ML20247H414
| ML20247H414 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 04/22/1998 |
| From: | DUKE POWER CO. |
| To: | |
| Shared Package | |
| ML20247H384 | List: |
| References | |
| NUDOCS 9805210157 | |
| Download: ML20247H414 (38) | |
Text
_. . _ . _-____ _____- _______-_ ____-___ -_--__ _ - - - -
O INSERVICEINSPECTION REPORT UNIT 2 CATAWBA 1997 REFUELING OUTAGE 8 Location: 4800 Concord Road, York, South Carolina 29745 NRC Docket No. 50-414 National Board No.173 Commercial Service Date: August 19,1986 Owner: Duke Energy Corporation O- 526 South Church St.
Charlotte, N. C. 28201-1006 Revision 1 Prepared By: @/ .
Date M [8 Ty (/ y ' '
Reviewed By: 4/ MM Date [8/ 'fo Approved By: Date O
Copy No. 2 Assigned To NRC Document Control Controlled X Uncontrolled A K 0414 G PDR.
O TABLE OF CONTENTS Section Title Revision
- 1. General Information 0
- 2. Summary of Inservice inspections 1
- 3. Second Ten Year interval Inspection Status 1
- 4. Finalinservice Inspection Plan 0
- 5. Results of Inspections Performed 0
- 6. Reportable Indications 0
- 7. Personnel, Equipment, and Material Certifications 0 l
- 8. Corrective Action 0
- 9. Reference Documents 1
- 10. Class 1 and 2 Repairs and Replacements 0 1
- 11. Pressure Testing 0 l
O 1
L-_- - - - - _ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
2.0 Summary ofinservice inspections O The information shown below provides an abstract of ASME Section XI Class 1, C! ass 2, and Augmented items scheduled and examined during Outage 8 at Catawba Nuclear Station, Unit 2.
l 2.1 Class 1 Inspection Examination Category B-A Pressure Retaining Welds in Reactor Vessel item TotalExamined Number During Outage Description s . & c:
B01.010 Shell Welds & rE ' 'r I.
B01.011 Circumferential 0 B01.012 Longitudinal 0 B01.020 Head Welds B01.021 Circumferential 1 B01.022 Meridional 4 B01.030 Shell to Flange Welds O B01.040 Head to Flange Welds 1 B01.050 Repair Welds '
1R ~ 'G B01.051 Beltline Region NA TOTALS 6 O
Refueling Outage Report EOC 8 Page 1 of 20 Catawba Unit 2 Revision 1 Section 2 April 15,1998
- _ _ _ . =___ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
Examination Category B-B Pressure Retaining Welds in Vessels Other than Reactor Vessels item TotalExamined Number y,,,,,,,,,, During Oukge l f A r n {w$bk Pressurizer $$$":%ff$Q Jk WW 802.010 Shellto Head Welds ' w < n'5.i! . :
B02.011 Circumferential 0 B02.012 Longitudinal 0 w . J4 B02.020 Head Welds ~YDds;g$UMND)i B02.021 Circumferential NA B02.022 Meridional NA 9 Rwgngpg;:n q@wf ;p g99gh a Wa.1XM Steam Generators (Primary Side)
?)&QNf T~ iww B02.030 Head Welds O B02.031 Circumferential t] NA B02.032 Meridional NA B02.040 Tubesheet to Head Weld 0
$$f!@ % 4 %
%@?pwgqgy wmbH Heat Exchangers V:M gwiN C #'
al @SiM (Primary Side)- Head 'M SM&'
B02.050 _, Head Welds 24sMsg n% i' A .xk QMI v.]
B02.051 Circumferential NA B02.052 Meridional NA QMita "W& Heat Exchangers
% 5Mi' %
$5W (Primary Side)- Shell $E"M
- ? 'Ni$ $$ }
B02.060 Tubesheet to Head Welds NA B02.070 Longitudinal Welds NA B02.080 Tubesheet to Shell Welds NA TOTALS 0 Refueling Outage Report EOC 8 Page 2 of 20 Catawba D' nit 2 Revision 1 Section 2 April 15,1998
Examination Category B-D Full Penetration Welds of Nozzles in Vessels inspection Program B ltem TotalExamined Number During Outage Reactor Vessel B03.090 Nozzle-to-Vessel Welds O B03.100 Nozzle Inside Radius Section 0
,grre xcmgbSN$
$ Pressurizer ibwYw NINIb : m u m$ by B03.110 Nozzle-to-Vessel Welds O B03.120 Nozzle inside Radius Section 0
,g -' an wtw chm;,w h&;
a'$
9td T Steam Generators (Primary Side) $*$k~h);f@h R * '
B03.130 Nozzle-to-Vessel Welds NA B03.140 Nozzle inside Radius Section 0 I Wi
%j+ {@!i Heat Exchangers $f;R73%jiMiMM
) 1 g g ig
.. WW (Primary Side) M Ly a % * * + MQppfJi B03.150 Nozzle-to-Vessel Welds NA B03.160 Nozzle inside Radius Section NA TOTALS O Examination Category B-E Pressure Retaining Partial Penetration Welds in Vessels REFERENCE SECTION 11.0 OF THIS REPORT i
i 1
l
' i i
i Refueling Outage Report EOC 8 Page 3 of 20 l Catawba Unit 2 Revision 1 j Section 2 April 15,1998 l l
1
Examination Category B-F Pressure Retaining Dissimilar Metal Welds V Item TotalExamined Number During Outage y,,,,,,,,,,
A&w 6 y ;
Qll$$$$k!Ib$$li' Reactor Vessel @h%yy%g$k e 805.010 Nominal Pipe Size 4"or Larger 4 Nozzle-to-Safe End Butt Welds B05.020 Nominal Pipe Size Less Than 4" NA Nozzle-to-Safe End Butt Welds 805.030 Nozzle-to-Safe End Socket Welds NA wmY wn e W1 Mp ;,t:n
- a. cz. un . +v Pressurizer
-3" rw+
m @c~
W;.Nn: ex
. at.Ow B05.040 Nominal Pipe Size 4" or Larger 0 Nozzle-to-Safe End Butt Welds B05.050 Nominal Pipe Size Less Than 4" NA Nozzle-to-Safe End Butt Welds B05.060 Nozzle-to-Safe End Socket Welds NA Qf$$$$a~57MuMu Steam Generator $l5 n*. KGCM4 HEW 5 g
() 805.070 Nominal Pipe Size 4" or Larger Nozzle-to-Safe End Butt Welds 0
B05.080 Nominal Pipe Size Less Than 4" NA Nozzle-to-Safe End Butt Welds 805.090 Nozzle-to-Safe End Socket Welds NA
- n. + 4l % -
s #
ang2y:GP. Heat Exchangers n%%nA B05.100 Nominal Pipe Size 4" or Larger NA Nozzle-to-Safe End Butt Welds B05.110 Nominal Pipe Size Less Than 4" NA Nozzle-to Safe End Butt Welds B05.120 Nozzle-to-Safe End Socket Welds NA i
Refueling Outage Report EOC 8 Page 4 of 20 Catawba Unit 2 Revision 1 Section 2 April 15,1998 L__________._____-______-------------.--
l Examination Category B-F (Continued) l otalExamined Number During Outage Description
-}y?f B05.130 Nominal Pipe Size 4" or Larger 4 Dissimilar Metal Butt Welds B05.140 Nominal Pipe Size Less Than 4" NA Dissimilar Metal Butt Welds l l B05.150 Dissimilar Metal Socket Welds NA TOTALS 8 l
O l
l l
l 1
O !
Refueling Outage Report EOC 8 Page 5 of 20 Catawba Unit 2 Revision 1 Section 2 April 15,1998
Examination Category B-G-1 Pressure Retaining Bolting, Greater Than 2"in Diameter item TotalExamined Number During Outage 9,,,,,,,,,,
dN'hh4Mn n n% Mypr$@$(IQ Reactor Vessel en -s <
B06.010 Closure Head Nuts 18 B06.020 Closure Studs (in place) O B06.030 Closure Studs (when removed) 18 B06.040 Threads in Flange 18 B06.050 Closure Washers, Bushinos 18 r, m . , r nn
+gtjg ~y , ~,
,; - j v. M B06.060 Bolts and Studs NA l
B06.070 Flange Surface (when connection NA disassembled)
B06.080 Nuts. Bushings and Washers NA
,. ew s,w y m. <~
?n;;tlq;OV Steam Generators ?*^ t Y B06.090 Bolts and Studs NA B06.100 Flange Surface (when connection NA disassembled) l 806.110 Nuts, Bushings and Washers NA hybhbfg;Q y,,, g,,y,,,,,, + , z B06.120 Bolts and Studs NA B06.130 Flange Surface (when connection NA disassembled) B06.140 Nuts, Bushings and Washers NA z w w y.uIn - WYES vae.xn-:e $$ic$1 Piping NIYW N* B06.150 Bolts and Studs NA B06.160 Flange Surface (when connection NA disassembled) B06.170 Nuts, Bushings and Washers NA l Refueling Outage Report EOC 8 Page 6 of 20 Catawba Unit 2 Revision 1 Section 2 April 15,1998
Examination Category B-G-1 (Continued) Item TotalExamined Number During Outage Description h ;;; :"' *;*~, - pump, f{l hl , ' *, . 806.180 Bolts and Studs O B06.190 Flange Surface (when connection 0 disassembled) B06.200. Nuts , Bushings and Washers NA 3 10;:jb' $2?%Tf a . N dt";'?
. dx n Valves *dG di'Ny' .
806.210 Bolts and Studs NA B06.220 Flange Surface (when connection NA disassembled) 806.230 Nuts. Bushings and Washers NA TOTALS 72 O Refueling Outage Report EOC 8 Page 7 of 20 Catawba Unit 2 Revision 1 Section 2 April 15,1998
1 Examination Category B-G-2 Pressure Retaining Bolting,2"
,J i
and Less in Diameter ltem TotalExamined Number During Outage Description r , 9, m ,# , < -+p; y
..:g.:W5G
. n +s i.. .
Reactor Vessel r.hatsa&ge@. v@.;
> e.m u ~:. w i
B07.010 Bolts, Studs and Nuts NA ) MMM$AB" , "l;u%"fss;MM WMa.M:n ' Pressurizer n : a n'~, \ i B07.020 Bolts, Studs and Nuts O nxoun :$.2 . , m;uw.99 p lqpH%y?'1;
- Steam Generators S W W 'S Y B07.030 Bolts, Studs and Nuts 0 w a,,, s s.
$$$r.m m 7., ,$$f%?%$$ Heat Exchangers W N5N' n' Y j B07.040 Bolts, Studs and Nuts NA
- - r nwygp a , - , n
- .e IdDMyli
~~ v f?.M/*
ahn Piping WFiMyli%Di < s m.t.. m B07.050 Bolts, Studs and Nuts O
, ngw w . i ClIkp.vgA:%{+didI5NIND v J Pumps @5NSdtENIN l B07.060 Bolts, Studs and Nuts 0 O 'S, ' ; G:n ,
&, w'l% .% ::u m
% $..%.b Valves ~ '**
B07.070 Bolts, Studs and Nuts O e5 Rog g.9 .g ; . , l
% , a L CRD Housing M ~>
B07.080 Bolts, Studs and Nuts in CRD Housing 0 (when disassembled) TOTALS 0 l l l I l b o Refueling Outage Report EOC 8 Page 8 of 20 Catawba Unit 2 Revision 1 Section 2 April 15,1998
1 Examination Category B-H Integral Attachments for Vessels item TotalExamined Number During Outage 9,,,,,,,,,, as .-m - g
% x,% , jf .
QQM& ";
- Reactor Vessel #$ A '
B08.010 Integrally Welded Attachments 0 Okhby 5$
.%qijM:h S g .. ;m Pressurizer @Mk@4W0[YN
%: 3r %
B08.020 Integrally Welded Attachments 0 W Q $ jjj;f'"t i. M'b& & &7 WSteam W- Generators ' NHM+AGO' Muh
- W I B08.030 Integrally Welded Attachments NA we.mwgen . : .y 1, 9@Mg Heat Exchangers ?W ' ?l, B08.040 Integrally Welded Attachments NA TOTALS 0 I
Examination Category B-J Pressure Retaining Welds in Piping item TotalExamined Number During Outage Description s.,:y . y;Q B09.010 Nominal Pipe Size 4" or Larger +
~' -
- B09.011 Circumferential Welds 11 809.012 Longitudinal Welds' O 4,
B09.020 Nominal Pipe Size Less than 4" cI0" "~ B09.021 Circumferential Welds O B09.022 Longitudinal Welds NA l 8 Longitudinal Welds that intersect circumferential welds are examined as required by ASME Section XI, Table IWB-2500-1, Category BJ. However, for reporting purposes, the totals as shown in Section i 3.0 of this report do not include the number oflongitudinal welds examined during this outage. V Refueling Outage Report EOC 8 Page 9 of 20 Catawba Unit 2 Revision 1 Section 2 April 15,1998
Examination Category B-J (Continued) C\ Q ltem Number TotalExamined During Outage Description a ; < n u;w... ; u.e
~4d#. -
~
B09.030 Branch Pipe Connection Welds *'/' $" "Ts ' o ud ; ?'P.' . B09.031 Nominal Pipe Size 4" or Larger 0 B09.032 Less than Nominal Pipe Size 4" 3 B09.040 Socket Welds 11 TOTALS 25 Examination Category B-K-1 Integral Attachments for Piping, Pumps and Valves item TotalExamined Number 'I"* *** Description
< ,p e s p.u~sy-rn G7,5bNi%D?5.
ir p 2^ Piping A'IWUE C*M i ' B10.010 Integrally Welded Attachments NA g=i; . .. hhith(y' M >
^' ^
Pumps
- N' hr * <
- 2
_=l B10.020 Integrally Welded Attachments NA eig ,,e. .s
- -- Valves - ' c-- a !
B10.030 Integrally Welded Attachments NA TOTALS NA l O , Refueling Outage Report EOC 8 Page 10 of 20 Catawba Unit 2 Revision 1 Section 2 April 15,1998
Examination Category B-L-1, B-M-1 Pressure Retaining Welds in Pump Casings and Valve Bodies B-L-2, B-M-2 Pump Casings and Valve Bodies item TotalExamined Number During Outage b Y Pumps lY B12.010 Pump Casing Welds (B-L-1) NA B12.020 Pump Casing (B-L-2) 0 3 (when disassembled for Maintenance I Repair or Volumetric Examination) Yhkkk$fh yapyes h;k b? B12.030 Valves, Nominal Pipe Size Less than NA 4' Valve Body Welds (B-M-1) 812.040 Valves, Nominal Pipe Size 4" or 0 Larger Valve Body Welds (B-M-1) B12.050 Valve Body, Exceeding 4" Nominal 2 x Pipe Size (B-M-2) TOTALS 2 i I l l \ Refueling Outage Report EOC 8 Page 11 of 20 Catawba Unit 2 Revision 1 Section 2 April 15,1998
i Examination Category B-N-1 Interior of Reactor Vessel
\ B-N-2 Integrally Welded Core Support Structures and Interior Attachments to Reactor Vessels I B-N-3 Removable Core Support Structures item Number TotalExamined Description "A ***
w .s,ap
%%y .",~;w m W' yy Reactor Vessel ?~WW, -
B13.010 Vessel Interior (B-N-1) 1 l
$hh ?!W Reactor Vessel (PWR) k$
B13.050 Interior Attachments Within the NA Bettline Region (B-N-2) B13.060 Interior Attachments Beyond Beltline O Region (B-N-2) B13.070 Core Support Structure (B-N-3) 0 TOTALS 1 l xJ ! Examination Category B-O Pressure Retaining Welds in Control Rod Housings l Item Number Total l Examined Description og,ygg agg,g, kl}$hdh ' g ,,ggo,y ,,,,, 00j ik B14.010 Welds in CRD Housing 0 TOTALS 0 Examination Category B-P All Pressure Retaining Components 1 REFERENCE SECTION 11.0 OF THIS REPORT (h L) Refueling Outage Report EOC 8 Page 12 of 20 Catawba Unit 2 Revision 1 Section 2 April 15,1998 l _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ -
Examination Category B-Q Steam Generator Tubing Item TotalExamined Number Dudng W age Description B16.010 Steam Generator Tubing in Straight NA Tube Design B16.020 Steam Generator Tubing in U-Tube NA Design
- TOTALS NA Examination Category F-A Class 1 Component Supports (Code Case N-491)
Item TotalExamined Number During Outage Description F01.010 Class 1 Piping Supports (One- 2 Directional) F01.011 Class 1 Piping Supports (Multi-O Directional) 2 F01.012 Class 1 Piping Supports (Thermal 3 Movement) F01.040 Class 1 Supports other than Piping 2 _ F01.050 Class 1 Snubbers' NA TOTALS 9 2 Steam Generator Tubing is examined and documented by the Diversified Services Group of the Electric System Support Department as required by the Station Technical Specifications and is not included in this report. O 8 See Request for Relief 96-01 in Section 9.0 of this report. Refueling Outage Report EOC 8 Page 13 of 20 Catawba Unit 2 Revision 1 Section 2 April 15,1998
h 2.2 Cissa 2 Inspections 1 1 (O Examination Category C-A Pressure Retalning Welds in Pressure i Vessels
)
Item Number Total Description During Outage C01.010 Shell Circumferential Welds 1 C01.020 Head Circumferential Welds O C01.030 Tubesheet to Shell Weld 0 TOTALS 1 i Examination Category C-B Pressure Retaining Nozzle Welds in Vessels O ltem TotalExamined Number During Outage Description
<w-
, q #, . . . ;
CO2.010 Nozzles in Vessels s 1/2" Nominal 4 jjf 3 ,[Q Thickness *
~
, c.i CO2.011 Nozzle to Shell (or Head) Weld 0 iQ fgr m.
CO2.020 Nozzles Without Reinforcing Plate t , ":%f ig ? e in Vessels >1/2" Nominal Thickness ygg,e
-a w -gq,i -
CO2.021 Nozzle to Shell(or Head) Weld 0 CO2.022 Nozzle Inside Redius Section 0 0 Refueling Outage Report EOC 8 Page 14 of 20 Catawba Unit 2 Revision 1 Section 2 April 15,1998
1 l Examination Category C-B (Continued) ! (") en pwcgga;. V CO2.030 Nozzles With Reinforcing Plate in h'h,h'1*,lNY Vessels >1/2" Nominal Thickness ~ '- l CO2.031 Reinforr:ng Plate Welds to Nozzle NA ; and Ve ,sel ' CO2.032 Nozzle to Shell (or Head) Welds NA when InJde of Vesselis Accessible CO2.033 Nozzle to Shell(or Head) Welds NA when inside of Vesselis inaccessible l 1 TOTALS 0 Examination Category C-C Integral Attachments for Vessels, Piping, Pumps, and Valves l item TotalExamined
* ' During OWage Description sfiE4W9%d numme:r w ifiwd i/W < eM-Pressure Vessels " m"C:@ +
C I C03.010 Integral Welded Attachments 0 hkWWMn u.s WpmysyM?' w9nghpT4 Piping
- Y#PR N%I:
C03.020 Integrally Welded Attachments 13 wwn w , y
, e ,a ..u pypDg?
w w: .S . ^3 '
.ky..
Pumps <g<~ ;; pyy,
,m' 3 C03.030 IntegrallyWelded Attachments 0
$ $ $ ilu % K. ,sve@$45 WC WAMMr%bFM Valves 'V W8 "?
C03.040 Integrally Welded Attachments NA TOTALS 13 Refueling Outage Report EOC 8 Page 15 of 20 Catawba Unit 2 Revision 1 Section 2 April 15,1998
fm Examination Category C-D Pressure Retaining Bolting Greater Than 2" y in Diameter item Number Total Description Examined y,,,,, g,g,,,
.c g g ;r c -
r %=w& C n
.Whnt? ,
Pressure Vessels ^
'N' T'W5 C04.010 Bolts and Studs NA 3..%;d e , e ,. 4
- w w, G df Piping I"GN+ in '
C04.020 Bolts and Studs NA w+p t gy - f ,4 r, p US%%&&M Pumps %> ' : Y. - C04.030 Bolts and Studs NA WQ%%s.%!!'[ mmy :.
- K ," ,
a
. y,9y,,
C04.040 Bolts and Studs NA TOTALS NA l O V Examination Category C-F-1 Pressure Retaining Welds in Austenitic Stainless Steel or High ! Alloy Piping l Item TotalExamined Number During Outage Description
, o. n
< . w:y n ~ .- .
C05.010 Piping Welds 2 3/8" Nominal Wall > m a .m in.M Thickness for Piping > Nominal Pipe Q ' [" Size 4" ~ C W tw ' C05.011 Circumferential Weld 15 C05.012 Longitudinal Weld" 13 l l l U Refueling Outage Report EOC 8 Page 16 of 20 Catawba Unit 2 Revision 1 Section 2 April 15,1998
1 Examination Category C-F-1 (Continued) b) Item Number TotalExamined During Outage v=m 4.g L Qu C05.020 Piping Welds > 1/5" Nominal Wall A; l . f 't i Thickness for Piping 2 Nominal Pipe Mi ;N% $ l Size 2" and s Nominal Pipe Size 4" N F# % ^ ' 'M C05.021 Circumferential Weld 11 C05.022 Longitudinal Weld' 3 C05.030 Socket Welds 4 pg.h m.* .c C05.040 Pipe Branch Connections of Branch Piping 2 Nominal Pipe Size 2" "'[.k D1 iff C05.041 Circumferential Weld 1 C05.042 Longitudinal Weld' O 1 TOTALS 31 ( Examination Category C-F-2 Pressure Retaining Welds in Carbon or Low Alloy Steel Piping item Number TotalExamined Description ing %tage
-s z< ., ,..
C05.050 Piping Welds 2 3/8" Nominal Wall V@ Thickness for Piping > Nominal 2; _ . .e Pipe Size 4" ****~S C05.051 Circumferential Weld 3 C05.052 Longitudinal Weld 5 0 4 Longitudinal Welds that intersect circumferential welds are examined as required by ASME Section XI, Table IWC-2500-1, Category C-F-1. However, for reporting purposes, the totals as shown in Section 3.0 of this repo:t do not include the number oflongitudinal welds examined during this outage. 5 Longitudinal Welds that intersect circumferential welds are examined as required by ASME Section XI Table IWC-2500-1, Category C-F-2. 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. O Re . ling Outage Report EOC 8 Page 17 of 20 Catawba Unit 2 Revision 1 Section 2 April 15,1998 l
Examination Category C-F-2 (Continued) O Q ltem Number TotalExamined During Outage C05.060 Piping Welds > 1/5" Nominal Wall l Thickness for Piping 2 Nominal , Pipe Size 2" and s Nominal Pipe l Size 4" C05.061 Circumferential Weld NA l' C05.062 Longitudinal Weld NA C05.070 Socket Welds NA C05.080 Pipe Branch Connections of Branch Piping 2 Nominal Pipe Size 2" C05.081 Circumferential Weld 0 C05.082 Longitudinal Weld NA l r TOTALS 3 O 1 Examination Category C-G Pressure Retaining Welds in Pumps and ; Valves I Item TotalExamined Number During Oukge Description
& .$$,: 1N:
de$hf Pumps "ld;$$ W S hiM + ~ C06.010 Pump Casing Welds NA
%,m$,
ggShESEhfsW :.w y,fy,, MM -;! kwimEn ug . b C06.020 Valve Body Welds 1 l l TOTALS 1 l Refueling Outage Report EOC 8 Page 18 of 20 Catawba Unit 2 Revision 1 Section 2 April 15,1998
i l Examination Category C-H All Pressure Retaining Componsnts , REFERENCE SECTION 11.0 OF THIS REPORT Examination Category F-A Class 2 Component Supports (Code Case N-491) Item Tota! Examined \ Number During Outage 1 F01.020 Class 2 Piping Supports (One 16 1 Directional) F01.021 Class 2 Piping Supports (Multi- 14 Directional) F01.022 Class 2 Piping Supports (Thermal 3 l Movement) , F01.040 Class 2 Supports other than Pipina 0 F01.050 Class 2 Snubbers' 0, TOTALS NA 33 l l l
'A S See Request for Request for Relief 96-01 in Section 9.0 of this report.
Refueling Outage Report EOC 8 Page 19 of 20 Catawba Unit 2 Revision 1 Section 2 April 15,1998
l l 2.3 Augmented Inspection i l 4 Item TotalExamined Number Dwing Outap Description 1 G01.001 Reactor Coolant Pump Flywheels 2 G02.001 Postulated Pipe Failures Main Steam 11 System G03.001 Thermal Stress Piping (NRC Bulletin 88- 0 08) ? TOTALS 13 , i A detailed description of each examination listed in Section 2.1 through 2.3 are located in Section 4.0 of this report. Results of ; each examination are located in Section 5 of this report. I 1 O [ O Refueling Outage Report EOC 8 Page 20 of 20 Catawba Unit 2 Revision 1 3 Section 2 April 15,1998 (
- - - - - - _ . _ _ _ _ _ - . _ _ _ - - - - - _ . l
1
\
1 ( 3.0 Second Ten YearIntervalInsoection Status The completion status of inspections required by the 1989 ASME Section XI l Code, no Addenda, is summarized in this section. The requirements are listed ! by the ASME Section XI Examination Category as defined in Table IWB-2500-1 for Class 1 Inspections and Table IWC-2500-1 for Class 2 Inspections. Augmented inspections are also included. Class 1 Inspections l Examination Description inspections inspections Percentage ' Deferral j Category Required Completed Completed Allowed B-A Pressure Retaining Welds 24 6 25 % Yes in Reactor Vessel B-B Pressure Retaining Welds 5 0 0% No in Vessels Other than Reactor Vessel B-D Full Penetration Welds of 36 0 0% Partial O Nozzles in Vessels inspection Program B B-E Pressure Retaining Partial Penetration Welds in Vessels REFERENCE SECTION 11.0 OF THIS REPORT B-F Pressure Retaining 46 8 17.39 % No Dissimilar Metal Welds B-G-1 Pressure Retaining Bolting 224 72 32.14 % No ! Greater than 2 inch Diameter l B-G-2 Pressure Retaining Bolting 29 0 0% No 2 inches and Less in Diameter l Refueling Outage Report EOC 8 Page 1 of 4 Catawba Unit 2 Revision 1 Section 3 April 15,1998 L--- - _ _ _ - _ _ _ _ _ - . . _ _ __ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
1 l r% Class 1 Inspections (Continued) j Examination Description inspections inspections Percentage ' Deferral Required Category Completed Completed Allowed B-H Integral Attachment for 8 0 0% No Vessels B-J Pressure Retaining Welds 222 25 11.26 % No in Piping B-K-1 Integral Attachments for N/A N/A N/A No Piping, Pumps and Valves B-L-1 Pressure Retaining Welds N/A N/A N/A N/A in Pump Casings B-L-2 Pump Casings 1 0 0% Yes i i B-M-1 Pressure Retaining 2 0 0% Yes Welds in Valve Bodies B-M-2 Valve Bodies 7 2 28.57 % Yes B-N-1 Interior of Reactor Vessel 3 1 33.33 % No h B-N-2 Integrally Welded Core Yes C./ Support Structures and 2 0 0*/o Interior Attachments to Reactor Vessels B-N-3 Removable Core Support 1 0 0% Yes Structures B-0 Pressure Retaining Welds 3 0 0% Yes in Control Rod Housings B-P All Pressure Retaining REFERENCE SECTION 11.0 OF THIS REPORT Components B-O Steam Generator Tubing' N/A N/A N/A N/A F-A Class 1 Component 66 9 13.64 % No Supports F01.010, F01.011, F01.012 & F01.040 (Code Case N-491) 7 Deferral ofinspection to the end of the interval as allowed by ASME Section XI Table IWB-2500-1. l 8 Steam Generator Tubing is examined and documented by the Diversified Services Group of the Electric System Support Department as required by the Station Technical Specifications and is not included in this g report. Refueling Outage Report EOC 3 Page 2 of 4 Catawba Unit 2 Revision 1 Section 3 April 15,1998
l i i Class 2 Inspections i Examination Description Inspections ' Inspections Percentsge ' Deferral Categom % ired g,,,,,,,g g,,,,,,,g ,,,,,,g l ! C-A Pressure Retaining Welds 29 1 3.45% No in Pressure Vessels C-B Pressure Retaining Nozzle 12 0 0% No i Welds in Vessels C-C Integral Attachments for 68 13 19.12 % No Vessels, Piping, Pumps and Valves C-D Pressure Retaining Bolting N/A N/A N/A N/A Greater Than 2 Inches in Diameter C-F-1 Pressure Retaining Welds 278 25 9% No ! in Austenitic Stainless 'O Steel or High Alloy Piping I C-F-2 Pressure Retaining Welds 46 3 6.52 % No in Carbon or Low Alloy Steel Piping C-G Pressure Retaining Welds 20 1 5% No in Pumps and Valves C-H All Pressure Retaining REFERENCE SECTION 11.0 OF THIS RtiPORT Components F-A Class 2 Component 222 33 14.86 % No Supports F01.020 F01.021, F01.022 & F01.040 (Code Case N-491) i 8 Deferral ofinspection to the end ofinterval as allowed by ASME Section XI Table IWC-2500-1. Refueling Outage Report EOC 8 Page 3 of 4 l l Catawba Unit 2 Revision 1 j Section 3 April 15,1998 )
- - - - 9
D
'd Augmented inspections Description Percentaae Reactor Coolant Pump Flywheels 100% of requirements for EOC 8 Postulated Pipe Failures - Main Steam 100% of requirements for EOC 8 System Thermal Stress Piping (NRC Bulletin 88-08) Not scheduled for EOC 8 O
l O Refueling Outage Report EOC 8 Page 4 of 4 Catawba Unit 2 Revision 1 Section 3 April 15,1998 l l
i i I 6.0 Recortable Indications Outage 8 had no reportable indications. h l I O l I l I O Refueling Outage Report EOC 8 Page 1 of 1 Catawba Unit 2 Revision 0 Section 6 April 15,1998
t 8.0 C0iinlive Action No corrective action was required as a result of examinations performed during Outage 8. l l O l l i i i l l i i l l O Refueling Outage Report EOC 8 Page 1 of 1 Catawba Unit 2 Revision 0 Section 8 April 15,1998 l
l 0b 9.0 Reference Documents The following reference documents apply to the inservice inspection performed during Outage 8 at Catawba Nuclear Station, Unit 2.
- Duke Power Company Request for Relief Serial No. 96-01 Snubber inspection Intervals for Catawba Unit 2 l . NRC Letter; Herbert N. Berkow to Mr. William R. McCollum, Catawba Nuclear Station, Unit 2 - Second 10 Year Inservice inspection Program, Relief Request Regarding Snubbers (TAC No. M95255 And M97982)
. Duke Power Company Request for Relief Serial No. 97-03 Limited Weld Inspection Coverage EOC 8
. PIP # 2-C97-2098 Ultrasonic Transducers l
l O 1 l i Refueling Outage Report EOC 8 Page 1 of 1 Catawba Unit 2 Revision 1 Section 9 April 15,1998
Catawba Nuclear Station Problem Investigation Process - PIP ! O I Problem Investigation Form (J PIP Serial No: 2-C97-2098 LER Serial No: MSE Serial No: Other Report: N/A
- 1. Problem ID Discovered Time /Date: 15:00 06/26/97 Occurred Time /Date:
Unit (s): 2 Status at Time Discovered Umt 1 Umt 2 Mode N/A N/A
% Power Unit Status Remarks:
System (s) Affected: N/A Not Applicable to Any System Affected Equipment Comp. WMS Eauioment ID No. Code Manufacturer 1,v) Location of Problem - Bldg: Column Line: Elev: Location Remarks: Method Used to Discover Problem: Problem was discovered during data review by the ANII. Brief Problem
Description:
This PIP documents a problem with UT Inspections. , UT inspections were performed using search units other than those required oy '.nc .NDE Program. Procedure l NDE-600, revision 9, requires that only search units shown on Table I are to tx- esed Nr examination. Contrary to ! this requirement, other search units were used by UT inspectors for the examica. w. No Operability Concern was identified during initial screening by the Centralized Screening Team. Detailed Problem
Description:
l j Procedure NDE-600, revision 9. requires that only search units shown on Table I se to be used for examination. I Contrary to th;s requirement, other search units were used by UT inspectors for the examinations. (This is entered for Jim McArdle) [ \ l Originated By: EBM8304: MILLER JR EUGENE B Team: EBM8304 Group: DSD Date: 06/26/97
\]
4/13/98 2:16:26 PM Pagee ____________ _ ___ -___ ___ ___ . _ _ _ _ ___ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ___ _-_____ s
Catawba Nuclear Station Problem Investigation Process - PIP f Problem Investigation Form t PIP Serial No: 2 C97-2098 LER Serial No: MSE Serial No: Other Report: N/A Other Units / Components / Systems / Areas Affected (Y N.U): Industry Plants Affected (Y.N.U): U Immediate Corrective Actions: The transducers that were used for the examinations at CNS were demonstrated to the CNS ANII. All transducers were shown to be capable of detecting flaws in welded mock-ups. Based on the results of this demonstration, the UT exams performed at CNS are acceptable. (This is entered for Jim McArdle) i Originated By: EBM8304: MILL ER JR, EUGENE B Team: EBM8304 Group: DSD Date: 07/22/97 Problem Found While Working with Document No. . Immediate Corrective Action Work Request / Work Order No. k/ Indiy Team Group Datc; Problem Identified By: EBM8304 EBM8304 DSD 06/26/97 Problem Entered By: EBM8304 EBM8304 DSD 06/26/97
- 11. Screening Is the Problem Significant? N Action Category: 3 OEP No: N/A Other Report Nos: N/A l l
l Event Codes: Alb Adherence \ Failure to follow procedure \ Technical Screening Remarks: Screened by the Centralized Screening Team on 6-30-97. l Originated By: JWG6081: GLENN, JOHN W Team: DPK7345 Group: SRG Date: 06/30/97 Q Responsible Group for Proposed Resolution (s): DSD Responsible Group for Prob!cm Evaluation-ESSD/Diversif. Sves DSD ESSD/Diversif. Sves - Responsible Group for Overall PIP approval: DSD ESSD/Diversif. Sves 4/13/98 2:16:27 PM Page 2 l
Catawba Nuclear Station Problem Investigation Process - PIP Problem Investigation Form bp. PIP Serial No: 2-C97-2098 LER Serial No: MSE Serial No: Other Report: N/A Indiv Team Group Date Screened By: JWG6081 DPK7345 SRG 06/30/97 111. Operability Present Operability: Responsible Group: Status: Sys/ Comp Operable?(Y,N,C,E) : Required Mode: Comments: Indir Icam Group Dalc l No current Signatures for this section. Past Operability: Responsible Group: Status: Sys/ Comp Operable?(Y.N.C.E) : Required Mode: Comments: Indir Icam Group Date No current Signatures for this section. IV. Reportabilitv/ investigation Responsible Group: Status: l Problem Reportable (Y,N,E): Reportable Per: Comments: G Indix Icam Group Date No current Signatures for this section. 4/13/98 2:16:27 PM Page 3 L
Catawba Nuclear Station Problem Investigation Process - PIP Problem Investigation Form PIP Serial No: 2-C97-2098 LER Serial No: MSE Serial No: Other Report: N/A Investigation Report: Responsible Group: Act Date: Investigator: Due Date: Date Due to VP or Sta. Mgr: Date Regulatory or Agency Rpt Due: Date Investigation Report Approved: NRC Cause Codes: V. Problem &aluation Responsible Group: DSD Status: Closed System (s) Affected: N/A Not Applicable to Any System Affected Equipment Comp. WMS Eauinment ID No. Code Manufacturer littat Cause CJ Cause Description Primary Causing Groun(s) Alb B3h Inappropriate emphasis of step /information Yes DSD Problem Evaluation: The UT technicians overlooked the requirement to use only the search units listed in Table 1. The review of the inspection data package by another technician did not identify the error. Procedure NDE-600 did not emphasize the use of Table I for search unit selection. (This is entered for Jim McArdle) Originated By: EBM8304: MILLER JR EUGENE B Team: EBM83M Group: DSD Date: 07/02/97 Indir Itain Group D;tte Due Date: 07/26/97 Accepted By: EBM83N EBM8304 DSD 06/30/97 Assigned To: EBM83N EBM8304 DSD 06/30/97 Ready For Approval: EBM8304 EBMb304 DSD 07/02/97 Approval Assigned To: EBM8304 EBM8304 DSD 07/02/97 Approved By: EBM8304 EBM8304 DSD 07/02/97 4/13/98 2:16:28 PM Page 4
Catawba Nuclear Station l Problem Investigation Process - PIP p Problem Investigation Form l Q PIP Serial No: 2 C97-2098 LER Serial No: MSE Serial No: Other Report: N/A VI. Proposed Resolution Proposed Resolution From: Resp. Group: DSD Status: Closed OEDB Checked: No Procedure NDE-600 should be revised to clarify the requirement that only search units shown in Table I be used for the examination. i l The transducers used at CNS will be formally qualified at the EPRI NDE Center the week of September 8,1997. A l copy of this P!P, when completed, will be placed in the CNS ISI Report (hard copy). (This is entered for Jim McArdle) Originated By: EBM8304: MILLER JR, EUGENE B Team: EBM83N Group: DSD Date: 07/02/97 Last Upda ted By: EBM8304: MILLER JR, EUGENE B Team: EBM8304 Group: DSD Date: 07/22/97 f~'N IndiE IcaIn GInua D.aic Due Date: ('#) Accepted By: 07/26/97 EBM83N EBM8304 DSD 06/30/97 Assigned To: EBM8304 EBM8304 DSD 06/30/97 Approval Assigned To: EBM8304 EBM8304 DSD 07/02/97 Ready For Approval: EBM8304 EBM83N DSD 07/22/97 Approved By: EBM83M EBM8304 DSD 07/22/97 VII. Corrective Actions Seq. No: 1 Resp Group: DSD Status: Closed Orig Group: DSD Event Code: Alb Prop CAC: A3 Cause Code: B3h Pronosed Corrective Action: Revise Procedure NDE-600 to clarify that only search units shown in Table 1 are to be used for the examination. 1 (This is entered for Jim McArdle) Originated By: EBM8304: MILLER JR. EUGENE B Team: EBM8304 Group: DSD Date: 07/02/97 Indix Icam Group Date Ready For Approval: EBM8304 EBM8304 DSD 07/02/97 Approval Assigned To: EBM8304 EBM8304 DSD 07/02/97 g Approved By: EBM8304 EBM8304 DSD 07/02/97 l 4/13/98 2:16:29 PM Page5 l
Catawba Nuclear Station Problem Investigation Process - PIP l (, Problem Investigation Form (>) PIP Serial No: ?-C97-2098 LER Serial No: MSE Serial No: Other Report: N/A General: Outage: Mode: Other Tracking Processes In!c Number Int Actual Corrective Action: Actual CAC: A3 Status: Closed Due Date: 11/20/97 Procedure NDE-600 has been revised (and issued) to chrify that only search units shown in Table 1 are to be used for the examination, (This is ente.ed for Wendy Cochran and Jim McArdle) Originated By: EBM8304: MILLER JR, EUGENE B Team: EBM8304 Group: DSD Date: 11/19/97 Indir Icam Group Date Accepted By: EBM83N EBM8304 DSD 07/08/97 Assigned To: EBM8304 EBM83N DSD 07/08/97 Due Date: 11/20/97 Ready For Approval: EBM8304 EBM8304 DSD 11/19/97 ApprovM Assigned To: EBM8304 EBM8304 DSD 11/19/97 Approved By: EBM8304 EBM83N DSD 11/19/97 l VHI. Finaland Overall PIP Approval Responsible Group: DSD Status: Closed Indix Icm Group Date Assigned To: DSD 06/30/97 Approved By: EBM8304 EBM8304 DSD 11/19/97 Closure Document Tyne Closure Document No Sunclemental Concurrences - These do not affect PIP closure. Concurrences Associated with External Commitments:
/
Indix Itam Group Date Concurred By: 4/13/98 2:16:30 PM ' Page 6
Catawba Nuclear Station Problem Investigation Process - PIP q Problem Investigation Form V , l PIP Serial No: 2-C97-2098 LER Serial No: MSE Serial No: Other Report: N/A IX. Attachments l Generic Applicability Generic Applicability Review Not Required for this PIP. , i Environmental No Environmental for this PIP. 1 Failure Prevention Investiention j Quality of CA: UN Quality of Cause: N2 Resp. Group: SRG Status: Closed
- 1) Ersat Inano. Action #
Alb 001
Description:
UT inspectors used transducers that were not specified in NDE procedure. Process: PM Process: Group: ESM Group: Sub-Group: Sub-Group-O and P Failure Mode: UN l HE Failure Mode: UN HE Type: UN Key Activity: in I Associated Corrective Actions: None l l Comments ladiE Iram Group Date Assigned To: GTF7700 DPK7345 SRG 09/25/97 R,eady For Approval: GTF7700 RLB0645 SRG 10/19/97 Approval Assigned To: RLB0645 RLB0645 SRG 10/19/97 Approved By: GTF7700 RLB0645 SRG 10/19/97 Remarks l No Remarks for this PIP I Maintenance Rule 4/13/98 2:16:30 PM Page 7 l f 1
l Catawba Nuclear Station Problem Investigation Process - PIP q Problem Investigation Form l PIP Serial No: 2-C97-2098 LER Serial No: MSE Serial No: Other Report: N/A No Maintenance Rule for this PIP End of the Document for PIP No: 2-C97-2098 The status of this PIP is: Closed The duranon of this PIP was: 146 days l l l l l O l I i 1 ' 1 l I l lO l l 4/13/98 2:16:31 PM Page 8 L----________ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _-. _._ _ . _ _ . - - -- - - - - - - - . _ _ _ _ . - - . . - - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
10.0 Class 1 and 2 Repairs and Replacements As required by ASME Section XI 1989 Edition, no Addenda, a record (Form NIS-
- 2) of the Class 1 and Class 2 Repairs and Replacements for work performed from November 30,1995 to May 2,1997 is included in this section of the roport.
The individual work request documents are on file at Catawba Nuclear Station. O Refueling Outage Report EOC 8 Page 1 of 1 Catawba Unit 2 Revision 0 Section 10 April 15,1998}}