ML052590564
| ML052590564 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 09/08/2005 |
| From: | Jamil D Duke Power Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 05-CN-004 | |
| Download: ML052590564 (91) | |
Text
Duke D.M. JAMIL r WPowere Vice President Duke Power Catawba Nuclear Station 4800 Concord Road / CN01 VP York, SC 29745-9635 803 831 4251 803 831 3221 fax September 8, 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-004 Limited Weld Examinations During End-of-Cycle 15 Refueling Outage Pursuant to 10 CFR 50.55a(g)(5)(iii), please find attached Request for Relief 05-CN-004. 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, D.M. Jamil LJR/s Attachment frcS Ali Catawba Nudear Station20th Anniversag www. dukepower. corn 1985-2005
Document Control Desk Page 2 September 8, 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
Request for Relief 05-CN004 Revision 0 Page 1 of 9 Proposed Relief in Accordance with 10 CFR50.55a(g)(5)(iii)
Inservice Inspection Impracticality Duke Energy Corporation Catawba Nuclear Station - Unit 1 (EOC-15)
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. II. Ill. IV. &V. VI. Vill. Vill.
Request Limited Weld System / Code Requirement from Impracticality/ Proposed Implementation Justification Number 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 IRPV.W03 Reactor Vessel Category B-A, Item Number See Paragraph "A" See Paragraph "G" See Paragraph "1I" See Paragraph Shell-to-Lower Head 101.01 1.001 Circumferential Weld Figure Number IWII-2500-1(b)
Volume Limitation 72.76%
(Attachment A) 2 IRPV`-WOI Reactor Vessel Category B-A, Item Number See Paragraph "A" See Paragraph "G" See Paragraph "`H" See Paragraph Lower Head to Bottom 1301.021.001 a Head Figure Number IWB-2500-3 Circumferential Weld Volume Limitation 87.19%
(Attachment B) 3 IPZR-WI Pressurizer Category Bl-D, Item Number See Paragraph "B" See Paragraph "G" See Paragraph "II" See Paragraph Surge Nozzle to Lower B03.1 t0.OOIA "A" Head Figure Number IWB-2500-7(b)
Volume Limitation 77.20%
(Attachment C) 4 l PZR-W4A Pressurizer Category B1D, Item Number See Paragraph "B" See Paragraph "G" See Paragraph "H" See Paragraph Safety Nozzle to Upper B03.1 10.004A T",
Head Figure Number IWB-2500-7(b)
Volume Limitation 79.20%
(Attachment D) 5 IPZR-W4B Pressurizer Category B-D, Item Number See Paragraph "B" See Paragraph "G" See Paragraph "H" See Paragraph Safety Nozzle to Upper B03.110.005 "."
Head Figure Number IWB-2500-7(b)
Volume Limitation 79.20%
._ (Attachment E)
Request for Relief 05-CN.004 Revision 0 Page 2 of 9
- r. II II. IV. &V. VI. Vll. Vill. l Request Limited System / Code Requirement from Impracticality/ Proposed Implementation Justification Number Weld Component for Which Which Relief is Requested: Burden Caused Alternate Schedule and for Granting I.D. Relief is Requested: 100% Exam Volume Coverage by Compliance Examinations Duration Relief Number Area or Weld to be Exam Category or Testing Examined Item No.
Fig. No.
Limitation Percentage 6 IPZR-W4C Pressurizer Category B-D, Item Number See Paragraph "B" See Paragraph "G" See Paragraph "H" See Paragraph 'J" Safety Nozzle to Upper Hlead B03.1 I0.00A Figure Number IWB-2500-7(b)
Volume Limitation 79.20%
(Attachment F) 7 IRPV-W18-SE Reactor Vessel Category B-F. Item Number See Paragraph "C"' See Paragraph "G" See Paragraph "H" See Paragraph "I" INC23-01 Outlet Nozzle to Safe End 1305.010.008, B05.010.008A and Safe- End to Pipe B05.130.005, B05.130.005A (Buttering Weld) Figure Number IWB-2500-8 (c)
Volume Limitation 82.45%
(Attachment G) 8 INC286-1 NC System Category 13-, Item Number B09.011.048 See Paragraph "D" See Paragraph "G" See Paragraph "H" See Paragraph "K" UHI Adapter to Pipe Cap Figure Number IWB-2500-8(c)
Volume Limitation 37.50%
(Attachment H) 9 IND-37A ND System Category B-M-l, Item Number See Paragraph "E" See Paragraph "G" See Paragraph "`I' See Paragraphs "L" Valve IND-37A Valve Body B12.040.002D to Bonnet Weld Figure Number IWB-2500-17 Volume Limitation 69.30%
(Attachment I) .
10 IND39-12 ND System Category C-F-I, Item Number See Paragraph "F' See Paragraph "G" See Paragraph "H" See Paragraphs "L" Valve IND2A-to- Pipe C05.011.049 Circumferential Weld Figure Number IWC-2500-7(a)
Volume limitation 76.10%
(Attachment J)
Request for Relief 05-CN-004 Revision 0 Page 3 of 9 IV. & V. ImpracticalitylBurden Caused by Code Compliance Paragraph A:
During the ultrasonic examination of Weld ID Number lRPV-W03, Reactor Vessel Shell to Lower Head Circumferential Weld, 100% coverage of the required examination volume could not be obtained. Scanning limitations were caused by proximity of the bottom mounted instrument tubes, which prevented scanning 100% of the weld length from four orthogonal directions. The procedure, qualified through the Performance Demonstration Initiative, requires scanning in four orthogonal directions using 45'single element shear waves, 450 single element refracted longitudinal waves (RL), and 450 dual element RL waves.
During the ultrasonic examination of Weld ID Number 1RPV-WO1, Reactor Vessel Lower Head to Bottom Head Circumferential Weld, 100% coverage of the required examination volume could not be obtained. Scanning limitations were caused by the core support lugs, which prevented scanning 100% of the weld length from four orthogonal directions. The procedure, qualified through the Performance Demonstration Initiative requires scanning in four orthogonal directions using 45'single element shear waves, 450 single element refracted longitudinal waves (RL), and 45° dual element RL waves.
The percent of coverage reported represents the aggregate coverage from all scans performed on the welds. In order to scan all of the required surfaces for the inspection of the shell to lower head circumferential weld and the lower head to bottom head circumferential weld, the interferences would have to be moved to allow scanning the full length of the welds, which is impractical. These examinations were performed using personnel, procedures and equipment qualified in accordance with ASME Section XI, Appendix VIII, 1995 Edition through the 1996 Addenda as administered through the Performance Demonstration Initiative (PDI).
(Examination Data is shown in Attachments A and B)
Paragraph B:
During the ultrasonic examination of Weld ID Number lPZR-Wl, 100% coverage of the required examination volume could not be obtained. Scanning limitations were caused by the nozzle geometry that restricts scanning from the nozzle side. The percent coverage reported represents the aggregate coverage of all scans performed. The examination volume was scanned using 350 and 450 shear waves, and straight beam longitudinal waves in accordance with ASME Section V, Article 4, T-441.3.2.1.
The 350 beam covered 88.5% of the examination volume perpendicular to the weld from the vessel head side and 62.5% of the examination volume perpendicular to the weld from the nozzle side. Scans parallel to the weld with the 350 beam covered 79.3% of the examination volume in two opposite directions.
The 450 beam covered 81.2% of the examination volume perpendicular to the weld from the vessel head side and 59.7% of the examination volume perpendicular to the weld from the nozzle side. Scans parallel to the weld with the 450 beam covered 79.3% of the examination volume in two opposite directions.
The straight beam covered 79.3% of the examination volume. In order to achieve more coverage, the nozzle would have to be re-designed to allow scanning in four orthogonal directions. This examination was performed using procedures prepared in accordance with ASME Section V, Article 4 using personnel qualified in accordance with ASME Section XI, IWA-2300, including Appendix VII, 1995 Edition through the 1996 Addenda.
(Examination Data is shown in Attachment C)
During the ultrasonic examination of Weld ID Numbers lPZR-W4A, IPZR-W4B and IPZR-W4C, 100% coverage of the required examination volume could not be obtained. Scanning limitations were caused by the nozzle geometry
Request for Relief 05-CN-004 Revision 0 Page 4 of 9 that restricts scanning from the nozzle side. The percent coverage reported represents the aggregate coverage of all scans performed. The examination volume was scanned using 450; 600 shear waves, and straight beam longitudinal waves in accordance with ASME Section V, Article 4, T-441.3.2.1.
The 450 beam covered 92.0% of the examination volume perpendicular to the weld from the vessel head side and 66.7% of the examination volume perpendicular to the weld from the nozzle side. Scans parallel to the weld with the 450 beam covered 79.6% of the examination volume in two opposite directions.
The 600 beam covered 94.2% of the examination volume perpendicular to the weld from the vessel head side and 60.5% of the examination volume perpendicular to the weld from the nozzle side. Scans parallel to the weld with the 600 beam covered 79.6% of the examination volume in two opposite directions.
The straight beam covered 79.6% of the examination volume. In order to achieve more coverage, the nozzle would have to be re-designed to allow scanning in four orthogonal directions. This examination was performed using procedures prepared in accordance with ASME Section V, Article 4 using personnel qualified in accordance with ASME Section XI, IWA-2300, including Appendix VII, 1995 Edition through the 1996 Addenda.
(Examination Data is shown in Attachments D, E and F)
Paragraph C:
During the ultrasonic examination of Weld ID Numbers IRPV-W18-SE and INC23-01, 100% coverage of the required examination volume could not be obtained. Limitations were due to the ID configuration which consists of counter-bore and root protrusion. Ultrasonic detection scans for the DM welds were examined from the ID surface using 70 degree L wave transducers applied four-directionally. This exam interrogated the inner 1/3 thickness volume. Eddy Current examination was also employed to examine inner surfaces of the dissimilar metal welds and the adjacent examination volumes where ID geometry presented a limitation to the detection of axial flaws as defined in the PDQS for the qualified Appendix VIII techniques.
The percent of coverage reported represents the aggregate coverage from all scans performed on the welds. In order to scan all of the required surfaces, the counter bore and root protrusions would have to be removed, which is impractical. These examinations were performed using personnel, procedures and equipment qualified in accordance with ASME Section XI, Appendix VIII, 1995 Edition through the 1996 Addenda as administered through the Performance Demonstration Initiative (PDI).
(Examination Data is shown in Attachment G)
Paragraph D:
During the ultrasonic examination of Weld ID Number INC286-1, 100% coverage of the required examination volume could not be obtained. Single sided access caused by the proximity of the pipe cap prevented scanning from the cap side of the weld. The percent coverage reported represents the aggregate coverage of all scans performed.
The examination volume was scanned using 450 and 600 shear waves.
The 450 beam covered 50% of the required volume in two opposite circumferential directions. The 60° beam covered 50% of the required volume in one axial direction from the pipe side of the weld. Because of the requirements of 10CFR50.55a(b)(2)(xv)(A)(2), coverage of the far side of the weld was not claimed.
In order to achieve more coverage, the weld would have to be re-designed to allow scanning from four orthogonal directions. This examination was performed using personnel, procedures and equipment qualified in accordance with ASME Section XI, Appendix VIII, Supplement 2, 1995 Edition through the 1996 Addenda as administered through the Performance Demonstration Initiative (PDI).
(Examination Data is shown in Attachment H)
Request for Relief 05-CN-004 Revision 0 Page 5 of 9 Paragraph E:
During the ultrasonic examination of weld ID Number IND-37A, 100% coverage of the required examination volume could not be obtained. Single sided access caused by the valve body and bonnet geometry prevented scanning from two opposing circumferential and axial directions. The percent coverage reported represents the aggregate coverage of all scans performed. The examination volume was scanned using 451and 600 shear waves.
The 450 beam covered 72.8% of the required volume in two opposite circumferential directions. A combination of 450 and 60° beams covered 65.81 % of the required volume perpendicular to the weld.
In order to achieve more coverage, the weld would have to be re-designed to allow scanning from four orthogonal directions. This examination was performed using personnel, qualified in accordance with ASME Section XI, ASME Section XI, IWA-2300, and Appendix VII, 1995 Edition through the 1996 Addenda.
(Examination Data is shown in Attachment I)
Paragraph F During the ultrasonic examination of Weld ID Number IND39-12, 100% coverage of the required examination volume could not be obtained. Single sided access caused by the valve configuration prevented scanning from the valve side of the weld. The percent coverage reported represents the aggregate coverage of all scans performed. The examination volume was scanned using 45'and 600 shear waves.
The 450 beam covered 100% of the required volume in two opposite circumferential directions. The 600 beam covered 52.9% of the required volume in one axial direction from the pipe side of the weld, and 51.4% from the valve side. A supplemental 600 longitudinal wave best effort scan covered 100% of the inside surface within the required volume in one axial direction from the pipe side of the weld but was not included in the coverage calculation because of the requirements of I OCFR50.55a(b)(2)(xv)(A)(2).
In order to achieve more coverage, the weld would have to be re-designed to allow scanning from four orthogonal directions. This examination was performed using personnel, procedures and equipment qualified in accordance with ASME Section XI, Appendix VIII, 1995 Edition through the 1996 Addenda as administered through the Performance Demonstration Initiative (PDI).
(Examination Data is shown in Attachment J)
VI. Proposed Alternate Examinations or Testing Paragraph G:
The scheduled 10-year code examination was performed on the referenced welds and resulted in the noted limited coverage of the required ultrasonic volume. No alternate examinations or testing are planned for the welds during the current inspection interval which ended on 6/29/05.
VII. Implementation Schedule and Duration Paragraph H:
The scheduled second 10-year interval plan code examination was performed on the referenced welds resulting in limited volumetric coverage. No additional examinations are planned for the welds and components during the current inspection interval which ended on 6/29/05. The same welds 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.
Request for Relief 05-CN-004 Revision 0 Page 6 of 9 VIII. Justification for Granting Relief Paragraph I:
Design and fabrication of the reactor vessel is carried out in strict accordance with ASME Code,Section III, Class I requirements. The head flanges, nozzles, and cylindrical portions of the unit 1 vessel are manufactured as forgings. The hemispherical heads are made from dished plates. The reactor vessel parts are joined by welding, using the single or multiple wire submerged arc and the shielded metal arc processes. The non-destructive examination of the reactor vessel and its appurtenances is conducted in accordance with the ASME Code Section III requirements; also numerous examinations are performed in addition to ASME Code Section III requirements. Nondestructive examination of the reactor vessel is discussed in UFSAR Section 5.3.1.3 and the reactor vessel quality assurance program is given in UFSAR Table 5-11.
The reactor vessel materials meet the fracture toughness requirements of 10CFR 50, Appendix G, to the extent possible. A summary of the fracture toughness data is given in UFSAR Table 5-13 and 5-15. Appendix G of 10 CFR 50 requires heatup and cooldown of the reactor vessel be accomplished within established pressure-temperature limits. The heatup and cooldown rates imposed by plant operating procedures are 50'F per hour and 80'F per hour, respectively, for normal operation. The heatup and cooldown rate limits are 60 IF per hour and 100 0F per hour, respectively, for abnormal or emergency conditions. The rate of 1000F per hour is the vessel design specification as a normal condition for conservatism for both heatup and cooldown. For Catawba unit 1, the heatup and cooldown limit curves for normal operation at 34 years provides a predicted operation window that is sufficient to conduct heatup and cooldowns. In addition, cyclic loads are introduced by normal power changes, reactor trips, and startup / shutdown operations. These design base cycles are selected for fatigue evaluation and constitute a conservative design envelope for the projected plant life. Vessel analysis results in a usage factor that is less than 1.
The reactor vessel has four inlet and four outlet nozzles located in a horizontal plane just below the upper head flange, but above the top of the core. Welds IPRV-W18-SE and INC23-01 are located on the reactor vessel outlet (i.e., hot leg) nozzle, which are typically covered with mirror insulation.. During each refueling outage while the primary system remains at temperature and pressure (Mode 3), all accessible areas within containment are inspected for any evidence of boric acid leaks. During this walkdown, any leakage from these welds would be recognized by a boron deposit buildup around the piping and mirror insulation.
Plant Technical Specifications dictate that a reactor coolant system water inventory balance be 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 (PTI1(2)/A/41501001D, NC System Leakage Calculation) establish 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. The water inventory balance provides repeatable results less than the 0.15 gpm administrative limit; however, an evaluation of sensitivity below this leak rate level has not been performed. No analysis has been done to quantify the flaw size in the reactor vessel which would be detectable by the leakage detection system.
Other leakage detection systems available to the operator per plant technical specifications are:
- Containment Atmosphere Particulate Radioactivity (EMF 38) Monitoring System which would detect airborne radiological activity;
Request for Relief 05-CN-004 Revision 0 Page 7 of 9 Containment Ventilation Unit Condensate Drain Tank Level Monitoring which collects and measures as unidentified leakage the moisture removed from the containment atmosphere.
The above leakage detection methods are dependant upon the Lower Containment Ventilation System, which provides for forced circulation of cooling air across the reactor vessel and for subsequent air return to lower containment. This provides the motive force for transporting moisture and radioactivity from any through wall leak in the reactor vessel to the above described leakage detection monitors.
Paragraph J:
100% bare metal visual (BMV) examinations were performed on all Alloy 600/ Alloy 821182 weld locations on the pressurizer during lEOC15; Reference Duke's Response to NRC Bulletin 2004-01, dated June 14, 2005, (See Attachment K) and W/O 98683639-01. The inspection scope included the surge line nozzle to lower head location and the three (3) pressurizer safety valve nozzle to upper head locations (i.e., including welds IPZR-WI, IPZR-W4A, IPZR-W4B, and IPZR-W4C). No evidence of leakage or boric acid deposits was observed at any of these locations. There was no wastage identified on the external surface of the pressurizer vessel head.
Plant Technical Specifications dictate that a reactor coolant system water inventory balance be 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/1(2)/A/4150/OOID, NC System Leakage Calculation) establish 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. The water inventory balance provides repeatable results less than the 0.15 gpm administrative limit; however, an evaluation of sensitivity below this leak rate level has not been performed.
Other leakage detection systems available to the operator and dictated per plant technical specifications are:
- Containment Atmosphere Particulate Radioactivity (EMF 38) Monitoring System which would detect airborne radiological activity;
- Containment Ventilation Unit Condensate Drain Tank Level Monitoring Subsystem which collects and measures as unidentified leakage the moisture removed from the containment atmosphere; Containment Floor and Equipment Sump Level and Flow Monitoring Subsystem where unidentified accumulated water on the containment floor would be monitored and evaluated as sump level changes.
Paragraph K:
The reactor pressure vessel upper head originally had four connections for the Upper Head Injection (UHI) system. Three of the four UHI penetrations are capped off. The other one serves as the Alternate Reactor Vessel Head Vent penetration. Weld INC286-1 is located at the pipe cap on a capped-off UHI nozzle at Catawba Unit
- 1. To meet the requirements of NRC Order EA-03-009, Catawba has established periodic inspection of the reactor vessel head area (Ref. SLC 16.5-8-2). This includes visual inspections performed each refueling outage to identify boric acid leaks for pressure-retaining components above the reactor vessel head. Any boric acid leakage from capped-off UHI nozzles would be identified during this inspection.
Plant Technical Specifications dictate that a reactor coolant system water inventory balance be 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
Request for Relief 05-CN-004 Revision 0 Page 8 of 9 be maintained below 1 gpm; however, plant operation procedure (PT/1(2)/A14150/OOlD, NC System Leakage Calculation) establish 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. The water inventory balance provides repeatable results less than the 0.15 gpm administrative limit; however, an evaluation of sensitivity below this leak rate level has not been performed.
Other leakage detection systems available to the operator per plant technical specifications are:
- Containment Atmosphere Particulate Radioactivity (EMF 38) Monitoring System which would detect airborne radiological activity;
- Containment Ventilation Unit Condensate Drain Tank Level Monitoring which collects and measures as unidentified leakage the moisture removed from the containment atmosphere.
The above leakage detection methods are dependant upon the Lower Containment Ventilation System, which provides for forced circulation of cooling air across the reactor vessel and for subsequent air return to lower containment. This provides the motive force for transporting moisture and radioactivity from any through wall leak in the reactor vessel to the above described leakage detection monitors.
ParagraphL:
The 1ND37A Body-to-Bonnet (IND-37A) and 1ND2A Body-to-Pipe (IND39-12) welds are located within the reactor building. These valves are second boundary isolation which remains normally closed to isolate the low pressure residual heat removal system from the high pressure reactor coolant system (i.e., Reactor Coolant Pressure Isolation Valves). These valves are opened to provide core cooling during plant shutdown. This piping and these welds are normally covered by mirror insulation. During each refueling outage while the primary system remains at temperature and pressure (Mode 3), all accessible areas within containment are inspected for any evidence of boric acid leaks. During this walkdown, any leakage from these welds would be recognized by a boron deposit buildup around the piping and mirror insulation.
In addition, any leakage at welds IND-37A or IND39-12 would be detected via other leakage detection systems available to the operator. These systems identified with plant technical specifications include:
- Containment Atmosphere Particulate Radioactivity (EMF 38) Monitoring System which would detect airborne radiological activity; Containment Ventilation Unit Condensate Drain Tank Level Monitoring Subsystem which collects and measures as unidentified leakage the moisture removed from the containment atmosphere; Containment Floor and Equipment Sump Level and Flow Monitoring Subsystem where unidentified accumulated water on the containment floor would be monitored and evaluated as sump level changes.
Request for Relief 05-CN-004 Revision 0 Page 9 of 9 IX. Other Information The following individuals contributed to the development of this relief request:
- Jim McArdle (Principle NDE Level III Inspector) provided UT related information for Sections III through VI
- Steve Mays (Mechanical Engineer) and Bill Callaway (Civil Engineer) provided information for Section VIII
- Andy Hogge (Sponsor) compiled the remaining sections Sponsored By:
l k ( vh ,I Date g//7/ 2~*
/ In v //
9/7/of Approved By: d. -6LA Date d ID N/
Attachment A Weld ID Number IRPV-WO3 Attachment B Weld ID Number lRPV-WI1 Attachment C Weld ID Number IPZR-W1 Attachment D Weld ID Number lPZR-W4A Attachment E Weld ID Number lPZR-W4B Attachment F WVeld ID Number IPZR-W4C Attachment G Weld ID Number lRPV-W18-SE and INC23-01 Attachment H Weld ID Number INC286-1 Attachment I Weld ID Number IND-37A Attachment J Weld ID Number IND39-12 Attachment K D. M. Jamil to U. S. Nuclear Regulatory Commission letter dated June 14,2005, Duke Energy Corporation Catawba Nuclear Station Unit 1 Docket No. 50-413 Response to NRC Bulletin 2004-01 Inspection of Alloy 82/182/600 Materials Used in the Fabrication of Pressurizer Penetrations and Steam Space Piping Connections at Pressurized - Water Reactors
WesDyne International Reactor Vessel Weld Results Summary CATAWBA UNIT 1 WELD NO. W4 DESCRIPTION LOWER SHELL TO (1RPV-W03) LOWER HEAD CIRC.
(BO1.O11.OO1)
LIMITATIONS NO D YES i COVERAGE = 72.76% 1s1 RESULTS NI NO. OF INDICATIONS o STATUS N/A I
EXAM DOCUMENTATION INDICATION DOCUMEN' FATION _
ANALYSIS LOG D]ASSESSMENT SHEET ACQUISITION LOG D1PARAGON HARD COPY SCAN PRINTOUT D-OTHER (specify)
COVERAGE BREAKDOWN WESDYNE ANALYST ~0 &/..=
K1
CATAWBA UNIT I DIRECTION / ORIENTATION RPV COVERAGE ESTIMATE BREAKDOWNS PARALLEL SCANS CCW/CW PERP. SCANS UP/DN WELD LOWER SHELL TO WELD NO. W4 (1RPV-W03)
DESCRIPTION LOWER HEAD CIRC.
BEAM ANGLES BEAM 450 L Dual 450 L Single 450 Shear DIRECTION WELD VOLUME WELD VOLUME WELD VOLUME WELD VOLUME WELD VOLUME cCW 63.67 22.0 100 80.02 100 80.02 CW 63.67 22.0 100 80.02 100 80.02 UP 63.67 63.67 63.67 63.67 81.83 100 DOWN 63.67 63.67 63.67 63.67 63.67 100 Combined Average = 72.76% LIMITATION DUE TO CORE SUPPORT LUGS.
ANALYST <925" r- -
I 47 2 orbs
WesDyne International Reactor Vessel Weld Results Summary CATAWBA UNIT 1 WELD NO. W5 DESCRIPTION LOWER HEAD TO (IRPV-WO1) BOTTOM HEAD CIRC.
(B01.021.001)
LIMITATIONS NO D2 YES I COVERAGE = 87.19%
RESULTS NI RI H
NO. OFXINDICATIONS 3 STATUS CODE ALLOWABLE EXAM DOCUMENTATION INDICATI ON DOCUMENTATION \Q FX ANALYSIS LOG X ASSESSMENT SHEET
[I ACQUISITION LOG [03 PARAGON HARD COPY FRI SCAN PRINTOUT L] OTHER (specify) nX COVERAGE BREAKDOWN 14)
WESDYNE ANALYST
CATAWBA UNIT 1 DIRECTION / ORIENTATION RPV COVERAGE ESTIMATE BREAKDOWNS PARALLEL SCANS CCW/CW PERP. SCANS UP/DN WELD LOWER HEAD TO WELD NO. W5 (IRPV-WO1)
DESCRIPTION BOTTOM HEAD CIRC.
BEAM ANGLES BEAM 450 L Dual 450 L Single 450 Shear DIRECTION WELD VOLUME WELD VOLUME WELD VOLUME WELD VOLUME WELD VOLUME ccw 86.6 87.5 100 93 100 93 cw 86.6 87.5 100 93 100 93 UP 85.97 81.65 81.29 78.43 78.77 79.07 DOWN 85.97 77.93 81.29 80.95 78.77 82.37 Combined Average - 87.19% LIMITATION DUE TO PROXIMITY OF PERIPHERAL BMI TUBES.
ANALYST
<;;zX 1.42 °'
UT Vessel Examination
- Enery, Site/Unit: Catawba / I Procedure: NDE-640 Outage No.: CNS1 EC )C15 Summary No.: B0Z1.110.001A Procedure Rev.: 3 Report No.: UT-05. .154 Workscope: 'Si Work Order No.: 98688944 Page: 1 of I Code: Asme Section Xi 1989 Cat./ltem: B-D-1B3.110.1A Location: N/A Drawing No.: CNM 1201.01-175/1
Description:
PZR Surge Nozzle to Lower Head System ID: NC Component ID: B03.110.001A/1PZR-W1 Size/Length: N/A Thickness/Diameter: 2.55" / 24.5" Limitations: Yes-See Attached Limitation Report Start Time: 1330 Finish Time: 1338 Examination Surface: Inside C] Outside ij Surface Condition: AS GROUND Lo Location: 9.2.3 Wo Location: Centeriine of Weld Couplant: ULTRAGEL II Batch No.: 03125 Temp. Tool Mfg.: D.A.S Serial No.: MCNDE32798 Surface Temp.: 82 *F Cal. Report No.: CAL-05-169 AngleUsed 0 45 45T L 60 60T Scanning dB 31.5 Indication(s): Yes 2 No i Scan Coverage: Upstream 9J Downstream i CW RJ CCW i1 Comments:
Results: Accept R Reject E Info E* - See Report No. UT-05-155 for actual percentage of coverage Percent Of Coverage Obtained > 90%: Yes.*** 7720/e Reviewed Previous Data: Yes Examiner Level II Slgtur Date Reviewer Signature Date Resor, James H. A M77 5117/2005 2, i -oS Examiner Level II (urD Date Site Review Signature Date Leeper, Winfred C. a - 5117/2005 N/A Other Level N/A Signature` Date ANII Review Signature Date N/A
-7 ° , .
V* S/? V/c F
,Z4 '"95-% A*4 U
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- Duke UT Vessel Examination olEnerss Site/Unit: Catawba / I Procedure: NDE-820 Outage No.: CNSIEOC15 Summary No.: B033.110.001A Procedure Rev.: 2 Report No.: UT-05-155 Workscope: Is' Work Order No.: 98688944 Page: 1 of 2 Code: Asme Section Xl 1989 Cat./Item: B-D-1B3.110.1A Location: N/A Drawing No.: CNM 1201.01-17511
Description:
PZR Surge Nozzle to Lower Head System ID: NC Component ID: B03.110.001A11PZR-W1 Size/Length: NIA Thickness/Diameter: 2.55" / 24.5" Limitations: Yes-See Attached Limitation Report Start Time: 1350 Finish Time: 1410 Examination Surface: Inside El Outside i Surface Condition: AS GROUND Lo Location: 9.2.3 Wo Location: Centerline of Weld Couplant: ULTRAGEL II Batch No.: 03125 Temp. Tool Mfg.: D.A.S Serial No.: MCNDE32798 Surface Temp.: 82 *F Cal. Report No.: CAL-05-170, CAL-05-171 Angle Used l 0 45 45T 60 60T 35 Scanning dB 67.2 67.2 62.8 Indication(s): Yes E No Pi Scan Coverage: Upstream i) Downstream i CW i CCW i Comments:
Results: Accept i] Reject a] Info a_
Percent Of Coverage Obtained > 90%: Yes - 77.2% Reviewed Previous Data: Yes Examiner Level ll ignature Date Reviewer;,, Signature Date Eaton, Jay A. 5/17/2005 L 5 Examiner Level II Si 0at Date Site Review Signature Date Jones, Russel 5/17/2005 N/A Other Level il-N ' .sMiiature Date ANII Reve,I ,<Sigr,9ture Date Keene, Douglas L (a .*1
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v c . 5/17/2005 (a- Qi2bW U
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M Duke Determination of Percent Coverage for rSEnergy. UT Examinations - Vessels Site/Unit: Catawba / 1 Procedure: NDE-820 Outage No.: CNS1EOC15 Summary No.: B03.110.001A Procedure Rev.: 2 Report No.: UT-05-155 Workscope: ISI Work Order No.: 98688944 Page: 2 of 2 0 den Planar Scan 100.000 % Length X 79.300 % volume of length / 100 = 79.300 % total for 0 deg 45 deg Scan 1 100.000 % Length X 81.200 % volume of length /100 = 81.200 % total for Scan 1 Scan 2 100.000 % Length X 59.700 % volume of length / 100 = 59.700 % total for Scan 2 Scan 3 100.000 % Length X 79.300 % volume of length / 100 = 79.300 % total for Scan 3 Scan 4 100.000 % Length X 79.300 % volume of length / 100 = 79.300 % total for Scan 4 Add totals and divide by # scans = 74.875 % total for 45 deg Other deg 35 Scan 1 100.000 % Length X 88.500 % volume of length / 100 =- 88.500 % total for Scan 1 Scan 2 100.000 % Length X 62.500 % volume of length /100 = 62.500 % total for Scan 2 Scan 3 100.000 % Length X 79.300 % volume of length / 100 = 79.300 % total for Scan 3 Scan 4 100.000 % Length X 79.300 % volume of length /100 = 79.300 % total for Scan 4 Add totals and divide by # scans = 77.400 % total for 35 deg Percent complete coverage Add totals for each angle and scan required and divide by # of angles to determine; 77.192 % Total for complete exam Note:
Supplemental coverage may be achieved by use of other angles / 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: David K. Zimmerman /,Ir ', <-4a' Date: 5/17/2005
CNS UNIT I PZR SURGE NOZZLE/LOWER ITEM NO. B03.110.001A I.D. NO. 1PZR-Wl ANGLE SCAN BASE METAL% WELD METAL% AGGREGATE%
0 0 58.6 100.0 79.3 35 1 70.7 91.6 81.2 35 2 70.7 48.7 59.7 35 3 58.6 100.0 79.3 35 4 58.6 100.0 79.3 45 1 81.7 95.2 88.5 45 2 81.7 43.2 62.5 45 3 58.6 100.0 79.3 45 4 58.6 100.0 79.3 Lr-Os - I S;5 Attachment I of 4 7 ,g CL bevy
DUKE POWER COMPANY ISI LIMITATION REPORT Component/Weld ID: 1PZR-W1 Item No: B03.110.001A remarks:
Li NO SCAN SURFACE BEAM DIRECTION Nozzle Configuration 0 LIMITED SCAN I1 i2 I I Z 2 0 cw L ccw FROM L N/A to L N/ INCHES FROM WO 1.15 to Beyond ANGLE: M 0 Z 45 E] 60 other FROM 0 DEG to 360 DEG L NO SCAN SURFACE BEAM DIRECTION Nozzle Configuration 3 LIMITED SCAN 1 LI 2 L0 1 Z 2 LI cw L ccw FROM L N/A to L N/A INCHES FROM WO 1.25 to Beyond ANGLE: Li 0 Li 45 Li 60 other 35 FROM 0 DEG to 360 DEG L NO SCAN SURFACE BEAM DIRECTION Nozzle Configuration LIMITED SCAN :1 I 2 ZI El 2 l cw i ccw FROM L N/A to L N/A INCHES FROM WO 0.85 to Beyond ANGLE: EL 0 l 45 L 60 other FROM 0 DEG to 360 DEG El NO SCAN SURFACE BEAM DIRECTION Nozzle Configuration Z LIMITED SCAN i1 [ 2 0 1 Li22 cw L ccw FROM L N/A to L N/A INCHES FROM WO 0.75 to Beyond Sketch(s) attached ANGLE: Li 0 Li 45 Li 60 other 35 FROM 0 DEG to 360 DEG S yes L No Prepared By: David Zimrnerman Lvl IIIll Date: 05/17/05l Sheet of 4A
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Reviewed By: Date Authfied Inp Date, V
e55So0 ).-
DUKE POWER COMPANY ISI LIMITATION REPORT Component/Weld ID: 1PZR-W1 Item No: B03.110.001A remarks:
0 NO SCAN SURFACE BEAM DIRECTION Nozzle Configuration LI LIMITED SCAN El 1 2 1 [1122 cw Z ccw FROM L N/A to L N/ INCHES FROM WO 1.3 to Beyond ANGLE: 0 0 Z 45 E0 60 other 35 FROM 0 DEG to 360 DEG I NO SCAN SURFACE BEAM DIRECTION El LIMITED SCAN I [ 2 0 1 0 2 0 cw [ ccw FROM L to L INCHES FROM WO to ANGLE: E 0 E 45 El 60 other FROM DEG to DEG El NO SCAN SURFACE BEAM DIRECTION El LIMITED SCAN El 1 2 El I 1 2 E cw E__ccw FROM L to L INCHES FROM WO to ANGLE: El 0 E 45 E] 60 other FROM DEG to DEG El NO SCAN SURFACE BEAM DIRECTION El LIMITED SCAN El I 2 El 1 E22 Ecw E ccw FROM L to L INCHES FROM WO to Sketch(s) attached ANGLE: El 0 El 45 El 60 other FROM DEG to DEG yes E No Prepared By: David ZimmrmanA Level:II Date: 05/17/05 l Sheet 3 of 4 UT>o-lic Reviewed By: Date 5 s. 7iAuthordInspect2, Date:
U-P5; (toceP
/f uake UT Vessel =xamination
.ssXEnergy.
Site/Unit: Catawba / I Procedure: NDE-640 Outage No.: CNSlEOC15 Summary No.: B03 .110.004A Procedure Rev.: 3 Report No.: UT-05-215 Workscope: SIt Work Order No.: 98688945 Page: 1 of I Code: Asme Section XI 1989 Cat./Item: B-D- IB3.110.4A Location: NIA Drawing No.: CNM 1201.01-17511
Description:
PZR Safety Nozzle to Upper Head System ID: NC Component ID: B03.110.004A11PZR-W4A Size/Length: N/A Thickness/Diameter: 1.9"! 15.0" Limitations: Yes - See Limitation Report for 820 Exam Start Time: 1249 Finish Time: 1253 Examination Surface: Inside Q Outside iJ Surface Condition: AS GROUND Lo Location: 9.2.3 Wo Location: Centerline of Weld Couplant: ULTRAGEL II Batch No.: 05125 Temp. Tool Mfg.: D.A.S Serial No.: MCNDE32798 Surface Temp.: 69 OF Cal. Report No.: CAL-05-228 Angle Used 0 45 45T1 60 60T Scanning dB 31.5 _
Indication(s): Yes No Scan Coverage: Upstream n Downstream R CWRI CCW ]I Comments:
Results: Accept R Reject a Info a Percent Of Coverage Obtained > 90%: No - 79.2% Reviewed Previous Data: Yes Examiner Level ii Situ Date Reviewer Signature Date Leeper, Winfred C. - 5/2612005 2c% o S5
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Examiner Level Il-N Sig at r Date Site Review Signature Date Keene, Douglas L. / 5/2612005 N/A Other Level Il-N hign ure Date ANII Review / Signatqt/j e 1 Date Ransom, Greg 5/26/2005 G
(,lt Ieekt Zf#695 -62V-604 47 4x ,
I5Duke UT Vessel Examination i ,Energy.
Site/Unit: Catawba / I Procedure: NDE-820 Outage No.: CNSlEOC15 Summary No.: B033.110.004A Procedure Rev.: 2 Report No.: UT-05-218 Workscope: ISI Work Order No.: 98688945 Page: 1 of 3 Code: Asme Section Xl 1989 Cat./ltem: B-D- 1B3.110.4A Location: N/A Drawing No.: CNM 1201.01-175/1
Description:
PZR Safety Nozzle to Upper Head System ID: NC Component ID: B03.110.004A11PZR-W4A Size/Length: N/A Thickness/Diameter: 1.9" /15.0" Limitations: Yes - See Attached Limitation Report Start Time: 1227 Finish Time: 1244 Examination Surface: Inside E Outside Ei Surface Condition: AS GROUND Lo Location: 9.2.3 Wo Location: Centerline of Weld Couplant: ULTRAGEL II Batch No.: 05125 Temp. Tool Mfg.: D.A.S Serial No.: MCN0E32798 Surface Temp.: 69 OF Cal. Report No.: CAL-05-229, CAL-05-230 Angle Used l0 45 1 45T 60 60T l l Scanning dB 53 67.4 Indication(s): YesC No Scan Coverage: Upstream Downstream3 CWnIl CCW!/i Comments:
Results: Accept i Reject E Info a_
Percent Of Coverage Obtained > 90%: No - 79.2 % Reviewed Previous Data: Yes Examiner Level II re Date Reviewer Signature Date Leeper, Winfred C. I 5/26/2005 Examiner Level Il-N , ) .Si~pfure Date Site Review Signature Date Keene, Douglas L. W O ,, t /t ~ - 5/26/2005 NIA A Other Level Il-N nature Date ANII Review A Signature Date Ransom, Greg / 5/26/2005 6 I/ J P -X t.3
h Duke Determination of Percent Coverage for rt-Energy- UT Examinations - Vessels Site/Unit: Catawba / I Procedure: NDE-820 Outage No.: CNSIEOC15 Summary No.: B03.110.004A Procedure Rev.: 2 Report No.: UT-05-218 Workscope: ISI Work Order No.: 98688945 Page: 2 of 3 0 deg Planar Scan 100.000 % Length X 79.630 % volume of length / 100 = 79.630 % total for 0 deg 45 decq Scan 1 100.000 % Length X 92.000 % volume of length / 100 = 92.000 % total for Scan 1 Scan 2 100.000 % Length X 66.710 % volume of length /100 = 66.710 % total for Scan 2 Scan 3 100.000 % Length X 79.630 % volume of length / 100 = 79.630 % total for Scan 3 Scan 4 100.000 % Length X 79.630 % volume of length / 100 = 79.630 % total for Scan 4 Add totals and divide by # scans = 79.493 % total for 45 deg Other deni 60 Scan 1 100.000 % Length X 94.230 % volume of length /100 = 94.230 %total for Scan 1 Scan 2 100.000 % Length X 60.520 % volume of length / 100 = 60.520 % total for Scan 2 Scan 3 100.000 % Length X 79.630 % volume of length / 100 = 79.630 % total for Scan 3 Scan 4 100.000 % Length X 79.630 % volume of length / 100 = 79.630 % total for Scan 4 Add totals and divide by # scans = 78.503 % total for 60 deg Percent complete coverage Add totals for each angle and scan required and divide by # of angles to determine; 79.208 % Total for complete exam Note:
Supplemental coverage may be achieved by use of other angles / 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: D tll rh S C'FP(3
V,&lik Limitation Record P011neray-SitelUnit: Catawba / I Procedure: NDE-820 Outage No.: CNS1EOC15 Summary No.: B03.110.004A Procedure Rev.: 2 Report No.: UT-05-218 Workscope: ISI Work Order No.: 98688945 Page: 3 of 3 Description of Limitation:
See Attachement for Limitation Calculations. Aggregate %
Coverage Sketch of Limitation:
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Radiation field:
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DUKE POWER COMPANY ISI LIMITATION REPORT Component/Weld ID: IPZR-W4A Item No: B03.110.004A remarks:
E NO SCAN SUIJFACE BEAM DIRECTION Nozzle Configuration
[1 LIMITED SCAN 1 [1 2 [ 1 Z 2 E cw E ccw FROM L to L INCHES FROM WO CIL+ to Beyond ANGLE: I 0 E 45 Z 60 other FROM 0 DEG to 360 DEG Z NO SCAN SURFACE BEAM DIRECTION Nozzle Configuration III LIMITED SCAN a 1 Z2 E 1 [ 2 0 cw E ccw FROM L to L INCHES FROM WO C/L+ to Beyond ANGLE: El 0 I 45 E] 60 other FROM 0 DEG to 360 DEG El 'NO SCAN SURFACE BEAM DIRECTION El LIMITED SCAN El1 [ 2 E0 1 2 [ cw E ccw FROM L to L INCHES FROM WO to ANGLE: 0 [° 45 E0 60 other FROM DEG to DEG LI NO SCAN SURFACE BEAM DIRECTION El LIMITED SCAN M [1 2 0 I 0 2 D cw D ccw FROM L to L INCHES FROM WO to Sketch(s) attached ANGLE: El 0 E 45 a1 60 other FROM DEG to DEG Z yes a No Prepared By: David Zimmerman / , Y_ee III Reviewed By: Re v i e we By, - Dat e:
Date:x Dte I ~7W44swr-5 Nisi7 r) 4(r ) f 5-)3
D.uke UT Vessel Examination 4&.,Energy.
Site/Unit: Catawba / 1 Procedure: NDE-640 Outage No.: CNSIEOC15 Summary No.: BO3.110.005 Procedure Rev.: 3 Report No.: UT-05-216 Workscope: 'SI Work Order No.: 98688945 Page: 1 of I Code: Asme Section XI 1989 Cat./Atem: B-D-1B3.110.5. Location: N/A Drawing No.: CNM 1201.01-175/1
Description:
PZR Safety Nozzle to Upper Head System ID: NC Component ID: B03.110.005 /1PZR-W4B Size/Length: NIA Thickness/Diameter: 1.9" 1 15.0" Limitations: Yes - See Limitation Report for 820 Exam Start lime: 1245 Finish Time: 1249 Examination Surface: Inside a Outside i Surface Condition: AS GROUND Lo Location: 9.2.3 Wo Location: Centerline of Weld Couplant: ULTRAGEL II Batch No.: 05125 Temp. Tool Mfg.: D.A.S Serial No.: MCNDE32798 Surface Temp.: 69 °F Cal. Report No.: CAL-05-228 Angle Used 0 45 45T l 60 l 60T l Scanning dB 31.5 Indication(s): Yes j No i/1 Scan Coverage: Upstream E Downstream i CW i CCW i Comments:
Results: Accept i Reject E Info E Percent Of Coverage Obtained > 90%: No - 79.2% Reviewed Previous Data: Yes Examiner Level iI Si ture Date Reviewer p_ Signature Date Leeper, Winfred C. - 5126/2005 5 2 C?
$ -°5 Examiner Level 11-N t.Slae Date Site Review Signature Date Keene, Douglas L. ., 512612005 NIA Other Level Il-N Signture Date ANII Review \ Sig-ty L Date Ransom, Greg , 5126/2005 g sOS NN\L .
Ial ,V PE-/ co-13
Du3£ke UT Vessel Examination IEnergy Site/Unit: Catawba / 1 Procedure: NDE-820 Outage No.: CNSIEOC15 Summary No.: BO, 3.110.005 Procedure Rev.: 2 Report No.: UT-05-219 Workscope: [St Work Order No.: 98688945 Page: 1 of 3 Code: Asme Section XI 1989 Cat./item: B-D- 1B3.110.5 Location: NIA Drawing No.: CNM 1201.01-175/1
Description:
PZR Safety Nozzle to Upper Head System ID: NC Component ID: B03.110.005I1PZR-W4B Size/Length: NIA Thickness/Diameter: 1.9"115.0" Limitations: Yes-See Attached Limitation Report Start Time: 1212 Finish Time: 1235 Examination Surface: Inside : Outside i] Surface Condition: AS GROUND Lo Location: 9.2.3 Wo Location: Centerline of Weld Couplant: ULTRAGEL II Batch No.: 05125 Temp. Tool Mfg.: D.A.S Serial No.: MCNDE32798 Surface Temp.: 69 *F Cal. Report No.: CAL-05-229, CAL-05-230 Angle Used 0l 45 l45T 60 l60T l l Scanning dB 53 67.4 l Indication(s): Yesrj NoRy Scan Coverage: Upstream f Downstream 3 CW2 CCW9 Comments:
Results: Accept i Reject a Info C_
Percent Of Coverage Obtained > 90%: No- 79.2% Reviewed Previous Data: Yes Examiner Level II gna re Date Reviewer // Signature > / Date Leeper, Winfred C. 512612005 'P7 5 Examiner Level Il-N a e Date Site Review Signature Date Keene, Douglas L. / 5126/2005 N/A Other Level Il-N Signature Date ANII Review ()igpature Date Ransom, Greg 512612005 gN i& Tah
/
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IE Duke Determination of Percent Coverage for revEnergy. UT Examinations - Vessels Site/Unit: Catawba / I Procedure: NDE-820 Outage No.: CNSIEOC15 Summary No.: B03.110.005 Procedure Rev.: 2 Report No.: UT-05-219 Workscope: ISI Work Order No.: 98688945 Page: 2 of 3 0 deg Planar Scan 100.000 % Length X 79.630 % volume of length / 100 = 79.630 % total for 0 deg 45 den Scan 1 100.000 % Length X 92.000 % volume of length / 100 = 92.000 % total for Scan 1 Scan 2 100.000 % Length X 66.710 % volume of length /100 = 66.710 % total for Scan 2 Scan 3 100.000 % Length X 79.630 % volume of length / 100 = 79.630 % total for Scan 3 Scan 4 100.000 % Length X 79.630 % volume of length /100 = 79.630 % total for Scan 4 Add totals and divide by # scans = 79.493 % total for 45 deg Other den 60 Scan 1 100.000 % Length X 94.230 % volume of length / 100 = 94.230 % total for Scan 1 Scan 2 100.000 % Length X 60.520 % volume of length / 100 = 60.520 % total for Scan 2 Scan 3 100.000 % Length X 79.630 % volume of length / 100 = 79.630 % total for Scan 3 Scan4 100.000 % LengthX 79.630 % volume of length / 100 = 79.630 % total for Scan 4 Add totals and divide by # scans = 78.503 % total for 60 deg Percent complete coverage Add totals for each angle and scan required and divide by # of angles to determine; 79.208 % Total for complete exam Note:
Supplemental coverage may be achieved by use of other angles / 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: &"11 .aLL Date:
/"j? -36,v-3
- i. Limitation Record Site/Unit: Catawba I Procedure: NDE-820 Outage No.: CNS1EOC15 Summary No.: B03. 1`10.005 Procedure Rev.: 2 Report No.: UT-05-219 Workscope: 151 Work Order No.: 98688945 Page: 3 of 3 Description of Limitation:
See Attachment for Limitation Calculations. Aggregate %
Coverage Sketch of Umitation:
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- iI 7Gt3 100.00 -e .. Gc Uimitations removal requirements:
Radiation field:
Examiner Level II 1 SJ e Date Reviewer Signature Date Leeper, Winfred C. 526J2005
_§1W -~ t ;5 0w Examiner Level Il-N ' In Date Site Review Signature Date Keene, Douglas L M T 512612005 NIA Other Level I-N Signhat, Date ANII Review t Signature Date Ransom, Greg 5 _ __ __12__2005 __ ___ ________
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DUKE POWER COMPANY ISI LIMITATION REPORT Component/Weld ID: 1PZR-W4B Item No: B03.110.005 remarks:
J NO SCAN SURFACE BEAM DIRECTION Nozzle Configuration E LIMITED SCAN ZI E2 a I Z 2 lZ cw ccw FROM L to L INCHES FROM WO C/L+ to Beyond ANGLE: 0 0 Z 45 Z 60 other FROM 0 DEG to 360 DEG
[ NO SCAN SURFACE BEAM DIRECTION Nozzle Configuration El LIMITED SCAN l1 Z 2 1 1 E 2 l cw E ccw FROM L to L INCHES FROM WO C/L+ to Beyond ANGLE: E 0 Z 45 Z 60 other FROM 0 DEG to 360 DEG El NO SCAN SURFACE BEAM DIRECTION El LIMITED SCAN r1 I 2 E 1 2 2 El cw D ccw FROM L to L INCHES FROM WO to ANGLE: El 0 El 45 Fl 60 other FROM DEG to DEG E NO SCAN SURFACE BEAM DIRECTION El LIMITED SCAN I E l2 El1i 2 E lcw E ccw FROM L to L INCHES FROM WO to Sketch(s) attached ANGLE: El 0 El 45 El 60 other FROM DEG to DEG Z yes E No Prepared By: David Zimmerman = Level: 11 Date: 05262005 8ht q of q Reviewed By: Date: =; Authorized Inspector: )b Date: 6 O J)
)36fL3
Xfl~uke UT Vessel Examination
, scenergy, Site/Unit: Catawba / I Procedure: NDE-640 Outage No.: CNSIEOC15 Summary No.: B03.110.006A Procedure Rev.: 3 Report No.: UT-05-217 Workscope: ISI Work Order No.: 98688945 Page: 1 of I Code: Asme Section XI 1989 Cat./ltem: B-D- IB3.110.6A Location: N/A Drawing No.: CNM 1201.01-17511
Description:
PZR Safety Nozzle to Upper Head System ID: NC Component ID: B03.110.006AI1PZR-W4C Size/Length: NIA Thickness/Diameter: 1.9" / 15.0" Limitations: Yes- See Limitation Report for 820 Exam Start Time: 1211 Finish Time: 1216 Examination Surface: Inside a Outside i] Surface Condition: AS GROUND Lo Location: 9.2.3 Wo Location: Centerline of Weld Couplant: ULTRAGEL II Batch No.: 05125 Temp. Tool Mfg.: D.A.S Serial No.: MCNDE32798 Surface Temp.: 69 -F Cal. Report No. CAL.05-228 Angle Used 0 l 45 l 45T l 60 l 60T l Scanning dB 31.5 a N i Indication(s): Yes E No 2J Scan Coverage: Upstream E Downstream Ed CW~ MCCW J Comments:
Results: Accept R] Reject ° Info C Percent Of Coverage Obtained > 90%: No - 79.2% Reviewed Previous Data: Yes 4
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- ev4em A IfA
,'..Dulke UT Vessel Examination (1&Energy, Site/Unit: Catawba / 1 Procedure: NDE-820 Outage No.: CNSlEOC15 Summary No.: B033.11 0.006A Procedure Rev.: 2 Report No.: UT-05-220 Workscope: ISI Work Order No.: 98688945 Page: 1 of 3 Code: Asme Section Xi 1989 Cat./Item: B-D- IB3.110.6A Location: N/A Drawing No.: CNM 1201.01-175/1
Description:
PZR Safety Nozzle to Upper Head System ID: NC Component ID: B03.110.006A1IPZR-W4C Size/Length: NIA Thickness/Diameter: 1.9" 115.0" Limitations: Yes-See Attached Limitation Report Start Time: 1217 Finish Time: 1236 Examination Surface: Inside a Outside i) Surface Condition: AS GROUND Lo Location: 9.2.3 Wo Location: Centerline of Weld Couplant: ULTRAGEL II Batch No.: 05125 Temp. Tool Mfg.: D.A.S Serial No.: MCNDE32798 Surface Temp.: 69 OF Cal. Report No.: CAL-05-229, CAL-05-230 AngleUsed l 0 45 l45Tl 60 60T Scanning dB 63 67.4 l Indication(s): Yes ] NoI I Scan Coverage: UpstreamE Downstream W CWZ CCWR Comments:
Results: Accept i Reject E Info E_
Percent Of Coverage Obtained > 90%: No - 79.2% Reviewed Previous Data: Yes Examiner Level II ture, Date Reviewer Signature S/ Date Leeper, Winfred C. 5/26/2005 Dae Ri Signature 5 Examiner Level 1-N Date Site Review Signature Date Keene, Douglas L. 5/26/2005 N/A A Other Level Il-N //
tSignature Date ANII Review SignDate Ransom, Greg 5/2612005 U U- 0\V\(\(IJ7Q A~-sp
lt Duke . Determination of Percent Coverage for ADEnergy. UT Examinations - Vessels Site/Unit: Catawba I 1 Procedure: NDE-820 Outage No.: CNS1EOC15 Summary No.: B03.110.006A Procedure Rev.: 2 Report No.: UT-05-220 Workscope: ISI Work Order No.: 98688945 Page: 2 of 3 0 den Planar Scan 100.000 % Length X 79.630 % volume of length /100 = 79.630 % total for 0 deg 45 den Scan 1 100.000 % Length X 92.000 % volume of length /100 = 92.000 % total for Scan 1 Scan 2 100.000 % Length X 66.710 % volume of length / 100 = 66.710 % total for Scan 2 Scan 3 100.000 % Length X 79.630 % volume of length / 100 = 79.630 % total for Scan 3 Scan 4 100.000 % Length X 79.630 % volume of length / 100 = 79.630 % total for Scan 4 Add totals and divide by # scans = 79.493 % total for 45 deg Other deg 60 Scan 1 100.000 % Length X 94.230 % volume of length.100 = 94.230 % total for Scan 1 Scan 2 100.000 % Length X 60.520 % volume of length / 100 = 60.520 % total for Scan 2 Scan 3 100.000 % Length X 79.630 % volume of length /100 = 79.630 % total for Scan 3 Scan4 100.000 % LengthX 79.630 % volume of length /100 = 79.630 % total for Scan 4 Add totals and divide by # scans = 78.503 % total for 60 deg Percent complete coverage Add totals for each angle and scan required and divide by # of angles to determine; 79.208 % Total for complete exam Note:
Supplemental coverage may be achieved by use of other angles / 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: &,Inches S i/'p i Date: ()<IZ t' /o P) 3"F[3
9 Duke Limitation Record rOEnergy.
Site/Unit: Catawba I 1 Procedure: NDE-820 Outage No.: CNSIEOCIS Summary No.: B03.1 10.006A Procedure Rev.: 2 Report No.: UT-05.220 Workscope: 'SI Work Order No.: 98688945 Page: 3 of 3 Description of Limitation:
See Attachment for Limitation Calculations. Aggregate %
Coverage Sketch of Uimitation:
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DUKE POWER COMPANY ISI LIMITATION REPORT Componentleld ID: 1PZR-W4C Item No: B_03.110.006A remarks:
E NO SCAN SURFACE BEAM DIRECTION Nozzle Configuration E LIMITED SCAN 1 El2 I Z 2 Z cw [E ccw FROM L to L INCHES FROM WO C/L+ to Beyond ANGLE: Z 0 Z 45 E 60 other FROM 0 DEG to 360 DEG 8 NO SCAN SURFACE BEAM DIRECTION Nozzle Configuration El LIMITED SCAN El I E 2 Z 1 0 2 0 cw l ccw FROM L to L INCHES FROM WO C/L+ to Beyond ANGLE: E 0 E 45 Z 60 other FROM 0 DEG to 360 DEG El NO SCAN SURFACE BEAM DIRECTION al LIMITED SCAN I1 02 E[1 En 2 E cw :1 ccw FROM L to L INCHES FROM WO to ANGLE: a0 E° 45 El 60 other FROM DEG to DEG El NO SCAN SURFACE BEAM DIRECTION El LIMITED SCAN E1 El 2 E I C 2 0 cw O ccw FROM L to L_ INCHES FROM WO to Sketch(s) attached ANGLE: ElO E 45 l 60 other FROM DEG to DEG Z yes E No Date: 05262005 Ifd,, ofeet44
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Authorized Inspector:
- , f 0(/ ig i Date:,7.d3 *t29
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WesDyne International Reactor Vessel Weld Results Summary CATAWBA UNIT 1 WELD NO. 1RPV-Wi8-SE DESCRIPTION OUTLET NOZZLE AND 1NC23-01 DM WELD (Q3380 (1105.010.008 &
B05.010.008A)
AND (B05.130.005 &
B05.130.005A)
LIMITATIONS NOBI YES X COVERAGE= 82.45%
RESULTS RI NO. OF INDICATIONS 5 STATUS 4 CODE ALLOWABLE AND 1 NON-ALLOWABLE EXAM DOCUMENTATION INDICATION DOCUMENTATION
[x ANALYSIS LOG [XI ASSESSMENT SHEET FR ACQUISITION LOG ix] PARAGON HARD COPY
- SCAN PRINTOUT RX OTHER (specify)
INDICATION LOCATION SKETCH
[-i COVERAGE BREAKDOWN WESDYNE ANALYST
CATAWBA UNIT 1 DIRECTION / ORIENTATION RPV COVERAGE ESTIMATE BREAKDOWNS PARALLEL SCANS CCW/CW PERP. SCANS UP/DN WELD OUTLET NOZZLE WELD NO. I RPV-WI 8-SE AND DESCRIPTION DM WELD @ 3380 1NC23-01 BEAM ANGLES BEAM 700L DUAL ET DIRECTION WELD VOLUME WELD VOLUME WELD VOLUME WELD VOLUME WELD VOLUME Ccw *71.1 58.69 *100 *100 cw '71.1 58.69 IN 100 100 OUT 100 100 UT Average = 82.45%
- CIRC SCANS LIMITED AS PER PROCEDURE PDQS DUE TO ID COMBINED COVERAGE (UT & COUNTERBORE AND ROOT CONFIGURATION. LIMITATION AREA FROM ET) = 100% 122.96" TO 123.40" FROM 0° TO 550; FROM 123.56" TO 124.0" FROM 0° TO 3600; AND FROM 121.76" TO 122.5" FROM 0° TO 360°. ET USED TO SUPPLEMENT EXAM FOR FULL COVERAGE.
ANALYST V-frl 41:2p3
Ax: Duke UT Pipe Weld Examination t-CrEnergy.
Site/Unit: Catawba / 1 Procedure: NDE-600 Outage No.: CN' 31 EOC1 5 Summary No.: BO9.011.048 Procedure Rev.: 16 Report No.: Ul7-05-168 Workscope: IS' Work Order No.: 98680794 Page: 1 of 3 Code: Asmo Section Xl 1989 Cat./ltem: B-J-1B9.11.48 Location: NIA Drawing No.: CN-INC-286
Description:
UHI Adaptor to Pipe Cap System ID: NC Component ID: B09.011.048 1NC286-1 Size/Length: N/A Thickness/Diameter: .864" 16" Limitations: Yes-See Attached Limitation Report Start Time: 1322 Finish Time: 1338 Examination Surface: Inside L Outside i Surface Condition: AS GROUND Lo Location: RT INT 0 Wo Location: Centerlino of Weld Couplant: ULTRAGEL II Batch No.: 05125 Temp. Tool Mfg.: D.A.S Serial No.: MCNDE32797 Surface Temp.: 78 °F Cal. Report No.: CAL-05-180, CAL-05-181, CAL-05-182 Angle Used 0 45 45T 60 60Ll l Scanning dB 41 42 40 Indication(s): Yes °I No 3 Scan Coverage: Upstream E Downstream i CW i CCW [D Comments:
FC 05-08 Results: Accept n3 Reject ° Info D_
Percent Of Coverage Obtained > 90%: No-37.5% Reviewed Previous Data: Yes Examiner Level jj Si ture Date Reviewer At 0 // Signature -P Leeper, Winfred C. 5/19/2005 5/S
<0$
Examiner Level 11S 00 atui Date Site Review Signature Date Jones, Russel 5/19/2005 N/A Other Level N/A Signature Date ANII Reyiew , ! S inature Date N/A 6sJk / Rdu-6 JR 4-uOr
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Limitation Record MDInergy.
Site/Unit: Catawba / I Procedure: NDE-600 Outage No.: CNS1EOC15 Summary No.: B09.011.048 Procedure Rev.: 16 Report No.: UT-05-168 Workscope: ISI Work Order No.: 98680794 Page: 2 of 3 Description of Limitation:
See Attached 0
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Radiation field:
Examiner Level II Sign Date Reviewer / Signature 1Date Leeper, Winfred C. 5/211912005 Oo> 1,5 Examiner Level I1 Date Site Review Signature Date Jones, Russel - 5119/2005 N/A Signature Date Other NIA Level N/A gnature 017 Date ANII Review e4/ s
'6 3f
rovers,~ Determination of Percent Coverage for UT Examinations - Pipe Site/Unit: Catawba/ 1 Procedure: NDE-600 Outage No.: CNSIEOC15 Summary No.: B09.011.048 Procedure Rev.: 16 Report No.: UT-05-168 Workscope: ISI Work Order No.: 98680794 Page: 3 of 3 45 den Scan 1 % Length X % volume of length / 100 = % total for Scan I Scan 2 % Length X % volume of length /100 = % total for Scan 2 Scan 3 100.000 % Length X 50.000 % volume of length / 100 = 50.000 % total for Scan 3 Scan 4 100.000 % Length X 50.000 % volume of length 1 100 = 50.000 % total for Scan 4 Add totals and divide by # scans = 50.000 % total for 45 deg Other den - 60 (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 I 100.000 % Length X 50.000 % volume of length /100 = 50.000 % total for Scan 1 Scan 2 100.000 % Length X 0.000 % volume of length / 100 = 0.000 % total for Scan 2 Scan 3 % Length X % volume of length / 100 = % total for Scan 3 Scan 4 % Length X % volume of length / 100 = % total for Scan 4 Percent complete coverage Add totals for each scan required and divide by # of scans to determine;
? 7 cq % Total for complete exam Site Field Supervisor: S F l u v ra Date: t 5 /l lot ---
b4
DUKE POWER COMPANY ISI LIMITATION REPORT Component/Weld ID: 1NC286-1 Item No: B09.011.048 remarks:
El NO SCAN SURFACE BEAM DIRECTION Cap Conf.
E LIMITED SCAN 1 0 2 I I l 2 0 cw El ccw FROM L N/A to L N/A INCHES FROM WO C/L to Beyond ANGLE: [] 0 al 45 E 60 other FROM 0 DEG to 360 DEG Z NO SCAN SURFACE BEAM DIRECTION Cap Conf.
El LIMITED SCAN I1 2 I E 2 3 cw E ccw FROM L N/A to L N/A INCHES FROM WO C/L to Beyond ANGLE: E 0 E 45 El 60 other FROM 0 DEG to 360 DEG E NO SCAN SURFACE BEAM DIRECTION Cap Conf.
E LIMITED SCAN I1 2 Z I E 2 l cw E ccw FROM L to L INCHES FROM WO C/L to Beyond ANGLE: 0 El 45 E 60 other FROM 0 DEG to 360 DEG El NO SCAN SURFACE BEAM DIRECTION D LIMITED SCAN El I E 2 El 1 0 2 E cw Fo ccw FROM L to L INCHES FROM WO to Sketch(s) attached ANGLE: E0 El 45 El 60 other FROM DEG to DEG E yes El No Prepared By: David Zimmerman Level: ill Date: 05/19/05 j. of - A rrOs-;oc-8 Reviewed By: Date: uth ized Inspect 5 a e 6~2,a 'Pd~~~1
-V p5L(=4
UT Vessel Examination Enrgyw Site/Unit: Catawba / I Procedure: NDE-630 Outage No.: CNSiEOC15 Summary No.: B12 .040.002D Procedure Rev.: 2 Report No.: UT-05-211 Workscope: ISI Work Order No.: 98688919 Page: 1 of 8 Code: Asme Section Xi 1989 Cat./Item: B-M-11B12.40.2D Location: NIA Drawing No.: CN-IND-037
Description:
Valve Body to Bonnett System ID: ND Component ID: B12.040.002D/IND-37A Size/Length: NIA Thickness/Diameter: 2.043"/ 20.0" Limitations: Yes - See Attached Limitation Report Start Time: 0900 Finish Time: 0936 Examination Surface: Inside F1 Outside R] Surface Condition: AS GROUND Lo Location: RT INT. #1 Wo Location: Centerline of Weld Couplant: ULTRAGEL II Batch No.: 03125 Temp. Tool Mfg.: D.A.S Serial No.: MCNDE32797 Surface Temp.: 74 *F Cal. Report No.: CAL-05-220, CAL-05-221, CAL-05-222, CAL-05-223 AngleUsed 0 45 45T 60 60T Scanning dB 40.6 46.6 54.7 Indication(s): Yes J No FiJ Scan Coverage: Upstream i] Downstream i CW i CCW i.
Comments:
FC 99-02, 03-17, 03-30
- 60°L Scanning Db 68.8, 45*L 74.8 Db Results: Accept I2 Reject ] Info E Percent Of Coverage Obtained > 90%: No - 69.3% Reviewed Previous Data: Yes Examiner Level lql ature Date Review r Signature Date Eaton, Jay A. _ 5/2512005 7r(5 Examiner Level Signature Date Site Review Signature Date Moss, Gary J. XVJt /5/25/2005 N/A Other Level N/A rSignature Date ANII Review nature 8 at N/A _ _ _ _ - _ _ _ ' _ _ _ _
1m Duke Determination of Percent Coverage for t&bEnergy- UT Examinations - Vessels Site/Unit: Catawba / I Procedure: NDE-630 Outage No.: CNSI EOC15 Summary No.: B12.040.002D Procedure Rev.: 2 Report No.: UT-05-211 Workscope: ISI Work Order No.: 98688919 Page: 2 of 8 0 deg Planar Scan % Length X % volume of length /100 = % total for 0 deg 45 den
'can 1 % Length X % volume of length 100 = % total for Scan 1 Scan 2 % Length X % volume of length / 100 = % total for Scan 2 Scan 3 % Length X % volume of length / 100 = % total for Scan 3 C % total for Scan 4 Scan 4 % Length X % volume of length /100 =
Add totals and divide by # scans = % total for 45 deg Other deg 45I600 Scan 1 100.000 % Length X 36.400 % volume of length / 100 = 36.400 % total for Scan 1 Scan 2 100.000 % Length X 95.220 % volume of length / 100 = 95.220 % total for Scan 2 Scan 3 100.000 % Length X 72.870 % volume of length / 100 = 72.870 % total for Scan 3 Scan 4 100.000 % Length X 72.870 % volume of length / 100 = 72.870 % total for Scan 4 Add totals and divide by # scans = 69.340 % total for 45°/60°* deg Percent complete coverage Add totals for each angle and scan required and divide by # of angles to determine; 69.340 % Total for complete exam Note:
Supplemental coverage may be achieved by use of other angles / 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:
\I--j 1 - Date: O*IVS lo /
b9'
DUKE POWER COMPANY ISI LIMITATION REPORT Component/Weld ID: IND-37A Item No: B12.040.002D remarks:
[3 NO SCAN SURFACE BEAM DIRECTION Valve Bonnett Conf.
E LIMITED SCAN l1 a 2 0 1 Z 2 0 cw g ccw FROM L N/A to L N/A INCHES FROM WO -.75 to Beyond ANGLE: Li 0 Z 45 RI 60 other FROM 0 DEG to 360 DEG Li NO SCAN SURFACE BEAM DIRECTION Valve Body Conf.
Z LIMITED SCAN L 1I Z2 Z 1 0 2 0 cw I ccw FROM L N/A to L N/A INCHES FROM WO +1.9 to +3.4 ANGLE: E] 0 0J 45 Z 60 other FROM 0 DEG to 360 DEG L NO SCAN SURFACE BEAM DIRECTION Valve Body Conf.
ZLIMITEDSCAN [31 2 1 E0 2 L cw L ccw FROM L N/A to L N/A INCHES FROM WO +1.9 to +3.2 ANGLE: [3 0 Z 45 a] 60 other FROM 0 DEG to 360 DEG L NO SCAN SURFACE BEAM DIRECTION E LIMITED SCAN LII 221 [i 2 L cw E ccw FROM L to L INCHES FROM WO to Sketch(s) attached ANGLE: LI0°O 45 L] 60 other FROM DEG to DEG Z yes EJ No Prepared By: David Zi nmerman f 1 Level:ill Date: 05/25/2005 Sheet LA of S Reviewed B Date: Authorized Inspector: Date:
Y Pt99
DUKE POWER COMPANY ISI LIMITATION REPORT Component/Weld ID: IND-37A Item No: B12.040.002D remarks:
El NO SCAN SURFACE BEAM DIRECTION Valve Bonnett Conf.
0 LIMITED SCAN 1 02 F1 LI I 0 2 0 cw E ccw FROM L N/A to L N/A INCHES FROM WO -.75 to Beyond ANGLE: Li 0 E 45 LI 60 other FROM 0 DEG to 360 DEG E NO SCAN SURFACE BEAM DIRECTION E LIMITEDSCAN I1 a2 Eli 0 2 0 cw E ccw FROM L to L INCHES FROM WO to ANGLE: LI 0 LI 45 L0 60 other FROM DEG to DEG El NO SCAN SURFACE BEAM DIRECTION D LIMITEDSCAN El I El 2Elcw 2Eli F ccw FROM L to L INCHES FROM WO to ANGLE: LI 0 La 45 E] 60 other FROM DEG to DEG E NO SCAN SURFACE BEAM DIRECTION ElLIMITED SCAN El 1 LI 2ElI 2Elcw l ccw FROM L to L INCHES FROM WO to Sketch(s) attached ANGLE: aI 0 El 45 LI 60 other FROM DEG to DEG Z yes E No Prepared By: David Z mmerman f Level: 11 Date: 05/25/2005 Sheet 3 of -,
Reviewed By: Date: Authorized Inspector: Date:
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DUKE POWER COMPANY ISI LIMITATION REPORT Component/Weld ID: IND-37A Item No: B12.040.002D remarks:
El NO SCAN SURFACE BEAM DIRECTION Valve Bonnett Conf.
(0 LIMITED SCAN 1 0 2 0 I E 2 0 cw L ccw FROM L N/A to L N/A INCHES FROM WO -.75 to Beyond ANGLE: E 0 E 45 El 60 other FROM 0 DEG to 360 DEG E NO SCAN SURFACE BEAM DIRECTION Valve Bonnett Conf.
E LIMITED SCAN E I E 2 l I E1l 2 El cw El ccw FROM L N/A to L N/A INCHES FROM WO -.75 to Beyond ANGLE: E 0 E 45 E 60 other FROM 0 DEG to 360 DEG E NO SCAN SURFACE BEAM DIRECTION Valve Body Conf.
E LIMITED SCAN El I [E 2 Z 1 E 2 l cw l ccw FROM L N/A to L N/A INCHES FROM WO +1.9 to +3.4 .
ANGLE: El 0 E 45 E 60 other FROM 0 DEG to 360 DEG El NO SCAN SURFACE BEAM DIRECTION Valve Body Conf.
Z LIMITED SCAN 0 1 Z 2 Z 1 l 2 E cw 1 ccw FROM L N/A to L N/A INCHES FROM WO +1.9 tC) +3.2 Sketch(s) attached ANGLE: El ° 45 E 60 01ther FROM 0 DEG to 360 DEG E yes l No Prepared By: David Zimmerman Reviewed By:
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ML Duke UT Pipe Weld Examination r&Energy.
Site/Unit: Catawba / 1 Procedure: NDE-600 Outage No.: CNSI EOC15 Summary No.: C0! 5.011.049 Procedure Rev.: 16 Report No.: UT-05-1 69 Workscope: 'SI Work Order No.: 98688907 Page: 1 of _^>
Code: Asme Section Xi 1989 Cat./Item: C-F-11C5.11.49 Location: NIA Drawing No.: CN-1ND-39
Description:
Valve (1ND2A) to PIpe System ID: ND Component ID: C05.011.049 /1ND39-12 Size/Length: NIA Thickness/Diameter: 1.125" / 12" Limitations: Yes-See Attached Limitation Report Start Time: 1201 Finish Time: 1239 Examination Surface: Inside E Outside i 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.: MCNDE32797 Surface Temp.: 79 OF Cal. Report No.: CAL-05-183, CAL-05-184, CAL-05-185 Angle Used 10 45 145T 60 60L l l Scanning dB 46.0 46.4 52.3 Indication(s): Yes D No i Scan Coverage: Upstream f Downstream E1 CW pi CCW iz Comments:
FC 05-08 Results: Accept Fi Reject E Info E Percent Of Coverage Obtained > 90%: No -76.1% Reviewed Previous Data: Yes Examiner Level iII Signature Date Reviewer Signature Date Zimmerman, David K. 5/20/2005 TU13.
Examiner Level // Signature, Date Site Review Signature Date Moss, Gary J. gash / 91/ 5/20/2005 N/A Other Level NIA V Signature Date ANII Review JfL.I Sign r? Date NIAl3w Act h8 S/e0-g>-~v tzatsar PAS
DUKE POWER COMPANY ISI LIMITATION REPORT ComponentlWeld ID: 1ND39-12 Item No: C05.011.049 remarks:
El NO SCAN SURFACE BEAM DIRECTION Valve Configuration E LIMITED SCAN 1 Z 2 3 1 0 2 a cw l ccw FROM L N/A to L N/A INCHES FROM WO +1.1" to Beyond ANGLE: 0 El 45 Z 60 other FROM 0 DEG to 360 DEG E NO SCAN SURFACE BEAM DIRECTION El LIMITED SCAN EI1 l2 0 I1 C 2 Ll cw E-c ccw FROM L to L INCHES FROM WO to ANGLE: EJ 0 El 45 El 60 other FROM DEG to DEG F] NO SCAN SURFACE BEAM DIRECTION E LIMITED SCAN EI E0 2 I1 0 2 E cw E ccw FROM L toLL INCHES FROM WO to ANGLE: El 0 El 45 El 60 other FROM DEG to DEG al NO SCAN SURFACE BEAM DIRECTION E LIMITED SCAN I l2 El 1 E22 l cw E ccw FROM L to L INCHES FROM WO to Sketch(s) attached ANGLE: El 0 El 45 El 60 other FROM DEG to DEG E yes E No David Zimmerman -lD III 05/20/2005 Sheet of , 7 Reviewed By: C A Date: .5,3iAuthorized Inspector: Date:
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Duke Determination of Percent Coverage for P1Energy. UT Examinations - Pipe Site/Unit: Catawba/ 1 Procedure: NDE-600 Outage No.: CNSIEOC15 Summary No.: C05.011.049 Procedure Rev.: 16 Report No.: UT-05-169 Workscope: IS1 Work Order No.: 98688907 Page: 3 of 3 45 den Scan I % Length X % volume of length /100 = % total for Scan 1 Scan 2 % Length X % volume of length / 100 = % total for Scan 2 Scan 3 100.000 % Length X 100.000 % volume of length / 100 = 100.000 % total for Scan 3 Scan 4 100.000 % Length X 100.000 % volume of length / 100 = 100.000 % total for Scan 4 Add totals and divide by # scans = 100.000 % total for 45 deg Other deg - 60 (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 1 100.000 % Length X 52.860 % volume of length 100 = 52.860 % total for Scan 1 Scan 2 100.000 % Length X 51.430 % volume of length /1 00 = 51.430 % total for Scan 2 Scan 3 % Length X % volume of length /1 00 = % total for Scan 3 Scan 4 % Length X % volume of length 1100 = % total for Scan 4 Percent complete coverage Add totals for each scan required and divide by # of scans to determine; 76.073 % Total for complete exam Site Field Supervisor {,,,/ Date:(<7O/
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I -c PDuke D.M. JAMIL Vice President OFPower, Duke Power Catawba Nuclear Station 4800 Concord Road / CNOI VP York. SC 29745-9635 803 831 4251 803 831 3221 {ax June 14, 2005 U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 ATTENTION: Document Control Desk
Subject:
Duke Energy Corporation Catawba Nuclear Station Unit 1 Docket No. 50-413 Response to NRC Bulletin 2004-01: Inspection of Alloy 82/182/600 Materials Used in the Fabrication of Pressurizer Penetrations and Steam Space Piping Connections at Pressurized-Water Reactors
Reference:
Letter from Duke Energy Corporation to the NRC, same subject, dated July 27, 2004 NRC Bulletin 2004-01, "Inspection of Alloy 82/182/600 Materials Used in the Fabrication of Pressurizer Penetrations and Steam Space Piping Connections at Pressurized-Water Reactors," required that within 60 days of plant restart following the next inspection of Alloy 82/182/600 pressurizer penetrations and steam space piping connections, submit to the I*
NRC a statement indicating that the inspections described in 11;)
the response to item (1)(c) of the bulletin were completed and 1 a description of the as-found condition of the pressurizer I shell, any findings~ of relevant indications of through-wall leakage, followup NDE performed to characterize flaws in leaking penetrations or steam space piping connections, a 31 summary of all relevant indications found by NDE, a summary of the disposition of any findings of boric acid, and any corrective actions taken and/or repairs made as result of the indications found.
During the Catawba Unit 1 Refueling Outage (lEOC15),
,Y1 inspections described in the response to item (1)(c) of the Iii bulletin were completed. A 100% bare metal visual (BMV) 11 Gwa Nudcar Stadon2Oth ni'd www.dukepower.com 19ss-2005
U.S. NRC June 14,2005 Page 2 examination was performed on all Alloy 82/182/600 weld locations on the pressurizer. These BMV inspections were performed by VT-2 qualified inspectors. The inspection scope included the following locations:
(1) pressurizer surge line nozzle weld (3) pressurizer safety valve nozzle welds (1) pressurizer spray nozzle weld (1) pressurizer PORV nozzle weld (1) pressurizer manway There was no evidence of leakage or boric acid deposits observed at any of these locations. The exterior surfaces are in very good condition with no wastage of the top or bottom heads.
There are no NRC commitments contained in this letter.
Inquiries on this matter should be directed to A. Jones-Young at (803) 831-3051.
Very truly yours, D.M. Jamil Site Vice President
U.S. NRC Jne 14,2005 Page 3 D. M. Jamil, being duly sworn, affirms that he is the person who subscribed his name to the foregoing statement, and that all matters and facts set forth herein are true and correct to the best of his knowledge.
Subscribed and sworn to me: '-141-OS
, Notary Public My commission expires: 7-/a- AO l SEAL
U.S.NRC June 14, 2005 Page 4 xc:
W. D. Travers U. S. Nuclear Regulatory Commission Regional Administrator, Region II Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 Atlanta, GA 30303 S. E. Peters NRC Project Manager U. S. Nuclear Regulatory Commission Mail Stop 0-8 H12 Washington, DC 20555-0001 E. F. Guthrie Senior Resident Inspector U. S. Nuclear Regulatory Commission Catawba Nuclear Site H. J. Porter Division of Radioactive Waste Management South Carolina Bureau of Land and Waste Management 2600 Bull Street Columbia, SC 29201
I *
- 6 U.S. NRC June 14,2005 Page 5 bxc:
L. F. Vaughn L. A. Keller W. 0. Callaway D. L. Ward A. D. Jones-Young K. E. Nicholson RGC Master File NSRB ELL Catawba Owners:
Saluda River Electric Corporation P. 0. Box 929 Laurens, SC 29360-0929 NC Municipal Power Agency No. 1 P. 0. Box 29513 Raleigh, NC 27626-0513 T. R. Puryear NC Electric Membership Corporation CN03G Piedmont Municipal Power Agency 121 Village Drive Greer, SC 29651