ML050610019
| ML050610019 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 02/17/2005 |
| From: | Jamil D Duke Energy Corp, Duke Power Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML050610019 (35) | |
Text
4* a Duke
- Power.
A Duke Energy Company D.M. JAMIL Vice President Duke Power Catawba Nuclear Station 4800 Concord Rd. / CNO1 VP York, SC 29745-9635 803 831 4251 803 831 3221 fax February 17, 2005 U.S. Nuclear Regulatory Commission Attention:
Document Control Desk Washington, D.C. 20555
Subject:
Duke Energy Corporation Catawba Nuclear Station, Unit 1 Docket Number 50-413 Request for Relief Number 05-CN-001 Limited Weld Examinations During End-of-Cycle 14 Refueling Outage Pursuant to 10 CFR 50.55a(g)(5)(iii), please find attached Request for Relief 05-CN-001.
This request for relief is associated with limited weld examination coverage during the subject outage.
The attachment to this letter contains all technical information necessary in support of this request for relief.
Duke Energy Corporation is requesting NRC review and approval of this request at your earliest opportunity.
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.
1 LJR/s Attachment Ac+Au www. dukepower. corn
7 Document Control Desk Page 2 February 17, 2005 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
Relief Request 05-CN-001 Page 1 of 9 Inservice Inspection Impracticality Duke Energy Corporation Catawba Nuclear Station - Unit 1 (EOC-14)
Second 10-Year Interval - Inservice Inspection Plan Interval Start Date-June 29, 1995 Interval End Date-June 29, 2005 ASME Section XI Code - 1989 Edition with No Addenda I.I.
III.
IV. &V.
VI.
VII.
Vlll.
Request Limited System/
Code Requirement from Impracticality/
Proposed Implementation Justification Number Area/Weld I.D.
Component for Which Relief is Requested:
Burden Caused Alternate Schedule and for Granting Number Which Relief is 100% Exam Volume Coverage by Code Examinations Duration Relief Requested:
Exam Category Compliance or Testing Area or Weld to be Item No.
Examined Fig. No.
Limitation Percentage
- 1.
lARHRHX-5-A 1A Residual Heat Category C-B, Item Number See Paragraph See Paragraph See Paragraph See Paragraph Removal Heat C02.021.006 "A"
"D" "E"
"F' Exchanger Inlet Nozzle-to-Shell Volume Limitation 14.25%
- 2.
IARHRHX-5-B IA Residual Heat Category C-B, Item Number See Paragraph See Paragraph See Paragraph See Paragraph Removal Heat C02.021.007 "A"
"D" "E"
"F' Exchanger Outlet Nozzle-to-Shell Volume Limitation 14.25%
- 3.
IRPV-Reactor Vessel Inlet See Paragraph See Paragraph See Paragraph See Paragraph SUPPORT-A Nozzle Support @ 67 Category F-A, Item Number "B"
"D" "E"l Deg. Loop A F01.040.007
- 4.
IRPV-Reactor Vessel Outlet See Paragraph See Paragraph See Paragraph See Paragraph SUPPORT-B Nozzle Support @ 158 Category F-A, Item Number "B"
"D" "E'
"G" Deg. Loop B F01.040.008
- 5.
IRPV-Reactor Vessel Inlet See Paragraph See Paragraph See Paragraph See Paragraph SUPPORT-C Nozzle Support @ 247 Category F-A, Item Number "B"
"D" "E"
Deg. Loop C F01.040.009
Relief Request 05-CN-001 Page 2 of 9 II.
III.
IV. &V.
VI.
VII.
VIII.
Request Limited System /
Code Requirement from Impracticality/
Proposed Implementation Justification Number Area/Weld I.D.
Component for Which Which Relief Is Requested:
Burden Caused Alternate Schedule and for Granting Number Relief is Requested:
100% Exam Volume Coverage by Compliance Examinations Duration Relief Area or Weld to be Exam Category or Testing Examined Item No.
Fig. No.
Limitation Percentage
- 6.
lRPV-Reactor Vessel Outlet See Paragraph See Paragraph See Paragraph See Paragraph SUPPORT-D Nozzle Support @ 338 Category F-A, Item Number "B"
"D" "E"
"G" Deg. Loop D F01.040.009
- 7.
INS6-25 NS System Category C-F-1, Item Number See Paragraph See Paragraph See Paragraph See Paragraph Valve INSIB-to-Pipe C05.011.208 "C"
"D" "E"
"H" Circumferential weld Figure Number IWC-2500-7 (a)
Volume Limitation 31.50%
Relief Request 05-CN-001 Page 3 of 9 IV. & V. Impracticality/Burden Caused by Code Compliance Paragraph A:
During the ultrasonic examination of the Residual Heat Removal (RHR) or (ND System) Heat Exchanger Nozzle-to-Shell Welds, IARHRHX-5-A and lARHRHX-5-B greater than 90% coverage of the required examination volume was not achieved. The examination coverage was limited to 14.25 % because of the nozzle-to-shell weld design shown in Attachments 1 through 5 within Attachments "A" and "B" (Data Sheets for Item Numbers C02.021.006 and C02.021.007, respectively) of this relief request. The weld joins a 13-7/8 inch outside diameter nozzle to a vessel shell. The weld length is approximately 50 inches. Both materials are SA-240 F304 austenitic stainless steel. The nozzle configuration is a "set-on" type, which is not shown in ASME Section XI, Figure IWC-2500-4.
The percentage of coverage reported represents the aggregate coverage of all scans performed on the weld.
Scans parallel to the weld axis using 450 shear waves covered 25% of the required examination volume in two opposite directions. Scans perpendicular to the weld axis using 700 refracted longitudinal waves covered 7%
of the required volume from the nozzle side of the weld only. See Figure 1. Weld joint geometry does not permit examination of the required volume from the vessel head side nor does it allow circumferential scanning for more than 25% of the weld length. In order to obtain more coverage, the weld would have to be re-designed, which is impractical.
(Examination Data for Weld ID. Number lARHRHX-5-A is shown on Attachment A)
(Examination Data for Weld ID. Number IARHRHX-5-B is shown on Attachment B)
Paragraph B:
During the visual examination of reactor vessel supports l-RPV-SUPPORT-A, 1-RPV-SUPPORT-B, l-RPV-SUPPORT-C and I-RPV-SUPPORT-D complete examination of the supports surfaces could not be achieved.
The interface between the concrete structure and the reactor vessel precludes access for a visual inspection of the reactor vessel side of the support An area 71 inches long and 36 inches high on each support was not examined because of the limited clearance between the support and the reactor vessel shell insulation. The reactor vessel supports rest on the concrete shield wall and are flush with the edge of the shield wall. The support extends approximately 23" down from the bottom of the nozzle forging to the concrete primary shield wall below. On each side of the nozzle forging, the support extends approximately 10" to the concrete primary shield wall enclosing the vessel. The gap between the shield wall and the reactor vessel insulation is only 2 inches. Consequently, there is insufficient access for cameras or mirrors to examine this area. In order to examine the area the insulation would have to be removed from the reactor vessel. See Figures 2 and 3.
(Examination Data for ID. Numbers IRPV-SUPPORT-A, IRPV-SUPPORT-B, IRPV-SUPPORT-C, and IRPV-SUPPORT-D are shown on Attachments C, D, E and F respectively)
Paragraph C:
During the ultrasonic examination of Containment Spray (NS System) weld INS6-25, greater than 90%
coverage of the required examination volume from two axial and two circumferential directions was not achieved. Coverage was limited to 31.50% because of single sided access limitations. Duke Energy does not take credit for far sided examination coverage when the sound beam must pass through austenitic weld metal.
A best effort examination using 600 refracted longitudinal waves and 70° shear waves covered the weld metal while a 60° shear wave covered the near side base material. A 450 shear wave probe covered 100% of the pipe base material and 1/2 of the weld in two opposite directions. The slope of the transition and the weld width prevented coverage on the valve side. The aggregate coverage from all scans equals 31.50% of the required volume. In order to achieve greater than 90% coverage in two axial and two circumferential directions, the valve would have to be re-designed to allow scanning from both sides of the weld, which is impractical. There were no recordable indications found during the inspection of this weld.
(Examination Data for Weld ID. Number INS6-25 is shown on Attachment G)
Relief Request 05-CN-001 Page 4 of 9 VI.
Proposed Alternate Examinations or Testing Paragraph D:
The scheduled 10-year code examination was performed on the referenced areas / welds and resulted in the noted limited coverage of the required ultrasonic volume and visual coverages. No alternate examinations or testing is planned for the areas / welds during the current inspection interval.
VII. Implementation Schedule and Duration Paragraph E:
The scheduled second 10-year interval plan code examination was performed on the referenced welds and components resulting in limited volumetric and visual coverages. No additional examinations are planned for the welds and components during the current inspection interval. The same welds and components may be examined again as part of the next (third) 10-year interval plan, depending on the applicable code year edition and addenda requirements adopted in the future.
VIII. Justification for Granting Relief Paragraph F Ultrasonic examinations were performed in accordance with ASME Section XI, Appendix III. The examinations were performed on the weld metal and far side base material used refracted longitudinal waves, which is considered to be the best available technique.
Welds 1ARHRHX-5-A and IARHRHX-5-B on the Residual Heat Removal or (ND System) Heat Exchanger are used to cool the water from the Reactor Coolant System (RCS) in Residual Heat Removal mode or the Containment Sump in Containment Sump Recirculation. The ND System is normally in standby during power operations. When the RCS is less than 3500 F, the ND system is aligned to RHR mode and the ND Heat Exchanger is used to remove decay heat during shutdown operations. In emergency core cooling mode, the Heat Exchanger is used to remove the heat energy from containment prior to the ND system returning the water back to containment.
The area that contains the Heat Exchanger Nozzle to Shell welds are surveyed twice a day by Operations staff during their routine rounds. One of the items that must be checked off is the general condition of the room containing the Heat Exchanger. It is reasonable for the operator making these rounds to detect any external leaks from this weld.
These same areas are also surveyed once a week by a periodic test that is used to specifically look for radioactive leaks outside containment. These areas must be surveyed and signed off. If a leak were encountered, it would be written up in a work request and Problem Investigation Process form filled out. The Fluid Leak Management Process then examines the leak. The leak is either repaired or set up for periodic monitoring. A leak in the ND system would also have to be entered into the Emergency Core Cooling System Leakage Program.
Potential Failure Mechanisms:
The Residual Heat Removal Heat Exchanger nozzle to shell circumferential welds joins two carbon steel components using compatible weld material. The welds are susceptible to one failure mechanism, thermal fatigue, that is initiated from the inside diameter of the welds and is associated with high temperature differences experienced during unit heat-up and cool-down cycles. This mechanism is not expected to result in cracking of these welds because it was accounted for by the number of acceptable heat-up and cool-down cycles factored into the system design.
Residual Heat Removal Heat Exchanger IA Inlet and Outlet Nozzle-to Shell Welds are located inside containment. If a leak were to develop at these weld locations discussed in this relief request, the instrumentation available to the operators for detection and monitoring of leakage would provide prompt and qualitative information necessary to permit them to take immediate corrective action.
Plant Technical Specifications dictate that a reactor coolant system water inventory balance be performed on a regular basis. A normal operating practice is to perform this computer based mass balance on a daily frequency and/or whenever the operators suspect any abnormal changes to other leakage detection systems.
Plant Operations perform a leak rate test once per 18 months to detect leakage on ND System Components
Relief Request 05-CN-001 Page 5 of 9 while the system is in RHR operation or recirculation alignment. The test is normally performed in recirculation alignment while the unit is on line. The test focuses on valve instrumentation and flanged joints.
Technical Specifications require that if the leak rate cannot be reduced below I gpm unidentified that the plant be put in hot standby within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in cold shutdown within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. Leakage as a result of a failed weld discussed in this section would show up as unidentified leakage and be subject to the 1 gpm limit. In this case, the leak would be isolated and plant shutdown should not occur.
Paragraph G:
The requested relief is associated with the four reactor vessel supports (ID. Nos. IRPV-SUPPORT-A, IRPV-SUPPORT-B, IRPV-SUPPORT-C and IRPV-SUPPORT-D. These supports are located on alternating nozzles around the reactor vessel. Two supports are associated with the hot leg nozzles and 2 supports with the cold leg nozzles. Each support is located immediately adjacent to the reactor vessel and provides restraint in the lateral and vertical directions through an integral nozzle forging attached to the bottom of the piping.
Under normal operating conditions, deadweight, pressure and thermal loads are transmitted from the reactor coolant loop components to the building structure. Transmitted forces resulting from design loads produce generally compressive stresses in the support.
The interface between the concrete structure and the reactor vessel precludes access for a visual inspection of the reactor vessel side of the support. As a result, the inspection was limited to the outboard side of the support. The justification for this limited inspection is that the supports are made of carbon steel (SA5 16, Grade 70, SA36) with a partial coating to protect the external surfaces from corrosion. The only significant degradation mechanism for the supports is corrosion. Other potential failure modes including thermal fatigue, high cycle fatigue due to vibration, stress corrosion cracking, creep, galvanic corrosion and erosion / corrosion may be eliminated from consideration based on material selection, operating stresses, environmental factors and operating experience. As for corrosion, there was no evidence of significant corrosion during the limited visual inspection. There was some very minor degradation of the coating at isolated locations, yet there was no wastage of the underlying steel. For these locations, the areas surrounding each support are normally dry.
The only periods when the support steel may be subjected to moisture is during refueling operations where leakage past the refueling cavity seals / nozzle inspection port seals may occur. During these periods, water temperature is generally low (approximately 1 00F) and boron concentration is relatively high. Even under these conditions, the corrosion rate of uncoated carbon steel material subjected to water with a boron concentration of 2500 ppm and a temperature of IOOF is approximately 0.007 in / year [1]. This small corrosion rate will not significantly affect the structural integrity of the supports. Based on these reasons, the limited inspection of the reactor vessel supports is justified.
Paragraph H:
This weld (Weld ID. No. INS6-25) is located on the Containment Spray (NS System) pump side of valve INS IB, which is the NS pump 1B suction from containment sump isolation valve. Its physical location in the plant is on the 522 elevation in room 103, which is the IB NS pump room. During normal operations, this valve is closed and the pipe is filled with stagnant Refueling Water Storage Tank (FWST) water at relatively low pressure (FWST static head). The only time flow would be forced through this pipe would be during a LOCA inside containment where the lB NS pump would be required to take suction from the ECCS sump inside containment.
Given the location of this valve and the boron concentration of the water in the system, there are several in place programs that would quickly identify a through wall leak on this valve. First, this valve is located in an area in the plant that is visited twice per day by operators when the Auxiliary Building rounds are performed.
Given the water is highly borated, a small leak would result in noticeable boron accumulation in the immediate area. Second, if a significant leak were to develop, the leakage is routed to a floor drain in room 103 that is then routed to the ND/NS sump on the 522 elevation. Leakage into this sump is monitored by radwaste chemistry on an ongoing basis. A significant leak causing an increase in the sump pump down frequency would be identified.
Relief Request 05-CN-001 Page 6 of 9 IX.
Other Information The following individuals contributed to the development of this relief request:
Jim McArdle (NDE Level III Inspector) provided UT related information for Sections II through V Ari Tuckman (CNS NS System Engineer), Chuck Hood (CNS ND System Engineer) and Bill Callaway (Catawba Civil Engineer) provided information for Section VI Andy Hogge (Sponsor) compiled the remaining sections Sponsored By:
Approved By:
Attachment Attachment Attachment Attachment Attachment Attachment Attachment A
Weld IARHRHX-5-A Examination Data B
Weld IARHRHX-5-B Examination Data C
Component IRPV-SUPPORT-A Examination Data D
Component IRPV-SUPPORT-B Examination Data E
Component 1RPV-SUPPORT-C Examination Data F
Component IRPV-SUPPORT-D Examination Data G
Weld INS6-25 Examination Data Date Date is6/or,
Relief Request 05-CN-001 Page 7 of 9 No coverage for 70 deg. axial scan No coverage for 45 deg. circumferential scan 0
i Length 12.5" 34% coverage with the axial scan from one direction 100% coverage with 45 deg.
circumferential scan length = 12.5 in.
24.7% coverage with the 70 deg. axial scan from one direction No circumferential coverage with 45 deg. scan Length 12.5" 270 90 No coverage for 70 deg. axial sca 180 No coverage for 45 circumferential scan Length 12.5" CNS-I RHR HX Inlet/Outlet Nozzle to Shell Weld Figure 1
Relief Request 05-CN-001 Page 8 of 9 lo/_.
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Relief Request 05-CN-OO1 Page 9 of 9 PRe-qAj -e-qTcre sse4 Save MAw em- ( -ecese
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i.- e e Site/Unit: Catawba /
Summary No.:
Co Workscope:
UT Vessel Examination 1
2.021.006 ISI Procedure:
Procedure Rev.:
Work Order No.:
NDE-630 2
98577128 Outage No.:
CNIEOC14 Report No.:
UT-03-304 Page:
1 of 1
Code:
Section Xl, 1989 Cat./ltem:
C-B- /C2.21.6 Location:
N/A Drawing No.:
CN-1561-1.0
==
Description:==
Inlet Nozle to Shell System ID:
ND Component ID: C02.021.006 /lARHRHX-5-A Size/Length:
14"/ 43.96" Thickness/Diameter:
.375" Limitations:
- See limitation sheets and drawings Start Time:
1047 Finish Time:
1110 Examination Surface:
Inside L Outside 0 Surface Condition: AS GROUND Lo Location:
Rule 1 Wo Location:
Centerline of Weld Couplant:
ULTRAGEL II Batch No.:
01225 Temp. Tool Mfg.:
FISHER Serial No.:
MCNDE32770 Surface Temp.:
87
-F Cal. Report No.:
CAL-03-417, CAL-03.418, CAL-03-419 Angle Used l
0 45 45T 1 60 60T 70RL Scanning dB na 50 50 56 58 58 Indication(s):
Yes LI No i Scan Coverage:
Upstream 0 Downstream J CW i CCW i Comments:
Scan DB set to maintain 2:1 signal to noise ratio / See Drawings for Scan Coverage Results:
Accept i Reject 2 Info 2 Exam best effort due to weld configuration Percent Of Coverage Obtained>90%
No 404%- tp Reviewed Previous Data:
No Examiner Level ii Signature Date Reviewer 7 ".,yignature Date Resor, James H.
IV 10/28/2003 0fJ*-s2,A
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03 Examiner Level
-N C
Signature Date Site Review Signature Date Olson, Chad a
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10/28/2003 Other Level Signature Date ANII ew Signature Date
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ot atnst Ayd"I ML Determination of Percent Coverage for UT Examinations - Vessels SitelUnlt CAJS I /
Procedure:
/t-( % ° Outage No.:
//tv C
SummaryNo.:
O"?.o.?/,,0o ProcedureRev.:
ReportNo.:
r^03-3 oy Worlcsope:
J5 WoricOrderNo.:
of8771.2 4
of O dea Planar Scan.
L/ % Length X VJ//4
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% Length X
/
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Z S
% total f Scan 2 Scan 3
% Length X
% volume of length I 100 =
% total for Scan 3 Scan 4
% Length X
% volume of length 1000 =
% total for Scan 4 Add totals and divide by # scans 4.
%total for 45 deg Other dea 7° Scan 1 9
% Length X 2?
% volume of length I 100 7
% total for Scan I Scan 2
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% total for 7 0 deg Percent COmDlete coveraoe Add totals for each angle and scan required and divide by 4 of angles to determine;
%Totatforcomptetaexam Note:
Supplemental coverage may be achieved by use of other angles I methods. When used, the coverage for volume not obtained with angles as noted above shall be calculated and added to the total to provide the percent total for the complete examination.
Site Field Supervisor:
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Date:
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No coverage for 70 deg. axial scan No coverage for 45 deg. circumferential scan Length 12.5" 24.7% coverage with the 70 deg. axial scan from one direction No circumferential coverag with 45 deg. scan Length 12.5" 270 No coverage for 70 deg. axial scan No coverage for 45 circumferential scan Length 12.5" 34% coverage with the axial scan from one direction 100% coverage with 45 deg.
circumferential scan length = 12.5 in.
90 180 CNS-1 RHR HX Inlet/Outlet Nozzle to Shell Weld 25 inches (50%) of weld length received partial coverage in one axial direction:
34+24.7=58.7 58.7/2 = 29%
12.5 inches (25%) of weld length received full coverage in two circumferential directions.
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II Site/Unit: Catawba /
Summary No.:
Co:
Workscope:
UT Vessel Examination I
2.021.007
'SI Procedure:
Procedure Rev.:
Work Order No.:
NDE-630 2
98577128 Outage No.:
CNIEOC14 Report No.:
UT-03-305 Page:
1 of 1
Code:
Section Xl, 1989 Cat./ltem:
C-B- /C2.21.7 Location:
N/A Drawing No.:
CN-1561-1.0
==
Description:==
Outlet Nozzle to Shell System ID:
ND Component ID: C02.021.007 /1ARHRHX-5-B Size/Length:
14" / 43.96" Thickness/Diameter:
.375" Limitation~is:
- See limitation sheets and drawings Start Time:
1040 Finish Time:
1106 Examination Surface:
Inside [1 Outside i Surface Condition: AS GROUND Lo Location:
Rule 1 Wo Location:
Centerline of Weld Couplant:
ULTRAGEL II Batch No.;
01225 Temp. Tool Mfg.:
FISHER Serial No.:
MCNDE32770 Surface Temp.:
87 OF Cal. Report No.:
CAL-03-417, CAL-03-418, CAL-03-419 Angle Used 0
45 45T 60 60T 70RL1 Scanning dB na 50 50 56 58 58 Indication(s):
Yes -
No i Scan Coverage:
Upstream :1 Downstream i9 CW i CCW Pi Comments:
Scan DB set to maintain 2:1 signal to noise ratio / See Drawings for Scan Coverage Results:
Accept i Reject 2 Info F]
Exam best effort due to weld configuration Percent Of Coverage Obtained > 90%:
No 4KAYO% /
Reviewed Previous Data:
No Examiner Level,i Signature _
Date Reviewer Signature Date Resor, James H.
C 10/28/2003 II.
-t 3
Examiner Level Il-N Signatu*e' Date Site Review Sigrafure Date Olson, Chad 10/28/2003 Other Level Signature Date ANII Review A
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s,:L, -. LI = 1o0 e t (10,c9 1=
.CIO Co Ao.)
.-I
.ot0
- c. lo.qq =
(all
= (-:LI /
1 MN A i1 CDL. O2A. c0O7 100 Covre,-tApc P1I 0 %6 J
=
PCO FL O 1 D
,I06 GVhO QArN I
I I'
A+4c4440~
p 2-I
lbYL b
AL N1bIllt I Cb2. ol
.b8.7 l
14"- ex ",J9lL
-_ _ I
- _ _
I 70O Co\\Eta2A6C AhJAL 5CA-J 000 S000
'V.,
1-'0 7ib0 TZL fA e' 'C
- 11.6 -
7 _ 0,,JE IQ^ MS
,,o
=
07 c
.4 37
- LX
(,
bvl)
IELD n
V0L
- 10.9O2 (270'
,oT)
V/o L =
. ov-,
> I a.-m
. -L,5 7 3 lI-P.
4 EEb
- 4.
Os -t L
i =
I.0N D
o/<
Ct:xcUrz2W~
I ZI
- 2) 7
/
-3 4-5 (I-qb3 1-1-J-'.
4'-F W..~...
I..,=1
45 C-a Aco ec.t-Pho%-
270 (23OQ-Ar L1° CIPZLn5LAt3 0.
'St4 AlfDZE= I 1I b /.75"T I.'
-AaEA a-%r 'v-emeT r *
.1X X Y.% =.IZZo.
Ar~ei &'f (E
. 1,E v-l C.3
=. Lt o
°Je.
crc CO IJ@*c
.167' MA=. It G :)-/:5 PCI(tLC '
E I 2 bo
( U/
CLWEMACE bUC-s1o andb (g%-D-LtP
- 4kac kt%/-
q 0 5
,F
\\U "V wf -(Co 03 I 42d
I Co. -. o zan. o07 l
14CAr -
~
I Coz.ozi.007 dEAr
,A60 COVEM1 C tlecCaj 000
-C-.C XXIt oz ik zw 1-2'QoI:E q 90 Ad DoioaAa 0%
Co^6s aA6 t AE q
-o-zzie -ro 6 EL, VApVE -u p 1A+gOz e.-4 f-oss
/1-ci(c6)
DUKE POWER COMPANY ULTRASONIC BEAM ANGLE MEASUREMENT RECORD I,-
. 7 I
- 1. Take thickness measurements between wedge locations.
X
-D ' -
tan So = (d/2) t
- 2. Place search unit on straight run of pipe, and peak the signal.
- 3. Measure distance (d) between exit points.
- 4. Calculate beam angle with formula as shown using measured wall thickness.
EmN
- 5. Use the measured beam angle to determine coverage and when plotting any indications.
Pipe size:_
14 0
Pipe Schedule:_ 40ot Y
s For thin wall pipe use 2nd Vee path tan d= (d/2) r -
2t Nominal 45 deg: d=
7 5_;
t=._____; measured angle= 4t-deg CM. 0 z-1/ 0 0 7 Nominal 60 deg: d=_-L. a _; t=.. 31 ; measured angle= 5 3 deg Nominal 70 deg: d=_
_; t=
...- ; measured angle=--deg Examiner Level Date Examiner Level Date D'Z~'
,'lo-28-o3 Revie Level Date Art1riged Inspector Date L o r :
2
/- 7 1-
_ 3
? f Of II -a3-0'
12>lddeal Concepts, Inc.
I InrelJlikwt. Inntoathic. Idd'eal.
Determination of Percent Coverage for UT Examinations - Vessels SiteAJnjt eAtS
/ I SumrnyNo.: e02, 2?/1. 0°7 Wodrkcope:
( 5 1 Procedure:
, VbF-6 3 e3 Procedure Rev. __
Work Order No.: - Vff S 77/, 8 Outage No.:
Ce,.ij<TOc 1Y ReportNo.:
tL --63'-S° l of
/
O dea Peantt Scan A11A/
% LnthX x
/
f
% volume o lngth/ 100; AZA tbiotr10 deg 45 den Scan I Scan 2 Scan 3 Scan 4 c, 5-
% Length X
/0
% volume of length 1100 =
e 9-
% total for Scan 1 o2 5
% Length X
/IV
% volume of length I 00 a 25
% total for Scan 2
% LengthX _
%volumeoflength/
I100-___
%tootalforScan3
% Length X _
% volune of length I I00 = _
% total for Scan 4 Add totals and divide by I scans -
O?
% total for 45 deg Other deo 70 Scan I 1
% Length X e2 5
% volume of lengthI 100 -
7
% total for Scan I Scan 2 C0
% Length X
°
% volume of ength 1100 =
C
% total for San 2 Scan 3 _
% Length X _
% volume of length I tfJO
% total for Scan 3 Scan 4
% LengthX
% volume of length I 100= _
% total for Scan 4 Add totals and divide by 4 scans -
3_
% total for 70 deg Percent comDpete coverage Add totals for each angle and scan required and diide by # of angles to deternine; 4ZA >% Total for complete em Note Supplemental coverage may be achieved by use of other angles I methods. When used, the coverage obtained with angles as noted above shall be calculated and added to the total to provide the percent t examination.
P for volume not otal for the complete
?e i i
VOa.
Site Field Supervisor g k 4$
Date:
////G/°4 A
0
,O/
No coverage for 70 deg. axial scan No coverage for 45 deg. circumferential scan Length 12.5" 34% coverage with the axial scan from one direction 100% coverage with 45 deg.
circumferential scan length = 12.5 in.
270 No coverage for 70 deg. axial scan No coverage for 45 circumferential scan Length 12.5" 24.7% coverage with the 70 deg. axial scan from one direction No circumferential coverage with 45 deg. scan Length 12.5" 90 180 CNS-1 RHR HX Inlet/Outlet Nozzle to Shell Weld 25 inches (50%) of weld length received partial coverage in one axial direction:
34+24.7=58.7 58.7/2 = 29%
12.5 inches (25%) of weld length received full coverage in two circumferential directions.
QAL-14 Form QAL-14A Revision 15 PAGE 1
OF 1
DUKE POWER COMPANY PROJECT Catawba O PSI j
ISI ISI VISUAL EXAMINATION VT-3 HANGERS UNIT 1
W.O. #NSM g57lqi,3 2 - /
PROCEDUREOAL-14 REV.Z 5
INSPECTOR LEVEI DATE VISUAL METHOD: 5 DIRECT REMOTE VISUAL AIDS M&TE SERIAL NUMBER V__ _
W /-IA) 4 SYSTEM STATUS:
O HCOT RACOLD []OTHER (EXPLAIN IN COMMENTS)
S/R NUMBER REV. I.D. NUMBER Rigid Support ACTUAL SYSTEM TEMPERATURE CfA- /0 7D-/3 41RPV-SUPPORT-A I A)44
/Z-/o RESULTS:
f-ACCEPTABLE 5 UNACCEPTABLE (REQUIRES NDE, EVALUATION OR REPAIR) (See sketch / Dwg Attached) 5 SEE ENGINEERING JUSTIFICATION ATTACHED (OPTIONAL)
IND.
INDICATION NO.
TYPE LENGTH WIDTH REMARKS
=1020
_g MECHANICAL SHOCK SUPPRESSOR A
B LIMIT STOP A
B HOT SETTING WNAN/A ACTUAL TRAVEL (COMP/TENSION) l A
I WA COLD SETIING WNA N/A HYDRAULIC SHOCK SUPPRESSOR A
B ACTUAL PISTON SETTING WNA NJA FLUID LEVEL NWA N/A VARIABLE SPRING SUPPORTS A
B HOT SETIING NWA NWA HOT LOAD N/A N/A COLD SEtTING N/A N/A COLD LOAD WNA N/A ACTUAL PISTON SETTING N/A N/A LOAD IND. READING WNA N/A COMMENTS/DISPOSITION CONSTANT SUPPORT A
B Reactor Vessel Inlet Nozzle Support @ 67 Deg. '.
HOT LOAD NJA N/A Loop A 0
Mrfi-.
Pe-A*hfVw
-SI-A 7
COLDLOAD N/A N/A A40Ad kiC dXe, ya POSITION IND. READING N/A N/A 4d 7Z
- Sv! s-,5A/-,"
TOTAL NO. OF DIV. SCALE N/A N/A PIP: 5 YES 0
NO SERIAL NO.
FINAL REVIEW DATE AlEyIEW DATE
-t -.1.
k\\I d-a0 fisWJ>)f J2 j?/;2 C I
ITEM NUMBER F01.040.007
,6c-l e e-,@/
,r 7 't<f -Y
QAL-14 Form QAL-14A Revision 15 PAGE 1
OF 1
DUKE POWER COMPANY PROJECT Catawba 5 PSI
[m ISI ISI VISUAL EXAMINATION VT-3 HANGERS UNIT 1
W.O. #/NSM 98 ; 7Y -13 2 o0/
PROCEDUREQAL-14 REV.
INSPECTOR LEVEI DATE VISUAL METHOD: [
DIRECT
-9REMOTE X2
,Z"-I VISUAL AIDS M&TE SERIAL NUMBER SYSTEM STATUS: 0 HOT COLD [
OTHER (EXPLAIN IN COMMENTS)E StR NUMBER REV. I.D. NUMBER Rigid Support ACTUAL SYSTEM TEMPERATURE CA/ /o 70 -13 I
lRPV-SUPPORT-B NAJ4 6hyf /Z f
O -°3 RESULTS:
a ACCEPTABLE 5 UNACCEPTABLE (REQUIRES NDE, EVALUATION OR REPAIR) (See sketch / Dwg Attached) 5 SEE ENGINEERING JUSTIFICATION ATTACHED (OPTIONAL)
IND.
INDICATION NO.
TYPE LENGTH WIDTH REMARKS MECHANICAL SHOCK SUPPRESSOR A
B LIMIT STOP A
8 HOT SETTING NWA NA ACTUAL TRAVEL (COMP/TENSION) l N/A l
N/A COLD SETTING WA NtA HYDRAULIC SHOCK SUPPRESSOR A
B ACTUAL PISTON SETTING WA N/A FLUID LEVEL NWA N/A VARIABLE SPRING SUPPORTS A
B HOT SETTING N/A WA HOT LOAD NWA NJA COLD SEITING N/A NWA COLD LOAD NWA NWA ACTUAL PISTON SETTING NWA N/A LOAD IND. READING NtA N/A COMMENTS/DISPOSITION CONSTANT SUPPORT A
B Reactor Vessel Outlet Nozile Support 0 158 Deg. Loop B HOTLOAD N/A N/A
)Urifjwv r
S iwali 4
$$;/A COLDLOAD NIA WIA W- 0 44j4i/ S
- 5Vt4, hs-h*"
POSITION IND. READING NIA N/A p
-w?
If' TOTAL NO. OF DIV. SCALE NWA N/A PIP: 5 YES a
NO SERIAL NO.
FINAL REVIEW DATE ANII REVIEW DATE Rt I
- (A7,
- /i
@y-7 I
ITEM NUMBER F01.040.008 61/2I-" -&A/
6~6 /
/z, d/i//D/
QAL-14 Form QAL-14A Revision 15 PAGE 1
OF 1
DUKE POWER COMPANY PROJECT Catawba f
PSI p
ISI ISI VISUAL EXAMINATION VT-3 HANGERS UNIT 1
W8 *7'/
52 - /
PROCEDUREQAL-14 REV.
6 INSPECTOR LEVEI DATE VISUAL METHOD: 5 DIRECT
' REMOTE VISUAL AIDS M&TE SERIAL NUMBER t
Zz 03 At1 X4
/ 2 / 0 o 3 j J SYSTEM STATUS:
IN HOT VICOLD []OTHER (EXPLAIN IN COMMENTS)
S/R NUMBER REV. I.D. NUMBER Rigid Support ACTUAL SYSTEM TEMPERATURE CAI -/O70 -13 14 1RPV-SUPPORT-C NOII o3
-/Z
-03 RESULTS:
R ACCEPTABLE II ]UNACCEPTABLE (REQUIRES NDE, EVALUATION OR REPAIR) (See sketch/ Dwg Attached) 5 SEE ENGINEERING JUSTIFICATION ATTACHED (OPTIONAL)
IND.
INDICATION NO.
TYPE LENGTH WIDTH REMARKS MECHANICAL SHOCK SUPPRESSOR A
LIMIT STOP A
B HOT SETTING NWA N/A ACTUAL TRAVEL (COMP/TENSION)
WA WA COLD SETTING WA N/A HYDRAULIC SHOCK SUPPRESSOR A
B ACTUAL PISTON SETTING NWA N/A FLUID LEVEL NIA N/A VARIABLE SPRING SUPPORTS A
B HOT SETIING NWA N/A HOT LOAD NIA WNA COLD SETTING WA N/A COLD LOAD WNA NWA ACTUAL PISTON SEtIING N/A NWA LOAD IND. READING N/A N/A COMMENTS/DISPOSITION CONSTANT SUPPORT A
B Reactor Vessel Inlet Nozzle Support @ 247 Deg. Loop C HOT LOAD NA A
N~arIPahoh J
AwP..
-ds
~
9 COLDLOAD NWA N/A C.VA LAd e*ra-;*e. dm.f j.t
,r '.
w;jk POSITION IND. READING NIA NJA o -J.1po.
TOTAL NO. OF DIV. SCALE N/A MIA PIP: 5 YES B NO SERIAL NO.
FINAL REVIEW DATE ANII REVV DATE ITEM NUMBER F01.040.009 1tC-1247 5-zgA-eoo 4Ao C1
/
"6
jg 014 71/1
QAL-14 Form QAL-14A Revision 15 PAGE 1
OF 1
DUKE POWER COMPANY PROJECT Catawba a
PSI ag 1s, ISI VISUAL EXAMINATION VT-3 HANGERS UNIT 1
W.O. #INSM 98 7 YL132 -
_ PROCEDUREQAL-14 REV.
INSPECTOR LEVEI DATE VISUAL METHOD: 5 DIRECT JR REMOTE VISUAL AIDS M&TE SERIAL NUMBER Aa 2T
/Z'V003 vA A/W 4V*9 SYSTEM STATUS: []HOT,TCOLD
[]OTHER (EXPLAIN IN COMMENTS)
SIR NUMBER REV. I.D. NUMBER Rigid Support ACTUAL SYSTEM TEMPERATURE
-A A0 70 -/3 Z1 RPV-SUPPORT-D I* A
/ -9o3 RESULTS:
OACCEPTABLE EJ UNACCEPTABLE (REQUIRES NDE, EVALUATION OR REPAIR) (See sketch I Dwg Attached) 5 SEE ENGINEERING JUSTIFICATION ATTACHED (OPTIONAL)
IND.
INDICATION NO.
TYPE LENGTH WIDTH REMARKS MECHANICAL SHOCK SUPPRESSOR A
B LIMIT STOP A
B HOT SETTING NJA N/A ACTUAL TRAVEL (COMPITENSION)
NA NtA COLD SETTING NWA N/A HYDRAULIC SHOCK SUPPRESSOR A
B ACTUAL PISTON SETTING NIA N/A FLUID LEVEL NIA N/A VARIABLE SPRING SUPPORTS A
B HOT SETTING N/A N/A HOT LOAD N/A N/A COLD SEtTING N/A NIA COLD LOAD N/A N/A ACTUAL PISTON SETTING N/A INA LOAD IND. READING N/A _WA COMMENTS/DISPOSITION CONSTANT SUPPORT A
B Reactor Vessel Outlet Nozzle Support Q 338 Deg. Loop D HOT LOAD WNA N/A AwievaA243' O-'t'n of Q.
7 1
COLD LOAD N/A NIA
.c
/
8 t.j.4 Rcr
£/c/
-$ow 7
POSITION IND. READING N/A N/A P-J6/Mgev tc2gA v 2 sa.
TOTAL NO. OF DIV. SCALE WA N/A PIP: 5 YES f NO SERIAL NO.
FINAL REVIEW DATE ANII R IV DATE FINAL RI D2-3 ITEM NUMBER F01.040.010 x6,%e6'2 0-4 I /
ZEi'G//7 14111;1011w
1> Duke UT Base Metal Lamination Ehergy.
Site/Unit: Catawba /
Summary No.:
Co Workscope:
1 5.011.208 IS' Procedure:
Procedure Rev.:
Work Order No.:
NDE-640 2
98577096 Outage No.:
CNlEOC14 Report No.:
UT-03-468 Page:
1 of 2
Code:
Section Xl, 1989 Cat./Item:
C-F-1/C5.11.208 Location:
N/A Drawing No.:
CN-1NS-6
==
Description:==
Pipe to Valve (1NSIB)
System ID:
NS Component ID: C05.011.208/1 NS6-25 Size/Length:
12" Thickness/Diameter:
.375" Limitations:
No - Limitation on angle beam scans only Start Time:
1043 Finish Time:
1047 Examination Surface:
Inside D Outside 0 Surface Condition: AS GROUND Lo Location:
9.1.1.1 Wo Location:
Centerline of Weld Couplant:
ULTRAGEL II Batch No.:
03125 Temp. Tool Mfg.:
FISHER Serial No.:
MCNDE32770 Surface Temp.:
73 IF Scanning dB:
58 Cal. Report No.:
CAL-03-567 Ind Amplitude Position One Position Max Position Two Loss Remarks Back Wall Full Screen LI WI W2 MP LM WI W2 MP L2 WI W2 MP NRI Comments:
FC 03-20 Results:
Accept 3 Reject ° Info LI Initial Sect. XI exam.
Percent Of Coverage Obtained > 90%:
Yes -100%
Reviewed Previous Data:
No Examiner Level Ij Signature Date Reviewer at Date Weaver, Marion T.
_ t-11/27/2003 Gayle E Houser Level Ill 11/27/2003 Examiner Level Il-N re Date Site Review Sig atdre Date Potter, Michael E.
/
11/27/2003 Other Level N/A Signature Date ANII Review 4
1Snature Date N/A E lk 6rv5 a5-It-
/ 4!7~;7;9 61-/7 I/&
- )p4-S --
p9-;,l'tn
[Puke or~gokgrg Supplemental Report Report No.:
UT-03468 Page:
2 of 2
Summary No.: C05.0111.208 Examiner: Weaver, Marion T. ;
g Level:
II Reviewer:
Examiner: Potter, Michael E.
vel:
Il-N Site Review:
Other:
NWA Level:
NIA ANII Review:
Gayle E House Date: 11/27/2003 Date:
L fl mci Date:
_____-3 vA Comments: Profile/Plot.
Sketch or Photo: \\\\ngofsl\\IDDeaI7\\iddeal-Server\\Graphics\\Common\\ProfileLine2.jpg tt "I,
I X
r/L 6 LA/
VsbR
- 2)
I P
(Si)
AROk/e 7,14AAW 41 0a T
5
>Duke UT Pipe Weld Examination P4V"Ef Site/Unit: Catawba /
Summary No.:
Co Workscope:
1 5.011.208 ISI Procedure:
Procedure Rev.:
Work Order No.:
NDE-600 15 98577096 Outage No.:
CN1EOC14 Report No.:
UT-03-469 Page:
1 of 3
Code:
Section XI, 1989 Cat./ltem:
C-F-1/C5.11.208 Location:
N/A Drawing No.:
CN-1 NS-6
==
Description:==
Pipe to Valve (1 NS1 B)
System ID:
NS Component ID: C05.011.208/1 NS6-25 Size/Length:
12" Thickness/Diameter:
.375 Limitations:
Yes. See attached sheets.
Start Time:
1049 Finish Time:
1109 Examination Surface:
Inside El Outside i Surface Condition: AS WELDED Lo Location:
9.1.1.1 Wo Location:
Centerline of Weld Couplant:
ULTRAGEL II Batch No.:
03125 Temp. Tool Mfg.:
FISHER Serial No.:
MCNDE32770 Surface Temp.:
73 OF Cal. Report No.:
CAL-03-568, CAL-03-569, CAL-03-570 Angle Used 0
45 45T 60 70 l
Scanning dB 35 44 48 Indication(s):
Yes FII No i Scan Coverage:
Upstream El Downstream El CW iq CCW iv, Comments:
Results:
Accept i Reject El Info E Initial Sect. XI exam.
Percent Of Coverage Obtained > 90%:
No -J3.'SZ5%
Reviewed Previous Data:
No Examiner Level 11 Sinature Date Reviewer SintI re Date Weaver, Marion T.
VO b
.)
11/27/2003 Gayle E Houser Level III 9
11/27/2003 Examiner Level Il-N
/h A
Signature Date Site Review N"ibnriture Date Potter, Michael E.
_11/27/2003 Other Level N/A Signature Date ANII Review
/),6lgature
/
Date N /A ei, 3~-5
Duke V Energy.
Site/Unit: Catawba /
1 Summary No.:
C05.011.208 Workscope:
ISI Limitation Record Procedure:
Procedure Rev.:
Work Order No.:
NDE-600 15 98577096 Outage No.:
CN1 EOC1 4 Report No.:
UT-03-469 Page:
2 of 3
Description of Limitation:
No scan from valve side of weld in the axial or circ. direction due to valve configuration.
Sketch of Limitation:
VAA-\\11
-7cc
.t d
I x
x
\\
\\
5
\\
^
x
^
x\\
Altzm CV-Av\\%PC<
(o s 470'5 A, = (. S s- '<. kZS) -+ --I' V' -. t5 A 7=
0 rA 1
L$,
°/0 C '-A \\A,~
=_
0/C.7 i
IOD _ Z(. 1 5C-A,A I MTCA CYAm%'0CE
. Z-z
-Z =
,I k \\ ~,
1_>\\4 Z.
0/
-:i
"~ /6 3 V '
'SC)
S r-A,:)
'a 5t-L
-S C-A.
Z) -MD 1O/
TAA 04 r1 jZ f
I IZE1 4 1.3
. Z 3
'j7 Limitations removal requirements:
NWA Radiation field:
N/A Examiner Level II Signature Date Reviewer v/
igiqature Date Weaver, Marion T.
/d,*
1 11/27/2003 Gayle E Houser Level IlIl 11/27/2003 Examiner Level l-N /,)}i e
Date Site Review Signature Date Potter, Michael E.
/
lB ZII.
11/27/2003 Other Level N/A Signature Date ANII Review
/
,v
/
/Signature Date N/A
/Siena
I.
I r~oamr Determination of Percent Coverage for UT Examinations - Pipe Site/Unit: Catawba /
1 Summary No.:
C05.011.208 Workscope:
ISI Procedure:
Procedure Rev.:
Work Order No.:
NDE-600 15 98577096 Outage No.:
CN1EOC14 Report No.:
UT-03-469 Page:
3 of 3
45 deg Scan 1 Scan 2 Scan 3 Scan 4 0.000
% Length X 0.000
% Length X 100.000
% Length X 100.000
% Length X 0.000
% volume of length / 100 =
0.000
% volume of length / 100 =
50.000
% volume of length / 100 =
50.000
% volume of length / 100 =
0.000 0.000 50.000 50.000
% total for Scan 1
% total for Scan 2
% total for Scan 3
% total for Scan 4 Add totals and divide by # scans =
25.000
% total for 45 deg Other deg -
60 7A (to be used for supplemental scans)
The data to be listed below is for coverage that was not obtained with the 45 deg scans.
Scan 1 Scan 2 Scan 3 Scan 4 100.000 100.000 0.000 0.000
% Length X
% Length X
% Length X
% Length X 26.100 0.000 0.000 0.000
% volume of length /1 00 =
% volume of length / 100 =
% volume of length / 100 =
% volume of length / 100 =
26.100 0.000 0.000 0.000
% total for Scan 1
% total for Scan 2
% total for Scan 3
% total for Scan 4 Percent complete coverage Add totals for each scan required and divide by # of scans to determine; 31.525
% Total for complete flam Site Field Supervisor:
Date:
I lIIZf 10 3 T5t)