C-1BW N/A 104 Wet Lay Up Re-circulation System Diesel Generator Duke Power Co. C-1FD N/A 100 Fuel Oil System Component Duke Power Co. C-1KC N/A 129 Cooling System Residual Heat Duke Power Co. C-1ND N/A 115 Removal System Turbine Exhaust Duke Power Co. C-1TE N/A 113 System
' Refueling Outage Report EOC 10 Page 2 of 4
- Catawba Unit 1 Revision 0 Section 1 March 23,1998 u.
1 I e s, L,) Identification Numbers Continued i Manufacturer Manufacturer State or National item or Installer or installer Province Board Serial No. No. No. Diesel Generator Duke Power Co. C-1VN N/A 98 Starting Air System Diesel Generator Duke Power Co. C-1KD N/A 99 i Cooling Water i System I Spent Fuel Cool;1g Duke Power Co. C-1KF N/A 103 k System Diesel Generator { Duke Power Co. C-1LD N/A 105 Lube Oil System Nuclear Sampling Duke Power Co. C-1NM N/A 124 System Containment Duke Power Co. C-1 NW N/A 125 Penetration Valve injection Water System Nuclear Service Duke Power Co. C-1 RN N/A 117
- Water System (j'
Diesel Generator Duke Power Co. C-1VG N/A 95 Starting Air System Liquid Waste Duke Power Co. C1WL N/A 119 Recycle System Control Area Chil- Duke Power Co. C-1YC N/A 106 led Water System Seal 1Nator Pall Trinity Micro 1 A 29652 N/A 15626 Injection Filter Corporation 1B 29653 N/A 15627 Volume Control Lamco 452 N/A 183 Tank Industries Inc. Seal Water Heat Atlas industrial 3620 N/A 2976 Exchanger Manufacturing Company Regenerative Heat Joseph Oat 2255-1 A1 N/A 869 Exchanger Corporation Residual Heat Joseph Oat 1A 2267-3A N/A 846 Removal Heat Corporation 1B 2267-3B N/A 847 Exchanger Containment Spray Yuba Heat 1 A 74-N-008-2A N/A 3324 Heat Exchanger Transfer Corp. 1B 74-N-008-28 N/A 3325 ! /
'd Refueling Outage Report EOC 10 Page 3 of 4 Catawba Unit 1 Revision 0 Section 1 March 23,1998
i identification Numbers Continued Manufacturer State or National item - Manufacturer or Installer Province Board or Installer Serial No. No. No. Excess Letdown Atlas Industrial 3196 N/A 2574 ; Heat Exchanger Manufacturing Company ; Residual Heat Ingersol- Rand 1 A 077645 N/A 231 Removal Pump 1B 077646 N/A 232 Containment Spray Bingham - 1 A 230340 N/A 213 ! Pump Wiliamette 1B 230341 N/A 214 Safety injection Pacific Pumps 1 A 49359 N/A 232 Pump 1B 49360 N/A 233 Centrifugal Pacific Pumps 1 A 49778 N/A 256 Charging Pump 1B 49779 N/A 259 1.2 Authorized Nuclear Inservice inspector (s) G) Name: R. N. McGill Employer: The Hartford Steam Boiler Inspection & Insurance Company Business The Hartford Steam Boiler inspection & Insurance Company Address: 200 Ashford Center North Suito 300 Atlanta, GA 30338 i i l O Refueling Outage Report EOC 10 Page 4 of 4 l l Catawba Unit 1 Revision 0 l Section 1 March 23,1998 l l l
},
2.0 Summarv ofInsertIce !nsoections ' The information shown below provides an abstract of ASME Section XI Class 1, Class 2, and Augmented items scheduled and examined during Outage 10 at Catawba Nuclear Station. 2.1 Cissa 1 Insoections Examination Category B-A Pressure Retaining Welds in Reactor Vessel item Total 5xamined Number Description Duri Outa e B01.010 Shell Welds J B01.011 Circumferential 0 B01.012 Longitudinal 0 B01.020 Head Welds .. 3 B01.021 Circumferential 1 B01.022 Meridional Welds 0
, 801.030 Shell to Flange Welds 1 C
B01.040 Head to Flange Welds 1 N B01.050 Repair Welds I. 4: B01.051 Beltline Region NA TOTALS 3 l 1 ri G i Refueling Outage Report EOC 10 Page 1 of 20 Catawba Unit 1 Revision 0 Section 2 March 23,1998 ) l J
Examination Category B-B Pressure Retaining Welds in Vessels Other Than Reactor Vessels C' item TotalExamined Number Description During Outa e l E Pressurizer a g$ c
;- V:
B02.010 Shell to Head Welds ?,+ ' l r:jls Mh B02.011 Circumferential 0 B02.012 Longitudinal 0 l .m B02.020 [ Head Welds N B02.021 Circumferential NA B02.022 Meridional NA Steam Generator #, a
???PQ$ ff;Mi;j;py?gl;}l (Primary Side) Y:?'sf & "
l '$' B02.030 l Head Welds li ' W ^ B02.031 Circumferential NA /~N B02.032 Meridional NA u B02.040 Tubesheet to Head Weld 1 Heat Exchangers ._; >
,w .
)
(Primary Side) 1% * ' w .! .. , B02.050 Head Welds 'Q$q$p B02.051 Circumferential NA B02.052 Meridional NA W ifWMQ Heat Exchangers + Gh&hNi$$0A} (Primary Side)- SheII W. B02.060 Tubesheet to Head Weld NA B02.070 Longitudinal Welds NA B02.080 Tubesheet - to - Shell Welds NA TOTALS 1 O Refueling Outage Report EOC 10 Page 2 of 20 Catawba Unit 1 Revision 0 Section 2 March 23,1998 1
)
Examination Category B-D Full Penetration Welds of Nozzles in Vessels inspection Program B ltem TotalExamined Number . Durin Outa Reactor Vessel B03.090 Nozzle to Vessel Welds' 2 B03.100 Nozzle inside Radius Section' 4 Pressurizer B03.110 Nozzle to Vessel Welds 2 B03.120 Nozzle inside Radius Section 2 (Pr S B03.130 l Nozzle to Vessel Welds NA B03.140 Nozzle inside Radius Section 0 ) Heat Exchangers O (Primary Side) O B03.150 Nozzle to Vessel Welds NA B03.160 Nozzle Ins:de Radius Section NA TOTALS 10
' Reference Request for Relief 94-05 in Section 9.0 of this Report.
Examination Category B-E Pressure Retaining Partial Welds in Vessels REFERENCE SECTION 11.0 of This Report O Refueling Outage Report EOC 10 Page 3 of 20 Catawba Unit 1 Revision 0 l Section 2 March 23,1998 l
Examination Category B-F Pressurc Retaining Dissimilar Metal EWs O 1 l item TotalExamined Number Description During Outage Reactor Vessel .^. .. Nominal Pipe Size 4" or Larger B05.010 Nozzle to Safe End Butt Welds 8 Nominal Pipe Size Less Than 4" B05.020 Nozzle to Safe End Butt Welds NA
. Nozzle - to - Safe End Socket 805.030 Welds -
NA
; m.c- - --
N 3 Pressurizer ' Nominal Pipe Size 4" or Larger 805.040 Nozzle to Safe End Butt Welds 2 Nominal Pipe Size Less Than 4" B05.050 1 Nozzle to Safe End Butt Welds NA B05.060 Nozzle-to-Safe End Socket Welds NA Steam Generators >
. v @'
- Nominal Pipe Size 4" or Larger B05.070 Nozzle to Safe End Butt Welds 0 l Nominal Pipe Size Less Than 4"
] - B05.080 l Nozzle to Safe End Butt Welds Nozzle - to - Safe End Socket NA B05.090 Welds . .. NA
)l Heat Exchangers Nominal Pipe Size 4" or Larger l ~'
B05.100 Nozzle to Safe End Butt Welds NA l Nominal Pipe Size Less Than 4" B05.110 l Nozzle to Safe End Butt Welds NA - Nozzle- to -Safe End Socket B05.120 IWelds NA l A i
)
Refueling Outage Report EOC 10 Page 4 of 20 Catawba Unit 1 Revision 0 Section 2 March 23,1998
Examination Category B-F (Continued)- Item Total Examined Number Description During Outage
-e , ?<
Piping "n. *& ' Nominal Pipe Size 4" or Larger B05.130 Dissimilar Metal Butt Welds 8 Nominal Pipe Size Less Than 4" I B05.140 Dissimilar Metal Butt Welds NA Dissimilar Metal Socket I 805.150 Welds NA TOTALS 18 O O Refueling Outage Report EOC 10 Page 5 of 20 Catawba Unit 1 Revision 0 Section 2 March 23,1998
Examination Category B-G-1 Pressure Retaining Bolting Greater 7 Than 2" in Diameter Item TotalExamined Number Description During Outage Reactor Vessel .: . . . . B06.010 Closure Head Nuts 18 B06.020 Closure Studs, (in place) NA i Closure Studs, (when B06.030 removed) 18 B06.040 Threads in Flange 0 B06.050 18 Pressurizer "_. % B06.060 Bolts and Studs NA Flange Surface, (when 806.070 connection disassembled) NA B06.080 hnd Washers NA
;"if ,, .lM Steam Generators ?: ' .
)
B06.090 Bolts and Studs 0 Flange Surface, {when B06.100 connection disassembled) 8 { B06.110 0 Heat Exchangers 'O , B06.120 Bolts and Studs NA Flange Surface, (when B06.130 connection disassembled) NA B06.140 h NA Piping ' T. B06.150 Bolts and Studs NA ; Flange Surface,(when B06.160 connection disassembled) NA B06.170 Nuts, Bushings and Washers NA l Refueling Outage Report EOC 10 Page 6 of 20 Catawba Unit 1 Revision 0 Section 2 March 23,1998
j Examination Category B-G-1 (Continued) ) - (~\ ltem j
\}~ TotalExamined <
Number Descri tion Durin Outa.e Y 95fkV Pumps 1l$%lkt%QEW) V::n.f.:4 1 B06.180 Bolts and Studs 1 j Flange Surface,(when B06.190 l connection disassembled) O B06.200 Nuts, Bushings and Washers NA 1 d yp wvm , eg%g M s h$g$$jg@q:q dw1 Valves , B06.210 Bolts and Studs NA l Flange Surface, (when B06.220 l connection disassembled) NA B06.230 Nuts, Bushings and Washers NA TOTALS 63 ( $ V
)
l Refueling Outage Report EOC 10 Page 7 of 20 Catawba Unit 1 Revision 0 Section 2 March 23,1998
)
Examination Category B-G-2 Pressure Retaining Bolting,2" j and Less in Diameter Item TotalExamined Number Description During Outage Y \ $. Reactor Vessel ' B07.010 Bolts, Studs, and Nuts NA Pressurizer 807.020 Bolts, Studs, and Nuts O M Steam Generators .. ... . 1 B07.030 OM Heat Exchangers
' I.hj('.
B07.040 Bolts, Studs, and Nuts NA q :..- w - p ^$ Piping . li#: eg B07.050 Bolts, Studs, and Nuts O Pumps B07.060 Bolts, Studs, and Nuts 0 Valves _ . .. . :: ? B07.070 Bolts, Studs, and Nuts 0 y9y ;ggyg] x M CRD Housings Bolts, Studs, and Nuts (when B07.080 housing disassembled) 0 TOTALS 0 l l i O Refueling Outage Report EOC 10 Page 8 of 20 Catawba Unit 1 Revision 0 Section 2 March 23,1998
Examination Category B-H integral Attachments for Vessels .(q
') Item Yotal Examined Number M . , . . ., -
)
Reactor Vessel .{ . . Integrally Welded B08.010 Integrally Welded B08.020 Integrally Welded B08.030 t mjN d .. Integrally Welded B08.040 Attachments NA TOTALS 2 Examination Category B-J Pressure Hetaining Wolds in Piping (3 Q ltem Number Description TotalExamined During Outage Nominst Pipe Size 4"or *:
- B09.010 Larger i B09.011 Circumferential Welds 6 B09.012 Longitudinal Welds
- NA NominalPipe Size Less &
~
,( i B09.020 Than 4" , W
B09.021 Circumferential Welds O B09.022 Longitudinal Welds NA
' Reference Code Case N-524 " Alternative Examination Requirements for Longitudinal Welds in Class 1 and 2 Piping Section XI, Division 1".
O Refueling Outage Report EOC 10 Page 9 of 20 Catawba Unit 1 Revision 0 Section 2 March 23,1998
Examination Category B-J (Continued) / (3) Item Number Description Total Examined During Outage Branch Pipe Connection B09.030 Welds Nominal Pipe Size 4" or B09.031 Larger 0 Nominal Pipe Size Less B09.032 Than 4" 2 B09.040 Socket Welds 0 TOTALS 8 Examination Category B-K-1 Integral Attachments for Piping, Pumps and Valves item TotalExamined Number Description During Outage p x- __c [hk{'~' ._ ' = - . - - Piping <
~
N Integrally Welded B10.010 Attachments NA
! jD 4/w %%l,lg%g%
.a :
,$?hh d Pumps %{$
T: f'\v; Integrally Welded B10.020 Attachments NA hMI;( 4it;;g$37. 4 . w :n )i.V T i., Valves Integrally Welded B10.030 Attachments NA TOTALS NA Refueling Outage Report EOC 10 Page 10 of 20 Ca'.awba Unit 1 Revision 0 Section 2 March 23,1998
l l Examination Category B-L-1, B-M-1 Pressure Retaining Welds in (q) Pump Casings and Valve Bodies Examination Category B-L-2, B-M-2 Pump Casings and Valve Bodies item TotalExamined Number Description During Outage j.h$f-]f.;i;f,jf
. , , . - A . f e. ..' . , , .
I' Pumps Pump Casing Welds B12.010 (B-L-1) NA B12.020 Pump Casing (B-L-2) 0
, h i.9 R.; ; ; . +
g$YNl-]l0.ij,?$, l Valves Valves, Nominal Pipe Size B12.030 Less than 4" Valve Body Welds NA (B-M-1) Valves, Nominal Pipe Size 4" B12.040 or Larger Valve Body Welds 0
)
(B-M-1) i Valve Body, Exceeding 4" B12.050 Nominal Pipe Size (B-M-2) 1 Totals 1 V(3 i l I l i i I l l O Refueling Outage Report EOC 10 Page 11 of 20 Catawba Unit 1 Revision 0 Section 2 March 23,1998 j
Examination Category B-N-1 Interior of Reactor Vessel p B-N-2 Integrally Welded Core Support Structures 'y) and Interior Attachments to Reactor Vessels B-N-3 Removable Core Support Structures item . TotalExamined Number _ Description During Outage Reactor Vessel _ _ _ _ l? ' B13.010 h . 1 Reactor Vessel (PWR) . :. .. . . Interior Attachments Within B13.050 Beltline Region (B-N-2) NA I B13.060 I interior Attachments Beltline Region (B-N-2) Beyond 0 l Core Support Structure l B13.070 (B-N-3) 0 TOTALS 1 Examination Category B-O Pressure Retaining Welds in Control Rod Housings O l'em Number Descri tion Mo TotalExamined m m Reactor Vessel . . ; l. ?N o l
)
B14.010 Welds in CRD Housing 0 TOTALS 0 Examination Category B-P All Pressure Retaining Components Reference Section 11.0 of This Report i 1 l V Refueling Outage Report EOC 10 Psge 12 of 20 Catawba Unit 1 Revision 0 Section 2 March 23,1998
p Examination Category B-Q Steam Generator Tubing item Total Examined Number Description During Outage Steam Generator Tubing in B16.010 Straight Tube Design NA Steam Generator Tubing in B16.020 U-Tube Design NA TOTALS NA l I Examination Category F-A Class 1 Component Supports I (Code Case N-491) Item Total Examined Number Description During Outage Class 1 Piping Supports f F01.010 (One- Directional) 1 { Class 1 Piping Supports l F01.011 (Multi- Directional) 2 l Class 1 Piping Supports I F01.012 (Thermal Movement) 3 Class 1 Supports other than p F01.040 Piping 0 V F01.050 Class 1 Snubbers' NA ) TOTALS 6
' Steam Generator Tubing is examined and documented by the Diversified Services Group of The Electric System Support Department as required by the Station Technical Specifications and is not included in this report.
Reference Request for Relief 95-05 in Section 9.0 of this report. l
)
Refueling Outage Report EOC 10 Page 13 of 20 Catawba Unit 1 Revision 0 Section 2 March 23,1998
y j
, 2.2 CIsss 2 Insoections Examination Category C-A Pressure Retaining Welds in Pressure Vessels item TotalExamined Number Description During Outage C01.010 Shell Circumferential Welds 2 C01.020 Head Circumferential Welds 2 l C01.030 Tubesheet - to - Shell Weld 1 !
TOTALS 5 Examination Category C-B Pressure Retaining Nozzle Welds in Vessels item . Total Examined Description k Number During Outage i Nozzles in Vessels S % In. ;gl~$ yn~ ' (~% CO2.010 Nominal Thickness Y' :*% L - (. Nozzle - to - Shell (or Head) CO2.011 , Weld 0 Nozzles Without Q%, ,; ; CO2.020 Reinforcing Plate in ;*% Vessels > % In. Nominal 1 g@ l,lh~ ,' Thickness % Nozzle - to - Shell (or Head) CO2.021 Weld 2 Nozzle inside Radius CO2.022 Section 1 l l 4 O V Refueling Outage Report EOC 10 Page 14 of 20 f Catawba Unit 1 Revision 0 Section 2 March 23,1998
Examination Category C-B (Continued) Item TotalExamined Number Description During Outage Nozzles With Reinforcing CO2.030 Plate In Vessels > % In. \ Nominal Thickness
- l Reinforcing Plate Welds to I CO2.031 Nozzle and Vessel NA Nozzle to Shell(Head) Welds (
CO2.032 When inside of Vesselis NA { Accessible ) Nozzle - to - Shell (or Head) CO2.033 Welds NA When inside of Vesselis ! Inaccecsible l TOTALS 3 Examination Category C-C Integral Attachments for Vessels, Piping, Pumps, and Valves j Item TotalExamined Number Description During Outage M Pressure Vessels Integrally Welded C03.010 Piping .. .. Antegrally Weided , C03.020 l Pumps . Integrally Welded J C03.030 Attachments 0 Valves Integrally Welded l C03.040 I Attachments NA TOTALS 0 l l n 'J Refueling Outage Report EOC 10 Page 15 of 20 Catawba Unit 1 Revision 0 Section 2 March 23,1998 i
g Examination Category C-D Pressure Retaining Bolting Greater Than 2" t in Diameter item Total Examined Number M Pressure Vessels C04.010 Piping .W :Y C04.020 _NL_9 ;m. Pumps ,M Ng. C04.030 __NL
;.c, & ?
~
y ,, , C04.040 Bolts and Studs NA TOTALS NA Examination Category C-F-1 Pressure Retaining Welds in Austenitic Stainless Steel or High Alloy Piping item TotalExamined Number Description During Outage Piping Welds y 3/8 in. C05.010 Nominal Wall Thickness for , W Piping > NPS 4 C05.011 Circumferential Weld 4 5 C05.012 Longitudinal Weld NA
- Reference Code Case N-524 " Alternative Examination Requirements for Longitudinal Welds in Class 1 and 2 Piping Section XI, Division 1".
Refueling Outage Report EOC 10 Page 16 of 20 Catawba Unit 1 Revision 0 Section 2 March 23,1998
,o Examination Category C-F-1 (Continued) Item TotalExamined Number Description During Outage Piping Welds > 1/ Sin. ii% m C05.020 Nominal Wall Thickness for ;" *Q[ Piping g NPS2 ands " NPS 4 :& ^N C05.021 Circumferential Weld 6 C05.022 Longitudinal Weld NA C05.030 Socket Welds 16 Pipe Branch Connection of ! C05.040 Branch Piping ;> NPS 2 -
- 1 C05.041 Circumferential Weld - 0 8
C05.042 Longitudinal Weld NA TOTALS 26 Examination Category C-F-2 Pressure Retaining Welds in Carbon or Low f Alloy Steel Piping item Total Examined Number Description During Outage Piping Welds y 3/8 In. ,
"y C05.050 Nominal Wall Thickness for Piping > NPS 4 C05.051 Circumferential Weld 7 5
C05.052 Longitudinal Weld NA 8 Reference Code Case N-524
- Alternative Examination Requirements for Longitudinal Welds in Class 1 and 2 Piping Section XI, Division 1".
O Refueling Outage Report EOC 10 Page 17 of 20 Catawba Unit 1 Revision 0 Section 2 March 23,1998
Examination Category C-F-2 (Continued) t O item Total Examined Number Description During Outage Piping Welds > 1/S In. v:: C05.060 Nominal Wall Thickness for # ,; f ,, Piping g NPS2 ands '
'_' , 10 .
NPS 4 ^- < C05.061 Circumferential Weld NA 7 C05.062 Longitudinal Weld NA C05.070 Socket Welds NA Pipe Branch Connections a, y3 % C05.080 of Branch Piping > NPS 2 ^*' C05.081 Circurnferential Weld 0 7 C05.082 Longitudinal Weld NA TOTALS 7 Examination Category C-G Pressure Retaining Welds in Pumps and Valves item Total Examined Number M Pumps C06.010 NA Valves l n C06.020 Valve Body Welds 3 TOTALS 3 Reference Code Case N-524
- Alternative Examination Requirements for Longitudinal Welds in Class 1 I and 2 Piping Section XI, Division 1". )
i Refueling Outage Report EOC 10 Page 18 of 20 Catawba Unit 1 Revision 0 Section 2 March 23,1998
l I Examination Category C-H All Pressure Retaining Components Reference Section 11.0 Of This Report Examination Category F-A Class 2 Component Supports (Code Case N-491) Item TotalExamined Number Description During Outage Class 2 Piping Supports ! F01.020 (One- Directional) 17 Class 2 Piping Supports
' F01.021 (Multi- Directional) 6 Class 2 Piping Supports F01.022 (Thermal Movement) 7 Class 2 Supports other than j F01.040 Piping 2 l F01.050 Class 2 Snubbers a NA TOTALS 32 s
See Request for Relief 95-05 in Section 9.0 of this report. l l I 4 O Refueling Outage Report EOC 10 ! l Page 19 of 20 Catawba Unit 1 Revision 0 Section 2 March 23,1998 i (~
l 2.3 AuamentedInsoections ltem TotalExamined Number Description During Outage Reactor Coolant Pump G01.001 Flywheels 2 Postulated Pipe Failures Main G02.001 Steam System 0 Thermal Stress Piping (NRC G03.001 Bulletin 88-08) 0 TOTALS 2 A detailed description of each examination listed in Sections 2.1 through 2.3 are located in Section 4.0 of this repod. Results of each examination are located in Section 5.0 of this repod. O O Refueling Outage Report EOC 10 Page 20 of 20 Catawba Unit 1 Revision 0 Section 2 March 23,1998
3.0 Second Ten YearIntervalInsoection Status , The completion status of inspections required by the 1989 ASME Section XI-Code, with No Addenda is summarized 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 Table IWC-2500-1 for Class 2 Inspections. Augmented inspections are also included. Class 1 Inspection Examination Description Inspections inspections Percentage Deferral Category Required Completed Completed Allowed
- B-A Pressure Retaining Wek$s in 14 2.5 17.86 % Yes Reactor Vessel B-B Pressure Retaining Welds in 5 1 20% No Vessels Other than Reactor Vessel B-D Full Penetration Welds of 36 10 27.78 % Partial -
Nozzles in Vessels B-E Pressure Retaining Partial Reference Section 11.0 Of This Report Penetration Welds in Vessels t B-F Pressure Retaining 38 12.67 33.34 % No Dissimilar Metal Welds B-G 1 Pressure Retaining Bolting 248 81 32.66 % Yes Greater than 2 Inch Diameter B-G-2 Pressure Retaining Bolting 2 22 31.82 % No inches and Less in Diameter B-H integral Attachment for 5 1 20% No Vessels B-J Pressure Retaining Welds in 223 64 28.70 % No Piping
- Deferral of inspection to the end of the interval as allowed by ASME Section XI Table IWB 2500-1.
s d Refueling Outage Report EOC 10 Page 1 of 4 Catawba Unit 1 Revision 0 Section 3 March 23,1998
I D - (V Examination Description Inspections Inspections Percentage Deferral Category Required Completed Completed Allowed '* B-K 1 Integral Attachments for None N/A N/A N/A Piping, P"mps and Valves - B-L 1 Pressure Retaining Welds in None N/A N/A N/A Pump Casings B-L-2 Pump Casings 1 0 0% Yes B-M 1 Pressure Retaining Welds 2 0 0% Yes in Valve Bodies B-M-2 Valve Bodies " 7 4 57.14 % Yes B-N-1 Interior of Reactor Vessel 3 1 33.33 % No B-N-2 Integrally Welded Core 2 0 0% Yes Support Structures and Iriterior Attachments to Reactor Vessels B-N 3 Removable Core Support 1 0 0% Yes Structures B-0 Pressure Retaining Welds 3 0 0% Yes (V9 in Control Rod Housings B-P All Pressure Retaining Reference Section 11.0 of This Report Components B-O Steam Generator Tubing " N/A N/A N/A N/A FA Class 1 Component 68 19 27.94 % No Supports F01.010, F01.011, F01.012 & F01.040 (Code Case N-491)
Deferral of inspection to the end of the interval as allowed by ASME Section XI Table IWB-2500-1
" Reference ASME Section X', Paragraph IWB-2412, inspection Program B, (a).
'* Steam Generator Tubing is examined and documented by the Diversified Services Group of The Electric System Support Department as required by the Station Technical Specifications and is not included in this report.
O Refueling Outage Report EOC 10 Page 2 of 4 Catawba Unit 1 Revision 0 Section 3 ' March 23,1998
g~3 Class 2 Inspections i Examination Description inspections inspections Percentage Deferral Category Required Completed ' Completed Allowed" } C-A Pressure Retaining Welds 26 6 23.08 % No in Pressure Vessels C-B Pressure Retaining Nozzle 10 3 30 % No Welds in Vessels C-C - Integral Attachments for 48 9 18.75% No Vessels, Piping, Pumps and Valves C-D Pressure Retaining Bolting None N/A N/A N/A Greater than 2 in. In Diameter C-F-1 Pressure Retaining Weids 252 70 27.78% No in Austenitic Stainless Steel or High Alloy Piping , C-F-2 Pressure Retaining Welds 55 18 32.73 % No in Carbon or Low Alloy Steel Piping
\j C-G Pressure Retaining Welds 20 6 30 % Yes in Pumps and Valves C-H All Pressure Retaining Reference Section 11.0 of This Report Components FA Class 2 Component 260 82 31.54 % No Supports F01.020, F01.021, F01.022 &
F01.040 (Code Case N-491)
" Deferral of inspection to the end of the interval as allowed by ASME Section XI Table IWC-2500-1 pO Refueling Outage Report EOC 10 Page 3 of 4 Catawba Unit 1 Revision 0 Section 3 March 23,1998
O Augmented Inspections Description Percentage Complete Reactor Coolant Pump Flywheels 100% of requirements for EOC 10 Postulated Pipe Failures - Main Steam Not Scheduled for EOC 10 System Thermal Stress Piping (NRC Bulletin 88- Not Scheduled for EOC 10 08) O t Refueling Outage Report EOC 10 Page 4 of 4 Catawba Unit 1 Revision 0 Section 3 March 23,1998
i
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V 4.0 FinalInnervice Inscoction Plan The final inservice Inspection Plan shown in this section lists all ASME Section XI Class 1, ASME Section XI Class 2, and Augmented examinations credited for. Outage 10 at Catawba Nuclear Station, Unit 1. The information shown below is a field description for the reporting format included in this section of the report: Item Number = ASME Section XI Tables IWB-2500-1 (Class 1), IWC-2500-1 (Class 2), lWF-2500-1 (Class 1 and Class 2), and Augmented j Requirements - ID Number = Unique identification Number ISO / Dwg Numbers = Location and/or Detail Drawings Proc = Examination Procedures insp Req = Examination Technique - Magnetic Particle, Dye Penetrant, etc. Material / Sch = General Description of Material Dia / Thk = Diameter / Thickness Cal Blocks = Calibration Block Number Comments = General and/or Detail Description Refueling Outage Report EOC 10 Page 1 of 1 Catawba Unit 1 Revision 0 Section 4 March 23,1998 J
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'5.0 Results OfInsoections Performed The.results of each' examination shown in the final' Inservice Inspection Plan
.(Section 4.0 of this report) are included in this section. The completion date and status for_ each examination are shown. Limited examinations are described in further detail in Section 5.2. All examinations revealing reportable indications are described in further detail in Section 6.0.
5.1 The information shown below is a field description for the reporting format - included in this section of the report: Item Number = . ASME Section XI Tables lWB-2500-1
. (Class 1), IWC-2500-1 (Class 2), IWF-2500-1 --
(Class 1 and Class 2), and Augmented Requirements ID Number = Unique Identification' Number 3 System =- Plant System Designation insp Date = Date of Examination insp Status- = . CLR = Clear: REC = Recordable REP = Reportable Insp Limited =: ' Indicates inspection was limited.
. Coverage obtained is listed. {
Geo. Ref. = ' Y = Yes
- (Geometric Reflector N_ = No applies only to UT)
RFR _
= y_= Yes (Request for Relief) - .N_ = N o Comments' = General and/or Detail Description Refueling Outage Report EOC 10 Page 1 of 2 Catawba Unit 1 Revision 0 Section 51 March 23,1998
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28 e/ 9 g3 Pa/2 3 _ 0
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2 2 2 1 1 1 1 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 S 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 N I M E T CCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCC S NNNNNNNNNNNNNNNNNNNNNNNNNNNNNNNNNNNNN Y S 1 2 3 4 5 6 7 8 9 0 1 2 5 4 5 6 7 1 1 1 2 2 2 3 3 3 4 4 4 - - - - - 0 - 0 0 0 1
- 1 1 5 1 1 1 1 R EEEE 0- -000 - 0 - 0 - -003 303 2 3 323 23 32 3 23 32 3 23 3 2 323 2 3 2 2 2 2 2 2 2 -
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D PPPPNNNNRRRRRRRRRRRRRRRRRRRRRRRRRRRRR I 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 i R E B 2 A A8B83 AB A8 A8 2 3 3 1 5 9 3 7 7 7 8 8 8 9 9 9 0 0 0 1 2 3 4 5 6 7 8 9 0 1 2 3 4 5 6 7 A8 0 MM 0 0 0 0 0 0 0 1 1 1 1 1 1 1 1 1 1 2 2 2 0 0 0 0 0 0 0 0 0 1 1 1 1 1 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 - U 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 1 1
- N 4 4 4 4 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 0 0 001 1 1 1 C tna M 5 1 1 1 1 1 1 1 1 1 1 1 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 ._ .
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T b"e Eta c2 Cai v M U P NDr S EAn es N I . NRe EUuI n S Sc1 U - E K Sepe T A U Asb nw T RRRRRRRRRRRRRRRRRRRRRRRRRRRRRRRRRRRRR L L L L L L L L L L L L LLL L L L L L L LL L L LL L L L L L L L L L L DYia T t S CCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCC U a P A C S U N I Q E 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 T 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 A ////////////// / / / / / / / / / / / / / / / / / / / / / / / D 08 80 80 80 80 80 80 80 80 80 80 80 80 60808 08 00 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 P 2///////////////////////////////////// - S 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 21 121 21 12 1 21 12 1 21 12 12 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 N I M E T CCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCC S NNNNNNNNNNNNNNNNNNNNNNNNNNNNNNNNNNNNN Y S 8 1 1 2 23 3 4 4 5 5 6 6 7 7 8 8 9 9 0 0 1 1 2 2 5 5 4 4 5 5 6 67 7 8 8 1 -0 0- 00 - -0 0- 0 - 40 - 0 -1 1- - 1 5 -1 1 1 1 1 1 1 1 2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 R 3 3- 3 3 3
- 3 3 3 3 - o3 3 3- 3 3 3- 3 3 -3 3 3 E 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 B 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 M 7 7 7 7- 7 7 7 7 7 7 7 7 7 7 7 7 7 7- 7 7 7- 7 7 7 7 7 7 - - - - 7- 7 7 U V- V- V V- V V V V V- V- V- V- V- V V V- V V- V V V- VVVVVV- V- V V- VVVVVVV . .
N PPPP PPPPP PPPPPPP PPPPPPPPPP PPPPPPPPPPP _ _ D RRRRRRRRRRRRRRRRRRRRRRRRRRRRRRRRRRRRR I 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 a b R t w s E B A A A A A A A A 6 1 1 2 2 3 3 4 4 5 5 6 6 7 7 8 8 9 9 0 0 1 1 2 2 3 3 4 4 5 5 6 6 7 7 8 8 A A A A A A A A A A a M 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 0C U 0 0 0 0 0 0 0 0 00 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1
- N 0 0 0 0 0 0 0 0 0 0 0 0 0 0 00 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 _
t 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 _ _ C na M 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 . . Ol E 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 E P T I BBBBBBBBBBBBBBBBBBBBBBBBBBBBBBBB BBBBB _ _
O8 0 e/ g3 a2 P/3 0 S T N E M M O C S R E F NNNNNNNNNNNNNNNNNNNNNNNNNNNNNNNNNNNNN C R I g VI'n R i F NE t s E OS i R I TL L n O NNNNNNNNNNNNNNNNNNNNNNNNNNNNNNNNNNNNN A o G E C I i2 t N c D H e E - C E pWT s n I M I T e I E L _ c2 C i v P S N r e A s N I R n ES K U S I 1 o S U T U A h A RRRRRRRRRRRRRRRRRRRRRRRRRRRRRRRRRRRRR w T DYT s S L L L L L L L L L L L L L L L L L L L L L L L L L L L L L L LL L L L L L I L t o P CCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCC A C S U N I Q E 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 _ T 9 9/9 /9 9 9 9/ 9 9 9 9 9 9 / A /////// / 9/9 /9 9/ 9/9 /9 9/ 9 /9 / 9 9/ 9 /9 9
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D 8 8 8 0 0 0 8 8 0 0 0 0 0 0 1 1 1 1 3 4 3 3 3 3 3 3 4 4 4 2 2 2 2 2 1 2 1 0 0 0 1 1 1 0 0 1 1 1 1 1 1 1 1 1 1 2 2 2 2 2 2 2 2 0 1 1 0 0 0 0 0 0 0 0 P ///////////////////////////////////// S 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 N I M _ E - T CCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCC S NNNNNNNNNNNNNNNNNNNNNNNNNNNNNNNNNNNNN . _ Y S 1 2 2 2 1 2 2 2 1 00 2 30 00 4 50 60 07 18 191 05 11 2 5 4 15 6 7 8 YYXYYY - -XY - - - - - -
- - - - - - - - 1 - - - 1 1 1 2 1 1 1 2 .
3 3 3 3 3 3 R 3 3 3 33 3 33 3 3 3 3 3 3 3 3 3 3 3 XX XYX AB
- 3
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B 4 4 4 4 W W Y X X-WWWWWWF0- - A 1 1 1 1 1 1 5 WW3- 0- 0 7 7 7 7 7 7 7 7 7 7 -7 7 MMMMMMMM1 M 7- - - - 4 4 4 4 4 4 4 4 4 4 4 4 4 4
- - - - - - - - - - - WW5 - 4 4 4 4 7 7 9 9 U
N VVVVVVVV- VV VVVVVVVVAABBCCDDPRR2 2 2 2 1 1 1 1 PPPP P PPPPPPP PPP PPP GGGGGGGGCZZCCCCCCCC D RRRRRRRRRRRRRRRRRRS I S S S SS S SRPPNNNNNNNN 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 e _ t R A A A A w e E 1 2 3 4 5 6 t B a M 0 0 0 0 0 0 70 60 90 0 1 11 2 1 3 1 4 1 51 61 71 8 1 10 2 0 30 40 5 0 60 7 0 80 10 2 0 3 0 2 0 20 40 4 0 83 8 3 93 93 0C U N 00 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1
- 5 5 5 50 50 50 50 50 50 50 50 50 505 05 05 05 00 5 00000000100 0 0 0 0 02 02 01 11 11 11 11 11 11 1 1 01 01 01 01 81 1 1 0 0 0 0 0 0 0 0 10 0 1
t 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 C n a M 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 8 8 9 9 9 9 9 9 9 9 Ol E 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 C 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 E P T BBBBBBBBBB9BBBBBBBBBBBBBBBBBBBBBBBBBB I _ _
eM g M5Sa PM S d 2 2 0- 0-8 8 9 9
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l l ir a ir e e S S f f ie ie le le S R R T r o r o N f f E t s t s M e e M u q u q O e e C R R R ESW CS I g F R NNNNNNNNNNNYNNNNNNYNNNNNNNNNNNNNNNNNN V n F R i t E s R OS i I O NNNNNNNNNNNYNNNNNNNNNNNNNNNNYNNNYNNNN NEWL TL A C I NM-H x 2GE rtaE e gD C uI T T OM I 2 0 GC RN EA NR Eh "e E l o2 vl r aS ovN cr e L P I 3 7 nt i nSU EUW1A RRRRRRRRRRRRRRRRRRRRRRRRRRRRRRRRRRRRR ESS K A U h o I T DYWw s T S L L L L L L L L L L L L L L L L L L L L L L L L L L L L L L L L L L L L L P CCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCC T t I L a S U IN AhC Q b E T 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 7 7 7 7 7 7 7 7 7 7 9 9 9 9 9 9 9 9 9 9 9 A ///////////////////////////////////// D 2 1 2 1 2 2 1 8 6 6 6 G 5 01 0 0 4 0 5 4 0 0 5 5 5 5 8 0 0 0 0 0 0 1 1 0 1 1 0 2 2 2 1 2 1 1 2 2 2 2 8 8 8 8 8 8 8 8 8 8 2 2 1 1 1 1 1 1 1 1 1 1 1 P 2 /// / / / / / / / / / / / / / / / / / / / / / / / / / / / / / / / / / / S 1 121 21 12 1 21 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 1 1 1 1 2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 2 2 2 2 2 2 2 2 2 2 N I M E T CCCCCCI CSVVVCFFAACAAAADDDDI I I I I I I' I I I I S Y NNNNNN N NNNNNNCCCCNCCCCNNNN NNNNNNNNNNN S R O L DL G G A I FHF R E 0 0 4 4 NN S 9 R5 HHD E - 8 8 9 9 8 1 1 5 5 5 5 5 5 6 6 B 2- 2- 2 T SSH 6 2 2 2 2 2 2 2 64 46 2 62 16 1 2 2 M 0 0 0 0 WW9
- N X X X- 0 0 7 9 9- -- 8- 9 1- 1 1 2 2 U 9 91 9 9 2 2 I
- HHHH XWDDDDDDD7WWWWWWW2 A
N 1 1 1 2 2 1 2 CCCCCC - PNL L L GGGGGGGGAADDDD1 VSDDD 7 5 5 5 S 1 1 1 1 1 1 2 2 22 2 2 2 1 1 1 1 1 1 1 1 1 1 1 1 2 i 2 2 1 1 1 D NNNNNNI I 1 1 1 1 1 1 RAEEESSSSSS SSCCNNNNNNNNNNNNNNN N 111111111111111111111111111111 I V R A A A A A A A A A A A E A A 8 B 00 1 1 1 3 6 1 1 8 2 3 8 1 1 3 3 1 1 1 5 5 5 5 6 6 1 1 2 2 3 3 1 1 2 2 3 1 6 6 6 6 0 0 0 0 0 0 1 1 1 1 1 4 4 4 4 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 1 1 M 0 0 0 00 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 U 1 1 1 1 2 2 0 0 0 0 0 0 0 1 1 1 1 2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 N 1 1 1 1 3 3 5 1 1 1 2 2 3 2 2 2 2 2 1 1 1 1 1 1 1 1 2 2 2 2 2 2 2 2 2 2 2 C M 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 10 02 02 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 2 2 2 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 O E 9 0 9 9 9 9 9 2 3 1 1 1 1 0 0 0 0 0 1 1 0 0 0 0 0 O O O O O 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 T E T BBBBBBBBCCCCCCCCCCCCCCCCCCCCCCCCCCCCC
nM mss i a2 P/ 3 9 p S T N E M M O C n u Sk R Ey s F R NNNNNNNNNNNNNNNNNNNNNNNNNNNNNNNNNNNNN CS I g Vt nn F NEReu s E R OSmu I TLgn O NNNNNNNNNNNNNNNNNYNYNNNYNNNNNYNNNNNNN Aa e E Cn I a u: c e G NMegD H epaE Cs st n uIT EaiOM ----------- Tb Eta c2 ( e ai vl L P I - NDr aS EAn evN NRawe r I EUehtnS Sc1 I U E e T K Spe A U DYnw As e T RRRRRRRRRRRRRRRRRRRRRRR5 L L L L L L L L L L L L L L L L L L L L L L L LL L L RRRRRRRRRRRRR t L L L L L L L L L L I s S P CCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCC T t U a A C S U N I Q E 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 T 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 A ///////////////////////////////////// D 81 16 16 16 16 262 62 62 62 62 62 26 26 2G 26 26161 51 4 5 4 0 0 5 4 4 4 4 4 17 27 25151 81 51 51 91 1 1 2 2 2 0 0 2 P 2 2 2 2 2 1 1 1 1 1 1 1 1 1 1 1 1 2 2 2 2 2 2 2 2 2 2 2 2 2 2 1 1 1 2 2 1
//////////////// / / / / / / / / / / / / / / / / / / / / /
S 1111111111111111111111111111111111111 N I M E T 1 I I I I VVVVVVVVVVVVF FFFF F MMVVVVVVDI I CCD S Y NNNNN NNNNNNNNNNNNCCCCCCSS SSSSSSN NN KKF S R 0 0 8 21 E 0 1 2 9 0 3 4 5 6 6 6 7 6 0 2 2 5 5 4 5 0 B 3- 4 9- 1 - 1 2 2- 2 2- B1 1 0 M 3 3- M5- 0 0 0 0 0 009 09 09 90 909 0 -1 1-11 1 18 8 WW3 U 2 0 0 0 0 6 0 1 0 1 101 101 1 0 6 6t
- -3 5- 5
- 93 93 00 7 2- 3 B0 333363 6- 31 01 KKF 5 CCD 1 1 N 12 2 12 2 2 VVVVVVVVVVVVF F F F GGMMVVVVVVDl 1 1 1 4 4 3 3 DD3 3 3 - - - - -
D NNNNNNNNNNNNNNNNNCCCCSS SSSSSS S SNNN RRR t 1 1 I I 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 I 1 1 1 1 1 1 1 1 1 pk/.. R A A A A A A A E A B 3 1 23 4 8 9 0 1 2 3 4 5 67 8 9 3 3 4 4 7 7 2 2 3 3 4 4 5 5 2 4 8 0 1 5 1 1 1 1 1 0 0 1 1 1 1 1 1 1 1 1 1 5 5 5 5 5 5 1 1 5 5 5 5 5 5 0 0 0 2 2 0 M 0 0 0 0 0 1 1 1 1 1 1 1 1 1 1 1 1 0 0 0 0 0 0 1 1 1 1 1 1 1 1 0 0 0 0 0 0 0 1 U 1 0 0 0 0 0 0 0 0 0 0 0 0 0 00 0 1 1 1 1 1 1 1 1 1 1 1 1 1 1 0 0 0 0 0 0 N 2 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 5 5 5 5 5 5 5 5 5 5 5 5 5 5 2 2 2 2 2 4 C M 0 5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 O E 50 0 5 5 5 5 S 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 6 6 6 2 2 2 0 0 0 0 O 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 E T I CCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCDDD
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st e es M7saa Pw o O . S T N E - M M O C R sW g F R NNNNNNNNNNNNNNNNNNNNNNNNNNNNNNNNNNNNN mS n i e F E e s R
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A o 2 G E R i t O P Mec p D E s T n I T e M I AEhi i c2 v r e s L P S N I _@n hwa i 1 b t a a S U T A T RRRRRRRRRRRRRRRRRRRRRRRRRRRRRRRRRRRRR S L L L LL L L L L L L L L L L LLL L L LL L L L L L L L L L L L L L LL P CCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCC S _hC b IN E 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 T A 49 / /9/ /9/ / 9 / / /9 / /9/ / /9/ / 9
/ / 9
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/ / 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9. /9/ /9/ / 9 9 9 D 9 6 6 5 9 9 5 6 6 5 5 9 9 9 9 9 9 9 9 9 9 5 5 0 5 1 5 5 5 5 9 6 5 6 6 0 0 2 0 0 0 2 2 0 0 0 0 0 2 2////////////////////////////
2 2 2 2 2 2 2 2 0 0 3 0 0 0 0 0 0 0 0 0 0 0 2 2 P /J / / / / / / / S 11 121 21 12 121 21 12 1 21 2 2 2 1 1 1 1 1 1 1 1 1 1 2 2 1 2 2 2 2 2 2 2 2 2 2 2 2 2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 N I M E T DCCVCCVAAI I SSSSS SSSSSVVViI I VVVAAAF AMM S Y F NNNNNNCC NNNNNNNNNNNNNNNNNN NNNCCCCSSS S R 2 0 6 3 8 3 7 8 0 1 2 3 4 6 7 0 1 2 4 5 6 5 6 0 1 1 2 2 2 2 6 8 2 2 2 6 0 2 7 5 8 6 2 9 7 0 0 13 3 E 0 0 61 609 49 29 10 62 70 1 1 6 6 7 7 1 1 1 1 B 0 1- 1 1 1 1 1 0 8 38 30 00 00 00 00 00 00 00 00 00 03 13 13 00 33 32 43 5 51 101 101 101 10 5 0 0 1 1
- - 1 1 - - - - - - - - - - - - - 2 0 1 - - - - - - - - - -
M U D C C V- C C V- - - AAiI SSSSSSSSS SVYV1- - - I I VVVAAAF AMM N F- NNNNNNCCNNNNNNNNNNNNNNNNNNNNNCCCCSSS D RRRRRRRRRRRRRRRRRRRRRRRRRRRRRRRRRRRRR I 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 O 1 t e bw R a E B 6 1 1 3 9 7 1 1 2 1 2 1 2 3 4 5 6 7 8 6 7 1 2 7 1 2 3 1 2 3 1 2 3 1 1 5 6 a M 0 0 0 9 0 1 9 0 0 6 6 9 9 9 9 9 9 9 9 0 0 4 4 6 6 6 6 4 4 4 0 0 0 1 9 0 0 0C U 0 00 0 0 0 00 0 0 0 0 0 0 0 0 0 0 0 1 1 1 1 1 0 0 0 1 1 1 0 0 0 0 1 2 2 1
- N 0 4 1 0 11 11 21 2 1 1 2 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 1 1 1 1 1 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 M 0 0 0 0 0 0 0 0 0 0 00 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 t
C O s.n E 21 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 E p T I DF F F F F F F FFF F FF F F F FF F F F F F F F F F F F F F F F F F F
e g M88aM P 8 S T - N _ E . M M O C R F NNNNNNNNNNNNNNNNNNNNNNNNNNNNNNNNNNNNN SW E C I V g n R F R i t E s R OS I TL n O NNNNNNNNNNNNNNNNNNNNNNNNNNNNNNNNNNNNN NEWU A C I N H C e u2G c e egD paE st T n uI E OM . T e I EA NR ENI E C N i c2 vl r aS evN er e L P I nt I nS iU ES T EUW1 KS U A DYT I k t e u s a A T RCRRRRRRRRRRRRRRRRRRRRRRRRRRRRRCRRRRR S L EL L L L L L L L L L L L L L L L L L L L L L L L L L L L L EL L L L L P CRCCCCCCCCCCCCCCCCCCCCCCCCCCCCCRCCCCC S A N U LhC I Q E 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 k T 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 A 5//////////////5///////////////////// D 9 2 9 9 6 6 6 6 4 4 4 4 4 4 2 5 3 3 3 3 3 3 3 2 5 5 5 3 3 9 9 2 9 0 9 9 9 9 P f / / / / / / / / / / / / / / / / / / / / / / / / 0 2 2 2 2 2 2 2 2 2 2 2 2 1 0 1 1 1 1 1 1 1 0 0 / 0 1 /
/ / 1 /2 /2 /1 /2 /3 ///
2 2 2 2 S 11 111 11 111 11 11 111 11 111 11 11 111 11 121 21 12 1 21 2 2 2 2 2 2 2 2 2 2 2 1 1 2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 N I M E T CCCCCCCCCCCCCDDNNNNNNNCCCCNNDDDSVNNND S KKKK KKKKKKKKKKL RRRRRRRYKKKRRF F KNNVVVL Y S TT TRR ROO T OPP T RTPPP R ORPUU POUSS- P-O R 4 5 5 56 25 26 39 74 51 52 53 64 65 86 165 2 9 4 5 8 5 8 5 0 8 2 5 7 1 2 8 PPS1 AP E 54 4 4 3 3 3 6 1 1 1 1 1 3 1 0 0 6 0 0 0 2 2 0 0 4 5 7 7 6 7 7 7 8 8 4 9 7 6 2 2 0 0 3 B 0- -00 - - 000
- - - 0 M CCCCCCCCCCCCCDDNNNNNNNCCCCNNDDDA - - 000 00 0 0- 00 - - -0 - - 0 -0 30 30 00 000 SU UP SA-F /ACU S EIA#-A S
U KKKKKKK
- - - - - - -KKKKKKKL - - - - - - - RRRRRRRYKKKRRFF
- - - - - - - - - - - - - - KP - - PEEE C N
RRRRRRRRRRRRRRRRRRRRRRRRRRRRRRR NRDDDL S CGGG D D I 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 R E B 1 2 3 4 5 6 7 8 9 0 1 2 3 1 1 1 3 2 3 4 5 6 1 1 25 3 2 5 1 2 1 2 3 8 9 0 3 M 5 50 505 05 0 5 5 5 5 6 6 6 6 0 2 5 5 7 7 7 7 7 5 5 5 5 S 3 3 0 0 0 0 0 1 1 t U 0 0 0 0 0 0 0 0 0 1 1 1 1 1 1 1 1 1 2 0 0 0 1 i. 0 0 1 1 1 2 2 2 2 i N 3 3 3 3 3 3 03 03 03 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 13 1 1 1 1 2 2 2 0 0 0 0 0 0 3 3 3 3 4 4 4 4 4 4 _ C M 0 0 0 0 0 0 0 000 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 00 _ 1 1 1 1 1 1 1 1 1 1 1 O E 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 E T I F F F F F F F F F F F F F F F F F F FF F F F FF F F F F F F F F F F FF
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/
D WW9 4 4 f 2 2 2 0 0 P ///// S 11 111 11 12 2 N I M E T DDDCC S L L L NN Y S - T _ TT _ RR - OO - PP .- R PP UU
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B M U NSSPP N ODDCC D L I SS 1 A1 AB 1 AT - - L L RR 1 1 1 1 1 e i ERB 4 5 6 t t w a 1 2 0 0 _ a M 1 1 1 _
,C U 2. 2 2 101 0 N 04 04 04 0 0 t
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1 I l 5.2 Limited Examinations (i.e.,90% or less of the required examination l coverage obtained) identified during Outage 10 are shown below. A copy of the Request for Relief is contained in Section 9.0 of this report. Item Number Reauest for Relief SerialNumber B01.040.001 98-02 B03.090.005A 94-01 B03.090.006A 94-01 B03.090.007A 94-01 B03.090.008A 94-01 B03.100.005 94-01 B03.100.006 94-01 B03.100.007 94-01 B03.100.008 94-01 ' C01.020.003 98-02 C05.011.011. 98-02 1 O l l l i l O Refueling Outage Report EOC 10 Page 2 of 2 Catawba Unit 1 Revision 0 Section 5 March 23,1998
1
. 6.0 Recortableindications
- O'utage 10 had no reportable indications.
I O l 4 1 Refueling Outage Report EOC 10 Page 1 of 1 Catawba Unit 1 Revision 0 Section 6 March 23,1998
')
7.0 Personnel. Eauloment and Material Certifications All personnel who performed or evaluated the results of inservice inspections from October 4,1996 through January 5,1998 at Catawba Nuclear Station, Unit 1 were certified in accordance with the requirements of the1989 Edition of ASME Section XI, with No Addenda. The appropriate certification records for each inspector are on file at Catawba Nuclear Station or copies can be obtained by contacting the Duke Energy Corporate Office in Charlotte, North Carolina. Records of periodic calibration of inspection equipment are on file at Catawba Nuclear Station or copies can be obtained by contacting the Duke Energy Corporate Office in Charlotte, North Carolina. Records of materials used (i.e., NDE consumables) are on file at Catawba Nuclear Station or copies can be obtained by contacting the Duke Energy Corporate Office in Charlotte, North Carolina. O g \ Refueling Outage Report EOC 10 Page 1 of 1 Catawb Unit 1 Revision 0 Section 7 march 23,1998
8.0 - Corrective Action No corrective action was required as a result of examinations performed during Outage 10. 4 < O i O Refueling Outage Report EOC 10 Page 1 of 1 Catawba Unit 1 Revision 0 Section 8 March 23,1998
' 9.0 Referencepocuments The following reference documents apply to the inservice inspections performed during Outage 10 at Catawba Nuclear Station, Unit 1:
. Duke Power Company Request for Relief Serial No. 94-01 Limited Volumetric Examination identified During Refueling Outage #7.
. NRC Letter; Herbert N. Berkow to Mr. David L. Rehn, Catawba Nuclear Station, Unit 1 - First Ten Year Inspection Interval - Request for Relief No. 94-01 (TAC No. M89128); dated April 18,1995.
. Duke Power. Company Request for Relief Serial No. 94-05 Second Interval Intermediate Nozzle Examination
. NRC Letter; Herbert N. Berkow to Mr. William R. McCollum, Catawba Nuclear Station, Unit 1 - Evaluation of Second Ten Year interval inspection Program Plan and Associated Requests for Relief (TAC M92198), dated July 18,1996.
. Duke Power Company Letter; W.R. McCollum to USNRC Document Control Desk, Catawba Nuclear Station, Unit 1 Docket No. 50-413 Request for Relief ph Serial No. 95-05 Snubber inspection Intervals for Unit 1, dated August 23, ;
1 1995
. NRC Letter; Herbert N. Berkow to Mr. William R. McCollum, Catawba Nuclear Station, Unit 1 - Snubber inspection Frequencies - Request for Relief No. 95-r 05 (TAC No. M93355); dated January 11,1996.
. NRC Letter; Herbert N. Berkow to Mr. M.S. Tuckman, Catawba Nuclear l Station, Units 1 and 2, McGuire Nuclear Station, Units 1 and 2 ; Oconee l Nuclear Station, Units 1,2 and 3 - Authorization to implement ASME Code Case N-524 (TAC NOS. M96456, M96457, M96458, M96459, M96460, '
M96461, M96462); dated October 29,1996.
. Duke Energy Corporation Request for Relief Serial No. 98-02 Limited Weld Inspection Coverage EOC 10.
ij Refueling Outage Report EOC 10 Page 1 of 1 Catawba Unit 1 Revision 0 Section 9 March 23,1998
1- ll
, l DukeIbwerCompany y}'. Catawba Nuclear Generation Deparrinent DLRtm
( j 4800ConcordRoad Vice l' resident
,V (803)UIJ.T15 Onuce York.SC29743
. . . . (803>831-342%
; DUKEPOWER March 24,1994 U. S.' Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555
Subject:
Catawba Nuclear Station. Unit 1 Docket No. 50-413 Relief Request 94-01 IEOC7 Inservice Inspection Report j f Please find attached, Catawba's Request for Relief 94-01. The basis for this request is explained in Section III. ( Any questions concerning this request should be directed to L. J. Ruriy at l (803) 831-3084. G j I
'Q , . .
Very truly yours, l hAdk.,5 h ) D. L. Rehn KEN /1E0C71SI.RLF Attachment ,
)
xc: S. D. Ebneter, Regional Administrator ht. J. Freudenberger, SRI R. E. Martin, ONRR l l l l
. I (j
--mo r etw =-
O, March 15,1994 Z L Taylor Safety Assurance Manager Catawba NuclearStation Attention: K E Nicholson
Subject:
Catawba Nuclear Station Unit 1 Request forRelief Serial No. 94-01 ~ l Rndamad is Request for Relief 94-01 for your review and submittal to the NRC. Ifyou have any questions, please contact Jimmy Cherry at 382-5111. C. Potts QATechnical Services Manuals & Reports I i
/cp o j O
Sedal No. 94-01 Page 1 of 4 0 DUKE POWER COMPANY Request for ReliefFrom Inservice Inspection Requirement Station: Catawba ' Unit: 1 Requesting Department: Nuclear Generation Department Reference Code: ASME Boiler and Pressure Vessel Code, Section XI 1980 Edition through Winter 1981' Addenda I. Component for which exemption is requested:
- a. Name and Identification Number:
ReactorVessel Wald Numbers ItemNumben
- O 1RPV-WO3 1RPV-WO6 1RPV-W01 B01.01L001 B01.011.004 B01.021.001 1RPV-WO2-01 B01.022.001 1RPV-WO2-03 B01.022.003 1RPV-WO2-04 - B01.022.004 1RPV-WO2-05 B01.022.005 1RPV-WO2-06 B01.022.006 1RPV-W11 B03.090.001 1RPV-W11 B03.090.001A 1RPV-W12 B03.090.002 1RPV-W12 B03.090.002A 1RPV-W13 B03.000.003.
1RPV-W13 B03.090.003A 1RPV W14 B03.090.004 1RPV-W14 B03.090.004A 1RPV-W15 B03.090.005 1RPV-W15 B03.090.005A 1RPV-W16 B03.090.006 1RPV-W16 B03.090.006A 1RPV-W17 B03.090.007 1RPV-W17 B03.090.007A 1RPV-W18 B03.090.008
'1RPV-W18 B03.090.008A 1RPV-W11 B03.100.001 1RPV-W12 B03.100.002 4
Serial No. 94-01 Page 2 of 4 -; RemetorVeamal WahlNumbers Iten Numbers 1RPV-W13 B03.100.003 1RPV-W14 B03.100.004 . 1RPV-W15 B03.100.005 1RPV-W16 B03.100.006
.1RPV-W17 B03.100.007 1RPV-W18 B03.100.008 Pressedser WahlNumbers Item Numbers IPZR-W4A B03.110.006 )
IPZR.W4B B03.110.005 ' { 1PZR-W40 B03.110.006 1PZR-W4A B03.120.004 IPZR-W4B B03.120.005 1PZR-W40 B03.120.006 1 IPZR-W4ASE B05.040.004 1PZR.W4BSE B05.040.005 1PZR W4CSE B05.040.006 mm== Generator WahlNumbers Itan Numbers ISGC-INLET B03.140.005 ISGC-OUTLET B03.140.006 ISGC-INLET-SE B05.070.005 ISGC-OUTLET SE B05.070.006 BaacenenwdaMBystem(NC) WaldNumbers ItemNumbers INO2502 B05.130.014 INC25-03 B05.L10.015 1NC22-WN8 - B09.031.003 l
- b. Func'tion:
Reactor Vessel - Houses the fuel assemblies, control rods, and vessel l internals, also directs the flow of reactor coolant. Pressurizer - Maintains reactor coolant system pressure within set limits and provides a surge volume for the reactor coolant system. l Steam Generator - Acts as a heat exchanger in the reactor coolant system. Reactor Coolant System - Transports heat energy from reactor core to steam generator. , s . j
Serial No. 94-01 Page 3 of4
-; c. ASME Section XI Code Class: Class 1
- d. Construction Code and Class (If Applicable):
ASME Section III,1974 Edition through Summer 1974 Addenda, Class 1
- e. Valve Category (If Applicable): NA II.
. Reference Code Requirement that has been determined to be impractical:
Eramination Category B-A, Pressure Retaining Welds in Reactor Vessel, Table IWB-25001, Figure Nos. IWB-2500-1 and IWB-2500 3; " Note 2: Includes essentially 100% of the weld length". R===ination Category B-D, Full Penetration' Welds of Nozzles in Vessels - T= Mon Program B, Table IWB-2500-1, Figure No. IWB-2500-7; 100% examination coverage. R===ination Category B-F, Pressure Retaining Dis'similar Metal Welds, Table IWB-2500-1, Figure No. IWB-2500-8; 100% examination coverage. R===in= tion Category B J, Pressure Retaining Welds in Piping, Table IWB-2500-1, Figure No. IWB-2500-11;" Note 3: Includes essentially 100% of the weld length". III. Basis for Requesting Relief: During the ultrasonic ernmination of the welds shown in Attachment 1, the minimum 90% coverage requirement of ASME Section XI,1980 Edition through Winter 1981 Addenda, clarified by Cwle Case N-460, could not be obtained due to part geometry and actual physical barriers. A combination of multiple angles and UT techniques was used to obtain marimum coverage possible. The attached examination reports document the actual amount of examination coverage obtained. Although the coverage requirements of ASME Section XI could not be met, th'e-amount of coverage obtained for these examinations provides an acceptable level of quality and integrity. Based on these evaluations, the limited coverage will in no 4 way endanger the health and safety of the general public. Mo additional examinations are required. IV. Alternate Examination: " The use of radiograpity as_an alternate volumetric examination method is not practical due to component thicknesses and geometric configurations. Other restrictions == Mag radiography impractical are the use of double wall O techniques and physical barriers prohibiting access for placement of source, film, number bands,etc.
Serial No. 94-01 Page 4 of 4
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We will continue to use the most current ultrasonic techniques available for future examinations of the Item Numbers shown in Attachment 1. V. Implementation ' Schedule: These examinations will continue to be scheduled in accordance with requirements ofUnit ASME Nuclear Station, 1. Section XI for future Inspection Intervals at Catawba Evaluated By: !. h n Date: A/
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O m - Total Exam Area = 53.32 in" (N6ar Surface + Weld + T/2) Near Surface Area = 8.37 in' (Cross-Section) Weld Area = 6.37 ina (Cross-Section) T/2 Area = 38.58 in' (Cross-Section) i BETPfEEN LUGS CIRC ' 70' Gets'6.24 in8 of Near Surface Area (74.6 %) O' Gets 9.07 in8 of Total Exam Area (17.0. %) 45' & 60' Get 31.79 inn of T/2 Area, .44 in* of Weld Area Total Coverage = 31.79 + 0.44 + 0.44 = 63.7 % 38.58 + 6.37 + 6.37 l AXIAL 70' Gets 8.24 inn of Near Surface Area; however due to-the Full-Node Exam, 100 % Coverage of the Near Surface Area is obtained by the 45' & 60'. 45' - Gets 100 % of Weld and T/2 Area 60' Gets 100 % of Wald and T/2 Area BELOW LUG 8 , AXkAL' Due to the Full-Node Exam, 7.58 inn of the N' ear Surface Area is obtained by the 60' (90. 6 %) .-
. 45' Gets.3.79 in8 of T/2 Area (0 % Weld Area)
Total Coverage = 3.79 + 0.'00 + 0.00 = 7.4 %~ 38.58 + 6.37 + 6.37 60' Gets 9.11 in8 of T/2 Area and 1.23 in8 of Wald Area Total Coverage = 9.11 + 1.23 + 0.00 = 2'O.1 % OA , 38.58 + 6.37 + 6.37 Ssa. F4e. 94-01 kTTdtu b T 2 Got.o tt.001 litPV-idoS
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A U I., There are six (6) Segments Between Lugs, each 31.60' covered by the center of the head (0* and 60', Cire) . The outside transducers each cover an additional 2.06* which results in 35.72* covered by 7 0', ~60' & 45' Axial and 70* & 45' Circ. There are also six (6) Segments Below Lugs, each covering the remaining 24.28' for Axial Scans. l O' & 6 0' Circ Coverage = 189.60 x % Between 100 x 360 70' & 45' Circ Coverage = 216.32 x % Between 100 x 360 Axial Coverage = 214.32 x % Between + 145.68 x % Below 100 x 360 { i ( l l I H:.9.3 AXIAL CIRC 1 fQ 1 70 1 1 0 96.2 67.7 62.5 44.4 33.5 37.9 9 .30 Aggregate Coverage = , [ 96.2 x 8.37 + (67.7 + 62.5) x (38.58 + 6.37 + 6.37)
+.44.4 x 8.37 + (33.5 + 37.9) x (38.58 + 6.37 + 6'.37)
+ 9.0 x 53.32'] /
[ 8.37 x 2 + (38.58 + 6.37 + 6.37) x4 + 53.32 ] . I O- -
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Aggregate Coverage = 43.6 % ktrM.wT 2 601.e41.801 1 p. W W o s PG S O F 68
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8 ITTOM HEAD RADIUS CENTER , I "Z" = 342.38 s 'e j a I o '. ' J 6.' 45' I v. ^ . ', , l i , I ', l I . l "Z" = 349.12 '! ------- '.'- ! 1 ','
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n-as Total Exam Area = 93.65 in8 (Near Surface + Weld + T/2) Near Surface Area = 10.47 in8 (Cross-Section) Weld Area = 11.38 in* (Cross-Section) T/2 Area = 71;80 in8 (Cross-Section) CIRC 70* Gets 3.82 in8 of Near Surface Area (36.5 %) O' Gets 6.08 in8 of' Total' Exam Area (6.5 %) 45' & 60* Get 28.50 in8 of T/2 Area (0 %, Weld) Total Coverage = 28.50 + 0.00 + 0.00 - 30.1 % 71.80.+ 11.38 + 11.38 AXIAL 70' Gets 5.40 in8 of Near Surface Area (51.6 %) 45' Gets 63.34 in8 of T/2 Area 4 5'-UP Gets 11.10 in8 of Weld Area 4 5'-DOWN Gets 4.74 in8 of Weld Area Total' Coverage = 63.34 + 11.10 + 4.74 = 83.7 % 71.80 + 11.38 + 11.38 60' Gets 67.39 in8 of T/2 Area
'.60'-UP Gets 9.87 in 8 'of Weld Area 4
~ 60'-DOWN Gets 9.34 in8 of Weld Area Total Coverage = 67.39 + 9.87 + 9.34 = 91.6 %
71.80 + 11.38 + 11.38 1 4 Se.e..kl. 94-0 \ k rtudmorf I-- Sot. o u.c o + t 9.9V- W ob 94 S o F (,8 i J
O.f. (. H.~9.5L 1 AXIAL CIRC j 70 60 ., 15,,_ 70 _ ft9_ 1 0 3 51.6 91.6 83.7 36.5 30.1 30.1 6.5 Aggregate Coverage = [ 51.6 x 10.47 + (91.6 + 83'.7) x ( 71. 8 0 + 11. 3 8 + 11. 3 8) ;
+ 36.5 x 10.47 + (30.1 + 30.1)' x (71. 8 d + 11. 3 8 + 11. 3 8 )
+ 6.5 x 93.65,) /
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( 10. 4 7 x 2 + ' (71. 8 0 + 11. 3 8 + 11. 3 8 ) .x 4 + 94. 65 ]
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Aggregate Coverage = 48.2 % SEL.hje.9446i
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O (~L m Total Exam Area = 41.68 in8 (Near Surface + Weld + T/2) Near Surface Area = 7.27 in8 (Cross-Section), Weld Area = 5.11 in8 (Cross-Section) T/2 Area = 29.30 in8 (Cross-Section) CIRC 70* Gets 4.46 ina of Near Surface Area (61.3 %) 0* Gets 7.73 in8 of Total. Exam Area (18.5.%)
~
. ~45' & 60' Get 16.02 in8 of T/2 Area (100 % Weld)
Total Coverage = 16.02 + 5.11 + 5.11 = '66.4 % 29.30 + 5.11 + 5.11 AXIAL 70' Gets 6.20 in8 of Near Surface Area; however due to the Full Node Exam, 100 % of the Near Surface Area is obtained with the 45' & 60*. 45' Gets 100 % of Wald and T/2 Area 60* -Gets 100 % of T/2 Area 60"-UP Gets 100 % of Weld Area 60*-DONN Gets 4."77 in8 of Wald Area Total Coverage = 29.~a0 + 5.11 + 4. 7? = 99.1 % 29.30 + 5.11 + 5.11 m g.,44-oi O . G-60s.ott.coi 2
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k. . W-01 is Obstructed due to Instrument Nozzles. Six (6) Angular Portion's of the Weld are Scanned.
Segments are: 16.42', 13.44*, 59.84*; 76.46', 49.46' & 43.44' The outside transducers each cover an additional 2.01' which
. increases coverage by 4.02' for th.e 60' & 45' Axial and 70' & 45' Circ.
l O' & 60' Circ Coverage = 259.06 x k Bet. ween 100 x 360 70' & 45' Circ Coverage = 279.16 x % Between 100 x 360 70,* Axial Coverage = 259.06 x k Between 100 x 360 0 60* & 45' Axial Coverage = 279.16 x % Between 100 x 360 1 1 E 1'
, AYIAL C'IRC l 1 1 1 1 1 1 0 72.0 76.8 77.6 47.5 47.8 51.5 13.3 )
Aggregate Coverage = . [ 72.0 x 7.27 + (76.8 + 77.6) x (29. 3 0; + .5.11 + 5.11) .
+ 46.5 x 7.27.+ (47. 8 + 51. 5) x (29.30 + 5.11 + 5.11)
+ 13.3 x 41.68 ) /
( ( 7.27 x 2 + ( 2 9 . 3 0 + .5 .11 + 5 .11) x.4 + 41.68 ) = A r ac. Cov. ras. . 53.4 s hw% thot.oz .oin 2 t RN-wei P6 4 or 6 a
1 T ( ALPHA = 23.62 8 ALPHA = 25.63 i i 6S' RADIUS = 88.194 ' (CLAD) ,, '.
' 7 8
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1 ALPHA = 31.98 ,,- i
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F" ALPHA = 33.99 ' ,' , ' ' ' ' " ALPHA = 34.86 , O ALPHA = 36.07 - s N
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ALPHA = 36.87 3 . ,
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T'.'. E-22. Total Exam Area = 221.51 in2 (Near Surface + Weld + T/2) (Alpha Cross-Section)
,Near Surface Area = '38.21 in2 (Alpha Cross-Section)
Weld & T/2 Area = 183.30 in2 (Alpha Cross-Section) The Weld Area occupies 1.30 and T/2 Area occupies 4.48 in the Circumferential or Theta Direction. Coverage for the Weld & T/2 Areas is. based on: (4. 4 8 + 1.3 0 + 1.3 0) / 5.78 or 122.5 % Area. CIRC 70 Gets 28.58 in2 of Near Surface. Area (74.8 %) 45* & 60 Get 136.38 in2 of Weld & T/2 Area (74.4 %) AXIAL 70* Gets 30.32 in2 of Near Surface Area; however due to the Full Node Exam, 100 % of the Near Surface Area is ; obtained with the 45 & 60*. ' 0* Gets 137.45 in2 of Total Exam Area (62.1 %) 45 Gets 170.84 in2 of T/2 Area 4 5 -UP Gets 151.89 in2 of Wald Area 4'5*-DOWN Gets 170.84 in2 of Weld Area . Total Coverage = 170.84 x 4.48 + 151.89 x 1.30 + 170.84 x 1.30 183.30 x 4.48 + 183.30 x 1.30 + 183.30 x 1.30 i
= 91.3 % ;
60* Gets 175.32 in2 of T/2 Area i 60*-UP Gets 147.48 in2 of Weld Area 60*-DOWN Gets 175.32 in2 of Weld' Area
' Total Coverage = 175.32 x 4.48' + 147*.48 x 1.30 + 175.32 x 1.30 3 183.30 x 4.48 + 183.30 x 1.30 + 183.30 x 1.30 be.. % .94-ol
= 92.9 % gggg g Bot.oif..c o t i tW- W o t-ol S t.o22.co a TAN-Wot.os 60 4. o f 2.0** IK"*W'*~0+
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WO2-03, W2-04 & W2-06 are Unobstructed and Get the Following Coverages: , WO2 CIRC AXIAL 70 1 1 1 1 1 0 74.8 74.4 74.4 100 91.3 92.9 62.1 Aggregate Coverage =- . [ 100 x 38.21 + (91.3 + 92.9) x (183.30 x 122.5 %)
+ 74.8 x 38.21 + (74.4 +'74.4) x (183.30 x 122.5 %)
O + 62.1 x 221.51 ) / [ 3 8. 21 x 2 + (183.30 x 122.5 %) x 4 + 321.51 ) = Aggregate Coverage = 77.1 %
- 4 P
D %s.. no. 94-On
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O i .*_ WO2-01 is Obstructed due to Instrument Nozzles. CIRC , 70 Gets 22.40'in2 of Near Surface Area (58.6 %) 45 & 60 Get 106.02 in2 of We.ld & T/2 Area (57.8 %) AXIAL- 70* Gets 25'.89'in2 of Near Surface Area; however due to the Full Node Exam, 100 % of the Near Surface Area is obtained with the'450 & 60*. 0* Gets 92.65 in2 of Total Exam Area (41.8' %) - 45 Getis 169.70 in2 of T/2-Area 45 0 -UP Gets 147.82 in2 of Wald Area ~ . 450-DOWN Gets 152.94'in2 of Weld Area Total Coverage = 169.70 x 4.48 + 147.82 x 1.30 + 152.94 x 1.30 183.30 x 4.48 + 183.30 x 1.30 + 183.30 x 1.30
= 88.7 %
i 1 60* Gets 175.48 in2 of T/2 Area 600-UP Gets 156.'66'in2 of Wald Area 0 60 -DOWN' Gets 147.08 in2 of Weld-Area
^
Total Coverage = 175.48 x 4.48'+ 156.66 x 1.30 + 147.08 x 1.30 .
, 183.30 x 4.48 + 183.30 x 1.30 + 183.30 x 1.30
~
= 91.0 %
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-CIRC AXIAL 7o 59_ 15_. _.HS_ 19__ _i5_ o 58.6 57.8 57.8 100 91.0 88.7 41.8 Aggregate Coverage =
[ 100 x 38.21 + (91.0 + 88.7) x '(183.30 x 122.5 %)
+ 58.6 x 38.21 + (57.8 + 57.8) x ' (183.3'O x 122.5 %)
+ 41.8 x 221.51 ] /
[ 38.21 x 2 + (183.30 x 122.5 %) x 4 + 221.51 ],- Aggregate Coverage = 68.2 %
. . l I
l l l b .No.94-04 k, sam, z. 1 O, b\012.005 lt9V wot.0 g 001022.003 iKN 002.oS 041.022.0041RPV. Wo?. 04 6 0 t. 0 2 t.0 0 $ % K W - L4 0 2. b 608. 022.00(, IRPV- W82 0(, Pc.,i4 ow c,a
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W02-05 CIRC .70 0 Gets 5.52 in2 of Near Surface Area (75.9 %) 45 0 Gets 22.45 in2 of T/2 Area 450 -DOWN Gets 100 % of Weld Area l Total Coverage = 22.45 + 0.00 + 5.12 = 69.7 % 29.29 + 5.12 + 5.12 60 Gets 20.09 in2 of T/2 Area 60*-DOWN Gets 4.20 in2 of Wald Area Total Coverage = 20.09 + 0.00 + 4.20 = 61.4 % , 29.29 + 5.12 + 5.12 ) 1 ( AXIAL Gets 3.78 in2 of Near Surface Area (52.0 %) 70 0* Gets 3.77 in2 of Total Exam Area ( 9.0 %) 45 & 600 Get 14.57 in2 of T/2 Area
~
45* & 60 Get 3.3'O in2 of T/2 Area Total Coverage = 14.57 + 3.30 + 3.30 = 53.6 %
, 29.29 + 5.12 + 5.12
. 6E8.. N o . 94-01 As ,= = .J, 2 b(
V tot.att.io s s e.py. wax. o, bog.022.CoS 1R9V.uet.cs 60t.02f. 004 1 APV- W#1 04 sos.022.coC tnter-aos.os dos.off.00G _IRev W82 OG Ps ts av Gs
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CIRC ArIAL 70 ,,,g.Q_ _,,15_ 70 ,,,g,g_ g o 7 75.9 61.4 69.7 .52.0 53.6 53.6 9.0 Aggregate Coverage = ( 52.0 x 7.27 + (53.6 + 53.6) x ( 2 9 . 2 9. + 5 .12 + 5 .12')
+ 75.9 x 7.27 +~ (61.4 + 69.7) x (29. 29 + 5.12 + 5.12 )
+ 9.0 x 41'.68 ] /
[ 7.27'x 2 + (29.29 + 5.12 + 5.12) x'4 + 41.68 ) = Aggregate Coverage = 50.0 %
' Total Coverage - 50.0 % x Unobstructed + 50.0 % x obstructed 100 %
= 72.7 %
4 h .Bdo. 94-01 AT7Ac.umodr f. fion.022. cot ( ROV- w o2- o g 608.022.00S I R9V- Wo2 03 .Q[] .
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nas NOZZLE-TO-SERLL WELD & INSIDE RADIUS Tote.1 Area = 209.57 in2 (Near Surface + Weld + T/2) Near Surface Area = 13.87 in8 (Vertical Cross-Section) Weld Area = 24.95 in8 (Vertical Cross-section) T/2. Area = 170.75 in8 (Vertical Cross-Section) Inside Radius Area = 9.21 in8 (Vertical Cross-Section) Total Arek = 164.09 in8 (Near Surface + Weld + T/2) Near Surface Area = 13.62 in8 (Horizontal Cross-Section) Weld Area = 13 . 4 ird (Horizontal Cross-Section) T/2 Area = 137,4,' J.? (Horizontal Cross-Section) O \ Inside Radius Area = 5.50 J8 (Horizontal Cross-Section) INSIDE RADIUS CIRC 70' Gets 4.11 in2 Coverage Vertical Section 70' Gets 3.10 in8 Coverage Horizontal Section~ Covered Area
=
( L.11 + L19. ) x .50 = 50.2 % 9.21 5.56 AXIAL 70' Gets 6.24 in8 Coverage Vertical Section 70* Gets 5.01 in8 Coverage Horizontal Section Covered Area = ( 6. 24 + EJ1 ) x .50 = 78.9 % 9.21 5.56
. beg,.de.M-01 70* INSIDE RADIUS COVERAGE A m -r z BobMWL gg pv.W11 AXIAL ges m o.cotA
. CIRC' gog,Mo.001 gRPV-W12.
.O( V 78.9 50.2 606.e8to.002 A 606.M80*5 1 (t.PV-LJ 45 e,ee.Mo 88SA Aggregate Coverage = 64.6 % 60 ggff,+4g IW~
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g,,,ies.e as i(N- MLS g g,see.co4 i Arv-wI4 PG, t 8 o F G B
O l 1 NOZZLE-TO-SHELL WELD CIRC 70' Gets 13.70 in: Coverage Ver,tical Section 70' Gets 10.72 in8 Coverage Horizontal Section Covered Area - ( 13 . 70 + 10.72 ) x .5 = 88.7 % 13.87 13.62 i CIRC O' Gets 144.35 in8 Coverage Vertical Section O' Gets 98.40 in8 Coverage Horizontal Section Covered Area = ( 146.35 + 98.40 ) x .5 = 64.4 % 209.57 164.09 CIRC 45' & 60' Get 100 t Weld Coverage Vertical Section / 45o & 60' Get 167.93 in8 T/2 Coverage Upper Vertical Section k 45' Gets 145.24 in8 T/2 Coverage Lower Vertical Section 60' Gets 167.93 in8 T/2 Coverage Lower Vertical Section 45' & 60' Get 11.74 in8 Weld Coverage Horizontal Section 45' & 60' Get 75.95 in8 T/2 Coverage Horizontal Section
, Adjacent to Neighboring Inlet Nozzle 45' Gets 75.93 in8 T/2 Coverage Horizontal Section .
Adjacent to Neighboring Outlet Nozzle-60' Gets 75.95 in8 T/2 Coverage Horizontal Section Adjacent to Neighboring Outlet Nozzle Se.e }do. 94-0L A rrAcAm d T A gos.ogo.ool i e PV-wil g ego.cotA p ,oqo.062/ g (PV- Wi2. gg,ogo.cotA pg,cio.caS ggpv 96S
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O 4 5* - Covered Area- = [ ( 167.93 + 24.95 + 24.95 ) 170.75 + 24.95 + 24.95-
+ ( 145.24 + 24.95 + 24.95 )
170.75 + 24.95 + 24.95
+(
75.95 + 11.74 + 11.74 ) 137.05 + 13.42 + 13.42 l
+( 75.93 + 11.74 + 11.74-) ) x .25 137.05 + 13.42 + 13.42
= 77.1-%
60' Covered Area = [ (.167.93 + 24. 95 + 24. 95 ) 170*.75 + 24.95'+.24.95
+ ' ( 167.93 + 24. 95 + 24. 95 )
*170.75 + 24.95 + 24.95
+ ( 75.95'+ 11.74'+ 11.74 )
137.05 + 13.42 + 13.42
+( 75.95 + 11.74 + 11.74 ) ] x .25 137.05+y3.42+13.42 .
= 79.7 %
AXIAL 45' Gets 11.61 in8 Coverage Vertical Section Near Surface 45' Gets 2.78 in8 Coverage' Horizontal Section Near Surface Covered Area = ( 11.61 + 2.78 ) x .50 = 52.1 % 13.87 13.62 AXIAL 'O' Gets 128.63 in: Coverage Vertical Section
,
- O' Gets 31.15 in: Coverage Horizontal Section Covered Area = ( 128.63 + 31.15 ) x .50 = 43.2 %
195.70 150.47 ,
. AXIAL 45' Gets 15'8.01 in 8 Coverage Vertical Section 45* Gets 117.92 in* Coverage Horizontal Section .
Covered Area = (' 158.01 + 117.92 ) x. 50 = 79.6 % 195.70 150.47 Q ,Q,,qd-og An %4 mew,2. Pczo, S.09 . Ik
- Set 94.08Sa .8 'I Bt.1::.W *-=a aga..a;,;1 tu<-wi+ gt;;;.Id I,0:#".
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W-IN NOZZLE-TO-SEELL' WELD - AXIAL CIRC _,Hg_, 0 1 70 A __(1_ o 52.1 43.2 79.6 88.7 79.7 77.1" 64.4 Aggregate coverage =. [ 52.1 x (13.87 + 13.62) + (43.2 + 79.6) x (195.70'+ 150.47) l
+ 88.7 x (13.87 + 13.62) + (79.7 + 77.1) x (170.75 + 24.95 + 24.95 + 137.05 + 13.42 + 13.42) h di + 64.4 x '(209.57 + 164.09) ) /
k [ (13.87 + 13.62) x2+ (195.70 + 150.47) x2 '
+ (170.75 + 24.95 + 24.95 + 137.05 + 13.42 + 13.42) x2
+ (209.57 + 164.09) ]
Aggregate Coverage = 69.2 % S c t.. N o. 9 4 - O l bM.Ame4T f. 6eSo%c. col g gev.wn t bot.ogo.coI A ses.oge.cos. t gev. Wit. an.owo*2d 1 aos.oie.co 5 ggpv w,3 6ss.oio.co S4 O aos.oio.o 84 sos.eso.co4A 605.100.o o i l Rev, p #4 1 RPY- Wil l 6e s. loo.002 i rev- wit. l l Se a.ioo. co s ut.ev- W i 3 ' pos.:08. O o 4- I st.#V- W 84 Ps 21 or ss J
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W-OUT NOZZLE-TO-SHELL WELD & INSIDE RADIUS Total Area = 216.35 ina (Near Surface + Weld + T/2) Near Surface Area = 15.07 in8 (Vertical Cross-Section) Weld Area = 18.84 in8 (Vertical Cross-Section) T/2 Area = 182.44 in8 (Vertical Cross-Section) Inside Radius Area = 8.76 in8 (Vertical Cross-Section) Total Area = 204.11 in8 (Near S'urface + Wald + T/2) Near Surface Area = 15.10 in8 (Horizontal Cross-Section) Weld Area = 13.08 in8 (Horizontal Cross-Section) l T/2 Area = 175.93 in8 (Horizontal Cross-Section) b Inside Radius Area = 8.90 in8 (Horizontal Cross-Section) l
. \
INSIDE RADIUS l CIRC 70* Gets 7.82 in8 Coverage Vertical Section 70* Gets 7.07.in8 Coverage Horizontal Section covered Area = ( 2,JQ + 2,J)],) x .50 '= 84.4'% 8.76 8.90 , AXIAL 70' Gets 8.40 in8 Coverage Vertical Section
~ 70' Gets 7.66 in: Coverage Horizontal Section Covered Area
= ( 3_,.10. + L.if. ) x .50 = 91.0 %
8.76 8.90 g g ,q4.ci Amc.e4mors f
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AXIAL 45' a Gets 12.77 in - Coverage Vertical Section of Near Surface 45' Gets 9.96 in* Coverage Horizontal Section of Near . Surface Covered Area = ( 12.77 + 9.96 ) x .50 = 75'.'3 % 15.07 15.10 0' Gets 180.77 in: Coverage Vertical Section O' Gets 124.50 in* Coverage Horizontal Section Covered Area = ( 180.77 + 124.50 ) x .50 = 77.8 % 201.28 189.01 45' Gets 154.56 in8 Coverage Vertical Section 45' Gets 155.82 in' Coverage Horizontal Section Covered Area = ( 154.56 4 155.82 ) x'.50 = 79.6 % 201.28, 189_.01. W-OUT NOEELE-TO-SEELL WELD AXIAL CIRC
, .11, 0 ,,,,13 ,,, 70 f.Q 15 0
, 75.3 77t8 79.6 41.5 25.8 25.8 12*'6 Aggregate Coverage m-
,[ 75.3 x (15.07 + 15.10) + (77.8 + 79.6) x "(201. 28 + 18 9. 01)
+ 41.5 x,(15.07 + 15.10) + (25.8 + 25.8) x (182.44 *+ 18.84 + 18.84 + 175.93 + 13.08 + 13.08)
+ 12. 6 x (216.35 + 204.11) ] /
[ (15.07 +.15.10) x2+ (201.28 + 1'89.01) x2 .
+ - (182. 44 + 18.84 + 18.84 + 175.93 + 13.08 + 13.08) x 2
+ (216.35 + 204.11) ]
h e,hjo.94-on Aggregate Coverage = 43.7 % Attwmcwr 2 PG250FM T 6e0.040.001 O'*c*osA bas.e%o lt9v was bos.ess.co1A '^/4.py. a n 60s. 800.co$ llN-Wis" sos.oor.cev snpr. wth ben.oso. cat. ggpy.ggs sos. ope.oot iR/V-Mi*' sos. tot 441 I W "
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- NOZ27r-TO-Sgwr7. WELD CIRC 70' Gets 6.17 in8 Coverage Vertical Section 70' Gets 6.36 in8 Coverage Horizontal Section Covered Area = ( 6.17 + 6.36 ) x .50 = 41.5 15.07, 15.10 O' Gets 33.28 in8 Coverage Vertical Section O' Gets 16.47 in8 Coverage Horizontal Section Covered Area = ( 33.28 + 16.47 ) x .50 = 12.6 %
201.28 189.01 45' & 60* Get 3.75 in Weld Coverage Vertical Section 45' & 60' Get 56.95 in8 T/2 Coverage Vertical Section 45' & 60* Get 0.00 in8 Weld Coverage Horizontal Section t 45' & 60' Get 44.92 in8 T/2 Coverage Horizontal Section 45' & 60* Covered Area = [ ( 56.95 + 3.75 + 3.75 ) 182.44 + 18.84 + 18.84
+( 44.92 + 0.00 + 0.00 ) } x .50 175 . 93 + 13 . 0 8 + 13 . 0 8-
~
= 25.8 %
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