Text

Rev 0 to ISI Rept for Unit 1 Catawba 1995 Refueling Outage 8
	ML20085F228
Person / Time
Site:	Catawba
Issue date:	06/07/1995
From:	; DUKE POWER CO.
To:	;
Shared Package
ML20085F204	List: ML20085F200; ML20085F228;
References
	NUDOCS 9506190213
	Download: ML20085F228 (212)
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212 Pages O

FORM NIS-1 OWNERS' DATA REPORT FOR INSERVICE INSPECFION S As required by the Provisions of the ASME Code Rules

1. Ownen Duke Power Company,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 13Q

7. Components Inspected:

Component or Manufacturer or Manufacturer or State or National Appurentance Installer Installer Serial Providence No. Board No. ,

No.

See Section 1 Paragraph 1.1 in the Attached Report O

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Ncar Supplewental sheets in farm af h sketches er drawmss may to used provided 0) sum a S / 2in, a 11 in, m informatwa in mens I through 6 on this dets report is induded on each sheet and Q) each sheet as numbered and the numtwr af sheets se recorded at the top of the farm i

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9506190213 950612 PDR ADDCK 05000413 D PDR ,

212 PageS

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FORM NIS-1 (back)

8. Examination Dates 12/27/93 to 03/21/95 Inspection Interval from 06/29/85 to 06/29/95

10. Abstract of Examinations. Include a list of examinations and a statement concerning status of work required for current interval. See attached report.

11. Abstract of Conditions Noted. See attached report.

12. Abstract of Corrective Measures Recommended and Taken. See attached report.

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

Date g } O 19 i Signed Duke Power Co. By ~

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Owner Certificate of Authorization No. (if applicsble) N/A Expiration Date N/A CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and/or the State or Province of I and employed by

/] 'The HSBI&l Co of have inspected the components described in this Owners Data Report during the period 12./L7 /93 io 1/21/95 ana stai,ihai to the de,i of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owners' Data Report in accordance with the requirements of the ASME code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owners' Data Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for I any personalinjury or property damage or loss of any kind arising from or connected with this i l

inspection.

Date __ b' 19 r N Commissions -

bnspector's Signature National Board, State, Province and No.

'The Hartford Steam Boiler inspection & Insurance Co.

200 Ashford Center Nonh Suite 300 Atlanta Ca.,30338 O

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I INSERVICE INSPECTION REPORT l

UNIT 1 CATAWBA 1995 REFUELING OUTAGE 8 ,

.L l Locadon: 4800 ConcordRoad, York, South Camlina 29745 i

f. NATIONAL BOARD NO.130 i Commercial Service Date: June 29,1985 4

b Owner: Duke PowerCompany 1 l

526 S. Chumh St. ,

' Charlotte, N. C. 28201-1006 l l I j Revision 0 !

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l n PmparedBy: ( /. .

- Date d / 9f

ReviewedBy: , d/ Date / /96~ ,

Appmved By: Y M Date b 9b Copy No. 3 O AssignedTo NRC Document Control O Ce -iied x u--ned

l O coxrnot'sonisr^1= orion ,

Cony No. Assistned To ,

Original J. O. Barbour 1 J. E. Cherry 2 R. C. Giles 3 NRC Document Control 1 UNCONTROT TRD DISTRIBUTION 4 C. A. Ireland (AIA, Atlanta, GA)

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A' TABLE OF CONTENTS Section Title Revision

1. General Information 0

2. Summary of Inservice Inspections for Outage 8 0

3. First Ten Year Interval Inspection Status 0

4. Final Inservice Inspection Plan for Outage 8 0

5. Results ofInspections Performed During Outage 8 0

6. Reportable Indications 0

7. Personnel, Equipment, and Material Certifications 0

8. Problem Investigation Process Forms 0

9. Reference Documents 0

10. Class 1 and 2 Repairs and Replacements 0 i

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d. 1.0 GeneralInformation l This report describes the Inservice Inspection of Duke Power Company's l Catawba Nuclear Station Unit 1 during the 1995 Refueling Outage (also i referred to as Outage 8), which is in the Third Outage in the Third Inspection :

Period of the First 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 examinations and corrective action taken when unacceptable conditions were found. In addition, there is a section included for Repairs and Replacements required since ;

December 27,1993.

1.1 Identification Numbers LLem Manufacturerar Manufacturer State or National lan. taller or Installer Province Re Board Serial No. Ns Unit 1 Duke Power Co. N/A N/A 130 -

Reactor Vessel Westinghouse Duke Power Co. N/A N/A l Pressurizer Westinghouse DCPT-1911 N/A W18589 i

Steam Generator 1A Westinghouse DCPT-1902 N/A W11300 Steam Generator 1B Westinghouse DCPI'-1901 N/A W11299 Steam Generator 1C Westinghouse DCPT-9y4 N/A W11302 ;

j Steam Generator ID Westinghouse DCPf-1903 N/A W11301 !

Reactor Coolant Duke Power Co. C1NC N/A 126 l

" System Residual Heat Duke Power Co. C1ND N/A 115 l Removal System 3 Safety injection Duke Power Co. C 1NI N/A 128 l l

System Chemical and Duke Power Co. C1NV N/A 127 l l !

Volume Control .

I System Auxiliary Feedwater Duke Power Co. C-1CA N/A 121 l System Feedwater System Duke Power Co. C-1CF N/A 120 ,

C-1FW N/A 91 i Refueling Water Duke Power Co.

l System !

Main Steam Supply Duke Power Co. CISA N/A 114 !

to Auxiliary i

Equipment '

Main Steam System Duke Power Co. C-ISM N/A 122 ,

Main Steam Vent to Duke Power Co. C -ISV N/A 96 !

Atmosphere System ;

Containment Spray Duke Power Co. C-1NS N/A 118 l System {

Refueling Outage Report EOC 8 Page 1 of 2 Catawba Unit 1 Revision 0 ;

Section 2 June 6,1995

O hem Manufacturer Manufacturer Sandrar Nadional orInstaller orInstaller Provinro No. Board brint No.' h 1

Safety Injection Southwest ,

0020 N/A 310 i Accumulator Tank Fabrication & l 1A Welding Co. l Safety injection Southwest 0019 N/A 300 Accumulator Tank Fabrication &

IB Welding Co.

Safety injection Southwest 0018 N/A 308 Accumulator Tank Fabrication &

IC Welding Co. .

Safety Injection Southwest 0021 N/A 311 Accumulator Tank Fabrication & i 1D Welding Co.

f The Reactor Vessel, Steam Generators, Pressurizer, Safety Injection >

Accumulator Tanks, Reactor Coolant Pumps, and Reactor Coolant System .

Piping were manufactured by or for Westinghouse Electric Corporation, Pittsburgh, PA under purchase agreements from Duke Power Company.

All other systems were fabricated and installed by or for Duke Power i Company,526 South Church Street, Charlotte, N.C. 28201-1006. !

1.2 Authorized Nuclear Innervice InanectorM ,

Name: P N. McGill j Employer. The Hartford Steam Boiler Inspection & Insurance Company ,

Business The Hartford Steam Boiler Inspection & Insurance Co.

Address: 200 Ashford Center North Suite 300 Atlanta, GA 30338 1 i

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Refueling Outage Report EOC 8 Page 2 of 2 Catawba Unit 1 Revision 0 ;

Section 2 June 1,1995 l i

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2.0 Summarv ofInnervim Inanections for Outnae 8 The information shown below provides and abstract of ASME Section XI Class 1, Class 2, and Augmented Items scheduled and examined during Outage 8 at Catawba Nuclear Station.

2.1 Claca 1 Inanections Examination Category B A Pmssum Retnining Welds In Reactor Vessel Total Total Item Number Description Sch derki Examined During During Outage Outage B01.010 Shell Welds B01.011 Circumferential 0 0 B01.012 Longitudinal 0 0 B01.020 Head Welds B01.021 Circumferential 0 0 B01.022 Meridional Welds 0 0 B01.030 Shell to Flange Weld 0 0 O B01.040 Head to Flange Weld 0 0 B01.050 Repair Welds B01.051 Beltline Region N/A N/A TOTALS 0 0 0 Page 1 of 18 Refueling Outage Report EOC 8 Catawba Unit 1 Revision 0 Section 2 June 1,1995

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O Prnmination Category B-B Pressure Retaining Welds in Vessels Other l Than ReactorVessels Total Total \

Item Number Desenption Sch aurd Examined During Dunng i Outage Outage Pressurizer l B02.010 Shell to Head Welds B02.011 Circumferential 0 0 ;

B02.012 Longitudinal 0 0 l

B02.020 Head Welds B02.021 Circumferential N/A N/A -

B02.022 Meridional N/A N/A Steam Generator (PrimarySide)

B02.030 Head Welds B02.031 Circumferential N/A N/A ,

B02.032 Meridional N/A N/A -

B02.040 Tubesheet to Head Weld 1 1 Heat Exchangers (PrimarySide)

B02.050 Head Welds I

B02.051 Circumferential N/A N/A B02.052 Meridional N/A N/A B02.053 Longitudinal N/A N/A Shell(PnmarySide)

B02.060 Tubesheet to Shell(or Head) N/A N/A '

Welds B02.061 Tubesheet to Shell Welds N/A N/A

'IOTALS 1 1 i

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O Re ueling Outage Paport EOC 8 Page 2 of 18 Catawba Unit i Revision 0 Section 2 June 1,1995 l

' Examination Category B-D Full Penetration Welds of Nozzles in Vessels Inspection Program B Total Total Item Number Descdption Sch a ! M Examined During Dunng Outage Outage Reactor Vessel B03.090 Nozzle to Vessel Welds 0 0 B03.100 Nozzle Inside Radius See' tion 0 0 Pressurizer B03.110 Nozzle to Vessel Welds 0 0 B03.120 Nozzle Inside Radius Section 0 0 l Steam Generators (PdmarySide) l B03.130 Nozzle to Vessel Welds N/A N/A B03.140 Nozzle Inside Radius Section 0 0 l

Heat E.tchangers (Pdmary Side) i O B03.150 B03.160 Nozzle to Vessel Welds Nozzle Inside Radius Section N/A N/A N/A N/A TOTAIR 0 0 Examination Category B E Pressure Retaining PartialWelds in Vassels Total

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Total l Item Number Description Scheduled Examined Dunng Dunng Ne owe BM.010 PartialPenetration Welds )

BM.011 Vessel Nozzels N/A N/A BM.012 Control Rod Drive Nozzles T 20 B04.013 Instrumentation Nozzles 15 15 Pressurizer BM.020 Heater Penetration Welds 20. 20 i

7OTALS 55 55 I

o Refueling Outage Report EOC 8 Page 3 of 18

Catawba Unit 1 Revision 0 Section 2 June 1,1995

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Q Examination Category B-F Pressure Retaining Dissimilar Metal Welds Total Total Item Number Descdption Scheduled Examined During Dunng Outage Outage Reactor Vessel B05.010 Nominal Pipe Size 2.4" Nozzle to Safe End Butt 0 0 Welds B05.020 Nominal Pipe Size < 4" Nozzle to Safe End Butt N/A N/A Welds B05.030 Nozzle to Safe End Socket N/A N/A Welds Pressurizer B05.040 Nominal Pipe Size 2.4" Nozzle to Safe End Butt 0 0 Welds B05.050 Nominal Pipe Size < 4" Nozzle to Safe End Butt N/A N/A Welds O 80s.000 nezzie te sefe sea socket Welds n'^ N'^

Steam Generators B05.070 Nominal Pipe Size 2 4" Nozzle to Safe End Butt 0 0 Welds B05.080 Nominal Pipe Size < 4" Nozzle to Safe End Butt N/A N/A Welds B05.0W Nozzle to Safe End Socket N/A N/A Welds Heat Exchangers B05.100 Nominal Pipe Size 2 4" Nozzle to Safe End Butt N/A N/A Welds B05.110 Nominal Pipe Size < 4" Nozzle to Safe End Butt N/A N/A Welds B05.120 Nozzle to Safe End Socket N/A N/A Welds Refueling Outage Report EOC 8 Page 4 of 18 Catawba Unit 1 Revision 0 Section 2 June 1,1995

i Q A=mination Category B F (Continued) ;

l Tctal Total Item Number Desenption Scheduled Exumined Dunng Dunng ;

Outag Outage Piping ,

B05.130 Nominal Pipe Size z 4" l Dissimilar Metal Butt Welds 0 0 l B05.140 Nominal Pipe Size < 4" ;

Dissimilar Metal Butt Welds N/A N/A ;

B05.150 Dissimilar Metal Socket N/A N/A i Welds !

TOTALS 0 0 Examination Category B-G-1 Pressure Retaining Bolting, Greater Than l 2"in Diameter 1btal Total l Item Number Desenption Scheduled Examined l Dunng Dunng ;

Outage Outage :

0 B06.010 Reactor Vessel Closure Head Nuts 0 0 B06.020 Closure Studs, (in place) N/A N/A B06.030 Closure Studs, (when 0 0 removed)

B06.040 Threads in Flange 0 0 ]

B06.050 Closure Washers, Bushings 0 0

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Pressurizer N/A

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B06.060 Bolts and Studs N/A '

B06.070 Flange Surface, (when -

connection disassembled) N/A N/A B06.080 Nuts, Bushings, and N/A N/A Washers O

Refueling Outage Report EOC 8 Page 5 of 18 Catawba Unit 1 Revision 0 Section 2 June 1,1995 l

n Examination Category B G-1 (Continued)

U Total Total Item Number Description Scheduled Examined During During Outage Outage

> Steam Generators B06.090 Bolts and Studs NA NA B06.100 Flange Surface,(when connection disassembled) N/A NA B06.110 Nuts, Bushings, and Washers NA NA Heat Exchangers B06.120 Bolts and Studs NA N'A B06.130 Flange Surface,(when connection disassembled) N'A N'A B06.140 Nuts, Bushings, and Washers NA N'A Piping B06.150 Bolts and Studs NA NA B06.160 Flange Surface,(when (nj connection disassembled) N'A NA B06.170 Nuts, Bushings, and Washers NA NA Pumps B06.180 Bolts and Studs 0 0 B06.190 Flange Surface, (when connection disassembled) 0 0 (not disanasmbled)

B06.200 Nuts, Bushings, and Washers NA NA Valves B06.210 Bolts and Studs NA NA B06.220 Flange Surface,(when connection disassembled) N'A N'A B06.230 Nuts, Bushings, and Washers NA NA TOTALS 0 0 0

Refueling Outage Report EOC 8 Page 6 of 18 Catawba Unit 1 Revision 0 Section 2 June 5,1995

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m V Examination Category B-G 2 Pressure Retaining Bolting,2" and less in Diameter Total Total Item Number Description Scheduled Examined During During Outage Outage Reactor Vessel B07.010 Bolts Studs, and Nuts NA NA Pressurizer .

B07.020 Bolts Studs, and Nuts 0 0 Steam Generators B07.030 Bolts, Studs, and Nuts 2 2 Heat Exchangers B07.040 Bolts, Studs, and Nuts NA NA Piping B07.050 Bolts, Studs, ar.d Nuts 0 0 0 B07.060 Pumns Bolts. Studs, and Nuts 0 0 Valves B07.070 Bolts, Studs, and Nuts 5 5 i

CRD flousings B07.080 Bolts, Studs, and Nuts (when 0 0 housing disassembled) ***=='"*l* l TOTALS 7 7 l l

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Examination Category B-H Integral Attachments for Vessels

.] Total Total Item Number Descnption Scheduled Examined Dunng Dunng Outage Outage Reactor Vessel B08.010 Integrally Welded 3 3 Attachments Pressurizer 808.020 Integrally Welded 0 0 Attachments Steam Generators -

B08.030 Integrally Welded N/A N/A Attachments Heat Exchangers B08.040 Integrally Welded N/A N/A Attachments

'IOTALS 3 3 O

Refueling Outage Report EOC 8 Page 8 of 18 Catawba Unit 1 Revision 0 Section 2 June 1,1995

1 p Examination Category B J Pressure Retnining Welds in Piping I O

Total Total :

Item Number Description Scheduled Examined l During During \

Outage Outage l B09.010 Nominal Pipe Size 14" Circumferential Welds l B09.011 1 1 B09.012 Longitudinal Welds 1 0 0 i i

B09.020 Nominal Pipe Size < 4" ;

B09.021 Circumferential Welds 2 2 l B09.022 Longitudinal Welds 1 NA NA B09.030 Branch Pipe Connection Welds ;

B09.031 Nominal Pipe Size 2 4 0 0 B09.032 Nominal Pipe Size < 4" 0 0 i

B09.040 Socket Welds 1 1 i TOTALS 4 4 Examination Category B K 1 Integral Attachments for Piping, Pumps ;

and Valves Total Total Item Number Description Scheduled Examined During During Outage Outage Piping B10.010 Integrally Welded N'A NA Attachments Pumps B10.020 Integrally Welded NA Nh ;

Attachments Valves B10.030 Integrally Welded N'A NA Attachments TOTALS NA NA 1 Longitudinal welds that intersect circumferential welds are examined as required by ASME Section XI, Table IWB-2500-1, Category B-J. However, for reporting purposes, the totals do not include the number of longitudinal welds examined during this outage.

Refueling Outage Report EOC 8 -

Page 9 of 18 Catawba Unit 1 Revision 0 Section 2 June 6,1995

i (a3 Examination Category B-L 1, B-M 1 Pressure Retaining Welds in Pump Casings andValve Bodies ;

B-Ie2, B-M 2 Pump Casings and Valve Bodies Total Total Item Number Description Scheduled Examined During During Outage Outage Pumps B12.010 Pump Casing Welds N/A N/A )

B12.020 Pump Casing N/A N/A l Valves B12.030 Valves, Nominal Pipe Size < N/A N/A 4" Valve Body Welds B12.040 Valves, Nominal Pipe Size z 1 1 4" Valve Body Welds B12.050 Valve Body, Exceeding 4" 0 0 Nominal Pipe Size

'IOTALS 1 1 O

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R==mination Category B N-1 InteriorofReactorVessel ,

1 B N-2 IntegrallyWeldedCom Support j Stmetums and Interior AH=ahments ' i to ReactorVessels l B-N-3 Removable Com Support Structums i i

Total Total l Item Number Desenption Sch duid Examined i Dunng Dunng ;

Outage Outage i Reactor Vessel l B13.010 Vessel Interior 0 0

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Reactor Vessel (BWR) l B13.020 Interior Attachments Within N/A N/A i Beltline Region l B13.021 Interior Attachments N/A N/A !

Beyond Beltline Region B13.022 Core Support Structure N/A N/A l t

Reactor Vessel (PWR) )

B13.030 Interior Attachments N/A N/A Beyond Beltline Region l O B13.031 Interior Attachments Beyond Beltline Region N/A N/A !

i B13.032 Core Support Structure 0 0 !

TOTAIR 0 0 l I

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Framination Category B.O Pmssum Retaining Welds in Control Rod i Housings !

lbtal Total i Item Number Description Scheduled Examined i Dunng Dunng i Outage Outage i Reactor Vessel {

B14.010 Welds in CRD Housing 0 0 !

IDTAIA 0 0 i I

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All Pressure Retaining Components Examination Category B-P Total Total Item Number Description Scheduled Examined During During Outage Outage Reactor Vessel B15.010 Pressure Retaining Boundary 0 0 B15.011 Pressure Retaining Boundary 1 1 Pressurizer :

B15.020 Pressure Retaining Boundary 0 0 B15.021 Pressure Retaining Boundary 1 1 Steam Generators B15.030 Pressure Retaining Boundary 0 0 B15.031 Pressure Retaining Boundary 4 4 Heat E. whangers B15.040 Pressure Retaining Boundary N/A N/A B15.041 Pressure Retaining Boundary N/A N/A l l

Piping B15.050 Pressure Retaining Boundary 0 0 B15.051 Pressure Retaining Boundary 10 10 Pumps B15.060 Pressure Retaining Boundary 0 0 B15.061 Pressure Retaining Boundary 4 4 Valves B15.070 Pressure Retaining Boundary Covered in Covered in B15.050 B15.050 B15.071 Pressure Retaining Boundary Covered in Covered in B15.051 B15.051 7DTALS 20 20 l

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Refueling Outage Report EOC 8 Page 12 of 18 Catawba Unit 1 Revision 0 Section 2 June 1,1995

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L Ernmination Category B-Q Steam GeneratorTubing o Total Total }

Item Number Desenption Sch~I>>ld Examined 1 '

Dunng . Dunng Outage Outage -

B16.010 Steam Generator Tubing in N/A N/A :

Straight Tube Design l Steam Generator Tubing in 2- 2 B16.020 U-Tube Design IDTAIR N/A N/A F1.1 Component Supports Total Total Item Number Desenption Scheduled Examined Dunng Dunng Outage Outage F1.01 Reference Section 4.0 of this 2 2 report.

TOTAIR - 2 2 2.2 Class 2 Inspections Framirtation Category C-A Pressum Retaining Welds in Pressure Vessels Total Total Item Number Desenption Schamrar Examined During Dunng Outage Outage C01.010 Shell Circumferential Welds 2 2 C01.020 Head Circumferential Welds 0 0 C01.030 Tubesheet to Shell Weld 0 0 1DTAIR 2 2 2 Steam Generator Tubing is examined and documented by the Diversified Services Division /

NDE of the Electric System Support Department, as required by the Station Technical O- Specifications and is not included in this report.

Refueling Outage Report EOC 8 Page 13 of 18 Catawba Unit 1 Revision 0 Section 2 June 1,1995

Ernminntion Category C B Pressure Retaining Nozzle Welds in Vessels Total Total Item Number Description Scheduled Examined During During Outage Outage CO2.010 Nozzles in Vessels s 1/2" Nominal Thickness CO2.011 Nozzle to Shell (Or Head) 0 0 Weld CO2.020 Nozzles Without Reinforcing l Plate in Vessels > 1/2" Nominal Thickness l CO2.021 Nozzle to Shell (or Head) Weld 0 0 l CO2.022 Nozzle Inside Radius 0 0 l Section 3 l l

CO2.030 Nozzles With Reinforcing Pl 2te in Vessels > 1/2" Nominal Thickness CO2.031 Reinforcing Plate Welds to NA NA Nozzle and Vessel CO2.032 Nozzle to Shell (or Head) NA NA O- Welds Inside ofVessel Accessible Inside of Vessel Inaccessible TOTALS 0 0 3 Nozzle Inside Radius Sections are examined as required by ASME Section XI, Table IWC -

2500-1, Category C-B. However for reporting purposes, the totals do not include the number of inside radius sections examined during this outage.

Refueling Outage Report EOC 8 - Page 14 of 18 Catawba Unit 1 Revision 0 Section 2 June 6,1995

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Examination Category C-C Integral Attachments for Vessels, Piping, Pumps, and Valves Total Total i Item Number Description Scheduled Examined 7 Dunng Dunng Outage Outage Pressure Vessels C03.010 Integrally Welded 0 0 Attachments Piping C03.020 Integrally Welded 6 6 Attachments Pumps C03.030 Integrally Welded 0 0 Attachments Valves C03.040 Integrally Welded N/A N/A Attachments Examination Category C D Pressure Retaining Bolting Greater Than 2" in Diameter Tc:al Total Item Number Description Schululed Examined During Dunng Outage Outage Pressure Vessels C04.010 Bolts and Studs N/A N/A Piping C04.020 Bolts and Studs N/A N/A l Pumps C04.030 Bolts and Studs N/A N/A Valves C04.040 Bolts and Studs N/A N/A

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70TAIR N/A N/A O

Refueling Outage Report EOC 8 Page 15 of 18 Catawba Unit 1 Revision 0 Section 2 June 1,1995

Examination Category C-F Pressum Retaining Welds in Piping Total Tctal Item Number Desenption Sch d"1M Faumined During During .

Outage Outage C05.010 Piping Welds S 1/2" Nominal Wall Thickness C05.011 Circumferential Weld 13 13 C05.012 Longitudinal Weld 4 1 1 C05.020 Piping Welds > 1/2" Nominal Wall Thickness C05.021 Circumferential Weld 1 15 115 C05.022 Longitudinal Weld 4 0 0 C05.030 PipeBranch Connections >

4"NominalBrunch Pipe Size C05.031 Circumferential Weld N/A N/A C05.032 Longitudinal Weld N/A N/A TDTALS 25 25 O

Examination Category C-G Pmssum Retnining Welds in Pumps and Valves Total Total Item Number Description Sch de!!& Examined Dunng During Outage Outage Pumps C06.010 Pump Casing Welds N/A N/A Valves C06.020 Valve Body Welds 11 11 7DTALS 11 11 4 Longitudinal welds that intersect circumferential welds are examined as required by ASME Section XI, Table IWC-2500-1 Category C-F. However, for reporting purposes, the totals as shown in Section 3.0 of this report do not include the number oflongitudinal welds examined during this outage.

5 Four Feedwater (CF) Terminal End Welds were re-examined per PIP Serial # 0-C93-0631.

For reporting purposes these welds will not be counted in the totals as shown in Section 3.0 of O this report .

Refueling Outage Report EOC 8 Page 16 of 18 Catawba Unit 1 Revision 0 Section 2 June 1,1995

1 A Ernmination Category C-II All Pressure Retaining Components

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Total Total

. Item Number Description Scheduled Examined During During Outage Outage Pressure Vessels C07.010 Pressure Retaining 0 0 Components C07.020 Pressure Retaining 6 56 Components Piping C07.030 Pressure Retaining 1 06 Components C07.040 Pressure Retaining 48 456 Components -

Pumps C07.050 Pressure Retaining 0 0 Components C07.060 Pressure Retaining 7 66 Components O Valves C07.070 Pressure Retaining Covered in Covered in Components C07.030 C07.030 C07.080 Pressure Retaining Covered in Covered in Components C07.040 C07.040 TOTALS 62 566 F1.2 Component Supports Total Total Item Number Description Scheduled Examined During During Outage Outage F1.02 Reference Section 4.0 of this 1 1 report TOTALS 1 1 6 Items that were not examined before the end of EOC 8 will be examined prior to June 29,1995, which is the end of the First inspection Interval. The results of these examinations will be submitted in a separate report.

Refueling Outage Report EOC 8 Page 17 of 18 Catawba Unit 1 Revision 0 Section 2 June 6,1995

(. 2.3 .Auemented Insnections L)

Total Total Item Number Desenption Scheduled Examined During Dunng Outage Outage G01.001 Reactor Coolant Pump 3 3 Flywheels G02.001 Steam Generator Tube Ref. Note Ref. Note Examinations on Preheater from Item from Item Section No. No.

B16.020 B16.020 G03.001 Main Steam Pipe Rupture 6 6 Protection G04.001 Class 2 Piping Welds 0 0 ,

G05.001 Thermal Stress Piping (NRC 0 0 Bulletin 88-08)

G06.001 Safety Injection 1

/O Accumulator Nozzles (NRC 0 0 Information Notice 91-05)

G07.001 NI System Cold Legs (Ref. T 20 PIP # 2-C94-0874) 29 29 :

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TOTALS A detailed description of each examination listed in Sections 2.1 through 2.3 I are located in Section 4 of this report. Results of each examination are located in Section 5 of this report.

O Page 18 of 18 Refueling Outage Report EOC 8 Catawba Unit 1 Revision 0 Section 2 June 1,1995

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/'- 3.0 First Ten Year IntervalInsnection Status U

The completion status ofinspections required by the 1980 ASME Section XI Code, including addenda through Winter 1981, is summarized in this section. l The requirements are listed by the ASME Section XI Examination Category as ;

def'med 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 Inspections Examination Inspections Inspections Percentage Deferral Categorv Descrintion Reauired Completed Comnletegi Allowed 7 BA Pressure Retaining Welds 14 Welds 14 Welds 100 % Yes in Reactor Vessel B-B Pressure Retaining Welds 8 Welds 8 Welds 100 % No in Vessels Other than Reactor Vessel B-D Full Penetration Welds of 36 36 100 % Partial Nozzles in Vessels Inspections Inspections B-E Pressure Retaining 55 Welds 55 Welds 100 % No O Partial Penetration Welds in Vessels B-F Pressure Retaining 46 Welds 46 Welds 100 % No Dissimile.r Metal Welds B-G-1 Pressure Retaining 366 Items 366 Items 100 % Yes Bolting Greater than 2 Inch Diameter B-G-2 Pressure Retaining 59 59 100 % No Bolting 2 Inches and Less Connections Connections i in Diameter B-II Integral Attachment for 12 12 100 % No Vessels Attachments Attachments B-J Pressure Retaining Welds 206 Welds 206 Welds 100 % No in Piping 7 Deferral on inspection to the end of the interval as allowed by ASME Section XI Tables IWB-2500-1 and IWC-2500-1.

Refueling Outage Report EOC 8 Page 1 of 4 Catawba Unit 1 Revision 0 Section 3 June 6,1995

I Class 1 Inspections (Continued)

Examination Inspections Inspections Percentage Deferral Categorv Descriotion Reauired Comoleted Comoleted Allowed B-K-1 Integral Attachments for None N/A. N/A N/A !

Piping, Pumps and Valves B-L-1 Pressure Retaining Welds None N/A N/A N/A in Pump Casings B-L-2 Pump Casings None N/A N/A N/A B-M 1 Pressure Retaining Welds 2 Welds 2 Welds 100% Yes in Valve Bodies ,

B-M-2 Valve Body > 4 in. 5 Valves 8 5 Valves 100 % Yes Nominal Pipe Size B-N-1 Interior of Reactor Vessel 3 Items 3 Items 100 % No B-N-2 Integrally Welded Core None N/A N/A N/A Support Structures and Interior Attachments to 'l O Reactor Vessels B-N-3 Removable Core Support 1 Item 1 Item 100% Yes Structures B-0 Pressure Retaining Welds 3 Housings 3 Housings 100% Yes in Control Rod Housings B-P All Pressure Retaining Components System Leakage Test 140 140 100 % No Components Components System Hydrostatic Test 20 20 100% Yes Components Components B-Q Steam Generator Tubing As stated in 100% Station No Station Technical Technical Specifications Specifications Met F1.01 Class 1 Component 267 Supports 267 Supports 100 % No Supports 8 Reference Request For Relier Serial Number 94-03 Refueling Outage Report EOC 8 Page 2 of 4 Catawba Unit 1 Revision 0 Section 3 June 6,1995

Class 2 Inspections Examination Inspections inspections Percentage Deferral Catesorv Qggerintion Reauired Comnleted Comnieted Allowed C-A Pressure Retaining Welds 9 Welds 9 Welds 100 % No in Pressure Vessels CB Pressure Retaining Nozzle 6 Welds 6 Welds 100 % No Welds in Vessels ;

C-C Integral Attachments for 33 3 100 % No Vessels, Piping, Pumps Attachments Attachments and Valves C-D Pressure Retaining None N/A N/A N/A $

Bolting Exceeding 2 Inches in Diameter C-F Pressure Retaining Welds 347 Welds 347 Welds 100 % No in Piping CG Pressure Retaining Welds 26 Welds 26 Welds 100 % Yes in Pumps and Valves l

CH All Pressure Retaining Components i

System or Component 70 @ 98.57 %9 No Functional Test Components Components -

System Hydrostatic Test 88 8 94.32 %9 Yes !

Components Components l

F1.02 Class 2 Component 552 Supports 552 Supports 100 % No !

Supports i

i 1

9 Items that were not examined before the end of EOC 8 will be examined prior to June 29,1995, which is the end of the First Inspection Interval. The results of these examinations will be submitted in a separate report.

Refueling, Outage Report EOC 8 Page 3 of 4 Catawba Unit 1 Revision 0 Section 3 June 6,1995 1

)

i Augmented Inspections Descriotion Percentage Comniele Reactor Coolant Pump Flywheels 100% of Technical Specifications met Steam Generator Tubes on Preheater Section 100% of requirements .

Main Steam Pipe Rupture Protection 100% of requirements Class 2 Piping Systems 100% of requirements Thermal Stress Piping (NRC Bulletin 88-08) 100% of requirements NI System Cold Leg (Ref. PIP # 2-C94-0874) 100% of requirements i

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O Refueling Outage Report EOC 8 Page 4 of 4 Catawba Unit 1 Revision 0 Section 3 June 7,1995 .

i

4.0 Finni Innervice Insnection Plan For Outnae 8 The final ISI Plan shown in this section lists all ASME Section XI Class 1 1 and 2, and Augmented examinations credited for Outage 8 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:

A. Items examined by NDE (excluding Pressure Testing)

Item Number = ASME Section XI Tables IWB-2500-1 (Class 1), IWC-2500-1 (Class 2), IWF-2500-1 (Class 1, and Class 2), Augmented Requirements ID Number = Unique Identification Number Drawing Number = Location and/or Detail Drawing Locs. = Location Insp. Req. = Examination Technique - Magnetic Particle, Dye Penetrant, etc.

Proc. Numbers = Examination Procedures Material Type / Grade = General Description of Material -

Diam./ Thick = Diameterffhickness Calib. Block = Calibration Block Number Comments = General and/or Detail Description O

Refueling Outege Report EOC 8 Page 1 of 2 Catawba Unit 1 Revision 0 Section 4 June 1,1995

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PAGE 11 O
PROGRAM: NISIRUPe-GAISIO2 DUKE P0HED CCHPANY FILES COO 7133 DATE 05/31/95 PLANTS CATA>eA LNIT 1 PRE-SERVICE AND IN-SERVICE INSPECTItR4 SYSTEM KEY: ITEM NLABER 809 CATA>eA 1 INSERVICE INSPECTICH LISTING OUTAGE 8 INSP PROC. MATERIAL DIAM./ CALIB ITEM MDBER ID. NLR1BER DRAMING NUPSERS LOCS. REG. PARBERS TYPE / GRADE THICK BLOCK CCRf1ENTS
~~====== ==================== ==================== ===== ==== ======== ========== ====== ===== ========================~~
E09.010.000 CLASS 1 PIPING NOMINAL PIPE SIZE *** *** ******* ***** . m ** *************** m ************
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~~====== ==================== ==================== ===== ==== ======== ========== ====== ===== ========================~~
B09.021.073 1HC56-01 CH-1NC-056 PT NDE-35 SS 03.00 SELECTIG4 CRITERIA 4.2.1 CH-1553-1.0 00.438 D39.030.C00 CLASS 1 PIPING BRANCH PIPE *******ww m mum ***w . ***** *** m *w m ** m ****www*******
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PROGRAN: NISIRUNB-QAISIC2 DUKE PtMER CtN8ANY FILE: C007133 DATE 05/31/95 PLANT: CATAteA UNIT 1 PRE-SERVICE AND IN-SERVICE INSPECTIEM SYSTEN KEY: ITEN NUPSER B12 CATA>e41 INSERVICE INSPECTItN LISTING OUTAGE 8 4
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~~====== ==================== =================ss ===== ==== ======== ========== ====== ===== ========================~~
B12.050.003A INO-1B CH-1ND-038 VT3 QAL-14 SS 12.00 REF. REQUEST FOR RELIEF 594-03 CPM 1205.00-262 02.043 I
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s PROGRAM: NISIRUMB-GAISIS2 DtKE PmE2 COPANY PAGE 15 FILE: C007133 DATE 05/31/95 PLANT: CATAteA UNIT 1 PRE-SERVICE AND IN-SERVICE INSPECT 15N SYSTEM KEY: ITEM NUteER 812 CATAteA 1 INSERVICE INSPECTION LISTING OUTAGE 8
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~~====== ==================== ==================== ===== ==== ======== ========== ====== ===== ========================~~
C12.050.C04D INI-888 CH-1NI-021 VT3 QAL-14 SS 10.00 ----- REF. REQUEST FOR RELIEF #94-03 Ctet 1205.00-71 01.000 E12.050.005 INSPECT ENE OF THE FOLLtMING EIGHT *** ******* ***** , _ . _ ***** INSPECT IF DISASSEteLED*******
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PROGRAM: MISIRUPS-9AISIK2 DtKE PtDE2 Ctf9ANY PAGE 15 FILE: C007133 DATE 05/31/95 i
PLANT: CATAMBA UNIT 1 PRE-SERVICE AND IN-SERVICE INSPECTIt94 SYSTEM KEY: ITEM NUPSER B13 CATAPBA I INSERVICE INSPECTIt94 LISTING ERITAGE 8 INSP PROC. NATERIAL OIAM./ CALIB ID. MASER DRahING NL7BERS LOCS. RES. HUPSERS TYPE / GRADE THICK BLOCK CCDMENTS
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PLANT CATApeA tMIT I PRE-SERVICE Ape IN-SERVICE INSPECTIEM SYSTEM KEY: ITEM NUPEER B14 CATApeA 1 INSERVICE INSPECTItti LISTING OUTAGE 8 INSP PROC. MATERIAL' DIAM./ CALIS ITEM PRJPBER 10. PUBER DRAMING PRJPBERS LOCS. RE9. NUPSERS TYPE / GRADE THICK BLOCK CtWWENTS
====== ==================== ==================== ===== ==== ======== ========== ====== ===== ================s=======
E14.010.000 REACTOR VESSEL CR0 HOUSINGS MELDS ** *** ****www ***** _._ ***** INSPECT EDE OF THE FOLLEMING**
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PAGE 13 O
FILE: C007133 DATE 05/31/95 PLANT: CATAMBA UNIT 1 PRE-SERVICE AND IN-SERVICE INSPECTItM SYSTEM KEY: ITEM HutBER BIS CATA>BA 1 INSERVICE INSPECTION LISTING CUTAGE 8 INSP PROC. MATERIAL DIAM./ CALIB ITEpePAPBER ID. MJtBER DRAMING PAFBERS LOCS. REG. PARBERS TYPE / GRADE THICK BLOCK CtN91ENTS
~~====== ==================== ==================== ===== ==== ======== ========== ====== ===== ========================~~
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FILE: C007133 DATE 05/31/95 PLANT: CATAHBA UNIT 1 PRE-SERVICE AND IN-SERVICE INSPECTItN SYSTEM KEY: ITEM PAktER C05 CATANA 1 INSERVICE INSPECTItN LISTING OlJTAGE 8 INSP FROC. MATERIAL DIAM./ CALIS ITEM PU BER ID. taRSER ORAMING PARSEWS LOCS. REG. NUPBERS TYPE / GRADE THICK BLOCK Ct991ENTS
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O O PAGE 23 O
PROGRAM
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PROGRAM: NISIRUPS-4AISIO2
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FILE: COO 7133 OATE 05/31/95 PLANT: CATAleA UNIT I PRE-SERVICE AND IN-SERVICE INSPECTItN SYSTEM KEY: ITEM NUPBER C06 CATAMBA 1 INSERVICE ItGPECTItM LISTING OUTAGE 8 ItGP PROC. NATERIAL DIAN./ CALIB ITEM PRJPBER ID.tOBER DRAMING NLRBERS LOCS. REG. PAkBERS TYPE / GRADE THICK BLOCK CCR91ENTS
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DATE 05/31/95 PLANT: CATAPSA UNIT I PRC-SERVICE APG IN-SERVICE INSPECTIER4 SYSTEM KEY: ITEM NUPSER G07 CATAPSA I INSERVICE INSPECTION LISTING OUTAGE 8 INSP PROC. MATERIAL DIAN./ CALIB ITEM MASER 10. Nt7BER DRAMING NUPBERS LOCS. RES. NUPBERS TYPE / GRADE THICK BLOCK CtR9ENTS
, =s====== ss =ss ==== =========== =============..____s ===== ==== ======== ========== ====== ===== ==============================
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{ B. Items examined by Pressure Testing Item Number = ASME Section XI Tables IWB-2500-1 (Class 1), IWC-2500-1 (Class 2)
Drawing Number = Number of the Flow Diagram Revision = Revision of the Flow Diagram 1 Test = Type of Pressure Test Comp = Vessel, Piping or Pump ;
i Comp Name = Example: Reactor Vessel, etc., for piping - l System designation will be used Req.Insp = Type inspection performed, i.e., VT2 Req. Proc = Required inspection procedure Comments = General and/or Detail Description O !
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Refueling Outage Report EOC 8 Page 2 of 2 i Catawba Unit 1 Revision 0 Section 4 June 1,1995
PAGE NO. 1 CATAMBA tREIT N mmen 1 - 1st INTERVAL 05/31/95 CLkSS A (CETEGORY B-R) REQUIREMENTS rost oormaE NoumEn a REQ. REQ.
ITEN NO. DRANING REV TEST FCh NO. SYSTEtt Whsg INSP PROC COISBNTS B04.012.001 CNM-1201.1.52 N/A IEAK N/A RPV-INCORE VT-2 QAL-15 78 Welds CRDM to RPV Closure Head-Examine during C1.1 Leakage Test B04.013.001 CNM-1201.14-7 N/A LEAK CAT 1-0214 PZR-HEATER VT-2 QAL-15 58 Welds INCORE to RPV Bottom Head-Examine during C1.1 Leakage Test B04.020.001 CNM-1201.1.66 N/A LEAK N/A RPV-CRDM VT-2 QAL-15 78 Heater Penetrations in Lower Head-Examine during C1.1 Leakage Test
-_.______________________.__m______ _ _ _ _ _ _ _ _ _ _ ___-_____m_ _ _ _ _ - . _ _ _ _ _ _ --
O O O PAGE NO. 1 CATANBA UNIT NUBERER 1 - 1st INTERVAL 05/31/95 CLASS A (CATEGORY B-P) REQUIREkENTS FOR OUTAGE NummEn a REQ. REQ. J ITEM NO. DRANING REV TEST FCh NO. SYSTEM Nhag INSP PROC NS B15.011.001 CN-1553-1.0 22 HYDRO N/A UNIT 1 REACTOR VT-2 QAL-15 B15.021.001 CN-1553-1.1 14 HYDRO N/A PRESSURIZER VT-2 QAL-15 B15.031.001 CN-1553-1.0 22 HYDRO N/A STEAM GENERATORVT-2 QAL-15 1A l B15.031.002 CN-1553-1.0 22 HYDRO N/A STEAM GENERATORVT-2 QAL-15 l
1B B15.031.003 CN-1553-1.0 22 HYDRO N/A STEAM GENERATORVT-2 QAL-15 1C B15.031.004 CN-1553-1.0 22 HYDRO N/A STEAM GENERATORVT-2 QAL-15 1D B15.051.001 CN-1553-1.0 22 HYDRO N/A NC SYSTEM VT-2 QAL-15 B15.051.002 CN-1553-1.1 14 HYDRO CAT 1-0284 NC SYSTEM VT-2 QAL-15 B15.051.004 CN-1554-1.0 14 HYDRO CAT 1-0284 NV SYSTEM VT-2 QAL-15 B15.051.005 CN-1554-1.5 07 HYDRO N/A NV SYSTEM VT-2 QAL-15 B15.051.006 CN-1561-1.0 11 HYDRO CAT 1-0284 NV SYSTEM VT-2 QAL-15 I B15.051.007 CN-1561-1.1 08 HYDRO CAT 1-0284 ND SYSTEM VT-2 QAL-15 B15.051.008 CN-1562-1.0 07 HYDRO CAT 1-0284 NI SYSTEM VT-2 QAL-15
O O O' .
PAGE No. 2 CATABE. UNIT NUBAER 1 - 1st INTERVAL 05/31/95 CLASS A (ChTEGORT B-P) REQUIRESENTS ~
FOR OUTAGk
~~3 REQ. REQ.~~
ITERE NO. DRANING REV TEST FCh WO. SYSTERI Emas INSP PROC rYumerTS B15.051.009 CN-1562-1.1 12 HYDRO N/A NI GYSTEM VT-2 QAL-15 B15.051.010 CN-1562-1.2 08 HYDRO CAT 1-0284 NI SYSTEM VT-2 QAL-15 B15.051.011 CN-1562-1.3 06 HYDRO N/A NI SYSTEM VT-2 QAL-15 B15.061.001 C 1553-1.0 22 HYDRO N/A RCP-1A VT-2 QAL-15 B15.061.002 CN-1553-1.0 22 HYDRO N/A 'ACP-1B VT-2 QAL-15 B15.061.003 CN-1553-1.0 22 HYDRO N/A RCP-1C VT-2 QAL-15 B15.061.004 CN-1553-1.0 22 HYDRO N/A RCP-ID VT-2 QAL-15 4
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ITEtt NO. DBANING REV TEST FCA NO. SYSTEtt Nats INSP PROC CORSENTS C07.020.007 CN-1554-1.6 10 HYDRO N/A LETDOWN HEAT VT-2 QAL-15 i EXCHNGR C07.020.008 CN-1554-1.6 10 HYDRO N/A SEAL WATER VT-2 QAL-15
, HEAT EXC C07.020.009 CN-1554-1.1 08 HYDRO N/A VOLUME CONTROLVT-2 QAL-15 ,
TANK C07.020.020 CN-1563-1.0 13 HYDRO N/A CONT SPRAY HX VT-2 QAL-15 1A C07.020.021 CN-1563-1.0 13 HYDRO N/A CONT SPRAY HX VT-2 QAL-15 IB C07.020.022 CN-1571-1.0 16 HYDRO N/A REFUEL WTR STR VT-2 QAL-15 This Item will be examined after EOC8 start TANK up and included in a seperate surmnary report.
C07.030.003 CN-1554-1.2 16 LEAK CAT 1-0284 NV SYSTEM VT-2 QAL-15 This Item will be examined after EOC8 start up and included in a seperate sununary report.
C07.040.002 CN-1553-1.1 14 ~ HYDRO CAT 1-0284 NC SYSTEM VT-2 QAL-15 Code Case N-522 used C07.040.004 CN-1553-1.3 10 HYDRO N/A NC SYSTEM VT-2 QAL-15 Code Case N-522 used C07.040.005 CN-1554-1.0 14 HYDRO CAT 1-0284 NV SYSTEM VT-2 QAL-15 Penetrations M-256, M-273, M-330 and M-347 C07.040.006 CN-1554-1.1 08 HYDRO N/A NV SYSTEM VT-2 QAL-15
O O O PAGE NO. 2 CATAMBA UNIT NNMPR 1 - 1st INTERVAL 05/31/95 CIASS B (CATEGORY C-B) REQUIREBENTS FOR OUTAGE NUtBER 8 REQ. REQ.
ITEN NO. DRANING REV TEST FCA NO. SYSTEN NME INSP PROC NS C07.040.007 CN-1554-1.2 16 HYDRO N/A NV SYSTEM VT-2 QAL-15 This Item will be examined after EOC8 start up and included in a seperate surmary report.
C07.040.008 CN-1554-1.3 12 HYDRO N/A NV SYSTEM VT-2 QAL-15 C07.040.009 CN-1554-1.4 14 HYDRO N/A NV SYSTEM VT-2 QAL-15 C07.040.010 CN-1554-1.5 07 HYDRO CAT 1-0284 NV SYSTEM VT-2 QAL-15 Penetrations M-339, M-343, M-344 and M-350 C07.040.011 CN-1554-1,6 10 HYDRO CAT 1-0284 NV SYSTEM VT-2 QAL-15 This Item will be examined after EOC8 start up and included in a seperate summary
> report.
C07.040.012 CN-1554-1.7 11 HYDRO CAT 1-0284 NV SYSTEM VT-2 QAL-15 C07.040.013 CN-1554-1.8 03 HYDRO CAT 1-0284 NV SYSTEM VT-2 QAL-15 Penetration M-228 - Code Case N-522 used.
C07.040.014 CN-1555-1.1 09 HYDRO N/A NR SYSTEM VT-2 QAL-15 C07.040.015 CN-1556-1.0 07 HYDRO N/A NB SYSTEM VT-2 QAL-15 C07.040.016 CN-1556-2.0 11 HYDRO N/A NB SYSTEM VT-2 QAL-15 Code Case N-522 used C07.040.018 CN-1558-2.0 09 HYDRO N/A NF SYSTEM VT-2 QAL-15 Code Case N-522 used C07.040.019 CN-1559-1.0 04 HYDRO N/A VY SYSTEM VT-2 QAL-15 Code Case N-522 used C07.040.020 CN-1561-1.0 11 HYDRO CAT 1-0293 ND SYSTEM VT-2 QAL-15 Penetration M-276
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N' PAGE NO. 3 CATAMBk UNIT NUISER 1 - 1st INTERVAL 05/31/95 CIASS B (ChTEGORY C-R) REQUIRBENTS FOR OUTAGE NUISER S REQ. REQ.
ITEN WO. DRAWING REV TEST FCh 30. SYSTEN Nh3E IWSP PROC COIAENTS I -
C07.040.022 CN-1562-1.0 07 HYDRO CAT 1-0281 NI SYSTEM VT-2 QAL-15 Penetration M-351 C07.040.023 CN-1562-1.1 12 HYDRO CAT 1-0284 NI SYSTEM VT-2 QAL-15 Penetrations M-322 and M-331 - Code case N-522 used.
C07.040.024 CN-1562-1.2 08 HYDRO CAT 1-0284 NI SYSTEM VT-2 QAL-15 Penetrations M-207, M-317 and M-320 C07.040.025 CN-1562-1.3 06 HYDRO CAT 1-0284 NI SYSTEM VT-2 QAL-15 Penetrations M-210, M-303, M-307 and M-336 C07.040.027 CN-1563-1.0 13 HYDRO N/A NS SYSTEM VT-2 QAL-15 Penetrations M-362, M-369, M-370, M-380, M-381 and M-387 C07.040.028 CN-1565-2.0 14 HYDRO N/A WL SYSTEM VT-2 QAL-15 Code Case N-522 used.
C07.040.029 CN-1565-2.1 16 HYDRO N/A WL SYSTEM VT-2 QAL-15 Code Case N-522 used.
C07.040.030 CN-1565-2.4 10 HYDRO N/A WL SYSTEM VT-2 QAL-15 Code Case N-522 used.
C07.040.031 CN-1565-2.6 08 HYDRO CAT 1-0291 WL SYSTEM VT-2 QAL-15 Penetration M-359 - Code Case N-522 used.
C07.040.032 CN-1567-1.0 10 HYDRO N/A WG SYSTEM VT-2 QAL-15 C07.040.033 CN-1567-1.1 11 HYDRO N/A WG SYSTEM VT-2 QAL-15 C07.040.034 CN 1567-1.3 09 HYDRO N/A WG SYSTEM VT -2 QAL-15 C07.040.035 CN-1568-1.0 08 HYDRO N/A WE SYSTEM VT-2 QAL-15 Code Case N-522 used.
. _ _ _ _ , ~ . -. -, . . _ - __
O O O PAGE NO. 4 C2LTAMBA UIIIT NUbSER 1 - 1st INTERVAL 05/31/95 CIASS B (C&TEGORY C-H) REQUIREMENTS FOR OUTAGE NUteER S REQ. REQ.
ITEM NO. DRANING REV TEST FCh N0. SYSTEM NAas INSF PROC C0bestNTS C07.040.036 CN-1569-1.0 08 HYDRO CAT 1-0284 NW SYSTEM VT-2 QAL-15 Penetrations M-243 and M-253 l
C07.040.037 CN-1570-1.0 12 HYDRO N/A KF SYSTEM VT-2 QAL-15 C07.040.038 CN-1571-1.0 16 HYDRO CAT 1-0284 FW SYSTEM VT-2 QAL-15 This Item will be examined after EOC8 start up and included in a seperate sunnary report.
C07.040.040 CN-1572-1.1 05 HYDRO CAT 1-0284 NM SYSTEM VT-2 QAL-15 Penetration M-236 I 1
C07.040.041 CN-1572-1.2 07 HYDRO N/A NM SYSTEM VT-2 QAL-15 )
C07.040.042 CN-1572-1.4 15 HYDRO CAT 1-0284 NM SYSTEM VT-2 QAL-15 Penetrations M-335, M-338, M-340 and M-341 j C07.040.052 CN-1584-1.0 06 HYDRO CAT 1-0284 BW SYSTEM VT-2 QAL-15 l
C07.040.053 CN-1585-1.0 07 HYDRO N/A VQ SYSTEM VT-2 QAL-15 Code Case N-522 used.
C07.040.054 CN-1591-1.1 18 HYDRO CAT 1-0284 CF SYSTEM VT-2 QAL-15 Penetrations M-110, M-262, M-309 and M-422 l
C07.040.055 CN-1592-1.1 16 HYDRO CAT 1-0284 CA SYSTEM VT-2 QAL-15 Penetrations M-143, M-278, M-457 and M-3106 C07.040.056 CN-1593-1.0 14 HYDRO CAT 1-0284 SM/SV SYSTEM VT-2 QAL-15 Penetrations M-113, M-261, M-393 and M-423 C07.040.057 CN-1593-1.1 16 HYDRO CAT 1-0284 SA SYSTEM VT-2 QAL-15 C07.040.058 CN-1593-1.7 07 HYDRO N/A SM/SV SYSTEM VT-2 QAL-15
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ ____J
O O O PAGE NO. 5 CATA M A UNIT N m en 1 - 1st INTERVAL 05/31/95 CLASS B (ChTEGORY C-R) REQUIRERWITS FOR OUTAGE NUREBER 8 REQ. REQ.
ITEM NO. DRANING REV TEST FCA NO. SYSTEtt Nk33 INSP PROC COISENTS C07.040.060 CN-1599-2.2 10 HYDRO N/A RF SYSTEM VT-2 QAL-15 Code Case N-522 used.
C07.040.061 CN-1601-3.1 17 HYDRO N/A YM SYSTEM VT-2 QAL-15 Code Case N-522 used.
C07.040.062 CN-1605-1.1 14 HYDRO N/A VI SYSTEM VT-2 QAL-15 Code Case N-522 used.
1 l
l C07.040.063 CN-1605-2.1 09 HYDRO N/A VS SYSTEM VT-2 QAL-15 Code Case N-522 e=ed.
1 C07.040.064 CN-1605-3.2 03 HYDRO N/A VB SYSTEM VT-2 QAL-15 Code Case N-Sim C07.060.001 CN-1554-1.2 16 HYDRO N/A RECIP CHGR VT-2 QAL-15 This Item will be examined after EOC8 start PUMP up and included in a seperate summary repo rt .
C07.060.002 CN-1554-1.7 11 HYDRO N/A CENTRIF CHRG VT-2 QAL-15 PUMP 1A C07.060.003 CN-1554-1.7 11 HYDRO N/A CENTRIF CHRG VT-2 QAL-15 PUMP 1B C07.060.006 CN-1562-1.2 08 HYDRO N/A SAFETY INJ VT-2 QAL-15 PUMP 1A C07.060.007 CN-1562-1.2 08 HYDRO N/A SAFETY INJ VT-2 QAL-15 PUMP IB C07.060.008 CN-1563-1.0 13 HYDRO N/A CONT SPRAY VT-2 QAL-15 PUMP 1A .
O O O PAGE NO. 6 CATAWBA UNIT Namen 1 - 1st INTERVAL 05/31/95 CIASS B (CETEGORY C-R) REQUIREBENTS FOR OUTAGE NUBERER 8 REQ. REQ.
ITsu No. DRAWING REV TEST FCA NO. SYSTEM Egas INSP PROC CreamrTS j C07.060.009 CN-1563-1.0 13 HYDRO N/A CONT SPRAY VT-2 QAL-15 PUMP 1B b
_ - _ - - - _ . - - - - - _ - . _ _ _ . . . - - - - . - - - . - . _ _ - - _ - - _ _ _ - - - _ - _ - . - - - - . _ _ _ . -_- - - - - - _ . _ - - w--,-- --+r--,,, ,, en-,- . . , -en-,- , - , . - , + - . - , , , >c+- ,- ,,em- -e -~- - - .
O O O PAGE NO. 1 C&ThBah UNIT NUteER 1 - let INTERVAL 05/31/95 CIASS C (ChTEGORY D-A) REQUIREBIENTS FCEL OUTAGE NUBEER S REQ. REQ.
ITEat NO. DRANING REV TEST FCE NO. SYSTEtt Whba INSP PROC CoteENTS i D01.011.005 CN-1554-1.4 14 LEAK CAT 1-0260 NV SYSTEM VT-2 QAL-15 i
D01.012.005 CN-1554-1.4 14 HYDRO CAT 1-0293 NV SYSTEM VT-2 CAL-15 1
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O O -Q PAGE NO. 1 CATAleA UNIT NUMBER 1 - 1st INTERVAL 05/31/95 t nam C (CkTEGORY D-B) REQUIREbENTS FOR OtrfAGE NUteER S REQ. REQ.
ITEM NO. DRANING REV TEST FCh 30. SYSTEM unna INSP PROC CriametrrS D02.012.002 CN-1573-1.0 20 tiYDRO CAT 1-0284 KC SYSTEM VT-2 QAL-15 D02.012.003 CN-1573-1.1 13 HYDRO CAT 1-0265 KC SYSTEM VT-2 QAL-15 Static Head Test For Surge Tanks D02.012.007 CN-1573-1.5 08 HYDRO N/A KC SYSTEM VT-2 QAL-15 Tie - In From Static Head Test For Surge Tanks D02.012.024 CN-1609-1.0 11 HYDRO CAT 1-0284 KD SYSTEM VT-2 QAL-15 D02.012.027 CN-1609-3.0 16 HYDRO CAT 1-0260 FD SYSTEM VT-2 QAL-15 D02.012.028 CN-1609-3.1 14 HYDRO CAT 1-0260 FD SYSTEM VT-2 QAL-15 l
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Q 5.0 Resub OfInanections Performed Durina Outaae 8 The results of each examination shown in the final ISI Plan (Section 4 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.
5.1 The information shown below is a field description for the reporting format included in this section of the report:
A. Items Examined by NDE (excluding Pressure Testing)
Item Number = ASME Section XI Tables IWB-2500-1 (Class 1), IWC-2500-1 (Class 2), IWF-2500-1 (Class 1 and Class 2), Angmented Requirements ID Number = Unique Identification Number Inspection Date = Date of Examination Inspection Status = CLR = Clear REC = Recordable q
v REP = Reportable ,
Inspection Limited = L = Limited
__ = N o Geo. Ref. = X = Yes (Geometric Reflector N = No applies only to UT)
Comments = General and/or Detail Description l
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Refueling Outage Report EOC 8 Page 1 of 3 Catawba Unit 1 Revision 0 Section 5 June 1,1995
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PRODRAM: MISIRUNO-ElAISIO4 DLKE PSER CS9ANY PAGE 1 FILER COO 7133 DATE 05/31/*5 PLAPfT: -CATA>SA UNIT 1 PRE-SERVICE AND IN-SERVICE INSPECTI m SYSTEM KEY: 802 CATAPSA 1 INSERVICE INSPECTIcH RESULTS CUTAGE 8
. ITEM MASER INSPECTIW4 INSPECTION INSPECTIN GES.
ITEM MRSER ID MPSER DATE STATUS LIMITED REF. C99ENTS
~~====== ======sess========== ========== ========== ========== ==== ========================~~
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l INSPECTIm INSPECTI N INSPECTIN GE6.
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d KEYS ITEM PA79ER BOS CATApeA 1 INSERVICE INSPECTItM RESULTS CUTAGE 8 1
INSPECTitM INSPECTION GES.
INSPECTION ITEM MJPBER ID NBASER DATE STAitG LIMITED REF. Ct99ENTS
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N B08.010.003 IRPV-UH-LUG-3 03/03.'95 CLR _
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KEY: ITEM NLPBER B12 CAlist5A 1 INSERVICE INSPECTI N RESULTS OUTAGE 8 INSPECTI N INSPECTI m INSPECTI m CE S.
ITEM MLASER ID MUPSER DATE STATUS LIMITED REF. CtR91ENTS
. essass====== =================ss ========== ========== ========== ==== =================: m======== n 812.040.0020 IND-37A 02/28/95 CLR L N B12.050.003A 1re-18 _/_/_ _ _ REF. REQUEST FOR RELIEFS 94-03 812.050.0038 IND-2A / / _ ,,, REF. REQUEST FOR RELIEFS 94-03 i B12.050.003C IND-368 _/_/_ _ _ REF. REQUEST FOR RELIEF #94-03 812.050.0030 IND-37A _/_/_ _ _ REF. REQUEST FOR RELIEF 894-03 B12.050.004A INI-54A _/_/_ _ _ REF. REQUEST FOR RELIEF #94-03 812.050.0048 INI-658 _/__/_ _ _ REF. REQUEST FOR RELIEF 894-03 812.050.004C INI-76A _/_/_ _ _ REF. REQUEST FOR RELIEF 994-03 812.050.004D INI-888 _/_/_ _ _ REF. REQUEST FOR RELIEFS 94-03
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, KEY: ITEN MDBER C05 CATAMkA 1 INSERVICE INSPECTION RESULTS OUTAGE 8 INSPECTItR4 INSPECTI M INSPECTItD4 GES.
j ITEN MDSER IDPRDSER DATE STATUS LINITED REF. Ct99ENTS
===ss ===s = ==mem==smuzzss====ss ===amenss= azzs====== ========== ==== ===anazzm===sammansszensan== s-C05.011.050 ICA102-07 03/04/95 CLR _
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N C05.011.052 1CA111-04 03/04/95 CLR _
N C05.011.053 1CA111-05 03/04/95 CLR _
N C05.011.054 1CA112-03 03/04/95 CLR _
N C05.011.055 1CA112-04 03/04/95 CLR _
N C05.011.056 ICA112-18 03/05/95 CLR _
N C05.011.057 1CA113-03 03/04/95 CLR _
N C05.011.058 1CA113-15 03/04/?5 CLR _
N C05.011.059 1CA121-15 03/04/95 CLR _
N C05.011.060 ICA121-16 03/04/95 CLR _
N C05.011.452 ISV33-07 03/04/95 CLR _
N C05.011.453 ISV36-02 03/04/95 CLR _
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ITEM PAREER ID NLREER DATE STATUS LIMITED REF. Cat 1ENTS
~~====== ==================== ========== ========== ========== ==== ========================~~
C05.021.053 1CF22-01 02/24/95 CLR _
Y C05.021.056 1CF27-01 02/25/95 CLR _
Y C05.021.067 1CF34-13 02/24/95 CLR _
Y C05.021.410 ISH-8A-F 03/06/95 CLR _
N C05.021.410A ISM-8A-F 03/06/95 CLR _
N C05.021.411 ISM-8A-E 03/06/95 CLR _
N C05.021.411A ISM-8A-E 03/06/95 CLR _
N C05.021.412 ISH-8A-D 03/06/95 CLR _
N C05.021.412A ISH-8A-D 03/06/95 CLR _
H C05.021.424 ISM-BA-B 03/06/95 CLR _
N C05.021.4244 ISM-8A-B D3/06/95 CLR _
N C05.021.425 ISH-8A-C 03/06/95 CLR _
N C05.021.425A ISM-8A-G 03/06/95 CLR _
N C05.021.460 15V23-01 03/06/95 CLR _
N C05.021.460A 1SV23-01 03/05/95 CLR _
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PRODRAM: NISIRUND-4AISIO4 OtRE PONE 2 CWANY PAGE 10 FILE: COD 7133 DATE 05/31/95 PLANTt CATADSA LMIT 1 PRE-SERVICE AND IN-SERVICE INSPECTIEM SYSTEM KEY: ITEN te.MBER C05 CATApeA 1 INSERVICE INSPECTItM RESULTS MITAGE 8 INSPECTION INSPECTItM INSPECTItM GE ff.
ITEM NL99ER 10 MRSER DATE STATUS LINITED REF. Ct99ENTS
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C05.021.449 ISV25-05 01/06/95 CLR _
N C05.021.%9A 1SV25-05 03/05/95 CLR _
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O O PAGE 11 O!
PROGRAN: MISIRUNO-44AISIO4 DLEE PUNER CGTANY FILE: CD07133 OATE 05/31/95 PLANT: CATAMBA (MIT 1 PRE-SERVICE APG IN-SERVICE INSPECTIt90 SYSTEN '
KEY: ITEN NUPSER C06 CATADBA 1 INSERVICE INSPECTION RESULTS OUTAGE 8 INSPECTIN INSPECTION INSPECTICD1 GE S.
ITEN NUPBER 10 NUPSER DATE STATUS LIMITED REF. COPMENTS
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C06.020.022 INI1368 02/28/95 CLR _
N C06.020.060 1SV14 03/04/95 CLR _
N C06.020.061 ISV15 03/04/95 CLR _
N C06.020.062 ISV16 03/04/95 CLR _
N C06.020.063 ISV17 03/04/95 CLR _
N CD6.020.064 ISV18 03/04/95 CLR _
N C06.020.065 ISV20 03/05/95 CLR _
H i C06.020.066 ISY21 03/05/95 CLR _
N C06.020.067 ISV22 03/05/95 CLR _
N C06.020.068 ISV23 03/05/95 CLR _
N C06.020.069 ISV24 03/05/95 CLR _
N
O PAGE 12 PROGRANs MISIRUND-40AISIO4 OLEE PONE 2 CtRFANY FILER C007133 DATE 05/31/?5 PLANT CATA>eA UNIT 1 PRE-SERVICE AND IN-SERVICE INSPECTI M SYSTEN KEY: ITEN NUPBER F1. CATApSA 1 INSERVICE INSPECTI N RESULTS CUTAGE 8 INSPECTION INSPECTIN INSPECTIN GES.
ITEN IU SER 10 MASER 0 ATE STATUS LINITED REF. CtRNENTS mazan===mmas szzamazassamms sss== ========== ========== mass ====== _-s== ==============================
F1.01.190 1-R-NC-2320 03/15/95 CLR _
N F1.01.191 1-R-NC-2321 03/16/95 CLR _
N F1.02.889 1-R-$N-1546 03/09/95 CLR _
N F1.03.624A 1-R-KC-0875 02/14/95 CLR _
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PROGRAM: NISIRUND-9AISIO4 DUKE PtBE2 COWANif PAGE 14 FILE: COO 7133 DATE 05/31/95 PLANT: CATADBA LMIT 1 PRE-SERVICE AND IN-SERVICE INSPECTI N SYSTEM KEY: ITEM NUPBER G03 CATA>BA 1 INGERVICE INSPECTI N RESULTS OUTAGE 8 INSPECTItN4 INSPECTION INSPECTI N GES.
ITEM KNSER ID PADBER DATE STATUS LIMITED REF. Ct99fMTS
~~====== ==================== ========== ========== ========== ==== ========================~~
G03.001.030 ISM 33-02 03/08/95 CLR _
N G03.001.030A ISM 33-02 03/07/95 CLR _
N G03.001.O n ISM-52-A 03/08/95 CLR _
N 903.001.031A ISM-54-A 03/09/95 CLR _
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G03.001.032 ISH33-03 03/08/95 CLR _
N G03.001.032A ISM 33-03 03/07/95 CLR ,,
N G03.001.033 ISM 33-04 03/08/95 CLR _
N G03.001.0334 ISH33-04 03/07/95 CLR _
H G03.001.034 ISM-7A-A 03/08/95 CLR _
N G03.001.034A ISM-7A-A 03/07/95 CLR _
N 003.001.035 ISM-7A-B 03/08/95 CLR _
H G03.001.035A ISM-7A-B 03/07/95 CLR _
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PROGRAM NISIRUNO-GAISIO4 DNE PCMEQ Ct9PANY PAGE 15 FILER C007133 DATE 05/31/95 PLANT: CATAHBA UNIT 1 PRE-SERVICE AND IN-SERVICE INSPECTItN SYSTEN KEY: ITEM NUPSER G07 CATANA 1 INSERVICE ItGPECTION RESULTS OllTAGE 8 INSPECTION INSPECTION INSPECTItN GES.
ITEN NLMBER 10 PUBER DATE STATUS LIMITED REF. COP 91ENTS
~~====== ==================== ===== ==== ========== ========== ==== ========================~~
G07.001.001 INI9-03 02/21/95 CLR _
N G07.001.002 INIl0-02 02/21/95 CLR _
N G07.0C1.003 INI147-03 02/F1/95 CLR _
N G07.001.'J04 1NI147-04 02/21/95 CLR _
N G07.001.005 1NI148-09 03/02/95 CLR L Y G07.001.005A INI148-09 02/22/95 CLR _
N G07.001.006 INI148-10 03/02/95 CLR L N G07.001.006 A INI148-10 02/22/95 CLR _
H G07.001.007 INI148-11 03/02/95 CLR L N G07.001.007A INI140-11 02/22/95 CL3 _
N G07.001. 008 1NI151-02 02/21/95 CLR _
N G07.001.009 1NI151-04 02/21/95 CLR _
N G07.001.010 INI152-09 03/02/95 CLR L Y G07.001.010A INI152-09 02/22/95 CLR _
N G07.001.011 INI152-10 03/02/95 CLR L Y
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la FILER COO 1133 DATE 05/31/95 PLANTS CATAleA UNIT 1- PRE-SERVICE ADS IM-SERVICE INSPECTIt94 SYSTEN KEY: ITEN PRDSER GO7 CATADSA 1 INSERVICE INSPECTISI RESULTS OUTAGE 8 INSPECTIt94 INSPECTIt94 INSPECTItM GES.
ITEN DRNSER IDDRASER OATE STATUS LIMITED REF. Ct99ENTS
~~====== ==================== ========== ========== ========== ==== ========================~~
G07.001.011A INI152-10 02/22/95 CLR _
N G07.001.012 INI152-11 03/02/95 CLR L N G07.001.012A 1MI152-11 02/22/95 CLR _
N G07.001.013 1NI160-01 02/21/95 CLR _
N G07.001.014 1N1162-13 03/02/95 CLR L Y G07.001.014A 1NI162-13 03/01/95 REC _
N 907.001.015 INI162-14 03/02/95 CLR _ 74 -
G07.001.015A INI162-14 02/22/95 CLR ,, N G07.001.016 INI163-15 03/02/95 LLR L Y G07.001.0164 1NI163-15 02/22/95 CLR _
N 007.001.017 INI164-08 03/02/95 CLR L Y GO7.001.017A INI164-08 02/22/95 CLR _
N C07.001.018 INI165-08 03/02/95 CLR L Y 907.001.018A INI165-08 C2/22/95 CLR _
N 907.001.019 1NI165-09 03/02/95 CLR L N
O PAGE 17 O
PROGRAM: NISIRUND-GAISIO4 DL%E PG9ER C W ANY FILER CUD 7133 DATE 05/31/95 PLANTS CATAp6A LMIT 1 PRE-SERVICE Ate IN-SERVICE INSPECTIt24 SYSTEM KEY: ITEM NLfBER G07 CATA6SA 1 INSERVICE INSPECTIEM RESULTS OUTAGE 8 INSPECTIt24 INSPECTION INSPECTION GES. '
ITEM M.RSER 10 taASER DATE STATUS LIMITED REF. CtW9ENTS musssssssssa azz=mssssssssssmamms ========== =====ssssa sus =ssassa mass ==sss========suss=samassasssas G07.001.019A INI165-09 02/22/95 CLR _
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O. "- 'te- ex*-i ed 6 7Pre =re re ties Item Number = ASME Section XI Tables IWB-2500-1 (Class 1), IWC-2500-1 (Class 2)
Drawing = Number of the Flow Diagram Examination Date = Latest Examination Date Condition = Partial or Complete test Status = Clear, Recordable or Reportable Comments = General and/or Detail Description 4
0 O Page 2 of 3 Refueling Outage Report EOC 8 Catawba Unit 1 Revision 0 Section 5 June 1,1995
O O O PAGE NO. 1 CATANBk UNIT NUteER 1 - 1st INTERVAL 05/31/95 CLASS A (CATEGORY B-E) RESULTS FOR OUTAGE NUBBER S DATE IAST ITEM NO. DRAWING EXAntI15D GMCITION STATUS CORSENTS B04.012.001 CNM-1201.1.52 03/21/95 COMPLETE CLEAR 78 Welds CRDM to RPV Closure Head-Examine during C1.1 Leakage Test B04.013.001 CNM-1201.14-7 03/21/95 -COMPLETE CLEAR 58 Welds INCORE to RPV Bottom Head-Examine during C1.1 Leakage Test B04.020.001 CNM-1201.1.66 03/21/95 COMPLETE CLEAR 70 Heater Penetrations in Lower Head-Examine during C1.1 Leakage Test
O O -
LO PAGE NO. 1 CAvanna UNIT NUteER 1 - 1st DrTERVAL 05/31/95 CLASS A (CATEGORY B-P) RESULTS FOR OUTAGE NUteER S DATE LAST ITEst NO. DRANING EKMEINED COMITION STATUS CremmmTS B15.011.001 CN-1553-1.0 03/21/95 COMPLETE CLEAR B15.021.001 CN-1553-1.1 03/21/95 COMPLETE CLEAR B15.031.001 CN-1553-1.0 03/21/95 COMPLETE CLEAR B15.031.002 CN-1553-1.0 03/21/95 COMPLETE CLEAR B15.031.003 CN-1553-1.0 03/21/95 COMPLETE CLEAR B15.031.004 CN-1553-1.0 03/21/95 COMPLETE CLEAR B15.051.001 CN-1553-1.0 03/21/95 COMPLETE CLEAR B15.051.002 CN-1553-1.1 03/21/95 COMPLETE RECORDABLE B15.051.004 CN-1554-1.0 03/21/95 COMPLETE CLEAR B15.051.005 CN-1554-1.5 03/21/95 COMPIETE CLEAR B15.051.006 CN-1561-1.0 03/21/95 COMPLETE CLEAR
_ _ . . . . . . - - , , , - - .->e . - - - - -m e ----'---v- ,- --~ - -,~-- ---- - - - - - - -- e + - ---- - - - - - - - - - - - - - - - - -
O O O PAGE NO. 2 C&TA M UNIT NUteER 1 - 1st INTERVAL 05/31/95 CLASS A (CATEGORY B-P) RESULTS rom oDTacE weseEm s DhTE IAST 1T338 WO. DRANING EXABf1NED COISITION STATUS NS B15.051.007 CN-1561-1.1 03/21/95 COMPLETE CLEAR B15.051.008 CN-1562-1.0 03/21/95 COMPLETE CLEAR t
B15.051.009 CN-1562-1.1 03/21/95 COMPLETE CLEAR B15.051.010 CN-1562-1.2 03/21/95 COMPLETE CLEAR B15.051.011 CN-1562-1.3 03/21/95 COMPLETE CLEAR B15.061.001 CN-1553-1.0 03/21/95 COMPLETE CLEAR B15.061.002 CN-1553-1.0 03/21/95 COMPIETE CLEAR B15.061.003 CN-1553-1.0 03/21/95 COMPLETE CLEAR B15.061.004 CN-1553-1.0 03/21/95 COMPLETE CLEAR l
l
___.___ . _ _ _ _ - - _ _ _ _ _ _ _ . . .. _ _ _ _ _ _ _ _ _ _ _ - . . - . - , , - _ - - _ _ , _ , . - - - - ~ _ _ . _ . - . _ . _ _ . .
O O O PAGE NO. 1 CATANBA UNIT WOBBER 1 - 1st INTERVAL 05/31/95 CIAss B (CATEGORY C-5) RESUI.TS FOR ocTAGE usesER e DATE IAST ITEN NO. DRANING EKABEINED COWITION STATUS rYumeMTS l C07.020.007 CN-1554-1.6 02/15/94 COMPLETE CLEAR C07.020.008 CN-1554-1.6 02/15/94 COMPLETE CLEAR C07.020.009 CN-1554-1.1 02/15/94 COMPLETE CLEAR C07.020.020 CN-1563-1.0 02/22/94 COMPLETE CLEAR C07.020.021 CN-1563-1.0 02/15/94 COMPLETE CLEAR l
C07.020.022 CN-1571-1.0 / / NOT TESTED This Item will be examined after EOC8 start up and included in a seperate summary l report.
C07.030.003 CN-1554-1.2 03/26/92 PARTIAL CLEAR This Item will be examined af ter EOC8 start up and included in a seperate summary report.
C07.040.002 CN-1553-1.1 02/28/95 COMPLETE CLEAR Code Case N-522 used C07.040.004 CN-1553-1.3 03/09/95 COMPLETE CLEAR Code Case N-522 used C07.040.005 CN-1554-1.0 02/15/94 COMPLETE CLEAR Penetrations M-256, M-273, M-3'O and M-347 C07.040.006 CN-1554-1.1 02/15/94 COMPLETE CLEAR C07.040.007 CN-1554-1.2 08/24/94 PARTIAL RECORDABLE This Item will be examined after EOC8 start up and included in a seperate sumer.ary report.
O O .O u PAGE NO. 2 CATANBA UNIT NUBBER 1 - 1st INTERVAL 05/31/95 CIABS B (CATEGORT C-E) RESULTS FOR OUTAGE WUBBER 8 DATE LAST ITEtt NO. DRAWING EKANINED ColeITION STATUS COBSmrTS C07.040.008 CN-1554-1.3 02/15/94 COMPLETE CEAR C07.040.009 CN-1554-1.4 02/15/94 COMPETE CLEAR C07.040.010 CN-1554-1.5 02/15/94 COMPETE CLEAR Penetrations M-339, M-343, M-344 and M-350 C07.040.011 CN-1554-1.6 02/15/94 PARTIAL CEAR This Item will be examined after EOC8 start up and included in a seperate summary report.
C07.040.012 CN-1554-1.7 08/24/94 COMPLETE CLEAR C07.040.013 CN-1554-1.8 03/04/95 COMPLETE CLEAR Penetration M-228 - Code Case N-522 used.
C07.040.014 CN-1555-1.1 02/15/94 COMPLETE CLEAR l
C07.040.015 CN-1556-1.0 02/15/94 COMPLETE CLEAR C07.040.016 CN-1556-2.0 03/04/95 COMPLETE CLEAR Code Case N-522 used C07.040.018 CN-1558-2.0 03/17/95 COMPLETE CEAR Code Ctse N-522 used C07.040.019 CN-1559-1.0 03/03/95 COMPLETE CLEAR Code Case N-522 used C07.040.020 CN-1561-1.0 08/24/94 COMPLETE CLEAR Penetration M-276
O O O PACE NO. 3 CATANBA UNIT NUteER 1 - 1st INTERVAL 05/31/95 CLASS B (CATEGORY C-B) RESULTS FOR OUTacE mesmEn a DATE IAST ITEM WO. DRAWING EXAlfINED COWDITION STATUS CnnemsTS C07.040.022 CN-1562-1.0 02/15/94 COMPLETE CLEAR Penetration M-351 C07.040.023 CN-1562-1.1 03/11/95 COMPLETE CLEAR Penetrations M-322 and M-331 - Code Case N-522 used.
C07.040.024 CN-1562-1.2 03/11/95 COMPLETE CLEAR Penetrations M-207, M-317 and M-320 l
C07.040.025 CN-1562-1.3 02/17/94 COMPLETE CLEAR Penetrations M-210, M-303, M-307 and M-336 C07.040.027 CN-1563-1.0 08/24/94 COMPLETE CLEAR Penetrations M-362, M-369, M-370, M-380, M-381 and M-387 C07.040.028 CN-1565-2.0 03/15/95 COMPLETE CLEAR Code Case N-522 used.
C07.040.029 CN-1565-2.1 02/13/95 COMPLETE CLEAR Code Case N-522 used.
C07.040.030 CN-1565-2.4 03/13/95 COMPLETE CLEAR Code Case N-522 used.
C07.040.031 CN-1565-2.6 02/16/95 COMPLETE CLEAR Penetration M-359 - Code Case N-522 used.
C07.040.032~ CN-1567-1.0 02/15/94 COMPLETE CLEAR C07.040.033 CN-1567-1.1 02/15/94 COMPLETE CLEAR C07.040.034 CH-1567-1.3 02/15/94 COMPLETE CLEAR
O O -
O PAGE NO. 4 CATANBA UNIT NURSER 1 - 1st INTERVAL 05/31/95 CLASS B (CATEGORY C-E) RESULTS FOR OUTAGE NUBEBER S DATE IAST ITEat NO. DRAWING EXANINED CONDITIOtt STATUS COtSENTS C07.040.035 CN-1568-1.0 03/11/95 COMPLETE CLEAR Code Case N-522 used.
C07.040.036 CH-1569-1.0 03/30/94 COMPLETE CLEAR Penetrations M-243 and M-253 C07.040.037 CN-1570-1.0 09/21/94 COMPLETE CLEAR C07'.040.038 CN-1571-1.0 08/24/94 PARTIAL CLEAR This Item will be exa:dned after EOC8 start up and included ir. a seperate summary report.
C07.040.040 CN-1572-1.1 02/15/94 COMPLETE CLEAR Penetration n ~16 C07.040.041 CN-1572-1.2 02/15/94 COMPLETE CLEAR C07.040.042 CN-1572-1.4 03/15/94 COMPLETE CLEAR Penetrations M-335, M-338, M-340 and M-341 C07.040.052 CH-1584-1.0 01/31/95 COMPLETE CLEAR C07.040.053 CN-1585-1.0 03/13/95 COMPLETE CLEAR Code Case N-522 used.
C07.040.054 CN-1591-1.1 01/31/95 COMPLETE CLEAR Penetrations M-110, M-262, M-309 and M-422 C07.040.055 CN-1592-1.1 01/31/95 COMPLETE RECORDABLE Penetrations M-143, M-278, M-457 and M-3106 C07.040.056 CN-1593-1.0 01/31/95 COMPLETE RECORDABLE Penetrations M-113, M-2 61, M-393 and M-423 s ...e,- -_ -w .. r- -- . v.,, , w , .w,- -
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.PAGE No. 5 CATAlah UNIT NUISER 1 - 1st INTERVAL 05/31/95 CIABS B (ChTEGORY C-R) RESULTS FcR ourAGE NoteER e DATE IAST ITEII NO. DRANING EXAlfINED COISITION STATUS rNeNTS C07.040.057 CN-1593-1.1 01/31/95 COMPLETE CLEAR C07.040.058 CN-1593-1.7 01/31/95 COMPLETE CLEAR C07.040.060 CN-1599-2.2 03/14/95 COMPLETE CLEAR Code Case N-522 used.
C07.040.061 CN-1601-3.1 03/13/95 COMPLETE CLEAR Code Case N-522 used.
C07.040.062 CN-1605-1.1 03/01/95 COMPLETE CLEAR Code Case N-522 used.
C07.040.063 CN-1605-2.1 02/14/95 COMPLETE CLEAR Code Case N-522 used.
CO?.b?5.064 CN-1605-3.2 03/01/95 COMPLETE CLEAR Code Case N-522 used.
C07.060.001 CN-1554-1.2 / / NOT TESTED This Item will be examined after EOC8 start up and included in a seperate summary report.
C07.060.002 CN-1554-1.7 02/23/94 COMPLETE CLEAR C07.060.003 CN-1554-1.7 02/15/94 COMPLETE CLEAR 4
C07.060.006 CN-1562-1.2 04/21/94 CG5TLETE CLEAR C07.060.007 CN-1562-1.2 02/17/94 COMPLETE RECORDABLE
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O O O PAGE NO. 1 CATANBA UNIT NUBBER 1 - 1st INTERVAL 05/31/95 CLASS C (CATEGORY D-B) RESULTS FCR OUTAGE NUBBER S DATE IAST ITEst 30. DRANING EEAttINED COMITION STATUS C000ENTS D02.012.002 CN-1573-1.0 02/22/95 COMPLETE CLEAR D02.012.003 CN-1573-1.1 .09/19/94 COMPLETE CLEAR Static Head Test For Surge Tanks D02.012.007 CN-1573-1.5 09/19/94 COMPIETE CLEAR Tie - In From Static Head Test For Surge Tanks D02.012.024 CN-1609-1.0 02/27/95 COMPLETE CLEAR D02.012.027 CN-1609-3.0 02/12/95 COMPLETE CLEAR D02.012.028 CN-1609-3.1 03/05/95 COMPLETE CLEAR I
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PAGE NO. 1 CATAMBk UNIT NURSER 1 - 1st INTERVAL 05/31/95 CLASS C (CATNGORY D-C) RESULTS rom ocTAct NoemER 8 DATE IAST ITEM NO. DRANING EiramTNED COOWITIOtt STATUS CrinnerTS D03.011.001 CN-1570-1.0 09/13/94 COMPLETE RECORDABLE D03.011.002 CN-1510-1.1 09/12/94 COMPLETE CLEAR D03.011.007 CN-1568-1.0 09/12/94 COMPLETE CLEAR i
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O 5.2 Limited Framinations (i.e.,less than 90% of the requimd examination coverage obtained) identified during Outage 8 am shown below.
Item Number Request forRelief SerialNumber B12.040.002D 9541 C01.010.002 9541 C01.010.050 95-01 i
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O Refueling Outage Report EOC 8 Page 3 of 3 ,
Catawha Unit 1 Revision 0 Section 5 June 1,1995
O 8.o neeer,-sier aie. s m.
Outage 8 had no Class 1 or 2 reportable indications.
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O Refueling Outage Report EOC 8 Page1of1 Catawba Unit 1 Revision 0 Section 6 June 1,1995
Q 7.0 Personnel. Eauinment and Matedal Certifications All personnel who performed or evaluated the results of inservice inspec-tions from December 27,1993 through March 21,1995 at Catawba Nuclear Station Unit I were certified in accordance with the requirements of 1980 Edition of ASME Section XI with Addenda through Winter 1981. The appropriate certification records for each Duke Power Company inspector are on file at Catawba Nuclear Station or can be obtained through the Corporate Offices in Charlotte, North Carolina.
Records of periodic calibration of Duke Power Company inspection equipment are on file at Catawba Nuclear Station or can be obtained through the Corporate Offices in Charlotte, North Carolina.
O l
O Refueling Outage Report EOC 8 Page1of1 Catawba Unit 1 Revisi' , C Section 7 June 1,1995
8.0 Problem Investisration Process Forms No Problem Investigation Process Forms resulting from Class 1 or 2 reportable items were originated during Outage 8. However, there were inservice inspections performed during Outage 8 as a part of corrective actions and / or resolutions on the Problem Investigation Process Forms listed below.
Problem Investigation Process Forms:
PIP Serial No. 0-C93-0631 PIP Serial No.1-C93-0875 PIP Serial No. 2-C94-0874 o ;
i I
l O
Refueling Outage Report EOC 8 Page1ofI Catawba Unit 1 Revision 0 Section 8 June 7,1995
Today's Date : 05/31/95 MSE Serial No. -
. Time = 11:33 LER Serial No.:
Page No.: 1 Other Rpt. No. : IN 93-20 O, -
PIP Serial No. : 0-C93-0631 CATAWBA NUCLEAR STATION Problem Investigation Process Problem Investigation Form I. Problean ID occurred Time / Dates : / / Discovered Time /Date: 12:30 07/28/93 Unit (s): O Status at Time Discovered: Unit 1 Unit 2 Mode: 1 1
% Power: 100 100 Unit Status Remarks:
System (s) Affected:
1). CF = Feedwater System Problem Found while Working With Work Order No.:
Location of Problem - Bldg: Elev: Column Line:
Location Remarks:
Method Used To Discover Problem:
OEP IN 93-20 and NRC Inspection report 360/370/ 93-04 Brief Problem Descriotion:
Feedwater nozzle crack indications Detailed Problem Descriotion:
This Information Notice highlights cracks from themral fatique in feedwater lines which have proven to be a recurring problem. The mai,n cause appears to be fatigue induced by stresses from thermal stratification during cold, low flow, feedwater injections.
Inspection techniques specified in ASME Code Section XI do not appear adequate to identify these cracks. l Originated by: RFCOLE Group: OEA Date: 07/28/93 Other Units / Components / Systems / Areas Affected (Y,N,U): YES Immediate Corrective Actions:
None Originated by: RFCOLE Group: OEA Date: 07/28/93 Corrective Action Work Order No.:
i Today's Date : 05/31/95 MSE Serial No. :
Time : 11:33 LER Serial No.: :
I Page No. 2 Other Rpt. No. : IN 93-20
.O PIP Serial No. : 0-C93-0631 l
CATAWBA NUCLEAR STATION I Problem Investigation Process l Problem Investigation Form Problem Identified By: RFCOLE Group: OEA Date: 07/28/93 Problem Entered By : RFCOLE Group: OEA Date: 07/28/93 II. sienificance Is the Problem Significant? N Action Category: 3 MSE No.: LER No.: Other Report No.- IN 93-20 OEP No.: IN 93-20 Event Code (s) '
1). 07 = Operating Experience Program l
Screenina Remarks:
While these problems first surfaced at a TVA plant, the NRC questioned the results of ultrasonic data for the feedwater nozzle welds at McGuire based on the TVA problems. As a result O. of the NRC's concern, an agreement was reached where the nozzles would be reinspected during the next scheduled refueling outage s
for each unit at McGuire and at Catawba. This PIP is being initiated to track resolution of the nozzle inspections and l follow-up corrective actions. t Originated by: RFCOLE Group: OEA Date: 07/28/93 Responsible Group (s) for Proposed Resolution :
Original l Current l #
Due Date l Due Date l Ext.
1). QAT = QA Tech. Services 08/27/93 l 01/31/94 l 2 Responsible Group for Cause Code Evaluation : QAT Due Date: 01/31/94 Responsible Group for Overall PIP Approval : OEA Due Date: 02/15/94 Screened By: RFCOLE Group: OEA Date: 07/28/93 l
l III. Problem Evaluation l System (s) Affected :
1). CF = Feedwater System
() Affected Equipment:
WMS Equipment ID No. l Comp ~.
Code l Manufacturer Name l
1 i
i L
i Today's Date : 05/31/95 MSE Serial No. : t Time : 11:33 LER Serial No.: {
r'%g Page No.: 3 Other Rpt. No. : IN 93-20 k ,/
m PIP Serial No. : 0-C93-0631 -
CATAWBA NUCLEAR STATION l Problem Investigation Process Problem Investigation Form i Most Probable Group Causing Event Status: CLOSED ,
Group INPO Cause Code (s) : l 1). N/A - 03e = Testing not specified ;
l Cause(s) of Problem:
i The need for this type of testing was identified by the NRC after the original ISI plan had been prepared.
Originated by: JECHERRY Group: QAT Date: 04/76/94 !
)
Revised by: JWGLENN Group: SRG Date: 04/26/94 Is Cause Determination Complete (y,n) : Yes Assigned To : / Mgmt Exception: No l Orig Due Date : 01/31/94 Curr Due Date: 01/31/94 # of Ext.: 0 [
Approved By : JOBARBOU Group: QAT App Date : 04/28/94 O Proposed Resolution From: OAT Gro Status: CLOSED l
i The Feedwater (CF) Nozzle to pipe welds will be re-examined using ;
a new technique which utilizes surface waves and 60 degree i refracted long waves. An ISI plan addendum will be written to schedule the four CF nozzle to pipe welds in Unit 1 for Refueling i Outage #8 and Unit 2 for Refueling Outage #6. ;
Originated by: JECHERRY Group: QAT Date: 04/26/94 Is Prop. Resolution ready for approval? (y,n): Yes AsnToGrp: 07/28/93 Assigned To : / Mgmt Exception: No !
Orig Due Date : 08/27/93 Curr Due Date : 01/31/94 # of Ext.: 2 i Approved By : JOBARBOU Group : QAT App Date : 04/28/94 i
Remarks:
i IV. Corrective Actions Resp Grp: QAT Brief Proposed Corrective Action: Orig Grps QAT l
l l
Today's Date : 05/31/95 MSE Serial No. :
Time : 11:33 LER Serial No.:
Page,No.: 4 Other Rpt. No. : IN 93-20 ;
O PIP Serial No. : 0-C93-0631 ,
CATAWBA NUCLEAR STATION Problem Investigation Process Problem Investigation Form ,
1 Make ISI Plan addendums to schedule the CF nozzle to Pipe ;
Welds.
i I
Prop CAC: Al Actual CAC: Al Outage : I Work Orders / Requests:
MOD Infor Mode:
RGC Item : OEA Item:
SRG Item : QVD Item: ;
INPO Item:
Actual Corrective Action Resolution From: QAT Grp Status: CLOSED ,
i The following ISI Plan Addendums were written to reschedule the l CF Nozzle to pipe welds as shown below:
Unit 1 - Plan Addendum Serial No. CAT 1-0289 C05.021.050 1CF17-04 (SG1C) Examine RFO #8 C05.021.053 1CF22-01 (SG1D) Examine RFO #8 C05.021.056 1CF27-01 (SG1A) Examine RFO #8 C05.021.067 1CF34-13 (SG1B) Examine RFO #8 Unit 2 Plan Addendum Serial No. CAT 2-0171 ,
C05.021.056 2CF64-28 (SG2A) Examine RFO #6 C05.021.060 2CF65-27 (SG2B) Examine RFO #6 C05.021.065 2CF67-26 (SG2D) Examine RFO #6 These changes have been updated and are currently shown in the Catawba Units 1&2 first interval ISI Plan. Item Number C05.021.061, 2CF66-29 (SG2C), will be examined RFO #6 as originally scheduled in the Catawba Unit 2 First Interval ISI Plan.
Originated by: JECHERRY Group: QAT Date: 04/26/94 Is Corrective Action ready for approval? (y,n): Yes AsnToGrp: 04/26/94 O
V Assigned To : /
Orig Due Date : 10/26/93 Curr Due Date: 10/26/93 # of Ext.: 0 Mgmt Exception: 'No'
Today's Date : 05/31/95 MSE Serial No. :
Time . 11:33 LER Serial No.:
Og Page No.: 5 Other Rpt. No. : IN 93-20 PIP Serial No. : 0-C93-0631 CATAWBA NUCLEAR STATION Problem Investigation Process ,
Problem Investigation Form Approved By : JOBARBOU Group: QAT App Date : 04/28/94
Resp Grp: QAT Brief Proposed Corrective Action: Orig Grp: OEA 2 Review inspection results of CF nozzles and determine any additional corrective actions. Note: completion date will be revised to reflect refueling outage schedules for RFO#8 for Unit 1 and RFO#6 for Unit 2.
Prop CAC: A Actual CAC: A Outage :
Work Orders / Requests: !
MOD Info: Mode: 7 RGC Item : OEA Item:
SRG Item : QVD Item: [
INPO Items Actual Corrective Action Resolution From: QAT Grp Status: CLOSED j O The due dates provided are those when paperwork will be expected to be completed for each of the two refueling outages identified (RFO#6 and RFO#8) and do not constitute an extension.
The Catawba Units 1 and 2 Feedwater (CF) Nozzle to Pipe Welds have been re-examined using Procedure NDE-600 during Unit 1 EOC8 and Unit 2 EOC6. Indications from the Weld Root Area were verified to be Geometric Reflectors using a 70 degree scan.
There were no reportable indications.
Originated by: RFCOLE Group: OEA Date: 05/09/94 Revised by: KWSchmidt Group: QAT. Date: 05/11/95 Revised by: KWSCHMID Group: QAT Date: 05/11/95 Is Corrective Action ready for approval? (y, n) : Yes AsnToGrp: 05/05/94 Assigned To : JECHERRY / JECHERRY Mgmt Exception: No ,
Orig Due Date : 10/26/93 Curr Due Date: 06/01/95 # of Ext.: 1 Approved By : KWSCHMID Group: QAT App Date : 05/11/95 Resp Grp: OEA Brief Proposed Corrective Action: Orig Grp: OEA 3 This corrective action is being created to track the OEP item through ACCESS.
m . .
Today's Date : 05/31/95 MSE Serial No. : ,
Time : 11:33 LER Serial No.: l O Page No.: 6 Other Rpt. No. : IN 93-20 Q- PIP Serial No. : 0-C93-0631' i l
CATAWBA NUCLEAR STATION l Problem Investigation Process Problem Investigation Form Prop CAC: E Actual CAC: E Outage : -
Work Orders / Requests:
MOD Info: Mode: i RGC Item : OEA Item: OEA-SRG Item : QVD Item:
INPO Items Actual Corrective Action Resolution From: OEA Grp Status: CLOSED I
This item is being tracked through ACCESS.
Originated by: RFCOLE Group: OEA Date: 08/18/94 Is Corrective Action ready for approval? (y,n): Yes AsnToGrp: 08/18/94 Assigned To : RFCOLE / Mgmt Exception: No Orig Due Date : 10/26/93 Curr Due Date: 10/26/93 # of Ext.: 0 O
5 Approved By : RFCOLE OEA Concurrence: RFCOLE Group: OEA App Date : 08/18/94 Date : 02/24/95 V. Final and Overall PIP Accroval Criterion XVI Review:
XVI Review Not Required for this PIP Overall PIP Approval:
Assigned To: RFCOLE / Due Date: 02/15/94 Approved By: RFCOLE Group: OEA Date: 05/16/95 Supplemental Concurrences - These do not affect PIP Closure l l
Concurrences associated with External Committments i OEA Concurrence By : RFCOLE Date: 05/16/95 l l
End of the Document FOR PIP No.: 0-C93-0631 The Status of this PIP No, is : CLOSED Duration of this PIP was 657 days.
Today's Date - 05/31/95 MSE Serial No. : 1-C93-0875 Time : 11:38 LER Serial No.: N/A Page No.: 1- Other Rpt. No. : N/A O PIP serial No. : 1-C93-0875 CATAWBA NUCLEAR STATION Problem Investigation Process Problem Investigation Form I. Problem ID Occurred Time /Date: / / Discovered Time /Date: 14:00 10/21/93 Unit (s). 1 Status at Time Discovered: Unit 1 Unit 2 Mode: 1 N/A
% Power: 100 N/A Unit Status Remarks:
l System (s) Affected .
1). KC = Component Cooling System ;
1 Problem Found While Working With Work Order No. N/A
/
Location of Problem - Bldg: AUX Elev: 572 Column Line: HH-57 Location Remarks: room 300 Method Used To Discover Problem:
Visual examination, ASME Sect. XI inspection.
Brief Problem Descriotion:
Concrete anchors slipped out roughly 1/2".
Detailed Problem Descriotion:
)
.QA inspector identified that support 1-R-KC-0875 base plate was j separated from the ceiling roughly 1/2". This plate is secured to l the concrete with (4) 3/4" concrete anchors. Each anchor has slipped out of the concrete an equal amount. The middle bolt of the supports pipe clamp is also looso.
Originated by: CBCAUTHE Group CES Date: 10/21/93 l Other Units / Components / Systems / Areas Affected (Y,N,U): NO l
l Immediate Corrective Actions:
Corrective maint work order 93076868-01 issued to repair the support. Based on the operability review this repair work is scheduled as non-outage period work.
Originated by: CBCAUTHE Group: CES Date: 12/22/93 Corrective Action Work Order No.: 93076868-01
.. _ ~ _ _
1 Today's Date : 05/31/95 MSE Serial No. -
1-C93-0875 Time : 11:38 LER Serial No.: N/A ]
Page No.: 2 Other Rpt. No. : N/A O PIP Serial No. : 1-C93-0875 l
l CATAWBA NUCLEAR STATION Problem Investigation Process Problem Investigation Form s
Problem Identified By: CBCAUTHE Group: MCE Date: 10/21/93 Problem Entered By : CBCAUTHE Group: MCE Date: 10/21/93 II. Sionificance Is the Problem Significant? Y Action Category: 2
-Significance Code: 5 - Operability from Engineering MSE No.: 1-C93-0875 LER No.: N/A Other Report No.: N/A OEP No.: N/A Event Code (s) .
1). F3 = Equipment out of norm Esreenino Remarks:
() Screened By: CBCADTHE Group: MCE Date: 10/21/93 Operability: Status: CLOSED Sys/ Comp PRESENT Operable? (Y,N, C,E) : Y- Rqd Mode: N/A Resp. Grp for Present Operability : MCE Due Date: 10/28/93 l Evaluated By : DLCALDWE Group : CIV Act Date: / /
Comments: See Operability Screen Sys/ Comp PAST Operable ?(Y,N,C,E) . Y Status: CLOSED Resp. Grp for Past Operability : MCE Due Date: 10/28/93 Evaluated By -
DLCALDWE Group : CIV Act Date: 10/28/93 Comments: See Past Operability Screen I
Reportability: i Problem Reportable? (Y,N,E) : N Reportable Per: N/A Responsible Group for Reportability: SRG Due Date: 10/28/93 Evaluated By : JWGLENN Group : SRG Act Date: 10/28/93 Comments: Reviewed by RKS 11-4-93.
(
Notifications Made:
_~ - - - . - , -
Today's Date : 05/31/95 MSE Serial No. : 1-C93-0875 I Time : 11:38 LER Serial No.: N/A Page No.: 3 Other Rpt. No. : N/A 7 ,
PIP Serial No. : _1-C93-0875 CATAWBA NUCLEAR STATION Problem Investigation Process i Problem Investigation Form Regulatory Agency Contactee : N/A Duke Power Company Contactor : N/A Date . / /
Date NRC Res. Inspector Notified: / /
Date Notified VP or Sta. Mgr. : / /
Date Notified NS Duty Engineer : / /
Investigation Report:
Resp. Group for Invest. Report N/A Date : / /
Investigator a N/A Group: N/A Act Date -
/ /
Date Due to V.P. or Station Mgr.
/ /
Date Regulatory Agency Rpt. Due : / /
Data Investigation Report Apprvd: / /
NRC Cause Code (s) :
1). N/A = Cause code not applicable in this case l Operability Determination From: MCE Grp Status: CLOSED O An analysis has been performed based on removing S/R 1-R-KC-875 and the vertical component of 1-R-KC-874. Stresses are well below all code allowables. The remaining supports are capable of taking the resulting loads. The piping system is fully operable.
Originated by: RFKRAUSE Group: CIV' Date: 10/28/93 Revised by:- DLCALDWE Group: CIV Date: 10/28/93 Is Pres. Operability ready for approval? (y,n): Yes AsnToGrp:10/25/93 Assigned To : RFKRAUSE / Mgmt Exception: No Checked By FTRICKEN Orig Due Date -
10/28/93 Curr Due Date . 10/28/93 # of Ext.: 0 Approved By : DLCALDWE Group : op_ App Date : 10/28/93 Past Operability Determination From: MCE Grp Status: CLOSED See operability determination above.
Originated by: RFKRAUSE Group: CIV Date: 10/28/93 Revised by: DLCALDWE Group: CIV Date: 10/28/93 Is Past Operability ready for approval? (y,n): Yes AsnToGrp: 10/25/93 Assigned To :RFKRAUSE / Mgmt Exception: No Checked By :FTRICKEN Orig Due Date .
10/28/93 Curr Due Date : 10/28/93 # of Ext.. 0
-' Approved By . DLCALDWE Group . opi App Date . 10/28/93
r -
1 Today's Date : 05/31/95 MSE Serial No. : 1-C93-0875 Time : 11:38 LER Serial No.: N/A
-q. Page No.: 4 Other Rpt. No. : N/A PIP Serial No. : 1-C93-0875 CATAWBA NUCLEAR STATION Problem Investigation Process Problem Investigation Form Responsible Group (s) for Proposed Resolution .
Original l Current l #
Due Date l Due Date l Ext. .
1). MCE = Mechanical / Civil Equip 11/20/93 l 11/20/93 l 0 !
2). OEA = Op. Exper. Assess. 11/20/93 l 11/20/93 l 0 Responsible Group for Cause Code Evaluation : MCE Due Date: 11/20/93 Responsible Group for Overall PIP Approval : SRG Due Date: 08/02/94 III. Problem Evaluation '
System (s) Affected :
1). KC = Component Cooling System Affected Equipment: Comp. Manufacturer WMS Equipment ID No. l Code l Name l O Most Probable Group Causing Event Status: CLOSED Group INPO Cause Code (s) :
1). N/A - C4e = Unusual plant conditions / configuration Cause (e) of Problem:
The support uses sleeve type anchors that in some instances will loosen when exposed to constant vibration. The configuration of the support would place the anchor in tension loading with fairly constant vibration levels. This is believed to have caused the loosening of the anchors.
Originated by: CBCAUTHE Group: CES Date: 12/22/93 Is Cause Determination Complete (y,n) : Yes Assigned To : CBCAUTHE / ZLTAYLOR Mgmt Exception: No l Orig Due Date : 11/20/93 Curr Due Date: 11/20/93 # of Ext.: 0 Approved By : JSLYNCH Group: MCE App Date : 12/27/93 SRG Concurrence: JWGLENN Date : 12/28/93 Proposed Resolution From: MCE Gro Status: CLOSED The repair of this support will use a wedge type anchor which has proven to be much more resistive to constant vibration O conditions. The effectiveness of this repair will be verified by a follow up inspection of this support by the ISI inspection
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Today's Date : 05/31/95 MSE Serial No. : 1-C93-0875 Time : 11:38 LER Serial No.: N/A *
( Page No.: 5 Other Rpt. No. : N/A PIP Serial No. : 1-C93-0875 CATAWBA NUCLEAR STATION Problem Investigation Process Problem Investigation Form plan. Repair of the support is to be accomplished by work order 93076868-01.
Originated by: CBCAUTHE Group: CES Date: 12/22/93 Need to discuss if this were an isolated case or not. Does CNS .
need to review its installation procedures for anchors? Does CNS need to inspect a ramdon sample for similar misuse. In all cause analysis, everyone needs to address the issue of generic >
applicable.
Revised by: WFBEAVER Group CES Date: 02/10/94 l In the corrective action to repair this support numerous supports i up and down stream were inspected to see if loose anchors were present. No other anchor problems were located on this pipe that would have given the anchors similar operating conditions to the anchors that did pull loose. Based on this inspection this anchor problem is considered applicable only to this support location.
In addition hundreds of supports that utilize anchors are
'O inspected through the ASME ISI inspection each year. There have been some anchor discrepancies evaluated but these have not been significant enough to implicate a generic anchor or anchor installation problem exist at Catawba.
Revised by: CBCAUTHE Group: CES Date: 03/01/94 ,
Is Prop Resolution ready for approval? (y,n): Yes AsnToGrp: 10/25/93 '
Assigned To : CBCAUTHE / CBCAUTHE Mgmt Exception: No Orig Due Date : 11/20/93 Curr Due Date -
11/20/93 # of Ext.: 0 Approved By : GMCORNWE Group : res App Date : 03/01/94 !
SRG Concurrence: JWGLENN Date : 03/02/94 Pronosed Resolution From: OEA Gro Status: CLOSED Proposed resolution is to process this MSE through the OEP' (per the requirements of 10CFR50 Appendix B, Criterion XVI.
Originated by: PBNARDOCI Group: OEA Date: 10/25/93 Is Prop. Resolution ready for approval? (y,n): Yes AsnToGrps 10/25/93 Assigned To . PBNARDOC / RFCOLE Mgmt Exception: No Orig Due Date : 11/20/93 Curr Due Date : 11/20/93 # of Ext.: 0 Approved By : RFCOLE Group + OEA App Date : 10/25/93 SRG Concurrence: JWGLENN Date : 10/25/93 9
i Today's Date : 05/31/95 MSE Serial No. : 1-C93-0875 Time : 11:38 LER Serial No. N/A
,f ss Page No.: 6- Other Rpt. No. : N/A
) PIP Serial No. : 1-C93-0875 CATAWBA NUCLEAR STATION Problem Investigation Process Problem Investigation Form Remarks:
IV. Correctiva Actions Resp Grp: OEA Brief Proposed Corrective Action: Orig Grp: OEA 1 Perform generic applicability screening evaluation for the Duke sites, and take any resulting corrective actions necessary per OEP.
Prop CAC: G Actual CAC: G Outage .
Work Orders / Requests:
MOD Info: Mode:
RGC Item . OEA Item:
lp) SRG Item QVD Item:
INPO Item:
Actual Corrective Action Resolution From: OEA Grp Status: CLOSED This event met the PIP significance criteria because of the operability evaluation necessary to assure the piping system is fully operable. The overall technical merit with regards to the
. Anchor problem noted when combined with the past results of the ISI inspections at CNS indicate there are no significant lessons that can be learned through further Operating Experience Program action. A review of existing PIP data at MNS and ONS also support that conclusion. ISI inspection programs at all three sites are there to identify anchor discrepancies such as the one noted in this PIP.
Originated by: FAKRAUSS Group: OEA Date: 07/21/94 l Revised by: FAKRAUSS Group: OEA Date: 07/21/94 ;
l Is Corrective Action ready for approval? (y,n): Yes AsnToGrp: 10/25/93 Assigned To FAKRAUSS / Mgmt Exception: No !
Orig Due Date . '04/19/94 Curr Due Date: 04/19/94 # of Ext.: 0 l Approved By : FAKRAUSS Group: CEA App Date -
07/21/94 j SRG Concurrence: JWGLENN Date . 07/25/94 )
l Today's Date : 05/31/95 MSE Serial No. : 1-C93-0875 ;
Time : 11:38 LER Serial No.: N/A e Page No.: 7 Other Rpt. No. : N/A PIP Serial No. : 1-C93-0875 l i
CATAWBA NUCLEAR STATION-Problem Investigation Process [
Problem Investigation Form Resp Grp: WCG f Brief Proposed Corrective Action: Orig Grp: MCE 2 Plan and schedule completion of W/O 93076868-01. Specify wed '
ge anchors be used in the repair.
Prop CAC: Ble Actual CAC: Outage :
Work Orders / Requests:
MOD Info: Mode: r RGC Item : OEA Item:
SRG Item : QVD Item:
INPO Item:
f Actual Corrective Action Resolution From: WCG Grp Status: CLOSED The subject W.O. has been planned and scheduled. ,
i Originated by: SFHATLEY Group: WCG Date: 01/18/94 i
Is Corrective Action ready for approval? (y,n): Yes AsnToGrp: 12/22/93 ;
Assigned To : / DMJARMAN Mgu.t Exception: No Orig Due Date : 04/19/94 Curr Due Date: 04/19/94 # of Ext.: 0 Approved By : DCLESLIE Group: WCG App Date : 01/18/94 SRG Concurrence: JWGLENN Date : 02/01/94 l i
Resp Grp: SRG -
Brief Proposed Corrective Action: Orig Grp: SRG l 3 SRG to confirm completion of WO 93076868-01 ;
l 1
Prop CAC: Ble Actual CAC: Outage : i i
Work Orders / Requests: l I
MOD Info: Mode:
RGC Item : OEA Item:
SRG Item : QVD Item:
INPO Item:
Actual Corrective Action Resolution From: SRG Grp Status: CLOSED
Today's Date : 05/31/95 MSE Serial No. : 1-C93-0875 Time : 11:38 LER Serial No.: N/A Page No.: 8 Other Rpt. No. : N/A '
O PIP Serial No. : 1-C93-0875 CATAWBA NUCLEAR STATION Problem Investigation Process Problem Investigation Form WO 93076868-01 was completed on 2-7-94 per WMS.
Originated by: JWGLENN Group: SRG Date: 02/09/94 i
Is Corrective Action ready for approval? (y,n): Yes AsnToGrp: 02/01/94 1 Assigned To : JWGLENN / DPKIMBAL Mgmt Exception: No Orig Due Date : 04/19/94 Curr Due Date: 04/19/94 # of Ext.: 0 Approved By : JWGLENN Group: SRG App Date : 02/09/94 ,
SRG Concurrence: WFBEAVER Date : 02/10/94 V. Final and Overall PIP Ancroval Criterion XVI Review: '
XVI Status : Complete GO PIP No.:
Assigned To: FAKRAUSS / Due Date: 04/30/94 Approved By: TERYAN Group: OEA Date: 07/M/94 Overall PIP Approval:
Assigned To: JWGLENN / DPKIMBAL Due Date: 08/02/94 )
Approved By: JWGLENN Group: SRG Date: 07/26/94 )
l Microfilm Roll / Frame : /
End of the Document FOR PIP No.: 1-C93-0875 The Status of this PIP No. is : CLOSED Duration of this PIP was 278 days.
l l
O
Today's Date : 05/31/95 MSE Serial No. : 2-C94-0874 Time : 11:34 LER Serial No.t Page No.: 1 Other Rpt. No. :
O PIP Serial No. : 2-C94-0874 CATAWBA NUCLEAR STATION Problem Investigation Process Problem Investigation Form I. Problem ID Occurred Time /Date: 09:00 06/20/94 Discovered Tide /Date: 09:00 06/20/94 Unit (s) : 2 Status at Time Discovered: Unit 1 Unit 2 i Mode: N/A 5 I
% Power: N/A 0 )
Unit Status Remarks:
System (s) Affected:
1). NI = Safety Injection System Problem Found While Working With Work Order No.:
Location of Problem - Bldg: RX Elev: 560 Column Line: 54'-280 Location Remarks:
Method Used To Discover Problem:
Found while Type C, testing a new check valve installed per CE4379 Brief Problem
~~Description:~~
2NI-485 will not pass Type C test Detailed Problem DescriDtion:
Minor Mod CE-4379 installed an orifice and check valve (2NI-485) downstream of vent valve 2NI-423 to allow a pressure bleed off path should the NI Pump discharge header begin to pressurize due to leakage past NI check valves. The check valve specified to be used would not pass the Type C leak rate test. Discussions were held and it was decided that a different type of check valve would be more appropriate in this application; however, this new type of valve has a 300 degree limitation. The flow diagram list the design temperature for the line as 650 degtees. Upon further discussion with persons in MCE, it has been discovered that this particular portion of the NI system is analyzed for only 200 degrees from a piping / thermal expansion standpoint. With leakage past the NI check valves occuring, the possibility for this piping to exceed 200 degrees exist.
Originated by: GBSAXON Group: SES Date: 06/22/94 O Other Units / Components / Systems / Areas Affected (Y,N,U): UNK
_ . . - , _ ..u. .
l l 1
l Today's Date : 05/31/95 MSE Serial No. 2-C94-0874 Time : 11:34 LER Serial No.:
f- Page No.: 2 Other Rpt. No. :
PIP Serial No. : 2-C94-0874 CATAWBA NUCLEAR STATION Problem Investigation Process Problem Investigation Form I
Immediate Corrective Actions:
1 i
Valve 2NI-423 will be administratively controlled in the closed position. The possibility for temperature to exceed 200 degrees in this section of piping will be researched.
Originated by: GBSAXON Group: SES Date: 06/22/94 Corrective Action Work Order No.: N/A i
e Problem Identified By: GBSAXON Group: SES Date: 06/22/94 Problem Entered By : GBSAXON Group: SES Date: 06/22/94 l
II. Sianificance l
Is the Problem Significant? N Action Category: 3 .
( Significance Code: 5 MSE No. 2-C94-0874
- Operability from Engineering LER No.. Other Report No.
{
OEP No.- I
?
Event Code (s) : l 1). D6 = Engineering \ Drawings or calculations l Screening Remarks: [
I Penetration is currently operable. Addition of new check valve will require reanalysis of NI Piping on this penetration and also calculation of temperature profile from the NC System back to the new check valves at an assumed flow rate or 1 gpm.
Originated by: WMCARWIL Group: SES Date: 06/23/94 PIP upgradef. to Category 2 on 6/28/94. This is based on the concern of the temperature used for the stress analysis on the NI !
piping upstream of the first check valve off the loops. Current l analysis assumes temperatures < 200 F. If ANY leakage past the ,
primary checks occurs, this temperature will be > 200 F. This j will require an Engineering evaluation to determine if an
{
operability issue exists. This also is a past operability !
concern for Units 1 and 2 and potentially a current operability l concern for Unit 2 dependent upon if any leakage past the primary !
() checks occurs when at full system pressure and temperature. j 1
I t
_ _ _ . - . - -- .- - ._- - . - =
1 Today's Date : 05/31/95 MSE Serial No. 2-C94-0874 Time : 11:34 LER Serial No.:
q Page No.: 3 Other Rpt. No. :
PIP Serial No. 2-C94-0874 CATAWBA NUCLEAR STATION Problem Investigation Process Problem Investigation Form i
Revised by: EWFRITZ Group: SES Date: 06/28/94 PIP downgraded to an Action Category 3. Engineering evaluation I was done and no operability concerns were documented.
Revised by: WFBEAVER Group: SRG Date: 08/26/94 Operability: Status: CLOSED i Sys/ Comp PRESENT Operable? (Y,N, C, E) : Y Rqd Mode: NA Resp. Grp for Present Operability : SRG Due Date: 06/29/94 "
Evaluated By . JWGLENN Group : SRG Act Date: / /
Comments: See Present Operability Screen Sys/ Comp PAST Operable ?(Y,N,C,E) -
Y Status: CLOSED ;
Resp. Grp for Past Operability : MCE Due Date: 07/12/94 Evaluated By : DRKULLA Group : MCE Act Date: 08/22/94 l 5
Comments: See Past Operability Screen u
Reportability: f Problem Reportable? (Y,N,E) . N Tr-sportable Per: N/A l Responsible Group for Reportability: SRG Due Date: 07/12/94 Evaluated By : JWGLENN Group : SRG Act Date: 08/22/94 Comments: N/A Notifications Made:
Regulatory Agency Contactee . N/A [
Duke Power Company Contactor - : N/A Date : / / {
Date NRC Res. Inspector Notified: / / !
Date Notified VP or Sta. Mgr. : / /
Date Notified NS Duty Engineer : / /
?
Investigation Report:
Resp. Group for Invest. Report : N/A Date : / / '
Investigator : N/A Group: N/A Act Date 4 / /
Date Due to V.P. or Station Mgr.: / / '
Date Regulatory Agency Rpt. Due : / /
Date Investigation Report Apprvd: / /
I I
i
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1 Today's Date : '05/31/95 MSE Serial No. : 2-C94-0874 Time : 11:34 LER Serial No.:
Page No. : 4 Other Rpt. No.
O
+
PIP Serial No. 2-C94-0874 CATAWBA NUCLEAR STATION Problem Investigation Process l Problem Investigation Form I NRC Cause Code (s) 1). N/A = Cause code not applicable in this case Operability Determination From: SRG Grp Status: CLOSED See screening remarks that indicate present operability.
Originated by: JWGLENN Group: SRG Date: 06/29/94 ,
9 Is Pres. Operability ready for approval? (y,n): Yes AsnToGrpte 29/94 !
Assigned To : JWGLENN / Mgmt Exception: No -
Checked By :JWGLENN l Orig Due Date : 06/29/94 Curr Due Date : 06/29/94 # of Ext.: 0 Approved By : JWGLENN Group : SRG App Date : 06/29/94 Past Operability Determination From: MCE Grp Status:-CLOSED
() The piping and support / restraints are past operable based on the evaluation of these components to the conditions defined by SES. The evaluations are documented in the Unit 2 Analysis !
Problems listed below. Reference the following Unit 2 Analysis ,
and Support / Restraint calculations: .
ANALYSIS:
NI204 CNC-1206.02-82-0058 NI205 CNC-1206.02-82-0055 i NI206 CNC-1206.02-82-0059 NI207 CNC-1206.02-82-0056 ,
i SUPPORT / RESTRAINT:
NI204 CNC-1206.12-24-1036 -
NI205 CNC-1206.12-24-1037 j NI206 CNC-1206.12-24-1038 ,
NI207 CNC-1206.12-24-1039 The Unit 1 piping and Support / Restraints are also considered !
past operable per a review by Mark Shutt and Gary Pickeral. This l review indicated the piping geometry, support locations and type [~
along with the estimated temperature profiles were sufficiently similiar to Unit 2. .
Originated by: PWGERMER Group: MCE Date: 08/22/94 l
{.
n --.,-e - - - - - -, ,,v. - , ,
.Today's Date : 05/31/95 MSE Serial No. : 2-C94-0874 Time : 11:34 LER Serial No.:
q 'Page No.: 5 Other'Rpt. No. :
Q PIP Serial No. 2-C94-0874 CATAWBA NUCLEAR STATION Problem Investigation Process Problem Investigation Form Revised by: DRKULLA Group: MCE Date: 08/22/94 Is Past Operability ready for approval? (y,n): Yes AsnToGrp: 07/08/94 Assigned To :PWGERMER / DRKULLA Mgmt Exception: No Checked By :JFWILLIS Orig Due Date : 07/12/94 Curr Due Date -
07/12/94 # of Ext.: 0 Approved By : DRKULLA Group : MCE App Date : 08/22/94 Responsible Group (s) for Proposed Resolution .
Original l Current l #
Due Date l Due Date l Ext.
1). MCE = Mechanical / Civil Equip 07/20/94 l 07/20/94 l 0 .
2). SES = System Engineering 07/20/94 l 07/20/94 l 0 Responsible Group for Cause Code Evaluation : SES Due Date: ,07/20/94 Responsible Group for Overall PIP Approval + SRG Due Date: / /
Screened By: WMCARWIL Group: SES Date: 06/23/94 JII. Problem Evaluation System (s) Affected :
1). NI = Safety Injection System Affected Equipment: Comp. Manufacturer WMS Equipment ID No. l Code l Name l Most Probable Group Causing Event Status: CLOSED Group INPO Cause Code (s) :
1). b/A - M2 - Design Analysis Cause(s) of Problem:
Problem caused by original station design considering only normal system operating conditions for pipe stress analysis. This allowed a significant cost savings in the design of system supports and restraints. Consideration for check valve backleakage was not assumed. Subsequent to the design, NRC has issued notices on the potential for thermal stratification in O piping due to check valve backleakage. Duke has been evaluating the thermal stratification issue for several years now, but the
Today's Date : 05/31/95 MSE Serial No. : 2-C94-0874 l Time : 11:34 LER Serial No.: !
page No.: 6 Other Rpt No. :
PIP Serial No. 2-C94-0874 '
CATAWBA NUCLEAR STATION Problem Investigation Process Problem Investigation Form review had not progressed to this section of NI piping yet. .
Originated by: GBSAXON Group: SES Date: 07/14/94 Is Cause Determination Complete (y,n) : Yes Assigned To GBSAXON / EWFRITZ Mgmt Exception: No Orig Due Date : 07/20/94 Curr Due Date: 07/20/94 # of Ext.: 0 ;
~
Approved By EWFRITZ Group: SES App Date : 07/20/94 Pronosed Resolution From: MCE Gro-Status: CLOSED 6
The proposed resolution to this problem will consist of six ,
parts. These six parts are listed below.
~~1. Add additional ISI welds to the current list for the up ;~~
coming outage based on the operability calculation performed for j this PIP. ,
( 2. Review other possible leak paths that could be pressurizing the NI header.
~~3. Determine if the existing data collected to date on these ,~~
~~same lines at McGuire, could be used to revise the Catawba class i 1 Transient Specification.~~
~~4. If the McGuire data cannot be used, design a modification to~~
~~. instrument these lines to determine the actual temperatures during valve leakage and to determine if thermal stratification exists in the lines during valve leakage.~~
~~5. Based on the data gathered under part 3 or 4 a modification' would be generated to revise the Catawba Class 1 Transient Specification, and to requalify and or modify the piping as required.~~
~~6. Add a request to the Reactor Trip List, that the temperature j of these lines be checked the next time they are accessible with j~~
.the RCL at full temperature and pressure. !
Based on further consideration of data to be gathered and the !
amount of exposure to obtain this information at the time of a Reactor Trip, it'was concluded to delete this request.
() Originated by: JFWILLIS Group: MCE Date: 09/07/94
Today's Date : 05/31/95 MSE Serial No. : 2-C94-0874 Time : 11:34 LER Serial No.
rm Page No.: 7 Other Rpt. No. -
(j PIP Serial No. : 2-C94-0874 CATAWBA NUCLEAR STATION Problem Investigation Process Problem Investigation Form Revised by: DRKULLA Group: MCE Date: 09/20/94 Is Prop. Resolution ready for approval? (y,n): Yes AsnToGrp : 06/23/94 Assigned To : JFWILLIS / DRKULLA Mgmt Exception: No Orig Due Date -
07/20/94 Curr Due Date 07/20/94 # of Ext.: 0 Approved By : DRKULLA Group . MCE App Date : 09/14/94 ProDosed Resolution From: SES Gro Status: CLOSED The past operability determination for this issue revealed that check valve backleakage is not a problem when considering thermal stresses for normal operation. However, a potential problem can occur during a safety injection when check valve backleakage is present. Therefore, this piping must be analyzed whenever a safety injection (actual or inadvertent) occurs. A correction action is issued for the SES NI system engineer to revise the Technical Support Program for the NI system to include the need to analyze the NI piping after any safety injection.
O Q Originated by: GBSAXON Group: SES Date: 07/14/94 Is Prop. Resolution ready for approval? (y,n): Yes AsnToGrp: 06/23/94 Assigned To : GBSAXON / EWFRITZ Mgmt Exception: No Orig Due Date : 07/20/94 Curr Due Date 07/20/94 # of Ext.. O Approved By : EWFRITZ Group SES App Date . 07/20/94 Remarks:
IV. Corrective Actions Resp Grp: SES Brief Proposed Corrective Action: Orig Grp: SES 1 Revise the NI system Tech Support Prgm to include the need to analyze NI CL injection lines following any safety injection (actual or inadvertent) for thermal stresses.
Prop CAC: A3 Actual CAC: E Outage :
Work Orders / Requests:
O MOD Info:
RGC Item Mode:
OEA Item:
Today's Date : 05/31/95 MSE Serial No. : 2-C94-0874 Time : 11:34 LER Serial No.:
Page No.: 8 Other Rpt. No. :
PIP Serial No. 2-C94-0874 CATAWBA NUCLEAR STATION Problem Investigation Process Problem Investigation Form SRG Item : QVD Item:
INPO Item:
Actual Corrective Action Resolution From: SES Grp Status: CLOSED Per discussion with MCE, analysis of the NI Cold Leg Injection lines following an actual or inadvertent safety injection is not necessary. The current thermal analysis contains:" bounding conditions" that qualify the pipe for a given number of safety injections and heatup/cooldown cycles. TLe number of safety injections and heatup/cooldown cycles are tracked by the Reactor Engineering group. ' This proposed corrective action is not needed and no further action is required.
Originated by: GBSAXON Group: SES Date: 12/09/94 Is Corrective Action ready for approval? (y,n): Yes AsnToGrps 07/20/94 Assigned To : GBSAXON / EWFRITZ Mgmt Exception: No Orig Due Date : 12/17/94 Curr Due Date: 12/17/94 # of Ext.: 0 Appruved By : EWFRITZ Group: SES App Date : 12/13/94 O
Resp Grp: MCE Brief Proposed Corrective Action: Orig Grp: MCE 2 MCE will be responsible for Parts 1 and 6 of the MCE proposed resolution.
Prop CAC: A3 Actual CAC: Outage :
Work Orders / Requests:
MOD Info Mode:
RGC Item : OEA Item:
SRG Item : QVD Item INPO Item:
Actual Corrective Action Resolution From: MCE Grp Status: CLOSED Part I was completed. A marked up set of weld ISO's indicating the additional welds to be inspected was forwarded to Ron C Giles in the Plant ISI Group. The additional welds will be added to the augmented inspections for the upcoming Unit 1 outage.
Part 6, the request to obtain temperature information was deleted. See revised resolution.
Today's Date : 05/31/95 MSE Serial No. : 2-C94-0874 Time : 11:34 LER Serial No..
Page No.: 9 Other Rpt. No. :
y PIP Serial No. : 2-C94-0874 CATAWBA NUCLEAR STATION Problem Investigation Process Problem Investigation Form Originated by: DRKULLA Group: MCE Date: 09/20/94 Is Corrective Action ready for approval? (y,n): Yes AsnToGrp: 09/08/94 Assigned To : JFWILLIS / DRKULLA Mgmt Exception: No.
Orig Due Date : 09/18/94 Curr Due Date: 09/18/94 # of Ext.: 0 Approved By : DRKULLA Group: MCE App Date : 09/20/94 Resp Grp: SES Brief Proposed Corrective Action: Orig Grp: MCE 3 SES will be responsible for parts 2 and 3 of the MCE proposed resolution.
Prop CAC: B3a Actual CAC: B3a Outage :
Work Orders / Requests:
MOD Info: Mode:
RGC Item : OEA Item:
SRG Item . QVD Item:
INPO Item:
Actual Corrective Action Resolution From: SES Grp Status: CLOSED The ECCS team has been reviewing possible leak paths into the NI Pump discharge header for some time. The team feels that the leakage is coming through the NI Cold Leg injection lines based on the following:
1) During Pressure Boundary Valve testing in U2EOC5, the pressure in the NI' Pump discharge piping was bled off and the cold leg injection lines isolated by closing 2NI-162A, 2NI-118A and 2NI-150B. Pressure was monitored and no change occurred. This eliminated any leakage coming from the NI hot leg injection lines as well as leakage from the NI test header. Next, valves 2NI-162A, 2NI-118A and 2NI-150B were opened and the NI Pump discharge header subsequently pressurized.
2) While at full power prior to U2EOC6, valve 2NI-95A was opened and pressure observed at 2NIPG5220. Although the NI Pump discharge header was pressurized ('>600 psig), 2NIPG5220 only indicated approximately 100 psig. Once again, this ruled out any pressurization coming from the NI test header.
-O The ECCS team feels comfortable with identifying the leak path as
Today's Date : 05/31/95 MSE Serial No. : 2-C94-0874 Time : 11:34 LER Serial No.:
Page No.: 10 Other Rpt. No. :
O PIP Serial No. : 2-C94-0874 CATAWBA NUCLEAR STATION Problem' Investigation Process Problem Investigation Form j through the NI Cold Leg Injection lines. However, the specific
( leak path (Loop A, B, C or D) or combination of loop leak paths has not been determined.
l l
Although temperature data has been obtained at McGuire on these i lines, the ECCS team feels that this data alone would not be I
sufficient to revise the Catawba class 1 Transient Specification. l The team is still reviewing the possibility of using the McGuire l data to supplement some of our calculations. '
j Originated by: GBSAXON Group: SES Date: 10/11/94 Revised by: GBSAXON Group: SES Date: 10/11/94 1
Is Corrective Action ready for approval? (y,n): Yes AsnToGrps 09/08/94 l Assigned To : GBSAXON / EWFRITZ Mgmt Exception: No Orig Due Date : 09/18/94 Curr Due Date: 09/18/94 # of Ext.: 0 Approved By . EWFRITZ Group: SES App Date : 10/12/94 O Resp Grp: SES Brief Proposed Corrective Action: Orig Grp: MCE 4 SES will be responsible for part 4 of the MCE proposed resolution.
Prop CAC: Bic Actual CAC: B1c Outage :
Work Orders / Requests:
MOD Info: CN-21361 Mode:
RGC Item : OEA Item:
SRG Item : QVD Item:
INPO Item:
Actual Corrective Action Resolution From: SES Grp Status: CLOSED A proposed modification has been developed and will be sent to the October activation meeting that will allow the NI Cold Leg Injection lines to be instrumented at various locations to determine actual operating temperatures during check valve leakage. By instrumenting these lines, any thermal stratification that occurs during valve leakage may also be detected. In addition, temperature indication will help in O determining which check valves are leaking and in need of maintenance activity. The modification provides a method of J
Today's Date : 05/31/95 MSE Serial No. : 2-C94-0874 Time : 11:34 LER Serial No..
Page No.: 11 Other Rpt. No. :
O PIP Serial No. : 2-C94-0874 CATAWBA NUCLEAR STATION Problem Investigation Process Problem Investigation Form recording temperature data during startup/ shutdown and normal operating modes via computer without entering containment.
NOTE: The proposed resolution made reference to possibly using data obtained from McGuire. This option is currently under review; however, due to time constraints, the ECCS team felt that the process of developing a modification to instrument Catawba's injection lines should be started in case the McGuire data could not be used. ,
l l
Originated by: GBSAXON Group: SES Date: 10/11/94 Waiting on activation of modification before this item can be closed out.
Revised by: EWFRITZ Group: SES Date: 10/18/94 Modification activated on December 7, 1994 activation meeting.
Modification number is CN-21361.
Revised by: EWFRITZ Group: SES Date: 12/13/94 Is Corrective Action ready for approval? (y,n): Yes AsnToGrp: 09/08/94 Assigned To . GBSAXON / EWFRITZ Mgmt Exception: No Orig Due Date : 09/18/94 Curr Due Date: 09/18/94 # of Ext.- 0 Approved By : EWFRITZ Group: SES App Date : 12/13/94 .
i i
Resp Grp: SES l Brief Proposed Corrective Action: Orig Grp: MCE l 5 SES will be responsible for part 5 of the MCE proposed
'esolution.
r Prop CAC: B4c Actual CAC: Outage :
Work Orders / Requests:
MOD Info: Mode:
RGC Item : OEA Item:
SRG Item : QVD Item:
INPO Item:
Actual Corrective Action Resolution From: SES Grp Status: OPEN O Management Exception taken. Analysis of pipe thermal data cannot
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Today's Date : 05/31/95 MSE Serial No. : 2-C94-0874 '
Time : 11:34 LER Serial No..
Page No.: 12 Other Rpt. No. :
O' PIP Serial No. 2-C94-0874 CATAWBA NUCLEAR STATION Problem Investigation Process :
Problem Investigation Form be accomplished until after modification is installed to obtain this data and sufficient operating time has elapsed to gather data for analysis. Earliest modification can be installed is 2EOC7 (Oct 95), followed by one cperating cycle to gather data 2EOC8 (Mar 97). Add in three months to evaluate data, places earliest possible date for completion of this item at June 1997.
This date may need to be further revised dependent upon the quality of data received in the first cycle following modification installation.
Originated by: EWFRITZ Group: SES Date: 10/18/94 Is Corrective Action ready for approval? (y,n):. No AsnToGrp: 09/08/94 Assigned To : GBSAXON / EWFRITZ Mgmt Exception: Yes Orig Due Date : 09/18/94 Curr Due Date: 06/30/97 # of Ext.- 1 Approved By : Group: App Date : / /
() V. Final and Overall PIP Acoroval Criterion XVI Review:
XVI Review Not Required for this PIP Overall PIP Approval:
Assigned To: / Due Date: / /
Approved By: Group: SRG Date: / /
End of the Document FOR PIP No.: 2-C94-0874 The Status of this PIP No. is : OPEN ,
1 0
9.0 Refemnce Documents The following reference documents apply to the inservice inspections performed during Outage 8 at Catawba Nuclear Station, Unit 1:
Duke Power Company Request for Relief Serial No. 94-03 Duke Power Company Request for Relief Serial No. 95-01 Duke Power Technical Document 90-1 Catawba Unit 1 EOC 8 Eddy Current Report (This report is on file at McGuire Nuclear Station - Diversified Services Division / NDE of the Electrical System Support Department.
O O Page1ofI Refueling Outage Report EOC 8 Catawba Unit 1 Revision 0 Section 9 June 1,1995
Serial No. 94-03 Page1of3 g)
(- DUKE POWER COMPANY Request forReliefFmm InserviceInspection Requirement Station: Catawba Unit: 1 Requesting Department: Nuclear Generation Department Refemnce Code: ASME Boiler and Pressure Vessel Code,Section XI 1980 Edition through Winter 1981 Addenda I. Component for which reliefis mquested:
~~a. Name and Identification Number:~~
Class 1 Valves B
INSPECT ONE OF THE FOLLOWING FOUR (VT-3)
O #
B12.050.003A B12.050.003B IND-1B IND-2A B12.050.003C IND-36B
- B12.050.003D IND-37A INSPECT ONE OF THE FOLLOWING FOUR (VT-3)
B12.050.004A INI-54A B12.050.004B INI-65B B12.050.004C INI-76A B12.050.004D INI-88B
~~b. Function:~~
Valves IND1B, IND2A, IND36B, and 1ND37A are Residual Heat Removal Pump A and Pump B Suction Isolation Valves in the Residual Heat Removal System. These valves are closed during normal unit operation to provide isolation between the Reactor Coolant System and the Residual Heat Removal Pump Suction Line thus protecting the Residual Heat Removal System from over pressurization. Valves INI54A,1NI65B,1NI76A, and 1NI88B are Cold Leg Accumulator (A,B,C,D) Discharge Isolation Valves in the Safety Injection
( System. These valves are normally open with power removed to prevent inadvertent closure.
Serial No. 94-03 Page 2 of 3 ASME Section XI Code Class:
c.
4 Class 1
~~d. Construction Code and Class (If Applicable):~~
~~ASME Section III Class 1~~
~~e. Valve Category (If Applicable): j 1~~
B-M-2 l II. Refemnce Code Requimment that has been determined to be impracticah 1
l ASME Section XI Table IWB-2500-1, Examination Category B-M-2, Notes # 2 and
3 III. Basis for Requesting Reliefi Section XI 1980 Edition through Winter 1981 Addenda, Examination Category B-M-2 (B12.50), requires that a visual examination (VT-3) be performed on the O internal surfaces of one valve body in each group that are of the same constructional design and that perform similar functions in the system. It is permissible to defer this examination to the end of the interval.
Each group of valves was scheduled for examination during the first inspection interval so that the VT3 Examination could be performed in conjunction with a 1 scheduled maintenance activity where disassembly of a valve body in each group was required. The valves in the two groups from which relief from the VT3 Examination is requested have not been disassembled during the First Ten Year Inspection Interval for a scheduled maintenance activity. These valves, which are located in a high radiation area, are functioning properly and there is no operating history of any significant problems which would warrant concern.
There are no current plans to disassemble any of the valves in these two groups.
This request for reliefis based on the requirements of the 1989 Edition of Section XI, which is the code of record for the Second Ten Year Inspection Interval for Catawba Unit 1. The 1989 Edition of Section XI, Table IWB-2500-1, Examination Category B-M-2 Valve Body Exceeding NPS 4, Note 2, states that examinations are required only when a valve is disassembled for maintenance, repair, or -
volumetric examination. Duke Power Company feels that the words in the 1989 Edition clarify the examination requirements intended in the 1980 Edition of Section XI. During the Second Ten Year Inspection Interval, these examinations shall be scheduled to be performed the first time disassembly of a valve body in each of these two groups is required during a normal maintenance activity.
O
i Serial No. 94-03 ,
Page 3 of 3 Although the examination requirements of ASME Section XI could not be met for the l' First Ten Year Inspection Interval, this will not endanger the health and safetv of the
( general public. The past operating history and performance of these valves has revealed no significant problems. In addition, each valve receives a visual examination (VT-2) on the external surfaces during each refueling outage. This !
examination is performed during normal start-up and is used to verify valve integrity and to insure that there is no leakage.
IV. Alternate Eremination:
No alternate examinations are proposed to be performed on these valve bodies during the First Ten Year Inspection Interval.
V. Implementation Schedule:
These examinations will be scheduled to be performed during the Second Ten Year Inspection Interval the first time these valve bodies are disassembled for maintenance, repair, or volumetric examination.
O Evaluated By: -
Date: f f 20 1 o N4-Reviewed By: '
A Date: 12 20 4-I I :
I
,/ f Compliance Date: /JJ.10,J N O Review:
fw w
O DUKE POWER COMPANY STATION CATAWBA UNIT 1 10-YEAR INTERVAL REQUEST FOR RELIEF NO. 95-01 i
I. System / Component (s) for Which Relief is Requested: i
' ASME Section XI Code Class: 1 Examination Category: B-M-1 Valve - Residual Heat Removal System (ND) - Valve Body To Bonnet Weld ;
Weld Number Item Number IND-37A B12.040.002D ASME Section XI Code Class: 2 Examination Category: C-A Q Steam Generator - Lower Shell To Transition Cone Weld Weld Number Item Number 1SGC-04B-05 C01.010.002 !
ASME Section XI Code Class: 2 Examination Category: C-A :
Residual Heat Removal (ND) Heat Exchanger - Flange To Shell Weld Weld Number Item Number l 1RHRB-W3 C01.010.050 II. Code Requirement:
ASME Section XI, Examination Category B-M-1, Pressure Retaining Welds In Pump Casings And Valve l Bodies, Table IWB-2500-1, Item No. B12.40 requires a l O
C,, volumetric examination of essentially 100% of the weld length and adjacent base material on all Valve Body Welds greater than or equal to 4 inch nominal pipe size as defined by Figure No. IWB-2500-17. Examinations are limited to one valve within each group of valves that are of the same constructional design, manufacturing method, and that perform similar functions in the system.
ASME Section XI, Examination Category C-A, Pressure Retaining Welds In Pressure Vessels, Table IWC-2500-1, Item No. C1.10 requires a volumetric examination of essentially 100% of the weld length and adjacent base material on Pressure Vessel Shell Circumferential Welds at gross structural discontinuities as defined by Figure No. IWC-2500-1.
III. Code Requirement from which Relief is Requested:
Relief is requested for the above identified Class 1 Valve Body Weld from meeting the coverage requirements as defined in ASME Section XI, Appendix III, Article III-4000, III-4420.
Relief is requested for the above identified Class 2 Pressure Vessel Shell Circumferential Welds from meeting the coverage requirements of ASME Section XI, IWA-2232(a) as defined in ASME Section V, Article 4, T-441.4.4; T-441.5.
IV. Basis for Relief:
During the ultrasonic examination of the welds shown in Attachment 1, two directional coverage as required by ASME ;
Section XI, Appendix III and Section V, Article IV as modified ;
by Code Case N-460 could not be obtained. Causes of these ;
limitations are part geometry, physical barriers, and '
component / weld material. Where possible, a combination of angles and wave modes were used to maximize the coverage obtained. The weld and base metal at the component inside surface was covered from at least one direction with a minimum of one angle.
O
V. Alternate Evaminations or Testing:
'O. No additional examinations are planned for Weld ID Numbers, !
. IND-37A and ISGC-04B-05. In addition to the ultrasonic <
examination, radiography will be performed on Weld ID Number 1RIIRB-W3.
For Weld ID Numbers IND-37A and 1SGC-04B-05, the '
use of radiography as an alternate volumetric examination method is not practical due to component thicknesses and geometric configurations. Other ,
restrictions making radiography impractical are the necessity to use double wall techniques due to 1 inaccessibility of the ID surface and physical barriers prohibiting access for placement of source, film, number i bands, etc. We will continue to use the most current ,
ultrasonic techniques available to obtain maximum coverage for future examinations of these weld numbers. !
For Weld ID Number 1RIIRB-W3, radiography will be i' used as an alternate volumetric examination method Upon completion of a modification to the heat exchanger :
O- to allow access to the ID surface for source positioning !
and the qualification of an acceptable radiographic :
technique. This radiographic examination will be performed during Unit 1 EOC9, which is the first refueling ;
outage in the Second Ten Year Inspection Interval.
1 VI. Justification for the Granting of Relief:
Limitations are permanent obstructions and cannot be ;
removed for the components / welds listed in Section I '
above. Although the coverage requirements of ASME Section XI, as defined in Section V, Article 4 and Section XI, Appendix III could not be met, the amount of coverage obtained for these examinations provides an acceptable level of quality and integrity. Based on these evaluations, it is Duke Power Company's opinion that the limited coverage will not endanger the health and safety of the general public.
O i
Duke Power Company will perform UT examinations to the -
{ extent practical in accordance with ASME Section V, Article 4 and ASME Section XI, Appendix III.
VII. Implementation Schedule:
These examinations will continue to be scheduled in '
accordance with the requirements of ASME Section XI for future Inspection Intervals-at Catawba Nuclear Station, Unit 1.
Evaluated By: l> _
Date _6!9!N_6 i
[' /!
Reviewed By: Date 3 lO' M6 O O '
Attachment 1 Description Table !
Attachment 2 Component Drawings l Attachment 3 UT Examination Data ;
i l
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AS ass 1 And 2 Ir_ service Irrpection Request For Relitf No. L-wl 'V For Catawba Unit 1 Based On ASME Section XI- 1980 Code Through Winter 1981 Addenda Attachment 1 Page 1of 1 Ucensee item No. Exam Category System Or Area To Be Reason For Request Proposed A!!ernate
/Foure No. Component Examined Examination B12.040.002D B-M-1 Class 1 Valve Valve Body Umned scan due to geometre confguraton. None IWB-2500-1 Residual Heat To Actual coverage obtained - 84.1%
Removal System Bonnet (ND)
C01.010.002 C-A Steam Generator 1C SG1C Lower Umsted scan due to geometre confguraton. None IWC-2500-1 Shell To Adual coverage obtained - 52.1%
Transition Cone C01.010.050 C-A RHR Heat RHR HX 1B Umsted scan due to geometre confguraton. Radography IWC-2500-1 Exchanger 1B Flange To Adual coverage obtained =22.2%
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O O L O Exam Stad: //gg- Form NDE-UT-2A DUKE POWER COMPANY Exam Finish: ///9 Revision 4 ULTRASONIC EXAMINATION DATA SHEET FOR PLANAR REFLECTORS Date: c2.Jy 97 Unit: 1 ComponenUWeld ID: /hD-374 Station: C 47Rv b4 Surface Temperature: 6V 4 f Weld Length (in.): 6oo" Surface Condition: [cusn LO: //. 2.3 Pyrometer S/N:///EN4E J 7dzT Scans: T. hLevel: E Cal Due: '95 No/ Examiner: %~ . 45 dB 70 dB Configuration: C/EC Dech Level: Examiner: 45T dB70b dB S c- Flow S' Procedure: N M (, to Rev: I FC: g, 4
** Scan Surface: OD Calibration Sheet No: 60T dB Applies to NDE-680 only Cf 5 0 1 0 :L 7 O' 31 I dB Skew Angle: N//
Other: Beam Exam M MP W1 Mp1 W2 Mp2 Scan Damps L1 L2 Dir su . IND # f( i Max Mx Max g 20%dac 20%dac 20%dac 20%dac 20%dac 20%dac HMA HMA HMA HMA HMA HMA DO NOT WR IT E DO NO T W a lT E 50 M ac 50 M ac 50 M ac 50Mac 50Mac 50Mac IN "HIS SP 4CE IN THI S SF ACE 100% dac 100% dac 100% dac 100% dac 100% dac 100% dac p 0 /YO S:.0 L DA BLE l?Nb/C6/oN 5 n l Ly P p-(P
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Remarks: 4 sheet / of6 i 90% or greater coverage obtained; yes@ no O (A Limitations:(see NDE-UT-4) M Date item No: Y Level: Date: Author' ep Inspector Reviewed By: E IA. o ub.00.1p
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o x o <p Exam Stad: g)/ Form NDE-UT-2A DUKE POWER COMPANY Exam Finish: /,2/f Revision 4 ULTRASONIC EXAMINATION DATA SHEET FOR PLANAR REFLECTORS Unit: / Component / Weld ID: 1 AlD-3 7A Date: ) _? A ff Station: f /1T Ab/ba Surface Temperature: /e (/ ' ,[ Surface Condition: kud LO: //.L3 Weld Length (in.): (oa 0" Pyrometer S/N: AldNlt: 2 7a25-Scans: Examiner: 71Laj,,_, E t/m Level: I 45 37 og 70 dB Cal Due: 93'//O/ Configuration: Circ.tue14 Level: 3' Examiner: 45T 'S3 dB70TO eB 3* Flow ggg Rev: FC: 3"* " to bL" l Procedure: gpg qso po r7 q @ 2- 60 lb 3 4 dB Scan Surface: OD Calibration Sheet No: 933 jo fg NDE-680 only 60T O de APPiles 950/0/7 ego e o z.o Skew Angle: Other VST - 7MS 4tX -7 9 dB 9 y fcAr am Exam W1 Mp1 W2 Mp2 Scan Damps L1 L2 IND #. Max , 20%dac 20%dac 20%dac 20%dac 20%dac 20%dac HMA HMA HMA HMA HMA HMA DO NOT WR IT E DO NC T W R IT E 50Mac 50*/odac 50Mac 50Mac 50Mac 50Mac IN HIS SP 4CE IN THI S 15 F ACE 100% dac 100% dac 100% dac 100% dac 100% dac 100% dac WN/A f WClk 12 hClAfD A6ff ~ IVD/CA n\Al 3 y he nne ce 1mbica uom roa oxn c l R Ho (f5 *L Kmc d (_o M Ary L tb I $5 n h catoA tur ?N bicA T/oM3 % n2 h y ,D
.o gp{ Remarks: Sheet A of G (A , -4 90% or greater coverage obtained: yesMP no @
y Limitations:(see NDE-UT-4) @ Date item No: 3 Level: Date: Autlyvized, Inspector, Reviewed By
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O _ O O FORM NDE- UT-4 DUKE POWER COMPANY Revision 1 ISI LIMITATION REPORT remarks: Component / Weld ID:_lBb 37A Item No:_3 la . o n cotD SURFACE BEAM DIRECTION Dum +o 1/4 Lee h4 '
@ NO SCAN em A ;" om <re-O LIMITED SCAN O2 @1 @ O cw 0 ccw to L INCHES FROM WO l.8 to_3o FROM L o DEG to _d(ao_DEG ANGLE: 00 045 960 other 45"L 460 t FROM Due b va L og B o uuaw BEAM DIRECTION SURFACf;Y @ NO SCAN f1 f "" p' I " ""
O LIMITED SCAN O1 72 1 @z Ocw 0 ccw tc'L INCHES FROM WO 1. / Y to - Beyoud_ FROM L ANGLE: 00 945 @60 other 45*t, d-604 ROM o DEG to SGo DEG SURFACE BEAM DIRECTION O NO SCAN O LIMITED SCAN Oi Oz Di Oz Ocw 0 ccw INCHES FROM WO to FROM L to L FROM DEG to DEG ANGLE: 00 04s 060 other BEAM DIRECTION 3 SURFACE g O NO SCAN 2 0 LIMITED SCAN 010 z 01 Oz Ocw 0 ccw FROM L to L INCHES FROM WO t Sketch (s) attached fj FROM DEG to DEG @yes Ono g h$ ANGLE: 00 045 060 other g Lev Sheet 3 ok g 'b1 Pr:: pared By: a .qy- - Date: D e: Authorized inspector: R:vi;wed By:
RF R ses..No.9s-o t l Limited Exam Data Sheet Station J47Alb8A Unit / 1.D. # l A/ 0 E /) By kJh YtynAl1B Date 3'll'95 Item # bld, OM @00 Checked By /66y Date 3'2# f T Page Of DETERMINING THE CUMULATIVE TOTAL OF WELD VOLUME INSPECTED (in percentage) Total Cross Sectional Area _M x (Number of Scans) V 30.M (% Factor) Vessels: i Area Loss : Zone #1 1 Zone #2 : Zone #3 Total Zone Loss /(% Factor) x 100 - % of Loss Lump Sum Loss From Other Limitations + % Total Loss % 100% - (Total Loss) - % of Coverage ( Additional % of Partial Coverage) Qpalifies for Request for Relief O Yes O No e Piping: V4Lvr gg wgc Axial Scan W 5 / PL !/e#S ML (less)/0,36 /A JV (% Factor) x 100-lYU % of-Ioss-
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Ci - Y- /2- 90 Los Additional Losses.(Due to hangers, restraints, etc.) * % Loss Explain: Otte Ostue cw 'Mt AW/ Total % Ioss
+ cc u/ 7. rt ^ /S~./.2 4 30..?4' y 100 = 2)K 100% -(TotaiM 85/ /5 9 % of Co/Sgek Qpalifies for Request for Relief (D Yes O No 1 1
Disposition: , e By: Date: ATTAC.% met 47 9 AG,E 4 0 F St
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DUKE POWER COMPANY Revision 2 Exam Finish: /2 .Zf ULTRASONIC EXAMINATION DATA SHEET FG*' LAMINAR REFLECTORS l Component/weid lD:
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l3 $ (, O4g ,gg Date: .2 -/5-95 Station: (47gygg Unit: l Surface Tepmperature: M .Deg F 1 J. O 4, Weld Length (in.): y J r, - Nominal Material Thickness (in.): 2 7 o .2 O Pyrometer S/N: /4 c.NOE Measured Material Thickness (in.): y,Og Lo: W g f3 Calibration sheet No: cat due: //-/-91~ Surface Condition: g3 jy Ag.)g ConHguration: C /# C. dEM Examiner: g Level: g gg g jgg A.
/ Flow l Examiner: ppp;v , td & w Level:2 TRANSITxp Cops to loutz 5//rzt Procedure no:ygg ta go Rev: l F/C: Si g g.
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O O O Exam Stan: / gov Form NDE-UT-2A DUKE POWER COMPANY Exam Finish: /c/V.5 Revision 4 ULTRASONIC EXAMINATION DATA SHEET FOR PLANAR REFLECTORS Station:[Ifh,, J /x' Unit: / Component / Weld ID: /5(k'. -cy6 -0I Date:J/i'Y Surface Temperature: O</ *d Q' 2 (, Surface Condition: h, ///ry,,gf7 LO: fs Weld Length (in.): Pyrometer S/N://l'<t DE MB u o dd&/p/ % Scans: Examiner: Oc //, , g Level: 4 45 og 70 @ 70 dB Cal Due: 0> a o/
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~~Exam. iner:gj 2A.v. tr) g L,q _ Level:7 45T b W A dB70b dB / Flow A~~
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o o - o FORM NDE- UT-4 DUKE POWER COMPANY Revision 1 ISI LIMITATION REPORT C.o I . DI O.Co 2. remarks: Ccmponent/ Weld ID: 1SCxC -C)t4B -05 Item No: SURFACE BEAM DIRECTION e premew gw I NO SCAN d Oz MwMcw se e 0 LIMITED SCAN 016z
" b BC. hoc to Le 447 N t INCHES FROM WO FROM Le 4O FROM D DEG to 3G8 DEG ANGLE: N O @ 5 Y 60 other 13 b lO SURFACE BEAM DIRECTION O NO SCAN O LIMITED SCAN 010 z 01 Oz Ocw 0 ccw to L INCHES FROM WO S -tEFEZl'"l" FROM L FROM DEG to -DEG ANGLE: 00 045 Oso other SURFACE BEAM DIRECTION O NO SCAN O LIMITED SCAN O10 z 01 Oz Ocw 0 ccw INCHES FROM WO to FROM L to L FROM DEG to DEG ANGLE: 00 045 060 other A SURFACE BEAM DIRECTION
, O NO SCAN 01 Oz Ocw 0 ccw a O LIMITED SCAN 010 z INCHES FROM WO to Sketch (s) attached FROM L to L ANGLE: 00 045,Oh other FROM DEG to DEG bes O no h Pr:; pared By: Level: Date: Sheet - 3 of /7 4 .l o Date: r . Date: Authorized inspector:)b'l ,lll,'s(f{,4 $ }' Y)5 />
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AFR. 6ER. Alo. 95-os Limited Exam Data Sheet ATAl> jib A Unit $ I.D. # l M C.- 046- 0 5 4 ltation BY Date Item # 001.0) 0.0 o 2. Checked By Date Page TOf / 7 DETERMINING THE CUMULATIVE TOTAL OF WELD VOLUME INSPECTED (in percentage) Total Cross Sectional Area x (Number of Scans) = (% Factor) Vessels: Area Loss : Zone #1 . Zone #2 Zone #3 Total Zone Loss __.____ /(% Factor) x 100 s % of Loss
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Lump Sum Loss From Other Limitations Total Loss % 100% - (Total Loss) _- % of Coverage ( Additional _% of Partial Coverage) Qualifies for Request for Relief O Yes O No Pining: Axial Scan (Loss) / (% Factor) x 100- % of Ioss Circumferential Scan Over Root Area O Yes O No % of Loss Axial Loss + Circ. Loss = /2= % Loss
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. Technical Document 90-1 O Main Steam Header Alternative U Examination Qualification March 1,1990
~~1.0 PURPOSE~~
This paper pertains to the qualification of an alternative ultrasonic technique that will be employed at both McGuire and Catawba Nuclear Power Stations. The component is the main steam system. The weld joint of import is the main steam header (1) to transition piece (2) weld (see figure # 1). In accordance with Section XI of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME), an alternate examination technique may be substituted for techniques specified in the Code, provided that the Authorized Nuclear Inservice Inspector is satisfied that the results are demonstrated to be equivalent or superior to those of the specified method (see paragraphs lll-1100 (d) and IWA-2240 for more detail). O 2.c sacxonOuso l Inservice examinations are conducted in accordance with the 1980 edition of ASME Section XI, including all addenda through Winter 1980 at the McGuire Nuclear Station. At the Catawba Nuclear Station, all inservice e :aminations are conducted in accordance with the the 1980 edition of ASME Section XI, including all addenda through Winter 1981. Appendix 111, in both editions of above mentioned Codes, stipulates that an ultrasonic examination calibration block, for Class 1 and 2 ferritic piping, be of the same nominal diameter as the piping component to be examined. Due to the unique design of the transition piece, locating representative material to i produce a calibration standard of the same dimensions has not been possible to date. The transition piece tapers from a 10" outside dimension (O.D.),on the main steam header side, to 9.0" O.D. on the valve side. Ninety-six welds are of this configuration (forty-eight at each unit). The header side weld's O.D. varies from 11.5" to 12.0". O Page 1 of 13
. Technical Document 90-1 Main Steam Header Alternative (v~] Examination Qualification March 1,1990
~~3.0 SUPPOSITION~~
The valve side of the transition piece calibration is established with a 9.0" O.D. calibration block. The supposition is that this calibration block will provide a examination sensitivity equivalent or superior to one that would be obtained from a calibration block designed to the specifications of the Code. This supposition is based on the following: l 3.1 Due to the geometric configuration of the header to transition piece weld joint, the examination shall only be performed from the transition side of the weld. 3.2 The thickness of the 9.0" O.D. calibration block and the header side of the transition piece are the same. Therefore, the calibration block reflector O size end eentn iocetion requirements wouid be ine same for a 12.0 O.D. calibration block as are in the 9.0" O.D. block. 3.3 The surface area of the 9.0" O.D. block would tend to reflect more of the sound transmitted from a given transducer than the surface area of a 12.0" O.D. block. This would allow less sound to reach the reflective surface of the calibration bock reflectors. This means that more gain would be required to obtain the same amplitude from the calibration reflectors in the 9.0" O.D. calibration block than 12.0" block. Therefore a calibration from the 9.0" O.D. block should provide a more sensitive examination. 4.0 QUALIFICATION PROCESS i l The 9.0" O.D. calibration blocks from both the McGuire Nuclear Station (50249) and Catawba Nuclear Station (50356) were compared to a 12" O.D. calibration block l (50252). All the calibration blocks are of the same thickness and contain the same l O Page 2 of 13 i I
Technical Document 90-1 Q Main Steam Header Alternative Examination Qualification March 1,1990 QUAllFICATION PROCESS (CONT.) size calibration reflectors. The only difference is block 50252 does not have a notch reflector. The same instrumentation (UT instrument,' transducer, and cable) were utilized throughout the qualification process. Without changing the UT instrument settings, calibrations were constructed in accordance with the Babcock and Wilcox piping examination procedure ISI-120, revision 25. Each calibration was documented and any deviations were noted (see Calibration Sheets 90-1 A through 90-1F ). The comparisons were accomplished using a certified 2.25.MHz, .50" diameter, transducer (32908) coupled to a 6' microdot cable. The ultrasonic instrument was a Tokyo Keiki, model SM-100. No thermometer was used. The comparisons were performed in a environmentally controlled location. Each of the calibration blocks was in this environment 24 hours prior to the start of the comparisons and remained there throughout the process.
~~5.0 RESULTS~~
The initial distance amplitude correction (DAC) curve was performed on the 9.0" O.D. calibration block 50356 using the side drilled holes. The I.D. notch was compared to this DAC curve. The notch is use to determine the calibration curve's sensitivity to I.D. surface initiated degradation. The DAC curve was 10 Decibels (dB) more sensitive than the notch at reference level. This means that the DAC curve's sensitivity is more than 3 times greater than the calibration sensitivity obtained from the notch. Without changing the sensitivity of the instrument, a calibration was established from the side drilled holes in the 12" O.D. block, 50252. The amplitude obtained from these reflectors was less than 2 dB greater than the reference level of block 50356 (The SM-100 adds and subtracts gain sensitivity in 2 dB increments). Block 50252 does not have a notch, so no notch comparison was made. O Page 3 of 13 I
Technical Document 90-1 CN Main Steam Header Alternative V Examination Qualification March 1,1990 5.0 RESULTS (CONT.h A calibration was then generated from the other 9.0".O.D. block, 50249. The DAC curve obtained was identical to the one obtained from the 12" O.D. block,50252. It was not possible to measure the difference in sensitivity between these two calibration curves with the instrument control settings. A graph of all 3 DAC curves depicts these results in Figure No. 2. The 1.D. notch was then compared to this DAC curve. The DAC curve was again 10 dB more sensitive than the notch at reference level. DAC curves were generated on each calibration block in the axial and circumferential direction. In each case the calibration obtained from the DAC curvu ceae at least 10 dB greater in sensitivity than the sensitivity obtained from the notch. O e.0 conctusion : The 9.0" O.D. calibration block can be used for the examination of both welds attached to the the transition piece on main steam at both the Catawba and McGuire Nuclear Stations. The difference in examination sensitivity using any of the three blocks was < 2 dB. A 2 dB change is recognized by Code and throughout the industry to be an insignificant change in a calibration sensitivity. In any case, calibration blocks 50356 and 50249 provided an examination sensitivity equal to or greater than that obtained j from the 12" O.D. calibration block,50252. Using a calibration blow that has no notch reflector for this comparison did not hinder the results. A DAC calibration obtained from side drill holes normally results in a more sensitive calibration than one obtained from a notch. In all cases where a notch was available the DAC calibration sensitivity was 10 dB more sensitive than that obtained from the notch reflectors. O Page 4 of 13
. .= . . .-- . . Technical Document 90-1 P Main Steam Header Alternative -
~~Examination Qualification March 1,1990 -~~
~~6.0 CONCLUSION~~
(CONT.): This comparison was performed with a .50 diameter 2.25 MHz transducer. Since no other transducers were demonstrated, this alternative examination technique shall - only be performed with the transducer frequency and size demonstrated. This comparison shall not be used as a justification for any other alternative ! examination technique other than the main steam header to transition piece valve ; weld. O O . Page 5 of 13
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TECHNICAL DOCh 90-1 CAllBRATiON BLOCK CURVE COMPARISON 100------------------------------------------------------------------------------------------~. l . . 90 - - - - - - - - - - - - - ----------~~.---- ------------------------ t---------------------~-------. . . 8 0 -x ---^^-----
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.x- 5035 6 A 40 ---------------------------------------~~~~~~-------~~~-----c---'-------------*--- --- --*
C . 30 -------------------------------:------------------------------t----------------~~------~~-- g . . 20 -- - - - - - - - - - - - - - - - - - - - - - - - - - - - - ~ . - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ~ . - - - - - - - - - - - - - ~ ~ - - - - - - - - - - - - - - . ' 10 -- - - - - - - - - - - - - - - - - - - - - - - - - - - - - ..--------------------~~-------
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I I i 0 i i i 0.4 0.8 1.2 2 m THROUGH WALL (IN.) o 00 G W FIGURE # 2 i O ets M
~~- - _ . _ - .- _ - . . . _ _ ,,, ,. ._ _ . _ _ _ _ _ . . O~~
10.0 Cla== 1 and 2 hnairs and holacements (]~ As required by ASME Section XI 1980 Edition, a record of the Class 1 and 2 Repairs and Replacements for work performed from December 27, 1993 through March 21, 1995 is included in this section of the report. The individual work request documents are on file at Catawba Nuclear Station. O ! i l O Page1of1 Refueling Outage Report EOC 8 Catawba Unit 1 Revision 0 Section 10 June 1,1995
O i CATAWBA NUCLEAR STATION UNIT 1 EOC 8 REPAIR / REPLACEMENT LOG ASME SECTION XI-1981 . EXAMINATION DATES: FROM 12/28/93 TO 03/21/95 PREPARED BY: QA TECHNICAL SUPPORT l O 1 1 TRANSMllito BY: DATp 5- 2+ 9 r l O
~~$ WR#~~
91017337-01 Class A Description Replaced Stem and Plug Valve 1NC34A 91068940-01 B Replaced items 6 & 7 Hanger 1-R-KC-013 & E 1 -R-KC-812 92007136-02 B Replaced Valve 1CF-149 92054351-01 B Replaced Load Pin 1-R-SM-1018 93051476-01 B Replaced Bonnet Cap Screws Valve 1CF-058 93085877-01 A Disassemble / Reassembled 1NC-32B 94056339-01 A Replaced 2 Snubbers Hanger 1-R-NC-1655 94061869-05 A Added item #11 Hanger 1-R-NC-1583 94061869-06 A Replaced Valves 1NC004 & 1NC005 (Tie-Ins) 94061869-13 A Replaced Valves 1NC004 & 1NC005 (Pre-Fab) 94061869-15 A Replaced Valves 1NC004 & 1NC005 No Hydro (NIS-2) 94061870 A Replaced Valves 1NC094 & 1NC095 (Pre-Fab) 94061870-08 A Replaced Valves 1NC094 & 1NC095 (Tie-ins) 94061870-20 A Replaced Valves 1NC094 & 1NC095 No Hydro (NIS-2) 94061872-05 A Replaced Valves 1NC013 & 1NC016 (Tie-Ins) 94061872-13 A Replaced Valves 1NC013 & 1NC016 (Pre-Fab) 94061872-15 A Replaced Valves 1NC013 & 1NC016 9 94061873-06 No Hydro (NIS-2) A Replaced Valves 1NC019 & 1NC020 (Tie-Ins) 94061873-10 A Replaced Valves 1NC019 & 1NC020 (Pre-Fab) 94061873-16 A Replaced Valves 1NC019 & 1NC020 No Hydro (NIS-2) 94063678 01 B Replaced Socket Welds With Butt welds NV Pipe 94069858-01 B Replaced Valve & Flange Bolting Valve 1NV014 94082278-01 B Replaced Valve 1CA041 94082279 01 B Replaced Valve 1CA045 94082281-01 B Replaced Valve 1CA057 i 94082282-01 B Replaced Valve 1CA061 94093841-06 B Replaced Bonnet Capscrews Valve 1CA049 95001306-03 A Disassemble / Reassemble Mech. Joint RX Head 95001361-03 A Replaced Valve 1NC001 & Flange Studs / Nuts 95001362-04 A Replaced Valve 1NC002 & Flange Studs / Nuts 95001368-02 A Disassembled Valve 1N1094 95001369-02 A Disassembled Valve 1N1093 95001370-02 A Remove / Replace RX Head 95001372-02 A Disassemble / Reassemble Reactor Head 95001378-02 A Replaced Seal Housing 1NC PU B O
l O wa> 95001413-02 c' A
~~- o cr'aiiaa Disassembled Valve 1N1134 95001414-02 A Disassembled Valve 1N1175 !~~
95001439-02 B Replaced Nuts 1 A HX Manway ' 95001994-02 B Replaced Disc Valve 1SV009 95005010-04 A Replaced Valve 1NC003 & Flange Studs / Nuts 95005017-14 A Broke Mech. Joint 1NC HX B 95005018-10 A Disassemble / Reassemble Mech. Joint 1NC HX A 95005928-04 B Replaced Disc Valve 1CA065 l 95008195-12 A Remove / Replace SG Primary Manway Covers l 95008196-12 A Disassemble / Reassemble Mech. Joint 1NC HX D 95009950-09 B Replaced Bolting Matl. SG1D
)
95011402-01 B Replaced Valve 1NW-69B ( CE4953 ) l 95012944-02 B Replaced Disc Valve 1SV015 95013123-02 A Disassembled Valve 1NC298 95015285-02 B Replaced Valve 1NV835 95015409-02 B Replaced Disc Valve 1SV011 95016681-01 B Replaced Snubbers Hangers 1-R-CF-1539 and1-R-CF-1544 95019945-01 B Replaced Bolting SG1B O O
~~.}}~~

ML20085F228

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Description:

SUBJECT:

1.0 PURPOSE

3.0 SUPPOSITION

5.0 RESULTS

6.0 CONCLUSION

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