ML072640194
| ML072640194 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 07/11/2007 |
| From: | Morris J Duke Energy Carolinas, Duke Power Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 07-CN-001, 07-CN-002 | |
| Download: ML072640194 (50) | |
Text
Duke aEnergy JAMES R MORRIS Vice President Catawba Nuclear Station 4800 Concord Road / CNO1 VP York, SC 29745-9635 803 831 4251 803 831 3221 fax July 11, 2007 U.S. Nuclear Regulatory Commission Attention:
Document Control Desk Washington, D.C.
20555
Subject:
Duke Power Company LLC d/b/a Duke Energy Carolinas, LLC (Duke)
Catawba Nuclear Station, Unit 2 Docket Number 50-414 Request for Relief Numbers 07-CN-001 and 07-CN-002 Limited Weld Examinations During the End-of-Cycle 14 Refueling Outage Pursuant to 10 CFR 50.55a(g) (5) (iii),
please find attached Requests for Relief 07-CN-001 and 07-CN-002.
These requests for relief are associated with limited weld examinations during inservice inspection activities for the subject refueling outage.
During this outage, inservice inspection activities were conducted for the third period of the second inspection interval (Request for Relief 07-CN-001) and for the first period of the third inspection interval (Request for Relief 07-CN-002).
Both requests for relief are being submitted together, since the inservice inspection activities for both periods/intervals occurred during the same refueling outage.
The attachments to this letter contain all technical information necessary in support of these requests for relief.
Duke is requesting NRC review and approval of these requests at your earliest convenience.
There are no regulatory commitments contained in this letter or its attachments.
If you have any questions concerning this material, please call L.J. Rudy at (803) 831-3084.
4ltqIf- 0/# I A04--7 www. duke-energy. corl
Document Control Desk Page 2 July ii, 2007 Very truly
- ours, James R. Morris LJR/s Attachments
Document Control Desk Page 3 July 11, 2007 xc (with attachments):
W.D. Travers, Regional Administrator U.S. Nuclear Regulatory Commission, Region II Atlanta Federal Center 61 Forsyth St.,
SW, Suite 23T85
- Atlanta, GA 30303 A.T. Sabisch, Senior Resident Inspector U.S. Nuclear Regulatory Commission Catawba Nuclear Station J.F. Stang, Jr., Senior Project Manager (addressee only)
U.S. Nuclear Regulatory Commission Mail Stop 8-H4A Washington, D.C.
20555-0001
Document Control Desk Page 4 July 11, 2007 bxc (with attachments):
R.D. Hart L.J. Rudy K.E. Nicholson M.A.
Pyne A.J. Hogge, Jr.
R.N. McGill RGC File Document Control File 801.01 ELL-EC050 NCMPA-1 NCEMC PMPA SREC Request for Relief 07-CN-001
Relief Request 07-CN-001 Page 1 of 8 Relief Request 07-CN-001 Proposed Relief in Accordance with 10 CFR 50.55a (g)(5)(iii)
Inservice Inspection Impracticality Duke Energy Corporation Catawba Nuclear Station - Unit 2 (EOC-14)
Second 10-Year Interval - Inservice Inspection Plan Interval Start Date = 8-19-96 Interval End Date = 8-19-06 This Relief Request has two (2) welds for which relief is being sought.
The ID's and Item / Summary Numbers for the two (2) welds are as follows:
List Number Weld ID Item / Summary Number
- 1.
2ND-37A B 12.040.002B
- 2.
2ND24-16 C05.011.077 Attachment A contains the inspection data for Weld ID. 2ND-37A.
Attachment B contains the inspection data for Weld ID. 2ND24-16.
Items in this relief request were examined during March/April of 2006.
ASME Code Component Affected Weld ID = 2ND-37A Item / Summary Number= B 12.040.002B Residual Heat Removal System Valve 2ND37A Body to Bonnet Weld II.
Applicable Code Edition and Addenda
ASME Section XI Code - 1989 Edition No Addenda Code Case N-460 is applicable
Relief Request 07-CN-001 Page 2 of 8 III.
Applicable Code Requirement
Table JWB-2500-1, Examination Category B-M-1 Item / Summary Number B 12.40.
Appendix 11, MIl-4420 and 111-4430 Figure IWB-2500-17, 100% Volume Coverage of Examination Volume J -K-L-M Code Case N-460, Greater than 90% Volume Coverage of Examination Volume J-K-L-M IV. & V.
Impracticality/Burden Caused by Code Compliance The valve body to bonnet material is wrought stainless steel. This weld has a diameter of 20.0 inches and a wall thickness of 2.43 inches. During the ultrasonic examination 70.825% coverage of the required examination volume was obtained. The percentage of coverage reported represents the aggregate coverage from all scans performed on the weld and adjacent base material. ASME Section XI, Appendix III, IH-4420 requires coverage of the examination volume in two beam path directions and Appendix Ell, 111-4430 requires scanning on the weld crown and base material in two directions. These requirements could not be met because of the weld configuration. As shown on Attachment A, Page 5 of 8, the proximity of the machined radius on the valve bonnet prevented scanning on the bonnet side of the weld. The coverage from each scan was as follows: 450 scan parallel to the weld covered 75.30% in two beam directions; combinations of 450 and 60' shear and refracted longitudinal wave scans perpendicular to the weld covered, 37.10% from the valve bonnet side and 95.60% from the valve body side. All scans were performed using a one half V-path technique. Two beam path direction coverage is normally obtained using one half V-path shear waves from both sides of the weld or, alternatively, full V-path shear waves from one side of the weld. However, the weld joint geometry prevented scanning-from both sides of the weld in two beam path directions and a full V-path examination from one side is prevented because of the stainless steel weld metal properties which cause excessive attenuation with shear waves. Substituting full V-path refracted longitudinal waves for shear waves are not possible because of the mode conversion occurring at the inside surface when using refracted longitudinal waves. In order to meet the coverage requirements for this weld, the weld joint would have to be redesigned to allow more scanning area, which is impractical. There were no recordable indications found during the inspection of this weld.
(Examination Data is shown in Attachment A)
Relief Request 07-CN-001 Page 3 of 8 VI.
Alternate Examinations or Testing Radiography as an alternative would require disassembly of the valve, which is impractical; therefore, no alternate examination or testing for the weld was performed during the Second Ten Year Inspection Interval.
VII. Implementation Schedule and Duration No additional examination for the weld was performed during the Second Ten Year Inspection Interval.
VIII. Justification for Granting Relief Ultrasonic examination of the weld for Item Number B 12.040.002B was conducted using personnel qualified in accordance with ASME Section XI, Appendix VII of the 1989 Edition, No Addenda. The ultrasonic procedures used complied with the requirements of ASME Section XI, Appendix E11, 1989 Edition, No Addenda. Based on the following justification, the amount of coverage obtained for this examination provides an acceptable level of quality and integrity.
The piping containing valve 2ND37A is an ASME II, Class 1 line with a design temperature of 650'F and a design pressure of 2500 psia. The valve is located inside the Unit 2 containment. The subject weld is associated with a 12" Borg Warner, 1512 lb. gate valve. This secondary boundary isolation valve remains closed during normal operation to isolate the low pressure residual heat removal system from the high pressure reactor coolant system (i.e., Reactor Coolant Pressure Isolation Valves). The valve is opened during plant startup and shutdown to provide core cooling.
The subject weld is between the SA182 F316 valve body and the SA182 F316 bonnet neck. These materials are austenitic (16Cr-12Ni-2Mo) based materials and a) have a high corrosion resistance with low contribution of corrosion products to the coolant, b) have good mechanical properties and c) are highly weldable. Very few service induced problems with stainless steel in PWR primary system applications have been observed in operating plants. There has been limited susceptibility to stress corrosion cracking due to chloride contamination and cracking in stagnant borated systems.
Chemistry limits on chlorides, fluorides and sulfides and dissolved oxygen are controlled by Selected Licensee Commitment (SLC) and other administrative procedures at Catawba to ensure that any favorable conditions for SCC are precluded. Additionally, controls on welding filler material consistent with Regulatory Guide 1.31 also have served to limit the susceptibility of these welds to SCC. No other known degradation
Relief Request 07-CN-001 Page 4 of 8 mechanisms are applicable to this material at this particular location within the system.
This piping and valve body are normally covered by metal reflective insulation. During each refueling outage, multiple walkdowns of containment are performed to determine the presence of external leakage.
These walkdowns include a boric acid walkdown (PT/2/A/4150/001H) while the primary system remains at temperature and pressure (Mode 3).
Other walkdowns performed during the outage are system engineer walkdowns (PEP 3.09), operation walkdowns at 350 psi, 1000 psi and normal operation pressure (OP/2/A/6100/001) and the ASME XI, PWA-5000, system leakage test. During these various walkdowns, any leakage from this weld would be recognized by active leakage or boron deposit buildups around the valve and mirror insulation.
In addition, leakage during operation (assuming leakby of the primary isolation valve) at the body to bonnet, weld 2ND37A would be detected by various other leakage detection systems available to the operator. These systems identified with plant technical specifications include:
a) Containment Atmosphere Particulate Radioactivity (EMF 38)
Monitor which would detect airborne radiological activity; b) Containment Ventilation Unit Condensate Drain Tank Level Monitor which collects and measures as unidentified leakage the moisture removed from the containment atmosphere; c) Containment Floor and Equipment Sump Level Monitors where unidentified accumulated water on the containment floor would be monitored and evaluated as sump level changes.
d) A reactor coolant system water inventory balance is performed on a regular basis (i.e. at least once every three days). The normal operating practice is to perform this computer based program on a daily frequency and/or whenever the operators suspect any abnormal changes to other leakage detection systems. A Plant Technical Specification requires system leakage from "unidentified" sources be maintained below 1 gpm-; however, plant operation procedure (PT/l(2)/A/4150/00lD, NC System Leakage Calculation) establishes an administrative limit of 0. 15 gpm above which the source of leakage will be investigated. Leakage as a result of a leak in the weld discussed in this section would show up as unidentified leakage and subject to the 0. 15 gpm administrative limit.
Relief Request 07-CN-001 Page 5 of 8 Other leakage detection systems available to the operator include
- 1) Volume Control Tank (VCT) level changes, 2) VCT make-up frequencies and 3) Cold Leg Accumulator level changes.
These walkdowns and leakage detection systems provide a high level of confidence that any leakage would be promptly identified at this welded joint inside containment.
References:
- 1) Weld Isometric CN-2ND-066
- 2) Piping Isometric CN-2491-NDOOI
- 3) Flow Diagram CN-2561-1.1
- 4) Valve Drawing for 2ND37A, CNM-1205.00-0262
- 6) Technical Specification 3.4.15, RCS Leakage Detection Instrumentation
Relief Request 07-CN-001 Page 6 of 8
- 1.
ASME Code Component Affected Weld ID = 2ND24-16 Item / Summary Number = C05.011.077 Residual Heat Removal System Pipe to Flange Weld II.
Applicable Code Edition and Addenda
ASME Section XI Code - 1989 Edition No Addenda Code Case N-460 is applicable III.
Applicable Code Requirement
Table 1WC-2500-1, Examination Category C-F-I Item / Summary Number C5.11 Figure IWC-2500-7(a), 100% Volume Coverage of Examination Volume C-D-E-F Code Case N-460, Greater than 90% Volume Coverage of Examination Volume C-D-E-F IV. & V. Impracticality/Burden Caused by Code Compliance The flange and pipe material are wrought stainless steel. This weld has a diameter of 12.00 inches and a wall thickness of 0.375 inch. During the ultrasonic examination of this weld, 62.50% coverage of the required examination volume was obtained. The percentage of coverage represents the aggregate coverage from all scans performed on the weld and adjacent base material. The coverage from each scan was as follows: 450 shear wave circumferential scans, both clockwise and counter-clockwise covered 100% of the weld and base material; 600 shear wave scan from the pipe side perpendicular to the weld covered 50% of the weld and base material. A supplemental scan using a 70' shear wave search unit covered 50% of the examination volume on the flange side from one direction perpendicular to the weld but is not included in the coverage calculations because of the requirements of IOCFR50.55 a (b)(2)(xv)(A)(1) which mandates scanning from four directions. The limitation was caused by the taper on the flange side of the weld which does not provide enough scanning area from that side. In order to meet the coverage requirements for this weld, the weld joint would have to be redesigned 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 is shown in Attachment B)
Relief Request 07-CN-001 Page 7 of 8 VI.
Alternate Examinations or Testing No alternate examination or testing for the weld was performed during the Second Ten Year Inspection Interval.
VII.
Implementation Schedule and Duration No additional examination for the weld was performed during the Inspection Interval.
VIII. Justification for Grantiuig Relief Ultrasonic examination of the weld for item number C05.011.077 was conducted using personnel qualified in accordance with ASME Section XI, Appendix VII of the 1989 Edition, No Addenda. The ultrasonic procedures used complied with the requirements of ASME Section XI, Appendix 111, 1989 Edition, No Addenda.
In addition, a dye penetrant examination was performed on the weld in accordance with ASME Section XI, 1989 Edition, No Addenda. No recordable or reportable indications were found. Based on the following justification, the amount of coverage obtained for this examination provides an acceptable level of quality and integrity.
Weld 2ND24-16 is a weld between 12" XS wall piping and a 12", 600 lb, raised face flange. The associated piping is located downstream of the Residual Heat Removal Heat Exchanger (NDHX) 2A on ASME Class 2 piping with a design temperature of 400'F and design pressure of 615 psia.
This piping is located in the auxiliary building and is not normally pressurized during reactor operation. This weld maintains the pressure boundary as part of the ECCS flow path under accident conditions.
The subject weld is between the SA312 TP304 piping and a SA182 F304 flange. These materials are austenitic (18Cr-8Ni) based materials and a) have a high corrosion resistance with low contribution of corrosion products to the coolant, b) have good mechanical properties and c) are highly weldable. Very few service induced problems with stainless steel in PWR primary system applications have been observed in operating plants. There has been limited susceptibility to stress corrosion cracking due to chloride contamination and cracking in stagnant borated systems.
Chemistry limits on chlorides, fluorides and sulfides are controlled by Selected Licensee Commitment (SLC) and other administrative procedures at Catawba to ensure that any favorable conditions for SCC are precluded.
Additionally, controls on welding filler material consistent with Regulatory Guide 1.3 1 also have served to limit the susceptibility of these welds to SCC. No other known degradation mechanisms are applicable to this material at this particular location within the system.
Relief Request 07-CN-001 Page 8 of 8 This piping and flange are normally covered by calcium silicate insulation.
This piping is in the Unit 2 mechanical penetration room of the auxiliary building. Leakage during normal operation would be seen as active leakage due to ambient temperature conditions and readily identified on the 543 ft. floor elevation below. The room is accessible during normal operation and is within the scope of weekly operation walkdowns.
Periodic system engineer walkdowns are also performed that include leakage identification on the ND system.
In addition to walkdowns, an operational leak rate test (PT/2/A/4202/002) for the ND system is performed with the system pressurized on an annual basis. An ASME XI, IWA-5000 system leakage test is also performed every ISI period. Either of these tests would identify leakage at this particular weld.
These walkdowns and leakage tests provide a high level of confidence that any leakage would be promptly identified at this welded joint in the Auxiliary Building mechanical penetration room. As a result, the limited volumetric coverage associated with this particular weld has no significant impact on the continued assurance of structural integrity for the ND piping.
References:
- 1) Weld Isometric CN-2ND-0024
- 2) Piping Isometric CN-2492-ND019
- 3) Flow Diagram CN-2561-1.0 IX.
Other Information The following individuals contributed to the development of this relief request:
James J. McArdle (Principal UT NDE Level III Examiner) provided Sections HII, IV, V, VI, VII and part of Section VIII.
W.O. Callaway (Catawba Engineering) provided part of Section VIII.
Andy Hogge (Catawba ISI Plan Manager) compiled the remaining sections.
Request for Relief 07-CN-001 Attachment A Weld 2ND - 37A Number of Pages = 8
Site/Unit: Catawba /
2 Summary No.:
B12.040.002B Workscope:
ISl UT Vessel Examination Procedure:
Procedure Rev.:
Work Order No.:
NDE-3630 0
98732469 Outage No.:
CNS2-14 Report No.:
UT-06-162 Page:
1 of 8
Code:
Asme Section XI 1989 Cat./Item:
B-M-1/B12.40.2B Location:
Drawing No.:
CN-2ND-66
==
Description:==
Valve Body to Bonnet System ID:
ND Component ID: B12.040.O02B/2ND-37A Size/Length:
N/A Thickness/Diameter:
2.430 / 20.0 Limitations:
Yes-See Attached Limitation Report Start Time:
0930 Finish Time:
0955 Examination Surface:
Inside []
Outside [
Surface Condition: AS GROUND Lo Location:
RT INT. #1 Wo Location:
Centerline of Weld Couplant:
ULTRAGEL II Batch No.:
05125 Temp. Tool Mfg.:
D.A.S Serial No.:
MCNDE32021 Surface Temp.:
68
°F 7
//
Cal. Report No.:
CAL 157, CAL-06-158, CAL-06-159, CAL-06-160 Angle Used 0
45 45T 60 60T 60L Scanning dB 49 59 64 79 Indication(s):
Yes []
No wj Scan Coverage:
Upstream [
Downstream RJ CW R CCW R Comments:
FC 06-02 Results:
Accept [
Reject R Info E_
Percent Of Coverage Obtained > 90%:
No - 70.8 %
Reviewed Previous Data:
Yes
/37 - 6W/- 1)6~/
7Ye*//A-/~~~J7 '4/
. Duke
- Enew Determination of Percent Coverage for UT Examinations - Vessels Site/Unit: Catawba /
2 Summary No.:
B12.040.002B Workscope:
IsI Procedure:
Procedure Rev.:
Work Order No.:
NDE-3630 0
98732469 Outage No.:
CNS2-14 Report No.:
UT-06-162 Page:
2 of 8
0 degt Planar Scan 45 deg Scan 1 Scan 2 Scan 3 Scan 4
% Length X
% Length X
% Length X
% Length X
% Length X
% volume of length 1 100 =
% vol~me of length / 100 =
% volume of length / 100 =
% volume of length / 100 =
% volume of length / 100 =
% total for 0 deg
% total for Scan 1
% total for Scan 2
% total for Scan 3
% total for Scan 4 Add totals and divide by # scans =
% total for 45 deg Other deg 450/600 Scan 1 100.000
% Length X Scan 2 100.000
% Length X Scan 3 100.000
% Length X Scan 4 100.000
% Length X Add totals and divide by # scans =
37.100
% volume of length / 100 =
95.600
% volume of length / 100 =
75.300
% volume of length / 100 =
75.300
% volume of length / 100 =
70.825
%total for 450/60* deg 37.100
% total for Scan 1 95.600
% total for Scan 2 75.300
% total for Scan 3 75.300
% total for Scan 4 Percent complete coverage Add totals for each angle and scan required and divide by # of angles to determine; 70.825
% Total for complete exam Note:
Supplemental coverage may be achieved by use of ther angles / methods. When used, the coverage for volume not obtained with angles as noted above shall be calcul ted and added to the total to provide the percent total for the complete examination.
Site Field Supervisor:
A Date:
L* I A 10(
SI' I I
DUKE POWER COMPANY ISI LIMITATION REPORT Component/Weld ID:
2ND-37A Item No:
B12.040.002B remarks:
Li NO SCAN SURFACE BEAM DIRECTION Valve Bonnett Configuration
[
LIMITED SCAN 1
[:] 2 E]
1 2
icw iccw FROM L N/A to L N/A INCHES FROM WO
-0.8 to Beyond ANGLE:
Li 0 Z 45 Li 60 other FROM o DEG to 360 DEG i
NO SCAN SURFACE BEAM DIRECTION Valve Body Configuration
[
LIMITED SCAN
[:I 1 Z
2 Z
1 0
2 L-cw
- cCw FROM L N/A to L N/A INCHES FROM WO
+2.0 to
+3.55 ANGLE:
i 0 [] 45 Z 60 other FROM o DEG to 360 DEG Li NO SCAN SURFACE BEAM DIRECTION Valve Body Configuration
[
LIMITED SCAN L-'
1 Z
2 Z
1
] 2 [1 cw
[-] ccw FROM L N/A to L N/A INCHES FROM WO
+2.0 to Beyond ANGLE:
E] 0 N 45 Li 60 other FROM o DEG to 360 DEG Li NO SCAN LIMITED SCAN SURFACE
-J 1
[]i2 BEAM DIRECTION
[L] 1 [:1 2 0 cw El ccw I= D " 11,A I fr% I INCHES FROM WO ANGLE:
0
[Li ]
0 45
[L 60/, ýt.er to DEG to DEG Sketch(s) attached Z
yes
[i-No FROM Prepared By:
Jay Eaton
<]-W\\
Level:
11, Date:
04/01/2006 Reviewed By:.Za.-4 A y'/o..Aho I II Date:
./
IAuthori
DUKE POWER COMPANY ISI LIMITATION REPORT Component/Weld ID:
2ND-37A Item No:
B12.040.002B remarks:
17 NO SCAN SURFACE BEAM DIRECTION Valve Bonnett Configuration Z
LIMITED SCAN
[1 E1 2
l' 1
[
2 [ cw E7 ccw FROM L N/A to L N/A INCHES FROM WO
-0.8 to Beyond ANGLE:
El 0 E 45 11 60 other FROM 0
DEG to 360 DEG i7 NO SCAN SURFACE BEAM DIRECTION 17 LIMITED SCAN I-1 2
Ei 1 2 E cw Dccw FROM L to L INCHES FROM WO to ANGLE:
RJ 0 FJ 45
[] 60 other FROM DEG to DEG F1 NO SCAN SURFACE BEAM DIRECTION ZLIMITED SCAN Ei 1 N
2 Z i1
[] 2 EI cw
[-1 ccw FROM L to L INCHES FROM WO to ANGLE:
F] 0 E] 45
[] 60 other FROM DEG to DEG E1 NO SCAN SURFACE BEAM DIRECTION Li LIMITED SCAN Mi 1 E-12 D-1
[7 2
[-7 Cw
[:ccw FROM L to L INCHES FROM WO to Sketch(s) attached ANGLE:
[] 0 45
[1 60 /-\\t DEG to DEG r
FROM Z
yes El No Prepared By:
I
Item No: B12.040.002B Weld No: 2ND-37A Total Exam Area = 7.69 sq. in.
Valve Bonnet S1 Valve Body S2 Inspector / Date:
Page 5 of J5
Item No. B12.040.002B Weld No: 2ND37A 450 Axial Scan coverage from S I = 2.85 sq. in.
% Coverage = 2.85 / 7.69 x 100 = 37.1%
450 Valve Bonnet Si Valve Body S2 Pv Inspector / Date:
Page 0o of B
Item No. B12.040.002B Weld No: 2ND-37A Combination of 45' & 60' Axial Scan coverage from S2 = 7.35 sq. in.
% Coverage = 7.35 / 7.69 x 100 = 95.6%
600 450
,- U\\r Valve Bonnet S1 Ou-Valve Body S2 Inspector / Date:
qicc~
Inspector / Date:
4 Page -7 of B
Item No: B12.040.002B Weld No: 2NO-37A 450 Circ. Scan coverage S3 & S4 = 5.79 sq. in.
% Coverage = 5.79 / 7.69 x 100 = 75.3%
Valve Bonnet S1
'1/4 I.
ICC Valve Body S2 K~C
<>'1/4' Inspector / Date:
Lý I I I I'D Page S of J5
Request for Relief 07-CN-001 Attachment B Weld 2ND24 - 16 Number of Pages = 2
mob-L UT Pipe Weld Examination Site/Unit: Catawba /
Summary No.:
Co Workscope:
2 5.011.077 ISI Procedure:
Procedure Rev.:
Work Order No.:
NDE-600 16 98761111 Outage No.:
CNS2-14 Report No.:
UT-06-061 Page:
1 of 2
Code:
Asme Section Xl 1989 Cat./Item:
C-F-1/C5.11.77 Location:
Drawing No.:
CN-2ND-24
==
Description:==
Pipe to Flange System ID:
ND Component ID: C05.011.077 /2ND24-16 Size/Length:
N/A Thickness/Diameter:
.375/12.0 Limitations:
Yes-See Attached Limitation Report Start Time:
1022 Finish Time:
1036 Examination Surface:
Inside D-Outside r]
Surface Condition: AS GROUND Lo Location:
9.1.1.1 Wo Location:
Centerline of Weld Couplant:
ULTRAGEL II Batch No.:
03125 Temp. Tool Mfg.:
D.A.S Se'ial.No.:
/
MCNDE3,2821 Surface Temp.:
80 OF 7/
/
V/
Cal. Report No.:
CAL-06-082, CAL-06-083, CAL-06-084 Angle Used 0
45 45T 60 70 Scanning dB 40 48 49 Indication(s):
Yes []
No 7]
Scan Coverage:
Upstream [
Downstream D CW [
CCW I]
Comments:
FC 05-08 Results:
Accept P]
Reject D]
Info []
Percent Of Coverage Obtained > 90%:
No-62.5%
Reviewed Previous Data:
Yes Examiner Level 11 nat Date Reviewer Signature Date L eeper, W in fred C.
--,Z
.f.
t_...
3115/2006
-2_5-*/
Eaier Level,.-
ignatue*
Date Site Review Signature Date Griebel, David M.
3/15/2006 N/A Other Level N/A Signature
/
Date ANII Rev' w nature
/
Date N/A
ýJop
,TVAx v1U. CM1'1J-PAW4-A'U 700 Shear Pipe - S2 Coverage Claimed = 50%
Flange - S1 No Coverage Claimed Supplemental coverage with 700 Shear Wave Only See Note:
Scale: I"= "
Note: 70' shear scan not included in percentage coverage due to requirements of I0CFR50.55a(b)(2)(xv)(A)(1). Best effort scan with 70 shear obtained 50% coverage in one axial direction.
No scan with the 60" shear from the Surface 1 side of the weld due to flange configuration.
Limited 0' to 360' from the weld C/L + 0.85" and beyond.
Pipe 0 = 12.75
'T' =
0.375 1/3 "t" =
0.13 Weld Length =
Weld + 1/4" ea. Side Flange = Surface 1 Pipe = Surface 2 Total Exam Volume (Weld + 1/4" ea. Side) x 1/3 "t" x Weld Length 40.1 5.21 in 3 1.00 Aaareaate Cover&uae CalcuI3tion at ov r
a Cal...
at....
S1 = Flange S2 = Pipe 83 = CW S4 = CCW 0%
50 %
100 %
ý!22 %
( 0% of the Length x 0% of the Volume)
( 100% of the Length x 50% of the Volume)
( 100% of the Length x 100% of the Volume)
( 100% of the Length x 100% of the Volume)
Total =
250 + 4 =
62.5%
Aggregate Coverage r1t9 3zofot..
Inspector / Date:
Report No. UT-06-061 Page 2 of 2 Request for Relief 07-CN-002
Relief Request 07-CN-002 Page 1 of 11 Relief Request 07-CN-002 Proposed Relief in Accordance with 10 CFR 50.55a(g)(5)(iii)
Inservice Inspection Impracticality Duke Energy Corporation Catawba Nuclear Station - Unit 2 (EOC-14)
Third 10-Year Interval - Inservice Inspection Plan Interval Start Date = 10-15-2005 Interval End Date = 8-19-2016 This Relief Request has three (3) welds for which relief is being sought.
The ID's and Item / Summary Numbers for the three (3) welds are as follows:
List Number Weld ID Item / Summary Numbers
- 1.
2NI55-11 B09.011.165
- 2.
2NI55-8 B09.011.171
- 3.
2NV12-10 C05.021.209 Attachment A contains the inspection data for Weld ID 2NI55-1 1.
Attachment B contains the inspection data for Weld ID 2NI55-8.
Attachment C contains the inspection data for Weld ID 2NV12-10.
Items in this relief request were examined during March, 2006.
ASME Code Component Affected Weld ID = 2NI55-11 Item / Summary Number = B09.011.165 Safety Injection System (NI)
NI System Valve 2NI081 to Pipe Circumferential Weld II.
Applicable Code Edition and Addenda
ASME Section XI Code - 1998 Edition thru the 2000 Addenda Code Case N-460 is applicable
Relief Request 07-CN-002 Page 2 of 11 II.
Applicable Code Requirement
Table IWB-2500-1, Examination Category B-J Item / Summary Number B9.11 Figure IWB-2500-8 (c), 100% Volume Coverage of Examination Volume C-D-E-F Code Case N-460, Greater than 90% Volume Coverage of Examination Volume C-D-E-F IV. & V. Impracticality/Burden Caused by Code Compliance The valve and pipe material is stainless steel. This weld has a diameter of 10.75 inches and a wall thickness of 1.0 inch. During the ultrasonic examination of this weld, 37.50%
coverage of the required examination volume was obtained. The percentage of coverage represents the aggregate coverage from all scans performed on the weld and adjacent base material. The coverage from each scan was as follows: 450 shear wave circumferential scans, both clockwise and counter-clockwise covered 50% of the weld and base material; 60' shear wave scan from the pipe side perpendicular to the weld covered 50% of the weld and base material. In accordance with Duke Energy Procedure NDE-91, scan areas S1 and S2 are defined as scans perpendicular to the weld and scan areas S3 and S4 are the clockwise and counter-clockwise scans parallel to the weld. A supplemental scan using a 600 refracted longitudinal wave search unit covered 50% of the examination volume on the valve side from one direction perpendicular to the weld but is not included in the coverage calculations because of the requirements of 10CFR50.55 a (b)(2)(xv)(A)(1) which mandates scanning from four directions. The limitation was caused by the taper on the valve side of the weld which did not allow placement of the search unit on that side of the weld. In order to scan all of the required volume for this weld, the valve would have to be redesigned 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 is shown in Attachment A)
VI.
Alternate Examinations or Testing No alternative examinations or testing for the scheduled weld inspection were performed.
VII. Implementation Schedule and Duration No alternative examinations are planned for the weld during the current inspection interval.
VIII. Justification for Granting Relief Ultrasonic examination of the weld for Item / Summary Number B09.011.165 was conducted using personnel, qualified in accordance with ASME Section XI, Appendix VII.
The ultrasonic procedures and equipment complied with the requirements of ASME Section XI, Appendix VIII as administered by the Performance Demonstration Initiative
Relief Request 07-CN-002 Page 3 of 11 (PDI), 1998 Edition through the 2000 Addenda. In addition, a dye penetrant examination was performed on the weld in accordance with the ASME Section XI. No recordable or reportable indications were found. Based on the following justification, the amount of coverage obtained for this examination provides an acceptable level of quality and integrity assurance.
The piping containing weld 2NI55-11 is an ASME 111, Class 1 line with a design temperature of 650'F and a design pressure of 2500 psia. The weld is located inside the Unit 2 Containment. The piping line connects the cold leg accumulator 2C to the reactor coolant system and also ties the residual heat removal (RHR) pump discharge header back to the reactor coolant loop (RCL) cold leg 2C. As such, the primary function of this piping is to serve as part of the flow path that a) supplies emergency core cooling system (ECCS) injection from the NI and RHR systems to the RCL during accident conditions and b) provides core decay heat removal during shutdown / startup operations. This line is normally stagnant during normal plant operation.
Weld 2NI55-11 is a circumferential butt weld just upstream of valve 2NI8 1. The weld is between valve 2NI81 and a section of 10", schedule 140 pipe. The valve body material is SA182 F316 and the attached piping is SA376 TP316.
These materials are austenitic (16Cr-1 2Ni-2Mo for TP316 and F316), base materials and a) have a high corrosion resistance with low contribution of corrosion products to the coolant, b) have good mechanical properties and c) are highly weldable. Very few service induced problems with stainless steel in pressurized water reactor (PWR) primary system applications have been observed in operating plants. There has been limited susceptibility to stress corrosion cracking (SCC) due to chloride contamination and cracking in stagnant borated systems. Chemistry limits on chlorides, fluorides and sulfides and dissolved oxygen are controlled by Selected Licensee Commitment (SLC) and other administrative procedures at Catawba to ensure that any favorable conditions for SCC are precluded.
Additionally, controls on welding filler material consistent with Regulatory Guide 1.31 also have served to limit the susceptibility of these welds to SCC. No other known degradation mechanisms are applicable to this material at this particular location within the system.
This piping is not insulated. During each refueling outage, multiple walkdowns of containment are performed to determine the presence of external leakage. These walkdowns include a boric acid walkdown (PT/2/A/4150/OO1H) while the primary system remains at temperature and pressure (Mode 3). Other walkdowns performed during the outage are system engineer walkdowns (PEP 3.09), operation walkdowns at 350 psi, 1000 psi and normal operation pressure (OP/2/A/6100/001) and the ASME XI, IWA 5000, system leakage test. During these various walkdowns, any leakage from this weld would be recognized by active leakage or boron deposit buildups around the valve and piping.
In addition, leakage during operation at the weld location would be detected by various leakage detection systems available to the operator. The primary detection method at this location is the Containment Floor and Equipment Sump Level Monitors where unidentified accumulated water on the containment floor would be monitored and
Relief Request 07-CN-002 Page 4 of 11 evaluated as sump level changes. Leakage would also be promptly identified through a continuous decline in the Cold Leg Accumulator level.
These walkdowns and leakage detection systems provide a high level of confidence that any leakage would be promptly identified at this welded joint inside containment. As a result, the limited volumetric coverage associated with this particular weld has no significant impact on the continued assurance of structural integrity of the piping.
References:
- 1) Weld Isometric CN-2NI-055
- 2) Piping Isometric CN-2491-NII 15
- 3) Flow Diagram CN-2562-1.1
Relief Request 07-CN-002 Page 5 of 11 I.
ASME Code Component Affected Weld ID = 2NI55-8 Item / Summary Number = B09.011.171 Safety Injection System (NI)
NI System Pipe to Tee Circumferential Weld II.
Applicable Code Edition and Addenda
ASME Section XI Code - 1998 Edition thru the 2000 Addenda Code Case N-460 is applicable III.
Applicable Code Requirement
Table IWB-2500-1, Examination Category B-J Item / Summary Number B9.11 Figure IWB-2500-8 (c), 100% Volume Coverage of Examination Volume C-D-E-F Code Case N-460, Greater than 90% Volume Coverage of Examination Volume C-D-E-F IV. & V. Impracticality/Burden Caused by Code Compliance The tee and pipe material is stainless steel. This weld has a diameter of 6.375 inches and a wall thickness of 0.719 inch. During the ultrasonic examination of this weld, 62.50%
coverage of the required examination volume was obtained. The percentage of coverage represents the aggregate coverage from all scans performed on the weld and adjacent base material. The coverage from each scan was as follows: 450 shear wave circumferential scans, both clockwise and counter-clockwise covered 100% of the weld and base material; 600 shear wave scan from the pipe side perpendicular to the weld covered 50% of the weld and base material. In accordance with Duke Energy Procedure NDE-91, scan areas S 1 and S2 are defined as scans perpendicular to the weld and scan areas S3 and S4 are the clockwise and counter-clockwise scans parallel to the weld. A supplemental scan using a 600 refracted longitudinal wave search unit covered 50% of the examination volume on the tee side from one direction perpendicular to the weld but is not included in the coverage calculations because of the requirements of IOCFR50.55 a (b)(2)(xv)(A)(1) which mandates scanning from four directions. The limitation was caused by the radius on the tee side of the weld which prevented placement of the search unit on that side of the weld. In order to scan all of the required volume for this weld, the tee would have to be redesigned 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 is shown in Attachment B)
Relief Request 07-CN-002 Page 6 of 11 VI.
Alternate Examinations or Testing No alternative examinations or testing for the scheduled weld inspection were performed.
VII.
Implementation Schedule and Duration No alternative examinations are planned for the weld during the current inspection interval.
VIII. Justification for Granting Relief Ultrasonic examination of the weld for Item / Summary Number B09.011.171 was conducted using personnel qualified in accordance with ASME Section XI, Appendix VII.
The ultrasonic procedures and equipment used complied with the requirements of ASME Section XI, Appendix VIII as administered by PDI, 1998 Edition through the 2000 Addenda. In addition, a dye penetrant examination was performed on the weld in accordance with the ASME Section XI. No recordable or reportable indications were found. Based on the following justification, the amount of coverage obtained for this examination provides an acceptable level of quality and integrity assurance.
The piping containing weld 2NI55-8 is an ASME III, Class 1 line with a design temperature of 650'F and a design pressure of 2500 psia. The weld is located inside the Unit 2 Containment. This piping line connects the cold leg accumulator 2C to the reactor coolant system and also ties the RHR pump discharge header back to the RCL cold leg 2C.
As such, the primary function of this piping is to serve as part of the flow path that a)
.supplies ECCS injection from the NI and RHR systems to the reactor coolant loop during accident conditions and b) provides core decay heat removal during shutdown / startup operations. This line is normally stagnant during normal plant operation.
Weld 2NI55-8 is a circumferential butt weld on a 6" schedule 160 line between valves 2NI81 and 2NI82. The weld is between a 10" x 10" x 6" seamless, reducing tee and 6" schedule 160 piping. The tee material is SA403 WP316 and the piping is SA376 TP304.
These materials are austenitic (16Cr-12Ni-2Mo for WP316, 18Cr-8Ni for TP304) base materials and a) have a high corrosion resistance with low contribution of corrosion products to the coolant, b) have good mechanical properties and c) are highly weldable.
Very few service induced problems with stainless steel in PWR primary system applications have been observed in operating plants. There has been limited susceptibility to stress corrosion cracking due to chloride contamination and cracking in stagnant borated systems. Chemistry limits on chlorides, fluorides and sulfides and dissolved oxygen are controlled by Selected Licensee Commitment (SLC) and other administrative procedures at Catawba to ensure that any favorable conditions for SCC are precluded. Additionally, controls on welding filler material consistent with Regulatory Guide 1.31 also have served to limit the susceptibility of these welds to SCC. No other known degradation mechanisms are applicable to this material at this particular location within the system.
Relief Request 07-CN-002 Page 7 of 11 This piping is normally covered by metal reflective insulation. During each refueling outage, multiple walkdowns of containment are performed to determine the presence of external leakage. These walkdowns include a boric acid walkdown (PT/2/A/4150/001H) while the primary system remains at temperature and pressure (Mode 3). Other walkdowns performed during the outage are system engineer walkdowns (PEP 3.09),
operation walkdowns at 350 psi, 1000 psi and normal operation pressure (OP/2/A/6100/001) and the ASME XI, IWA 5000, system leakage test. During these various walkdowns, any leakage from this weld would be recognized by active leakage or boron deposit buildups around the valve and mirror insulation.
In addition, leakage during operation (assuming leakby of the primary isolation valve, 2N182) at the weld location would be detected by various other leakage detection systems available to the operator. (Note: without leakby of the primary isolation valve, leakage would be promptly identified through a continuous decline in the Cold Leg Accumulator level.) These systems identified with plant technical specifications include:
a)
Containment Atmosphere Particulate Radioactivity (EMF 38) Monitor which would detect airborne radiological activity; b)
Containment Ventilation Unit Condensate Drain Tank Level Monitor which collects and measures as unidentified leakage the moisture removed from the containment atmosphere; c)
Containment Floor and Equipment Sump Level Monitors where unidentified accumulated water on the containment floor would be monitored and evaluated as sump level changes.
d)
A reactor coolant system water inventory balance is performed on a regular basis (i.e. at least once every three days). The normal operating practice is to perform this computer based program on a daily frequency and/or whenever the operators suspect any abnormal changes to other leakage detection systems. A Plant Technical Specification requires system leakage from "unidentified" sources be maintained below I gpm; however, plant operation procedure (PT/1(2)/A/4150/001D, NC System Leakage Calculation) establishes an administrative limit of 0.15 gpm above which the source of leakage will be investigated. Leakage as a result of a failed weld discussed in this section would show up as unidentified leakage and subject to the 0.15 gpm administrative limit.
Other leakage detection systems available to the operator include 1) Volume Control Tank (VCT) level changes, 2) VCT make-up frequencies and 3) Cold Leg Accumulator level changes.
These walkdowns and leakage detection systems provide a high level of confidence that any leakage would be promptly identified at this welded joint inside containment. As a result, the limited volumetric coverage associated with this particular weld has no significant impact on the continued assurance of structural integrity of the piping.
Relief Request 07-CN-002 Page 8 of 11
References:
- 1) Weld Isometric CN-2NI-055
- 2) Piping Isometric CN-2491-NI115
- 3) Flow Diagram CN-2562-1.1
Relief Request 07-CN-002 Page 9 of 11
- 1.
ASME Code Component Affected Weld ID = 2NV12-10 Item / Summary Number = C05.021.209 Chemical and Volume Control System (NV)
NV System Tee-to-4x3 Reducer Circumferential Weld II.
Applicable Code Edition and Addenda
ASME Section XI Code - 1998 Edition thru the 2000 Addenda Code Case N-460 is applicable III.
Applicable Code Requirement
Table IWC-2500-1, Examination Category C-F-1 Item / Summary Number C5.21 Figure IWC-2500-7 (a), 100% Volume Coverage of Examination Volume C-D-E-F Code Case N-460, Greater than 90% Volume Coverage of Examination Volume C-D-E-F IV. & V. Impracticality/Burden Caused by Code Compliance The tee and reducer material is stainless steel. This weld has a diameter of 4.5 inches and a wall thickness of 0.531 inch. During the ultrasonic examination of this weld, 78.70%
coverage of the required examination volume was obtained. Coverage was limited on the tee side for 8 inches of weld length. There were no limitations on the reducer side of the weld. The percentage of coverage represents the aggregate coverage from all scans performed on the weld and adjacent base material. The coverage from each scan was as follows: 450 shear wave circumferential scans, both clockwise and counter-clockwise covered 100% of the weld and base material; 600 shear wave scan from the reducer side perpendicular to the weld covered 71.60% of the weld and base material in two directions; 600 shear wave scan from the tee side where access was available covered 43.30% of the weld and base material in two directions and 56.74% in one direction. In accordance with Duke Energy Procedure NDE-9 1, scan areas S 1 and S2 are defined as scans perpendicular to the weld and scan areas S3 and S4 are the clockwise and counter-clockwise scans parallel to the weld. A supplemental scan using a 600 refracted longitudinal wave search unit covered 50% of the examination volume on the tee side from one direction perpendicular to the weld in the obstructed areas but is not included in the coverage calculations because of the requirements of I OCFR50.55 a (b)(2)(xv)(A)(1) which mandates scanning from four directions. The limitation was caused by the radius on the tee side of the weld which prevented placement of the search unit on that side. In order to scan all of the required volume for this weld, the tee would have to be redesigned 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 is shown in Attachment C)
Relief Request 07-CN-002 Page 10 of 11 VI.
Proposed Alternate Examinations or Testing No alternative examinations or testing for the scheduled weld inspection were performed.
VII.
Implementation Schedule and Duration No alternative examinations are planned for the weld during the current inspection interval.
VIII. Justification for Granting, Relief Ultrasonic examination of the weld for Item / Summary Number C05.021.209 was conducted using personnel qualified in accordance with ASME Section XI, Appendix VII.
The ultrasonic procedures and equipment used complied with the requirements of ASME Section XI, Appendix VIII as administered by PDI, 1998 Edition through the 2000 Addenda. In addition, a dye penetrant examination was performed on the weld in accordance with the ASME Section XI. No recordable or reportable indications were found. Based on the following justification, the amount of coverage obtained for this examination provides an acceptable level of quality and integrity assurance.
Weld 2NV12-10 is between a 4" schedule 160 butt welded tee and a 4" x 3" concentric reducer.
The weld is downstream of the Centrifugal Charging (NV) Pump 2B on ASME Class 2 piping with a design temperature of 250'F and design pressure of 2750 psia. The pipe containing this weld is located in the auxiliary building and is pressurized during normal operation. This weld maintains the pressure boundary as part of normal charging flowpath and the ECCS flow path under accident conditions.
The subject weld is between two seamless pipe fitting components made from SA403 WP304 material. This material is an austenitic (1 8Cr-8Ni) base material that a) has a high corrosion resistance with low contribution of corrosion products to the coolant, b) has good mechanical properties and c) is highly weldable. Very few service induced problems with stainless steel in PWR primary system applications have been observed in operating plants. There has been limited susceptibility to stress corrosion cracking due to chloride contamination and cracking in stagnant borated systems. Chemistry limits on chlorides, fluorides and sulfides are controlled by Selected Licensee Commitment (SLC) and other administrative procedures at Catawba to ensure that any favorable conditions for SCC are precluded. Additionally, controls on welding filler material consistent with Regulatory Guide 1.31 also have served to limit the susceptibility of these welds to SCC. No other known degradation mechanisms are applicable to this material at this particular location within the system.
This piping is not insulated and is located in Room 241 (NV2B Pump Room) on the 543 ft elevation of the auxiliary building. Leakage during normal operation would be seen as active leakage due to low fluid temperature conditions and readily identified on the 543 ft floor elevation below. The room is accessible during normal operation and is within the
Relief Request 07-CN-002 Page 11 of 11 scope of daily operation walkdowns. Periodic system engineer walkdowns are also performed that include leakage identification on the NV system.
In addition to walkdowns, this weld location is part of the NC system mass balance performed daily. An operational leak rate test (PT/2/A/4206/006) for the NV system is also performed with the system pressurized on an eighteen month frequency. Furthermore, an ASME XI, IWA-5000 system leakage test is also performed every ISI period. Any of these tests would identify leakage at this particular weld.
These walkdowns and leakage tests provide a high level of confidence that any leakage would be promptly identified at this welded joint in the NV2B Pump room of the Auxiliary Building. As a result, the limited volumetric coverage associated with this particular weld has no significant impact on the continued assurance of structural integrity for the NV piping.
References:
- 1) Weld Isometric CN-2NV-012
- 2) Piping Isometric CN-2492-NV076
- 3) Flow Diagram CN-2554-1.7 IX.
Other Information The following individuals contributed to the development of this relief request:
James J. McArdle (Principal UT NDE Level UI Examiner) provided Sections M11.,
IV, V, VI, VII and part of Section VII.
W.O. Callaway (Catawba Engineering) provided part of Section VIII.
Andy Hogge (Catawba ISI Plan Manager) compiled the remaining sections.
Request for Relief 07-CN-002 Attachment A Weld 2NI55-11 Number of Pages = 3
Pohirrgy.
UT Pipe Weld Examination Site/Unit: Catawba /
Summary No.:
BO 2
9.011.165 Procedure:
Procedure Rev.:
NDE-600 16 Outage No.:
CN2-14-1 Report No.:
UT-06-075 Workscope:
IS1 Work Order No.:
98738253 Page:
1 of 3
Code:
1998 thru 2000 Addenda Cat/Item:
B-J-/B9.11.165 Location:
Drawing No.:
CN-2NI-55
==
Description:==
VLV 2NI081 to Pipe System ID:
NI Component ID: B09.011.165 /2N155-11 Size/Length:
N/A Thickness/Diameter:
1.0/10.0 Limitations:
Yes-See Attached Limitation Report Start Time:
1222 Finish Time:
1332 Examination Surface:
Inside
- Outside [
Surface Condition: AS GROUND Lo Location:
9.1.1.1 Wo Location:
Centerline of Weld Couplant:
ULTRAGEL II Batch No.:
05125 Temp. Tool Mfg.:
D.A.S Serial No.:
MCNDE32821 Surface Temp.:
68 OF Cal. Report No.:
CAL-06-100, CAL-06-101, CAL-06-102 Angle Used 0
45 45T 60 60L Scanning dB 39 41 55 Indication(s):
Yes D No F/
Scan Coverage:
Upstream*
Downstream CW [
CCW M
Comments:
3f-A o FC 05-08 Results:
Accept [
Reject rD Info D Percent Of Coverage Obtained > 90%:
No-37.5%
Reviewed Previous Data:
Yes Examiner Level I,-N Sigature Date Reviewer Signature Date Mauldin, Larry E.
oo 3/23/2006--1 I.
Examiner Level 1-N Date Site ReviewSignature I
IDate Griebei, David M.
3/23/2006 N/A Other Level N/A Signature Date ANII Revie, I natur/
/,,
Date N/A/1
-4A{
i 7
C XC_';471e e) - `V t-)402
item iNo. im".uii.io3 Weld No. 2N155-11 Coverage Claimed = 50%
No Coverage Claimed Supplemental coverage with 60O RL Wave Only See Note:
Scale: V' = l" Note: 600 RL scan not included in percentage coverage due to requirements of IOCFR50.55a(b)(2)(xv)(A)(l). Best effort scan with 60' RL obtained 50% coverage in one axial direction.
Pipe 0 = 10.75
=
1.0 1/3 "t" =
033 Weld Length =
33.8 Weld + 1/4" ea. Side =
1.70 Valve = Surface 2 Pipe = Surface 1 Total Weld Volume
= (Weld + 1/4" ea. Side) x 1/3 "t" x Weld Length
=-
18916Ž in3 Aqgqregate Coverage Calculation S2 =
SI =
S3 =
S4=
50 %
%50
.50 %
150 - 4 (0% of the Length x 0% of the Volume )
(100% of the Length x 50% of the Volume )
(100% of the Length x 50% of the Volume )
(100% of the Length x 50% of the Volume )
37.5%
Aggregate Coverage Total =
Inspecto I Dae 37LO 1CL o~
Inspector / Date:
01.1
?AkKc Z or-3
DUKE POWER COMPANY ISI LIMITATION REPORT Component/Weld ID:
2NI55-11 Item No:
B09.011.165 remarks:
NO SCAN SURFACE BEAM DIRECTION Due to Valve Configuration Z
LIMITED SCAN.
-1 2
Z
- 1. [:] 2 X cw ccw FROM L N/A to L N/A INCHES FROM WO 1.5" to Beyond ANGLE:
E] 0 0 45 Z 60 other FROM 0
DEG to 360 DEG L-NO SCAN SURFACE BEAM DIRECTION El LIMITED SCAN 01
[E1 2 E]l
[1 2 E] cw [] ccw FROM L to L INCHES FROM WO to ANGLE:
El 0 E1 45 rl 60 other FROM DEG to DEG E-NO SCAN SURFACE BEAM DIRECTION D
LIMITED SCAN E] 1 E
2 l1
] 2
[-] cw
- ccw FROM L to L INCHES FROM WO to ANGLE:
El 0 El 45 E] 60 other FROM DEG to DEG E
NO SCAN SURFACE BEAM DIRECTION El LIMITED SCAN 1
E] 2 l1 El2 cw lccw FROM L to L INCHES FROM WO to Sketch(s) attached ANGLE:
E] 0 El 45
[E]/0 other FROM DEG to DEG E] yes Z
No Prepared By:
Larry Mauldin Level:
II Date:
03-23-2006 Sheet 3 of 3
Reviewed By:
Date:
Authoriz d Inspector:
Date:
{
J4Jl9-
":5
- ZI*[~-
I gt(-
- /wai.F*Date Si I
Request for Relief 07-CN-002 Attachment B Weld 2NI55-8 Number of Pages = 3
Duke t Eergy.
UT Pipe Weld Examination Site/Unit: Catawba /
Summary No.:
so Workscope:
2 9.011.171 ISl Procedure:
Procedure Rev.:
Work Order No.:
NDE-600 16 98738253 Outage No.:
CN2-14-1 Report No.:
UT-06-072 Page:
1 of
_2 Code:
1998 thru 2000 Adde Drawing No.:
CN-2NI System ID:
NI Component ID: B09.011.171 /2NI55-8 Limitations:
Yes-See Attached Lin nda
-55 Cat./Item:
B-J- /B9.11.171
==
Description:==
Pipe to Tee Location:
9?L 31 t% 10(1.
Size/Length iitation Report N/A Start Time:
1234 Thickness/Diameter:
.719/ 6.0 Finish Time:
1307 Examination Surface:
Lo Location:
Inside LA]
9.1.1.1 Outside []
Wo Location:
Surface Condition: GROUND Centerline of Weld Couplant:
ULTRAGEL II Batch No.:
05125 Temp. Tool Mfg.:
D.A.S Serial No.:
MCNDE32821 Surface Temp.:
68 OF Cal. Report No.:
Angle Used 0
Scanning dB Indication(s):
Yes []
Comments:
FC 05-08 CAL-06-091, CAL-06-092, CAL-06-093
- 45 45T 60 60L 45 50 60 No Fv Scan Coverage:
Upstream [,I Downstream [
CW 01/
CCW ov Results:
Accept W Reject n]
Percent Of Coverage Obtained > 90%:
Info Reviewed Previous Data:
Yes Exaine LD e
Examiner Level II Signature Date iReviewer Signature Date Resor, James H.
z__..
31320
=0:
- 3) zaeISt eiwt intr Examiner Level 11-N S.
Date SieRve intr Cochran, Lonnie D.
3/23/2006 N/A Other Level N/A Signature Date ANII R eiew ignature.
Date N/AV
/& /,,0-4!: 7'-,,_ -
e>&ý 606 2 Ar
ý/ w - /$/&/7ý
ý:5 U.
% Coverage Calculations Item No.: B09.011.171 Weld No. : 2NI55-8 Pipe 0 = 6.625 1=
0.719 1/3 "t" =
0.24 Weld Length =
20.8 Weld + 1/4" ea. Side = 1.70 Total Exam Volume 1.00%
= (Weld + 1/4" ea. Side) x 1/3 "t" x Weld Length
=
8.49 in 3 No scan with the 600 shear wave axial from the Surface 1 side of the weld due to the Tee configuration.
Aqqregate Coverage Calculation S1 = Tee 0%
S2 = Pipe 50%
S3 = CW 100%
S4 =CCW 100%
Total=
250 4=
(0% of the Length x 0% of the Volume )
(100% of the Length x 50% of the Volume)
(100% of the Length x 100% of the Volume )
(100% of the Length x 100% of the Volume )
62.5%
Aggregate Coverage Inpco ae31C 3 'týoq Page
.. of Inspector / Date:
600 RLWave 600 Shear Pipe S2 Coverage Claimed = 50%
Tee S1 Scale : 1"= 1" No Coverage Claimed Supplemental coverage with 600 RL Wave Only See Note:
Note: 60' RL scan not included in percentage coverage due to requirements of IOCFR50.55a(b)(2)(xv)(A)(1). Best effort scan with 600 RL obtained 50% coverage in one axial direction.
Side View - Not to Scale Surf. 2 Surf. 1 Weld 2NM55-8 Plan View - Not to Scale No scan with the 600 axial from the Surface 1 side of the weld due to the Tee configuration.
4o / Dat :
- -ge"o Inspector / Date :
Pav-e S of 3
Request for Relief 07-CN-002 Attachment C Weld 2NV12 - 10 Number of Pages = 4
P~hVPe~rgy.
Site/Unit: Catawba I Summary No.:
CO Workscope:
UT Pipe Weiu Examination 2
5.021.209 Procedure:
Procedure Rev.:
Work Order No.:
NDE-600 16 98761101 Outage No.:
CN2-14-1 Report No.:
UT-06-029 Page:
1 of 3
ISl Code:
1998 thru 2000 Addenda Cat./item:
C-F-11C5.21.209 Location:
Drawing No.:
CN-2NV-12
==
Description:==
Tee to 4X3 Reducer System ID:
NV Component ID: C05.021.209 /2NV12-10 Size/Length:
NIA Thickness/Diameter:
.53114.0 Limitations:
Yes - See Attached Limitation Reports Start Time:
1521 Finish Time:
1528 Examination Surface:
Inside D Outside []
Surface Condition: AS GROUND Lo Location:
9.1.1.1 Wo Location:
Centerline of Weld Couplant:
ULTRAGEL II Batch No.:
05125 Temp. Tool Mfg.:
D.A.S Serial No.:
MCNDE32821 Surface Temp.:
77
'F Cal. Report No.:
CAL-06-057, CAL-06-058 Angle Used 0
45 145T 60 Scanning dB 45 48.5 Indication(s):
Yes E]
No W Scan Coverage:
Upstream Dv Downstream W CW S/1 CCW E]
Comments:
FC 05-08 Results:
Accept V Reject D Info R_
Percent Of Coverage Obtained > 90%:
No-78.7%
Reviewed Previous Data:
Yes Examiner Level II 1
ur Date Reviewer Signature Date Leeper, Winfred C.
3/1/2006 Examiner Level li-N S-goture-.
Date Site Review Signature Date Cochran, Lonnie D.
"'Zy-3/1/2006 N/A Other Level N/A Signature Date AN,.
iew Signature Date FN/A
<AJi 4 7 6W 62' C/
Item No. C05.021.209 Weld No. 2NV12-10 601 RLWave Scale: 1"= 1" Reducer Tee SI S2 No Coverage Claimed Coverage Claimed = 50% /
Supplemental coverage with 600 RL Wave Only See Note:
Note: 600 RL scan not included in percentage coverage due to requirements of IOCFR50.55a(b)(2)(xv)(A)(1). Best effort scan with 60' RL obtained 50% coverage in one axial direction.
Plan View - Not to Scale Surf. 1 Weld 2NV12-10 Limited Area Limited Area
/ŽI1Z1W, 11X>X-(1-7A Surf. 2 Side View - Not to Scale Limited 4" on ea. side of Tee Hi throat area for a total of 8". From Lo + 1.5" to 5.5" and from Lo + 8.5" to 12.5" on Surface 2. I
(ý,V, 1XT
-3111 o -
Inspector / Date :
Page Z. of 3 01
Item No. : C05.021.20' Pipe 0 = 4.5
"=
0.531 1/3 "t" =
0.18 Weld Length =
14.1 Weld + 1/4" ea. Side = 1.14 Length of Obstucted Area =
S1 - Reducer S2 - Tee S3 - CW S4 - CCW 9
% Coverage Calculations Total Exam Volume 100%
= (Weld + 1/4" ea. Side) x 1/3 '1T x Weld Length 2.79 in 3 0
% of Length not Examined 100%
8.00
= (Length of Obstucted Area) - (Weld Length) x 100 56.7%
% of Length Examined 100%
= 100% - % not Examined
=
43.3%
Aggregate % of Coverage
= % of Length Examined 100% + % of Length not Examined 100% -2
=
43.3 +
28.4 71.6%
= % of Length Examined 100% - % of Length not Examined 100%
=
100 56.7
=
43.3%
= 100% of Length Examined
= 100% of Length Examined
( S1 + S2 + S3 + S4) - 4
78.7 % Coverage Inspector / Date:
Page _3 of "75
OWnergy.
Site/Unit: Catawba /
Summary No.:
CO
%A/r rL, e rr~ no UT Pipe Weiu Examination 2
5.021.209 Procedure:
- Procedure Rev.:
~n..
rnr(frcr MnP a NDE-600 16 Outage No.:
CN2-14-1 Report No.:
UT-06-030 D
f
,-j O07&44n4 II Code:
1998 thru 2000 Addenda Cat./Item:
C-F-11C5.21.209 Location:
Drawing No.:
CN-2NV-12
==
Description:==
Tee to 4X3 Reducer System ID:
NV Component ID: C05.021.209 /2NV12-10 Size/Length:
N/A Thickness/Diameter:
.53114.0 Limitations:
Yes - See Attached Limitation Report Start Time:
1350 Finish Time:
1353 Examination Surface:
Inside D]
Outside []
Surface Condition: AS GROUND Lo Location:
9.1.1.1 Wo Location:
Centerline of Weld Couplant:
ULTRAGEL II Batch No.:
05125 Temp. Tool Mfg.:
D.A.S Serial No.:
MCNDE32821::
Surface Temp.:
77
-F Cal. Report No.:
CAL-06-059 Angle Used 0
45 45T 60 60L Scanning dB 48 Indication(s):
Yes F1 No []
Scan Coverage:
Upstream D Downstream []
FC 05-08 Results:
Accept []
Reject E]
Info []
Percent Of Coverage Obtained > 90%:
No-78.7%
Reviewed Previous Data:
Yes Examiner Level II
-i/'Sinabare Date Reviewe Signature Date Leeper, Winfred C.
3/2/2006 Examiner Level 11-N Date Site Review Signature Date Jolly, B. Dale 3/2/2006 N/A Other Level N/A Sign re Date: ANII Reyvw Signature Date FN/A 4/ý