ML043570133
| ML043570133 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 12/07/2004 |
| From: | Jamil D Duke Power Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML043570133 (35) | |
Text
MkDuke riPowere A Duke Energy Company D.M. JAMIL Vice President Duke Power Catawba Nuclear Station 4800 Concord Rd. / CNOI VP York, SC 29745-9635 803 831 4251 803 831 3221 fax December 7, 2004 U.S. Nuclear Regulatory Commission Attention:
Document Control Desk Washington, D.C. 20555
Subject:
Duke Energy Corporation Catawba Nuclear Station, Units 1 and 2 Docket Numbers 50-413 and 50-414 Request for Relief Number 04-CN-001 Reply to Request for Additional Information
Reference:
Letter from NRC to Duke Energy Corporation, dated July 6, 2004 Pursuant to 10 CFR 50.4, please find attached the subject reply to the reference letter.
The format of the reply is to restate the NRC question, followed by Catawba's response.
There are no regulatory commitments contained in this letter or its attachment.
If you have any questions concerning this material, please call L.J. Rudy at (803) 831-3084.
Very truly yours, Dhiaa M. Jamil LJR/s Attachment c4q www. dukepower. corn
Document Control Desk Page 2 December 7, 2004 xc (with attachment):
W.D. Travers, Regional Administrator U.S. Nuclear Regulatory Commission, Region II Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 Atlanta, GA 30303 E.F. Guthrie, Senior Resident Inspector U.S. Nuclear Regulatory Commission Catawba Nuclear Station S.E. Peters, Project Manager (addressee only)
U.S. Nuclear Regulatory Commission Mail Stop 0-8 G9 Washington, D.C. 20555-0001
REQUEST FOR ADDITIONAL INFORMATION DUKE POWER COMPANY CATAWBA NUCLEAR STATION, UNITS 1 AND 2 DOCKET NOS. 50-413 AND 50-414 The U. S. Nuclear Regulatory Commission (NRC) staff has reviewed the licensee's submittal dated February 19, 2004, regarding a request for relief associated with Category B-J full penetration welds of nozzles in vessels, branch connection welds, nomtinal pipe size 4 or larger.
The NRC staff has identified the following information that is needed to enable the continuation of its review.
- 1. On page 2 of thp submittal, you reference the nozzle to branch connection weld JNC22-WNZ8. but no further information is provided.
Please provide the non-destructive examination worksheets and associated figures for this weld.
Catawba response:
Manufacturer's drartings, pro:1iles, and e:cnuinaf~ion records from the 1993 inspections are attached.
- a.
Catawba Unit 1 Drawing CNN 1201.01-181/4
- b.
Catawba Unit 1 Drawing CNM 1201.01-50
- c.
Catawba Unit 2 Drawing CNN 2201.01-104/4
- d.
Catawba Units 1 and 2 Drawing CNN 1201.01-50/3A
- e.
Examination records for Catawba Unit 1 Weld 1NC22-WN8
- f.
Examination records for Catawba Unit 2 Welds 2NC11-WN8 and 2NC11-WN7
If a butter was used, identify the butter material.
Identify the nominal reactor cooling system pipe diameter and the wall thickness for the branch connections.
Catawba response:
The weld material for all referenced branch connections is 308 stainless steel with no buttering. The reactor coolant loop piping has an inside diameter of 29 inches.
The wall thickness of the branch connections are as follows:
- a.
Weld 1NC22-WN8 is a 12" Schedule 140 (1.125") nozzle.
Attachment Page 1
4-
- b.
Weld 2NC11-WN7 is a 14" Schedule 160 (1.406") nozzle.
- c.
Weld 2NC11-WN8 is a 12" Schedule 140;(1.125") nozzle.
- 3. The American Society of Mechanical Engineers (ASME)
Boiler and Pressure Vessel Code (Code)Section XI, Appendix III, III-4450 states "Welds that cannot be examined from at least one side (edge) using the angle beam technique shall be examined by another volumetric method."
On page 2 of your submittal, you state that the connection is not accessible from the inside surface and that radiography cannot be performed because of geometry.
Discuss the radiography performed to satisfy Appendix III requirements and explain why radiography has not been proposed or considered.
Catawba response:
The branch connection welds were fabricated by Southwest Fabricating and Welding in accordance with the requirements of ASME Section III, 1974 Edition with no addenda.
Radiography was performed in the fabricator's shop where access was available from the inside for placement of the radiographic film.
After installation at Catawba Nuclear Station, access is no longer possible from the inside because of the welds connecting the piping section to the main coolant loop.
Radiography for inservice inspection is not an option because there is no access for film placement.
- 4.
On page 2 of the submittal, you indicate that the subject welds were volumetrically examined during preservice and the first 10-year inservice inspection (ISI) interval.
Discuss the coverage achieved, transducers used, ultrasonic testing (UT) technique (manual/automatic), and availability of the actual data from the inspections.
Describe the conditions that exist that have rendered UT ineffective for the second 10-year interval.
Catawba response:
During preservice and inservice inspections for the first interval, ultrasonic examinations were performed using a manual, contact technique.
The search units contained dual element, side by side, refracted longitudinal wave transducers having a frequency of 1.0 MHz, a refracted angle of 45 degrees and a focal depth of 2.5 inches.
Transducer element shapes were square with a size of 1.0" x 1.0" and rectangular with a size of 0.75" x 1.0".
Combinations of flat and contoured wedges were used to scan axially and Attachment Page 2
Ij circumferentially from the main coolant loop side of the weld to the extent practical.
ASME Section XI, Appendix III paragraphs 111-4420 requires coverage of the examination volume in two beam path directions.
Paragraph 111-4430 requires scanning over the weld crown in two opposing directions. The weld configuration as shown on the attached profile sketches, Figures 1, 2, and 3, only allows scanning from the main coolant loop side of the weld. The aggregate coverage achieved in 1993 was approximately 35% for each weld.
Preservice ultrasonic examination was performed in accordance with the requirements of ASME Section XI, 1974 Edition through the Summer 1975 Addenda.
The first interval inservice ultrasonic examination was performed in accordance with the requirements of ASME Section XI, 1980 Edition through the Winter 1981 Addenda.
These earlier code editions did not require that personnel demonstrate their capability to determine the difference between geometry and flaws. The second interval code of record is ASME Section XI, 1989 Edition with no addenda. Appendix III, paragraph 111-2200 (b) requires such a demonstration.
Beyond these factors is the recent acknowledgement within the industry that no effective UT technique or equipment is currently available to perform code examinations on cast stainless steel materials.
- 5. On page 2 of the submittal, your proposed alternative is to use liquid penetrant testing (PT) and visual testing (VT-
- 2) in lieu of volumetric examinations.
The Code-required PT is performed once per interval.
Will the PT be performed more frequently than once per interval? Discuss the PT and VT-2 examination frequency for the remaining ISI interval.
Catawba response:
Duke Energy Corporation will perform the code required examinations at these weld locations for the remainder of the interval.
These consist of a liquid penetrant examination (completed) and a VT-2 examination performed after each refueling outage during a system leakage test.
- 6. If UT examinations are not capable of providing reliable information of weld integrity, provide a discussion of the potential for flaws to develop in the weld area.
Influences upon the weld region include:
fluid temperature Attachment Page 3
fluctuations, fluid direction (into or out of the connection nozzle), flow fluctuations, vibrations,,cycling, water chemistry, etc.
Catawba response:
Flaws are not likely to develop in the stainless steel branch line nozzle to cast stainless steel reactor coolant system weld locations due to their similar metal properties, clean water chemistry, and relatively low number of thermal cycles.
Similar system operating conditions exist at the reactor coolant system to steam generator (SG) nozzle welds where dissimilar metal properties are more likely to experience flaws.
However, during the most recent Catawba Unit 2 outage, all eight SG nozzle welds were examined by radiography (this technique was used because of the cast stainless issue) with no service induced flaws being identified.
- 7. Are any of these welds included in risk-informed examination requirements? Are there other locations with similar materials and operating conditions that can be volumetrically examined?
Catawba response:
The Catawba plant does not have a risk informed inservice inspection (RI-ISI) program, but the McGuire plant does.
Since the two plants have nearly identical Westinghouse reactor coolant systems, some conclusions may be drawn by comparing RI examinations required at McGuire with what could be expected for Catawba. Main coolant loop branch connection welds of this type were not evaluated to be within a high safety significant piping segment that required examination.
There are circumferential piping welds joining static cast stainless steel elbows to carbon steel nozzles that can be volumetrically examined using radiography at Catawba Unit 2; however, because of the steam generator replacement at Catawba Unit 1, no such welds are in the inservice inspection plan.
- 8. The ASME Code provides minimum prescriptive-based examination criteria in Section XI, Appendix III.
In Appendix III, Supplement 4, Paragraph 4(c), the Code recommends licensees qualify examiners and procedures using welded samples and simulated or actual flaws located in positions where geometry may make them more difficult to detect. The purpose of the examination procedure Attachment Page 4
qualification is to determine that the proposed examination technique is capable of detecting the specified flaws of interest and that the examination capabilities and limitations are identified.
In the first paragraph of page 2 of the submittal, you indicate that the demonstration used a mock-up of similar materials with flaw depths required by Section XI, Appendix VIII, Supplement 2, 1995 Edition with 1996 Addenda.
The Supplement 2 flaw depths can be any through-wall depth and the inspection volume is the inner 1/3 of the through-wall depth.
What are the specific flaw depths, orientations, and locations used for the demonstrations?
Identify the flaw depths that can be effectively detected.
Catawba response:
The flaw depths used in the demonstration are shown below:
Flaw Flaw Flaw Location Flaw Length Depth Orientation 24.5%
Circumferential Wrought SS 0.750" Safe End 10%
Circumferential Cast 0.400" Stainless Elbow 15.5%
Circumferential Wrought SS 0.650"t Safe End 8%
Circumferential Wrought SS 0.485"1 Safe End 16%
Circumferential Cast 0.810"1 Stainless Elbow All flaws were normal to the inside surface within manufacturer's tolerance.
All scanning was performed from the cast stainless steel elbow. None of the flaws were detected.
The licensee may use additional equipment and expertise to perform an examination.
Extensive research, round-robin testing, and demonstrations have been performed on cast austenitic material using different transducer configurations (phase array, SAFT-UT, low frequency twin crystal, etc.) and data manipulation (computer) techniques. Discuss any other Attachment Page 5
equipment and UT techniques that were considered and were determined ineffective for this application.
Catawba response:
Other ultrasonic techniques were considered and rejected for these welds because of the weld joint geometry and a review of the data contained in EPRI Report TR-107481, "Status of the Ultrasonic Examination of Reactor Coolant Loop Cast Stainless Steel Materials," issued in March 1998.
The results of this study indicate that an ultrasonic*
examination of welds in cast stainless steel main loop piping is unreliable with currently available techniques including Phased Array, SAFT, and EMAT technology when performed from the outside surface. Duke Energy Corporation is aware that Pacific Northwest National Laboratory is investigating low frequency phased array in combination with SAFT to improve flaw detection in cast stainless steel piping and will remain cognizant of changing technology that can be employed in an operating nuclear plant environment.
Duke Energy Corporation will employ the latest proven techniques as they become commercially available.
- 10. With current capabilities for detecting flaws at depths beyond the volume identified in Figure IWB-2500-11, what is the maximum acceptable IWB-3600 flaw depth for each of the subject welds? The maximum depth should include flaw growth (based on the different flaw types, such as, low/high cycle fatigue, creep, primary water stress corrosion cracking) between examinations.
Discuss the effectiveness of using UT to detect the maximum flaw depth.
Catawba response:
There are three welds associated with this relief request.
Two are the welds between the Loop B hot leg and the pressurizer surge line on Units 1 and 2. The other weld is between the Loop B hot leg and the RHR suction line on Unit
- 2. These welds are between the centrifugally cast stainless steel piping and stainless steel nozzle forgings., Creep and primary water stress corrosion cracking are not a concern at this location based on properties of the base and weld filler materials.
For Duke Energy Corporation to respond to this question, expensive analytical work would have to be performed to establish a location-specific maximum allowable flaw depth in the piping based on IWB-3600 rules. This would involve:
Attachment Page 6
- 1) Postulating an initial flaw size and shape,
- 2) Determining the stresses at the location for all operating conditions,
- 3) Performing a fatigue crack growth analysis (a validation that stress corrosion cracking and thermal aging in cast austenitic stainless steels are not significant concerns will be required),
- 4) Determining the maximum flaw dimensions at the end of the evaluation period (10 year interval between inspections),
and
- 5) Comparing the maximum calculated flaw size to the maximum allowable flaw size for normal and upset conditions and for emergency and faulted conditions, then repeating this process to maximize the initial postulated flaw depth considering different flaw shapes while minimizing the margin between the final calculated and allowable flaw sizes.
The intent of this activity is to evaluate a location-specific flaw size with the capability of UT to detect this particular flaw. An estimate for the determination of this location-specific flaw size is roughly $75,000 for the three locations based on other recent analytical fracture mechanics evaluations.
Qualified vendors to perform this work are Westinghouse, Structural Integrity Associates, and AREVA.
Alternatively, in the event of flaw development, it can be stated that due to the weld configuration geometry, flaw path propagation would be longer through the weld material than through the pipe material.
- 11. The inspectability of cast austenitic cast material is dependent on the material microstructure which is dependent on material cleanliness, second phase precipitates, super-cooled liquid, and heat extraction from the mold surface.
Because of the variability between similar cast products, the results from a mock-up may also be a variable.
Besides material specification and configuration, discuss other comparisons between the subject welds and the mock-up that support the existence of comparable microstructures.
Catawba response:
The demonstration mock-up used a statically cast stainless steel elbow with an equi-axial grain structure.
The main Attachment Page 7
coolant loop piping is made of centrifugally cast stainless steel.
The microstructure of the main coolant loop piping is unknown, as only destructive means can determine this and no investigations were performed during construction or preservice inspection.
Attachment Page 8
SA-351 CF8A Main Coolant Loop Pipe
\\308 Stainless St Wed Metal el SA-182 Type 304N Nozzle 2.65"
/(
Examination Volume 0.89" Cross section view 90 deg. to the axis of the main run of pipe Figure 1 Cross-section Typical Branch Connection Attachment Page 9
- 2. 5" r
N Coverage in the axial direction = 98.8% from one direction Red triangle shows portion not covered by sound beam.
Figure 2 Typical Coverage Plot Attachment Page 10
- 2. 5"1 1
0 Circumferential scan coverage = 20% in two directions.
Shaded area covered, cross-hatch area no coverage.
Figure 3 Typical Coverage Plot Attachment Page 11
,4-'7-~10Ai-r-e.
az
/~
LLTRASONIC EXAMINATION DATA SHEET FOR PLANAR REFLECTORS Exam Filnsh a1nnn I
Revisionl Station:
- Cataba Unit:
1 Cornponentfweld ID:
1NC22-WN8 Date:
Noninal Matera Thicmess (hi.)
2_3" Weld Length (in.):
63 Surface Temperature:
.32' C deg F Measured Material Thicimess (in.)
Z.65.
Lo:
F er S/N:
MCNDE27016 Surface Condition:
BUFFED SCANS: 45 l 58 dB Conflguration:
.Bui nch-Examiner.
Level:
45T IXL.sLdB 60 n--dB i
Examiner.
oei 0.d B60TEL. n dB PIPF to fionchCannection ExrlerzLevel:
2Zr Other:
dB Calibration sheet 9301009 Appies only to NDE-620, 640 Aps tDEto 0 a
- X-Procedure
NDE 610 Rev.
1 FC:
N/A Sk-wdO wae:
NaA,,:
II 2
WI 1a Mp M1 T 0W@21 g
1 Max W
L MP 1Wi W
p 4
Beam
-Exam Scn Max Max-Max 20%dac 20%dac:. 20%dac 20%6dac 20%dac 20%doc DiJr Surf.
Sa.
D~
NO.
HMA HMA
-HMA HMA HMA HMA 50%d=c SOda=..
50%dac 50%da_
=O0"c 5,%dac I47 NO IN
)A_______
__~~
... =..'-_,... ' :
Resa Nrks:
.Uimitatiws see NDtE-UT-4
[5]
None: 5 sheeof 3
Reviewed B Level:
Date:.
Ispect Date Ite, No
....U1. 1,1/93' A 14I 1
NOV 1 5 t913 W09.031.003
1*S4
ii
3
iJ I -.
I C.
19-'i cr/4e Al -1t pe~jS7 tnmrmnnnant/Walri in.
1 NC 22-WN8 htgpm Nn%
sos nqi nnq rermaS:
rnmnnnt
~cW Il.iN 22WN Itv nrmrs
,i,.
j..
El NO SCAN El LIMITED SCAN SURFACE BEAM DIRECTION Duep'tn Ranr n1i 02 Z 01 (12 Fx]cwEIccw INCHES FROM WO to 2.0" FROM
° DEG to 36Q DEG
. weld, I
FROM L
-to L.
ANGLE: 00 Gi45L560 other -
[j] NO SCAN El LIMITED SCAN SURFACE El1 r
.BEAM DIRECTION
- . 1 El2 l Jcw [Occw FROM L to INCHES FROM WO to ANGLE OO IR145LE160 other FROM
°Q. DEG to 3f6Q DEG Not required h Connection bISI Plan:
all' El NO SCAN El LIMITED SCAN FROM L...
to I ANGLE So0 045 E60 ° SURFACE BEAM DIRECTION 0E1 0 2.
Eli El2 EcwEl ccw INCHES FROM WO_
to ther
- FROM,_-DEG to..
DEG A
5 NO.SCAN SURFACE BEAM DIRECTION ELIMITED SCAN Elt 1 EZ 01 El2 Elcwlccw FROM L
_to LI NCHES FROM WO_
to _________
ANGLE: C0 045 060 other FROM.
DEG to P.DEG 5
3yess
- [no RM*red L<&
g evel:
- .Date:
~
het>
f3*
Reviewed 8)y:
/.2
- Date:
Authorized Inspector/J/ o r
ae tC
//\\
9&A"4CA
// /9?
l;(?i ltg
-NV10j
. t1. I
.: Sy.,
fV, V
-.. #Vf W
I
%
. 1, 00
1yrtIlfm~AT-e.
C)
II*;.
- 3 0 1.I
~
I/ed
/
I s
2-1 a B
cbemntir,~ 4f-toer Ib.
- /WICo ON
-U I1TEAI N/o. - 13 C?. 0,31. oo3 I
I I
I I
Wmae o eK
0 I0 Wr'lR[6g57t-e i?
ria I 12 'XII2-2 L en
-De7&m1Awa '-L rttb ID-
--INC
-U 03 1 e-m~to. - L3 0'7.o03/.oo3
'p
./
.11,
.b 6j:fw6J4 aa
,fCV14JC:D Rp: Ja° Ac
- 1 O
1
,I '
I..
1
ODU POW1!R COMPANY
-ratiimT Fom 00184 (1
-F-b7 Station.
1 0-161 U nit /
A gv..... F in N o.
D U-&
S s t.. L
-i..
7 Z
75A
-7h
,/
.0.1u I -.
A
'u Date Prob No.J13W. 0,; /. 00 3 Chsaed By
-5111afflau.DAW IFY I I I I I I -I I I I I I iw v Jw "rho k. le. k1a el.
01 A
Lg -a
_v! 7-1
,:-w 'Aqr
Ve T -.a Z-4 JA AI LI 141
A tu Lu j Zhed JC's IF, a
O/ r-11 "A)A.T/A/d I a-6J11EFANCEF
/
I I
I I
I l
1::
1 1
1
-i
- ^.
4 &-
.I 1:
1 I -
l s
I I I I I.
DUKE POWER COMPANY ULTRASONIC CALIBRATION SHEET FOR ANALOG INSTRUMENTS FORM NDE UT-l A..
-kM&OlN'i..
-5
'a t.
I.
Station:
Catawba Unit:
I Date:
11-11-93 1Sheet nu._r_
9301009_
Procedwue:
NDE 610 Rev.
1 FC WA Coupla2nt:
Utragel I Batch No:
093001 ExAie Lee-calbato Block Taw 22 C l
940701 RffERENCE 8LOCW11
- l SIMULATOR BLOCK I-610OC 0I:
N/A SinlAp TYpO:
MOM tW RloeCk Materbk s/s Reflictor Type:
Mtal Path:
INSTRUMENT TRANSDUCER Modek USK-7D Type: Single E
.: Dual I1 Size: 2-7Z"XL.0 Freq 1
45 Manucturer.
Kraut9a0m1 M
't
- "'12 Ner 17R1 n922 Seri~al No
90145 Mantuftcurer.
o ii 4P" INSTRUMENT SEITINGS
- CALIBRATION':
METHOD CABLES Reject 0
Reflector amplitude metal path 100 RG0 PRF DUAL Type:Hole
% FSH.
Inches RGS8 0
Delay 7.6 1/8 node
.80 96
.946 80 --
-RG174 C
Rxnge 5.0" 2 /8 node 66 %
1.52 70 Beldan 828.Q..
Velodty 220.9 3/8 node
.50 2:43 60 Length 6'
Frequency
.S-7
/8 node l
- *0 l
0905 Gain so/8node Noc.Tle Filter Fufi Wave
/8 node
.**J.
CAL'll.
QfC ZERO 9.16 other
%30
=
=
=
Tlmeii.
i Thru []Putse/Echo 2
_0ositenotch
- 36':%
t-1045 S nx mosit noth
.'6';9 3.1 9 10-Jack Ustte T
caL cdrectlon: adad circ.
Mx
.iii R
0 1
2 3
4 5
6 7
8 9 10 Wave Mode:
1 MaJor Screen D
-500" nches; longitudmnal: El shear:
0 surface:.
Component/ltem No:
B09.031.003 REMARKS:
~ew re due~-.~3 i to notcht gain REVIEWID BY:
LEYEL!,
- l.
Athoized In.c.
199 I
rj I
34
- .? *,
.3.
I f~
I'll
'I
.3/4 L
lForm NDE-35A I Revision 1 DUKE POWER COMPANY STATION CATAWBA UK"T I LIQUJID PENMRA1NT EXAMINATION REPORT Weld/ID No.
1NC2?.WN_
MaterialType: 10SSOCS Diameter 12.00 ScheduleThickness 02.300 O Inconel Work Order No.
Procedure Revision No.
14 SKEICH OF ITEM EXAM/IED Surface Temperature
- 9...
F M&TE SIN:
tDEOOD04 Penetrant Materials Category:
AMl]A(SE) OB DC OD O MSE) Approved Penetrant Materials Data:
Batch Numbers Cleaner 90A04S Penetrant 78E084 Developer 92D06K Remover N/A FluorescentO0 Nonfluorescent l AcceptanceStandardsUsed: Appendix AO F[B BO GO klack Light Intensity Verified OtherAcceptance C
110 55me NVA Date NtA StandardsUsed:
NZA ED JC LightMeter&S/N:
NA Other 0 KD Indication Indication Construction ISI Inimber Type/Dimensions Reference Documents Relectable ReIbe NONE PIR SIN:
wNA Acceptable m
ExammLimitations:
IM None, (100 % Examined)
O_
%Examined Comments:
CNM1201.01-181/4 PC. C TOPC. PI Examiner AZ,.4 Level n Date I1.,1.9.
Examiner Ir.
Level Date Reviewed By:.%
. A<%;iLevel if Date 11.11-93 Final Reviewr Date ANII Review Date Item No.
/1 3
.o!-
B09.031.003A i
lb
4-771-m-f ip
.. I u s u/.
I 1 J.3 r
4TO-A I-I.
9 DUKE POWER COMPANY ULTRASONIC CAUBRAnON SHEET FOR ANALOG INSTRUMENTS I
-~..,I J~~n I
FORM NDE UT-lA,.
REVISION 2 Stntion:
Catsba Unit: Z Date:
2-11-93 Sheet nurtraw 9302006 Procedure:
NDE 610 Rev:
O FC: 911 17 V2w ss04Couplant:
Ultr Batdc No:
092041 Examiner.
g 1
Calibration Block ilX 50386 MCmeter 3ZN48 Exmier 4 AP V V
>,d Level:
.fcalbrAlon Bbloc Tow.:
22*C CaL due: 7/28/93 REFERENCE BLCKO SPIMULTOR BLOCK 11):
91-6549 ID:
RI II irgAV 79iGl 45 Type:
D SC Rld Material:
sts Reflector Tp
- HOle Metal Path:
AM" INSTRUMENT TRANSDUCER Model:
USK-7D Type: Single 0
Dual ElJ Size: 2Z.75'Xl.0 Freq:
Mhz Meas. 4 45-Manufacturer.
Krautkram0n Seral Nn-171fl-ggt Serial No:
90145 Manufaturer Meaasonr2 Nominal 4 45' 1NSTRUMENT sEr NGS CAUBR TlON METHOD CABLES Reject 0
Reflector amplitude metal path 100 0
RG62 0
PRF DUAL Type:Hole
% FSH Inches 90 RGS8 0
Delay 9.3 1/8 node 80 %
.903 80 RG174 li Range 5.0" 2/B node 66 9 1.729 70 o_
Belden 218 0 Velocity 229.6 3 /8 node 50 %
2.4 60 Length:
6' Frequency
.5-7
/8 node o
=_
Initial Calibration Gain 48
/8 node No_
40 I-EC03 Filter Full Wave
/8 node
_CAL ClECS 130-
.- lather 2 30
_-T
.Time Initials Thru [JPulse/Echo 3I opposite notch 36 %
3.19044 Jack Used: T caL crection: axi
[jJ circ.
nl l
LL +/-ii Ull IILL Liii UII tW UJ 0916 R
x 0
1 2
3 4
5 6
7 8
9 10 1025 Wave Mode:
1 Major Screen D'
- 5001 ches longltutinal:
Go shear 0
surface:
l onenItem No.
09.031.05 1809031 6
REMARKS:
SIu a
elfATBd with nrier on Ngld it8h REVIEWiED BWI LEVEL',
DATEM Authorized Insiecto1 13
?Is6.~-a-I 9---
-2
' *. e.
- A7OMfv7,-F 0*4-2al
- '2*.
- ..
- *
- ..
f
-,_5.
DUKE POWER COMPANY ULTRASONIC EXANNAT1ON DATA SHEET FOR PLANAR REFLECrORS Eim Stat
.9:02 I FORM NDE 3JTI2A IjDXam Filst 9:15 Revision 3 Station:
Catawba sUnit:
Z Comnponent/weld ID:
2NC1 1-WN8 -
Date:
2-11.93 Noflinfi Materbl iciCness (hi.)
.30 Weld Length (in.):
63" Surfee Temperature:
_2S C F
Measured Material Tlhkbess (in.)
2_5" Lo:
F
_erSfN-_A 32848 Surface Conditlon:
UFFED SCANS 4S fM 59 dB Configuration:
Brmnch Connection y,
-45Tlx dB 60 1 dB SI Flow -
9 Examiner.
Level:
-756Fw am r-.
Level:
,r o nL
.dB 60T [L.dB to B r Conect Calibration sheet 4-9302006 AA*e3 only to NDE-620, 640 Appfts to ND&680 ely Procedure:
NDE 610 Rev:
0 FCSEE NOTES wd 680 Skew fae:
NMA Li 12 WI W2 M41 Moz IND Max W
L MPBem Ea No 9
Max Max Max 2096dac 217"c 20%dac 20%dac ZO%dac 20%dac Dir Surf.
Scan Damps No dc MA "MA HMA HMA
?4MA "MA 5096dac SOdac 50%dac S0%dac 50%dac S096dac
=....4S NO RI COMA 3LE IN o
K:ATW S K=- -
-=-
-=_
II
=
=-
=
Remarks:
91-13 91-117 92-02 92-03 92-07 92-14 93-04 Limitations see NDE-U-4
[
None:0 of2 I
-rshD eet, of 4 5 Reviewed By:
Level:
Date:
D Aate Item No: B09.031.006 II.C'a<p-1-
2-/;-rZI FEB 1 19A 1 at a-
'4,
.1?
'.1/a
'I.
I II I
i I
S 4
P.,r--!1, 4,.
I C,
p
/
0 0 7 _
I 3 6 3 DU EKE POWER COMPANY ISI LIMITATION REPORT I
Revision 1 I
- Component/Weld ID:
2NC 1 1-WN8 Itom No:
BQ0 31.006 lremr.
J NO SCAN SURFACE BEAM DIRECTION Due to Branch Connection LIMITEDSCAN Eli1 OZ E li iElz El cw iMccw weld.
FROM L -
to L
INCHES FROM WO 0.-0 to
?.0" ANGLE: E00 (i45LE60 other FROM
°... DEG to 360 DEG 3 NO SCAN SURFACE BEAM DIRECTION E LIMITED SCAN 0 1 [ii 2
.[O 1 El 2 NEx cw Nrequiedby SIPlan FROM L to L INCHES FROM WO____
to ANGLE: Eo EJ45LE60 other FROM.Q. DEG to 360 DEG E
NO SCAN SURFACE BEAM DIRECTION El LIMITEDSCAN 01 E 2 1 iEl2 ElcwEccw FROM L..--to L INCHES FROM WO.._
to _-
ANGLE: 00 045 E60 other FROM DEG to DEG El NO SCAN SURFACE BEAM DIRECTION_
E LIMITED SCAN El El 2 at 02 Elcw ccw FROM l
-to L INCHES FROM WO to Sketch(s) attached ANGLE: El
,145 E60 other FROM DEG to DEG Eyes El no reCaed B
Lee:
D-Sheet
_2of Xw Reviewed Br 9
Date:
Authorized Inspect flZ l Date.,
(,u 5
1I FEB I81A
.11 I
c S
Ji
I N'L I'Fb-r '," `
4.."_.
DUKE POWER COMPANY I
I......
.1.s fy
$9D,4n, n
i rh ~J"
. Unit Z-Rev.._..e.o..
FileNo.
/ /~~T7A R ^S hi =
-Sheet 3 Ot -5 By
-Date
/--2
- Prob No. 3
.3
)6Checked By ka t Date Z-4f F
'SQ-
=/- tC-t
- Xf I
irU 3
J Xt-h
-/
J
_7 7 K 1
./
ir
-IT a}
~~~~X
/I
- We<
.F~~_42 C
s z" 4 re
?
l~~c el1
_I_
A IV A I
-I I I
_! _1 _I_
C 0
J f 1 trc Hf1 V" I -
t-I I
I
- I.,
0).O'O7'.NZ
! I.3. 8 DUKE POWER COMPANY ULTRASONIC CAUBRATION SHEETr FOR ANALOG INSTRUMENTS
}
+
l
{hl FORM NOR 1F-lAk..
,.e REVISO. 2 Sation:
Catawba Unit2 Date:
2-11-93 Sheet mwnber:
9302006 Procedure:
NDE 610 Rev.
0 FC: 9113 9117 92w 02 Couplant:
Utr I
Batch No:
092041 Examhn er::
Le:
Caibration BlockI.
50386 yrmetAer S8N Exalniner.
Ds SeraK Level:
M Calbratin BlfcTemp:__
22!C CsL. due 7/28/93 REFERENC BELlR SNMATOR BLOCK ID:.91-6549 ID:
RIllt Slm Anip:
R29f ar43-Tye:D-S Rkod*
Material:
s/s Reflector Type:
Hole Metal Path:
R-93 U INSTUMENT TRANSDUCE Model:
USK-7D3 Type: Single O
DURIll Size: 2-.75'XI.0Z Freq-I Mhz Meas.
AIS
_711(gi Serlal No:
90145 Manufacturer.
Me oIc Nominal &
-45!
INSTRUMENT SETIG CAUBR ATION METHOD
- CABLES Reject 0
Reflector amplitude metal path 100 RG6Z a
pRR DUAL TypeHdole
% FSH Inches 90-
-_RG58 0
Dlay 9.3 1 8 node 80 %
.903 80 _
RG174 EI Range 5.0" 2/8 node 66 '6 1.729 70
-_elden 8218 0
Vlodty 229.6 3 /8 node 50%Length:
62 Frequency
.5-7
/8 node so
___nia Gain 48
/8 node
% _ot I0 Filter Fail Wave
/8 node 30 other 3
==
Time Initials mhru [] Pulse/Echo j 20 to opposite notch 36 %
3.19 10 Jck Used: T caL. drector. aa
[Em circ.
3
- I 091W 6U I i L
I R
0 1
2 34 S 6 7 8910 1025 Wave Mode:
1 Major Screen Div
- 5 0 0 nhes longitudinal:
Iii shear:
0 surface:
03 Component/ftern No:
809.031.005 809.031.006 REMARKS:
Simnubltr was erformed wfth nuer on hidh i.th REVIEWED By ILEVEL:
- DATE, IAuthorized InspectorW 1
3 KU r
-1_
),
,N'ew I
. 'I, IJ.1 J
a'. -
, 8.Z
^
f Fer4 I
Form NDE-25A I. Rrevon 1 DUKE POWER COMPANY PROJECT CAMAWRA MANETIC PARTICLE/IQUID PENTRAT EXAMINATION REPORT WeIdNo.
iUk Nc 2
Date 2-11-93 Dlr 17.oo Schdulefic 2t300 Type Mateft SS m cs o OrderNoL N/A QACondimon I
PrcedueNFlSA-F / Rev 1 SKETCH OF ITEM EXAMINED NDE-98 Appoved N/A R&on Lee N/A Le Irlcation
~
oDkinesks Number Ln D
eW et Acceptable Reportable Reference Documents MT DATA PT DATA MT Method Used PT Batch Number o Fluorescnt 0 Nonfluorescent a Wet 0 Dry Cleaner
_ 9ER4K Peletrant 7RE084 MT Unit SOI NQo Developer 92Gr07K Remo/
N/A Particle Batch No.
/
Floscent 0 Nonfluorescent MT Technque Used:
j Block Ught MMt Vefiecd Circular Time D__
0 D o Diect Contact Amp Seril No. Ught O Cenal Conduct Srah MTFleldlsd-caaorUsed pnarke CNM 2201.01-104/4 E3 o6e o C 3 ooc
~
PC C TO PC P1
/0 Yoke O AC O DC O3 ProzdPCCTPC1 G
Number Tuns hi Coll aI Dte Fial QA Review I>t liemllf FEB 1 1993
%r..-
n B09.031.006A II
Arrh-ct e~r-l:
,04o-7r 1r H
P f.
_J/
OO7.,i.
! T. 'X..;-
I.
.; I.
)L... Wu.s DUKE POWER COMPANY ILTRASONC EUMINATMON DATA SHET FOR PLANAR REFLECTORS
.Exam Fiart Examr fl:s 8:45
_J 4I i
I..;r I,.
9:00 R.
3
.7 r RevfW 3 1:- 1.
- I Station:
Catawbe Unit:
2 Component/weld ID.
2NC11-WN7 Date:
2-11-93" Nonminal Mate"l TkIness (in.)
Weld Length (n):
69" Surface Temperature:
25 c F
Measured Material Thlcmess (hi.)
Lo:
__A
-P__S/N:
MCQA 32848 Surface Condtlon:
BUFFED SCANS 45 E 59 dB Configuration:
RrA CnUUl 45T nx 5 dB 60 l
dB s1 n
Examiner.
Level:
6 do Examiner:
Level:
dtodB Calibration sheet No:
9302006 Apples aoW to NHE-620, 640 Apples to NDE-680 tiy Procedure:
NDE 610 Rev 0
FQSEE NOTES d680 Skew ge:
NI
_ _Li L2 WI W2 Mpl Mp2 IND Max W
L MP
-LV1Wi W
Beam Exwn W
Max M
axx 20%dac 20%dac 20%dac 20%dac O0%dac 20%dac Ba btam Scan Dwmps NO.
dcHMA HMA HMA HMA HMA HMA 50%dac 50%dac 50%dac 50%dac SO%dac S06dac 450 NO R A E 0 ______
Remarks:
91-13 91-17 92-02 92-03 92-07 92-14 93-04 Umitations: see NDE-Ur-4 f
None: ]
sheet
/
of_. L.v
.~Ie
_~o
_9.,0.3..._.0.
I I
Reviewed By:
I II
/7 Level:
7r Date:
Ied Irrpq7 tor
-7 "I.%/*
S rl
-FEB 1 a8 199A Item No: 809.031.005s Ir,,
FEB i 8I99S-U_
gg II.y' 4
14
'O 0 7
! 3 '5 5 DUlKE POWER COMPANY FORM ND) UT4 ISI LlMITATION REPORT Revision I Component/Weld ID:
7NC 11 -WN7 Itpm No:
BQQ1QQL remarks:
I]
NO SCAN SURFACE BEAM DIRECTION Due to Branch Connecton LIMITEDSCAN Eil Li2
[I
[XI2
[l cwElccw weld.
FROM L to L INCHES FROM WO 0-0" to 2.0" ANGLE Lb0 EJ45L060 other FROM
°... DEG to HQa DEG I3 NO SCAN SURFACE BEAM DIRECTION L LIMITED SCAN 01 [1 1
a Eh Iz 2 El NotwrequiredEbyllPlan FROM L1 -..
--.to 1 INCHES FROM WO___
to -_-
ANGLE: L00 E45L-060 other FROM
°.
DEG to 360Q DEG
[J NO SCAN SURFACE BEAM DIRECTION Due to Ultrasonic Level I] LIMITED SCAN
[1 1 EL 2 Ell 1z2 [AIcw[Ilccw Detector and 2.0" nozzle FROM L_
to L INCHES FROM WO 28" to 38B ANGLE: Lb
[EI45L-060 other FROM -
DEG to -
DEG L
NO SCAN SURFACE BEAM DIRECTION L LIMITEDSCAN lii 1iz 2 01 Iz L2cw lccw FROM L to L.__
INCHES FROM WO0 to Sketch(s) attached ANGLE: 50 a45 060 other FROM
_DEG to DEG E yes 6&q ELJno Prepared By.,
Lev:
D~te:-
Sheet 2 of l~
Revl ew
%r Date:
Authori 8 19 3 I-.
a i
~
~
,~.DUKE POW2 COMPANY
- Z.-1I io
'Oe?~
'U~
.Rev.......File N6cge1!C//-AL1LZS t A..
5: E'-"
(
i ~..I
-Zlia
.ve A
V&A At,-~7!
O L-1
.i A.6 V ? ~zsyot I
-fs 7-IdI 1Ž VLA
_7 I
et-.i7cJ U-u a
.0
iDUKE POWER COMPANY
- W-->z
- r
'-
4.
)
0 It Iat
.uu_
T'
- .. Unit Z-Rev... File NA.'t A,& Sheat L O 6 I1A A 4 7 7 I
,,il
/
- czt-By w@0
>° ae 2f
-Prob No.
oi uZ 4 ?/.60(J' Checked By Date__
1-9 I-o 7 a -'-
Al I~~~~
~
~
I. III1t H
I i-7 g+/-
~r A Xc) 74 X
1 6 t 101
-- 7
- - - _-___i I1_-
II _
II H
I I I
I I
I I_
I_
I' I I 1
I_ I I _1 1lI-L l11 1 11 1 I
~
I I-Ilil I.
T
- -lLlI-- I I~
I
,--l_
I i 1-1.-i--
t..l
~ la
.T
.I I
I I
nmg km v
l1
'Z~~'.
~
I Form NDE.2r;A IRvso
-... ~ ~
S.
I.
e*..j Q
0 DUKE POWER COMPANY PROJECT CATAWBA
.MAGNETIC PART"CLE/UQUID PENETRANT EXAMINATION REPORT WIjhdNao 2NCII-WN7 UnitNM.
2 Date 2-11-93 Diameter 140 0 Scheduler 2.300 TypeMateriaiSS 3 CSO Work 0 N/A OA Coditin 1
Procec NnfRlAE / Rv 1
SKETCH OF ITEM EXAN NED NDE98 ApptM N/A Redlation L" N/A i
II lndicaton Indkan Dhxesw Number Length/WidUh/Diarneter otcz Acceptable Reportble Refrence Documents NONE MT DATA MT Method Used 3 Fluorescent 0 Nonfluorescent 0 Wet 0 Dry MT Unit Seriaw Nof Partile Batch No._____
MT Tedrnque Used:
O Dhct Co Amp O Cental Conduct PT DATA PT Batch Number COaner 91P.04K Peneant 7 R EO4 Dekper aq rfn7K PR er m
N/A O Fluorescent Bl Nonfluorescent Black Ught Intensity Verified Tlme -
I t)
Serh No. Light W SeMW1at LigUht_
MT Fbed Indiutor Used oYes o No
/Oo Yoke O AC a DC O Prd al Nurnber Turns In Coil Remarks nulM ?79f1 n_11A4/4 PC B TO PC P1 I
/
0.,
-THIS PAGE IS AIN OVERSIZED DRAWING OR
- FIGURE, THAT CAN BE VIEWED AT
- THE RECORD TITLED:
DWG. NO. CN-1 680-23R/3:
"DUKE POWER COMPANY
- CATAWBA NUCLEAR STATION UNIT 1 SPIN: RCPCFB" Attachment A WITHIN THIS PACKAGE..
OR BY SEARCHING USING DWG. NO.- CN-1 680-23 R1/3 1
Dl(
l: TIM r'm AX1T7 D-O1 17 I"l-JLXJLP I IAt\\L IL
THIS-PAGE IS AN, OVERSIZED DRAWING OR
- FIGURE,
-THAT CAN BE VIEWED AT
-THE RECORD TITLED:
. I wj He.-
i.
.. A%,I
- 1.
I
.i' I
I
.:I 6,
II l
. - - -A-.S.M.E.
SECTION II-I CLASS 1 BUTT WELDING NOZZLES" Attachment B WITHIN THIS PACKAGE..
PROPRIETARY
.'I.
l D-02
THIS-PAGE IS AN OVERSIZED DRAWING OR t
- FIGURE, THAT CAN BE VI EWED AT
'THE RECORD TITLED:
DWG. NO. CN-2680-1 (R)-
"ADDED AS BUILT DATA" Attachment C WITHIN THIS PACKAGE..
OR BY SEARCHING USING PROPRIETARY D-03 a
THIS PAGE IS AN OVERSIZED DRAWING OR
- FIGURE, THAT CAN BE VIEWED.AT, U THE RECORD TITLED:
i..
I..
I
- 4..
.Tw; "A.S.M.E. SECTION. III CLASS 1 BUTT WELDING NOZZLES" Attachment D WITHIN THIS PACKAGE..
I PROPRIETARY
- D-04 1'.