NLS2005105, Response to NRC Request for Additional Information Regarding Inservice Inspection Relief Requests RI-21, Rev 2, and RI-36
| ML053470118 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 12/08/2005 |
| From: | Edington R Nebraska Public Power District (NPPD) |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| NLS2005105, TAC MC8512 | |
| Download: ML053470118 (22) | |
Text
Nebraska Public Power District Always there when you need us 10 CFR 50.55a NLS2005105 December 8, 2005 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001
Subject:
Response to U.S. Nuclear Regulatory Commission Request for Additional Information Regarding Inservice Inspection Relief Requests RI-21, Revision 2, and RI-36 Cooper Nuclear Station, Docket No. 50-298, DPR-46
References:
- 1. Letter from Brian Benney, U.S. Nuclear Regulatory Commission, to Randall K. Edington, Nebraska Public Power District, dated November 21, 2005, "Cooper Nuclear Station - Request for Additional Information.
RE: Relief Requests RI-21, Revision 2, and RI-36 (TAC No. MC8512)"
- 2. Letter from Randall K. Edington, Nebraska Public Power District, to U.S.
Nuclear Regulatory Commission, dated September 28, 2005, "Inservice Inspection Relief Requests RI-2 1, Revision 2, and RI-36 and Withdrawal of Relief Request RI-20" The purpose of this letter is to submit the Nebraska Public Power District's response to the Nuclear Regulatory Commission's Request for Additional Information (Reference 1) regarding Inservice Inspection Relief Requests RI-21, Revision 2, and RI-36 (Reference 2). The response is attached. Per your request, drawings for Welds RVD-BJ-17 and RVD-BJ-18 pertaining to Relief Request RI-36 are provided on the enclosed data sheets.
Should you have any questions concerning this matter, please contact Paul Fleming, Licensing Manager, at (402) 825-2774.
Sincerely, Randall K. Edington Vice President - Nuclear and Chief Nuclear Officer COOPER NUMEAR STATION P.O. Box 98 / Brownville, NE 68321-0098 Telephone: (402) 825-3811 / Fax: (402) 825-5211 www.nppd.com
NLS2005 105 Page 2 of 2
/sl Attachment Enclosure cc: U.S. Nuclear Regulatory Commission w/attachment/enclosure Regional Office - Region IV Senior Project Manager w/attachment/enclosure USNRC - NRR Project Directorate IV- 1 Senior Resident Inspector w/attachment/enclosure USNRC - CNS NPG Distribution w/attachment/enclosure CNS Records w/attachment/enclosure
NLS2005105 Attachment Page 1 of 8 Attachment Response to NRC Request for Additional Information Regarding Inservice Inspection Relief Requests RI-21, Revision 2, and RI-36 Nebraska Public Power District Cooper Nuclear Station
References:
Letter from Brian Benney, U.S. Nuclear Regulatory Commission, to Randall K.
Edington, Nebraska Public Power District, dated November 21, 2005, "Cooper Nuclear Station - Request for Additional Information. RE: Relief Requests RI-21, Revision 2, and RI-36 (TAC No. MC8512)"
Letter from Randall K. Edington, Nebraska Public Power District, to U.S.
Nuclear Regulatory Commission, dated September 28, 2005, "Inservice Inspection Relief Requests RI-2 1, Revision 2, and RI-36 and Withdrawal of Relief Request RI-20" Relief Request Number RI-21, Revision 2 NRC Ouestion No. 1 Confirm that nozzles NVE-BD-N9 andNVE-BD-N4A&C are the only two components that are affected under Relief Request RI-21, Revision 2. There are 28 nozzles listed in this relief request; however, in the "Basisfor Relief' section, the discussionfocuses only on nozzles NVE-BD-N4A&C and NVE-BD-N9.
NPPD Response Yes, nozzles NVE-BD-N9 and NVE-BD-N4A&C are the only two components affected under Relief Request RI-2 1, Revision 2. The following relief was requested:
- 1. Request a reduction in coverage associated with the N9 nozzle-to-shell weld from 70% to 40%.
- 2. Remove the reference to the inner radius examination coverage for N9 [% examined is specified as 70% in Relief Request Table RI-2 1-1, Revision 1, approved by the NRC on October 23, 1997 (TAC No. M94000)].
- 3. Revise the access limitations for NVE-BD-N4A&C. The access limitations for N4A&C were revised to include limitations from adjacent nozzles. This information was provided for completeness and does not alter the basis of relief as approved by the Nuclear Regulatory Commission (NRC) in Revision 1 of this relief request.
NLS2005105 Attachment Page 2 of 8 NRC Ouestion No. 2 The licensee stated that the total volumetric examination coverage of nozzle NVE-BD-N9 was 40 percent. Thefigure in the attachmentto the September 28, 2005, letter does not provide sufficient information regardinghow the 40 percent coverage was achieved. Please demonstrate the 40 percent coverage by calculations and diagrams.
NPPD Response The ultrasonic examination volume includes the outer 85 percent thickness and the inner 15 percent thickness as measured from the inside diameter surface. The 60 degree RL scans were used to examine the entire weld volume with the exception of the lower 15 percent in the circumferential direction. The EPRI Model parameters were used to inspect the lower 15 percent of the examination volume using the required shear wave scans.
The 60 degree RL/Zone -1 and the 60 degree RL/Zone -2 scans, along with the combined model scans were used to calculate the total examination coverage and limited/no scan area not covered by these techniques. The examination limitations are shown in square inches in order to simplify calculations.
Required Examination Area = Upper 85% + Lower 15% = 45.10 in' + 6.56 in2 Required Examination Area = 51.66 in2 Upper 85% Scan Area Examined = 26.87 in2 Lower 15% Scan Area Examined = 6.56 in2 Upper 85% Limited Scan Area = 18.23 in 2 Lower 15% Limited Scan Area = 0.00 in2 No scan coverage in limited area due to adjacent insulation ring = 23.72%
Model and 60 degree RL Percentages:
Total Weld Coverage = (Upper 85% + Lower 15%) - (No Scan Coverage Area)
Total Weld Coverage = [(26.87 in 2 + 6.56 in2 ) - 51.66 in2 ] X 100 - 23.72%
Total Weld Coverage: 64.71% - 23.72% = 40.99%
Total Weld Coverage = 40.99%
NLS2005105 Attachment Page 3 of 8 The figure below shows the examination volume limitations to the applicable examination zones as required per ASME Section XI, Figure IWB-2500-7(a).
Sketch Of Lknitation(s):
N NozzleV MLEWIP.Oilt 60R Exil Posir 0- I I Ltpeu 85%
fto Lc,~ci 15%~
NVIR-BD-N9 (RPV Nozzle to Shell - Nozzle L NVE-BD-N9 Inner Radius Section) RPV Nozzle to Shell Weld Lower 15% (i.e., inner 100% coverage achieved. 15%) received 100% volume coverage.
Previous exam achieved 70%.
NLS2005105 Attachment Page 4 of 8 NRC Ouestion No. 3 The submittal stated that the inner radius examination of nozzle NVE-BD-N9 in the third intervalachieved 100 percent of the requiredexamination volume. It also statedthat the inner 15 percent of the nozzle received 100 percent coverage. Discuss why the volumetric examination can achieve 100 percent coverage in the inner radius region, but only 40 percent coverage was achieved.
NPPD Response The nozzle is divided into two distinct examination zones: the nozzle-to-shell weld zone (ASME Code Item B3.90) and the inner radius zone (ASME Code Item B3.100). Each zone for the N9 nozzle has two distinctive component identifiers in the Cooper Nuclear Station (CNS) Inservice Inspection (ISI) Program. The nozzle-to-shell weld is identified as NVE-BD-N9, and the inner radius zone is identified as NVIR-BD-N9. The nozzle-to-shell weld zone and also the inner radius zone each have their own respective code volumes that are required to receive a volumetric examination. Figure IWB-2500-7(a), "Nozzle in Shell or Head,"
illustrates the most applicable examination zones for CNS. Zone M-N-O-P is the inner radius zone, and Zone A-B-G-H-I is the nozzle-to-shell weld zone.
Revision 1 of the relief request originally listed the coverages for both zones on N9 as 70 percent (i.e., 70 percent for nozzle-to-shell weld zone and 70 percent for inner radius zone).
All the other nozzles listed in Relief Request Table RI-21-1 only referred to the nozzle-to-shell weld zones and did not include the inner radius zone as N9 did. All the other examinations for the nozzle inner radius zones achieved the required inner coverage.
Therefore, their respective coverages were not listed.
The 40 percent coverage stated in the relief request only applies to the nozzle-to-shell weld zone NVE-BD-N9. Within the required examination volume associated with NVE-BD-N9, that zone or volume is divided into the lower 15 percent region and upper 85 percent region of the nozzle-to-shell weld examination volume. The relief request stated that 100 percent coverage was achieved for the lower 15 percent region, which is the region of most concern for flaw initiation. The upper (outer) 85 percent region is less of a concern.
The figure on Page 3 of this attachment shows the exam volume associated with NVE-BD-N9 and NVIR-BD-N9. The inner radius zone (NVIR-BD-N9) is a different exam volume than the inner 15 percent region shown as the cross-hatched area in the figure. The area to the left of the cross-hatched area is the inner radius zone that is examined under a different technique and reported on a different data sheet. With our most recent examination, we achieved 100 percent of the inner radius zone compared to 70 percent in Interval 2 (1995). Since we achieved 100 percent code-required volume for the inner radius zone, we revised the table in the relief request to remove the inner radius zone coverage of 70 percent that was previously approved by the NRC in Revision 1 of the relief request.
NLS2005 105 Attachment Page 5 of 8 NRC Ouestion No. 4(A)
The submittal stated that "Based on EPPJ[ElectricPowerResearch Institute] modeling of the examination volume... a higher quality of examination was achieved even though less overall coverage was achieved.... " Discuss how does the EPRI modeling of the examination volume lead to a higher quality of examination.
NPPD Response The relief request should have stated that a more reliable examination was performed based on the EPRI Modeling and Performance Demonstration Initiative (PDI) techniques that were utilized. The EPRI modeling provides the geometric inputs and parameters so the PDI-qualified examiner can more reliably perform the examination and have more confidence that any flaw present would be detected.
NRC Ouestion No. 4(B)
The submittal also stated that '"..the requirementto use only PerformanceDemonstration Initiative (PDI)-qualifiedtransducerslimited the examination to coverage and contributed to a reduction of coverage compared to previous examinations in the outer 85% volume. "
Discuss whether an approach basedon less coverage with a higher quality examination (as opposed to more coverage with a lower quality examination) is appropriatein terms of detectingflaws in the nozzles in the CooperNuclear Station.
NPPD Response Since 10 CFR 50.55a requires the use of ASME XI Appendix VIII in detecting flaws in the nozzles in CNS, only qualified PDI procedures and specific qualified transducers may be used for this examination. Previous examinations may have reported additional coverage, but since the previous examiners and equipment were not qualified by performance demonstration, the coverage reported back then cannot be considered as reliable as today. Nozzle modeling in conjunction with PDI examination methods maximizes the coverage that can be "reliably" obtained, even though PDI-qualified transducers and associated procedures limit how much coverage an examiner is able to attain.
NLS2005105 Attachment Page 6 of 8 NRC Ouestion No. 4(C)
Discuss the results ofprevious examinations of nozzle NVE-BD-N9.
NPPD Response Examination of NVE-BD-N9 was first performed in Interval 1 in 1985 with no coverage percentage reported. Examination of NVE-BD-9 was next performed in Interval 2 in 1993 with a 70% coverage obtained. Both examinations predate the requirement to use PDI techniques. No recordable indications were detected in the weld.
NRC Ouestion No. 5 In a letter dated October 23, 1997, the NRC staff approvedRelief Request RI-21, Revision 1.
In the NRC staffs safety evaluation containedin that letter, the staffdiscussed a visual examination, VT-2, associatedwith inservice inspection of nozzle NVE-BD-N9. Discuss whether the visual examination, VT-2, has been conducted and will be performedfor nozzle NVE-BD-N9 in conjunction with the requiredvolumetric examinations.
NPPD Response Yes, the VT-2 examination of this nozzle is performed every refueling outage in accordance with the vessel pressure test per Category BP of ASME Section XI. It was last performed in Refueling Outage 22 (2005) with no visible leakage detected.
Relief Request Number RI-36 NRC Ouestion No. 6 Provide a drawing of the subject welds R VD-BJ-1 7 and R VD-BJ-18, including the volume that were volumetrically examined, angle and trace of transmittingand receivingsignals, and examination interferences.
NPPD Response The drawings of the welds are provided on the enclosed Ultrasonic Examination Scan Limitation Sheets (page 5 of 5 for each data set) for Welds RVD-BJ-17 and RVD-BJ-18.
The examination was performed manually; therefore, only the beam angle is provided. Since an automated examination was not performed, a trace of transmitting and receiving signals cannot be provided.
NLS2005105 Attachment Page 7 of 8 The limitation was due to the "as welded" crown. (See the enclosed Ultrasonic Examination Scan Limitation Sheets, page 5 of 5 for each data set.) Conditioning the crown may have achieved more examination volume coverage; however, the inadvertent removal of weld metal below code minimum on a thin material may have occurred on one or both of the segments and, therefore, was not performed. There were no other interferences identified.
NRC Question No. 7 Identify the pipingsystem with which subject welds R VD-BJ-1 7 and R VD-BJ-1 8 are associated. Discuss results of the previous volumetric examination of R VD-BJ-1 7 and R VD-BJ-18.
NPPD Response The piping welds are located on the Reactor Recirculation System.
Volumetric examinations of these two welds were first examined in Refueling Outage 22 (2005), with no recordable indications. Prior to the application of Risk-Informed ISI, volumetric examination of these welds was not required. These welds were recently added to the population of welds to be scheduled for volumetric examinations with the implementation of Risk-Informed ISI.
NRC Question No. 8 The submittalstated that alternateangles were used; however, due to high signal-to-noise ratios additionalcoverage could not be achieved. Identify the originaltransducerangles and alternateangles used. Discuss whether the originalangles used in the examination result in high signal-to-noise ratioand whether the examination results were not distorted by the signal-to-noise ratio.
NPPD Response 45-degree and 60-degree transducers were used with acceptable signal-to-noise ratios. The signal-to-noise ratio for the 70-degree transducer was not acceptable; therefore, it was not used. (See the enclosed examination summary data sheets for RVD-BJ-17 and RVD-BJ-18.)
NLS2005105 Attachment Page 8 of 8 NRC Ouestion No. 9 The submittal stated that the affected welds in Relief Request RI-36 were selected to be included in risk-informed inservice inspection. Discuss how does ReliefRequest RI-36 satisfy the reliefrequest guidelines in EPRI TR-112657, Revision B-A, "Revised Risk-Informed Inservice Inspection EvaluationProcedure (PWRMRP-05), " FinalReport, December 1999.
NPPD Response In accordance with EPRI TR-1 12657, Revision B-A, Section 6.4, if greater than 90%
coverage cannot be obtained for the selected welds, and none of the other welds in that segment would yield better coverage, the utility is directed to submit a relief request. RVD-BJ-17 and RVD-BJ-18 were selected because they gave the best access for examination.
These welds are located in two-inch small bore piping. These two welds are grouped with 15 other small bore welds that are either butt welded or socket welded. These welds are classified as risk Category 4 with a risk characterization ranking of medium, consequence ranking of high, and failure potential ranking of low. The reduction in coverage from the required 90% to slightly greater then 84% has little or no impact to the overall risk contribution.
NLS2005105 Enclosure Enclosure Areva Examination Summaries for the Cooper Nuclear Station Summary No. B9.21.0032.R1 System/Component ID NBDR/RVD-BJ-17 Data Package CNSDPO72-RF022 January 26, 2005 (Approved February 2, 2005)
Pages 1 - 3 & 5 and Attachment Summary No. B9.21.0033.R1 System/Component ID NBDR/RVD-BJ-18 Data Package CNSDPO71-RF022 January 26, 2005 (Approved February 8, 2005)
Pages 1 - 3 & 5 and Attachment
MAL6M00ol/d5 r4ckure- I 7avz e / e9 f /o DA EXAMINATION
SUMMARY
AREVA Summary No.: B9.21.0032.R1 Data Package: CNSDPO72-RF022 Exam Date: 01-26-2005 Customer Cooper Nuclear Station, NPPD Examination Methods: UT System I Component ID: NBDR I RVD-BJ-17 Examination Procedures: 544SI-836-08 Component
Description:
PIPE TO ELBOW Calibration Sheets No(s): CNS.05-061 &
CNS-05-062 Examination 1 No Reportable Indications Examination Category: RA Results:
[l Reportable Indications ISO I Drawing: X-2512-200 0 Geometric Summary.
This examination was done to ASME section Xl appendix Vill, 1995 edition with editions and addenda through 2000.
The 45- shear and the 60- shear were used for optimum flaw detection. A70 shear was not used due to high signal to noise ratio.
No recordable indication noted with either45 or 60- shear.
8421% code required volume achieved using the 45 and 60 transducers, due to the as welded crown height.
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ASL* d5L/3,b5 02 Pr c/h<ISret. ) 0 etqie ;~ 7C/c UT CALIBRATMlA DATA SHEET Customer: Cooper Nuclear Station, NPPD Exam Date: 01126r20D5 Summary No.: B9.21.0032R1 System/ Component I.D.: NBDR/ RVD-BJ-17 Calibration No.: CNS-05-061 Component
Description:
2.0f PIPETOELBOWWELD ISOi Drawing No.: X-2512-200 Procedure No. IRev.: 54-1S1S-808 Code / Accept. Criteria: IWB-3514 Material: STAINLESS STEEL Diameter: 2.0 Thickness: .215" INSTRUMENT SETTINGS SEARCH UNIT CALIBRATION STANDARD Mfg: KBA i Model: USN 58L DB/ISerial No.: 34570 Cal. Block No.: 7500285 Serial/ MT&E #: VH-9)74 Size: .25" Cal. Block Thiciness (in): .50r Mat. Cal. I Velocity: 0.1212 Freq. (MHz): 225 MHZ Cal. Block Dia. (in): NMA Delay: O.000 Zero Offset: 6.588 Long/ Shear1 Single/ Dual: SHEAR / SINGLE Temp (F) Block: 74 l Comp.: 84 Each Major Screen Div. 1: .1 Nominal Angle: 45 Measured: 45 Therm. No.: VH-8043 Channel#: N/A Fixture/ Size: MSWQC Couplant Type: EXOSEN 30 Range: 1.0 Freq (MHz): 2.25 CableType&Length: RG-174 Couplant Batch No.: 32104301 Damping: 10000 Reject; OFF No. of Connectors: 0 CALIBRATION STD. SIMULATOR Rep. Rate:AUTOHIGH Pulse: HIGH DAC PLOT Serial No.: N/A Gate: N/A Display: FULLWAVE Sweep Position / Depth: N/A Mode: P.E. Jack: T 100 - Signal Amp. (%): N/A Ref. Sensitivity: 31.0 dB90 - Gain DB (dB): N/A Scan Sensitivity: 37.0 dBo8 - EXAM DATA (Amt. DB to bring Notch to DAC) 70 -_Scan Direction to Wed:90T-WELD=TOWELD Noc Notch dB (Piping): NNA-B Ppn): 60--
0 __
- (0 to WRV; 0 to Material; 90 to Weld; = to Weld)
Notch dB (Vessels): NIA Recordable Geometry (Yes / No): NO 40 - --
CALIBRATION CHECK 30 -. Recordable Indications (Yes / No): NO Time OK Initials 20- _ _ _ _ _ _ LimitedExam(Yes/No): YES Initial Cal: 0300 OK TLK 10 _- _ - _ -_ _ _ Percent Scan Completed: 84.21%
Init. Sim. Cal: N/A N/A N/A 0 _ - Percent Exam Completed: 84.21%
Intermediate: N/A N/A N/A 0 1 2 3 4 5 6 7 8 9 10 0 DEG. WELD THICKNESS ONLY Intermediate: N/A N/A N/A Comp.: N/A Intermediate: N/A N/A NIA Amplitude vs. Range BM: NIA HAZ: N/A Intermediate: NIA N/A N/A Signal to Noise Ratio: 8:I- 9 C/L Weld: N/A Intermediate: N/A NMA N/A Comp: N/A Final Cal.: 0505 OK TLK BM: N/A HAZ: N/A Scan Direction on Cal. Block ODeg. I Axial ,I irc I flT B HA.
1A
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Description:
2.0 PIPETOELBOWWELD ISO/ Drawing No.: X-2512-200 Procedure No. / Rev.: -54451- 08 Code / Accept. Criteria: IWB-3514 Material: STAINLESS STEEL Diameter 20" Thickness: .21w INSTRUMENT SETTINGS SEARCH UNIT CALIBRATION STANDARD Mfg: KBA I Model: USN 58L DB I Serial No.: 34790 Cal. Block No.: 7500285 Serial / MT&E #M VH-9074 Size: .25 Cal. Block Thickness (in): .50' Mat. Cal./ Velocity: 0.1247 Freq. (MHz): 2.25 MHZ Cal. Block Dia. (in): N/A Delay: 0.000 I Zero Offset: 8.5269 Long / Shear / Single / Dual: SHEAR / SINGLE Temp (F) Block: 74 l Comp.: 84 Each Major Screen Div. #: .15' NominalAngle: 60 I Measured: 60 Therm. No.: VH-8043 Channel #: NIA Fixture / Size: MSWQC Couplant Type: EXOSEN 30 Range: 1.5" Freq (MHz): 2.25 Cable Type & Length: RG-174/ 12' Couplant Batch No.: 32104301 Damping: 10000 Rejed: OFF No. of Connectors: 0 CALIBRATION STD. SIMULATOR Rep. Rate:AUTOHIGH Pulse: HIGH DAC PLOT Serial No.: 7500772 Gate: NIA Display: FULLWAVE Sweep Position / Depth: 7.0 Mode: P.E. Jack: T 100 - - - - - - Signal Amp. (%): 40%
Ref. Sensitivity: 53.0 dB 90- _ _ _ _ _ Gain DB (dB): 34.0 dB Scan Sensitivity: 53.0 dB 80 - - _ _ -_ _ _ EXAM DATA 70 -
(Amt. DB to bring Notch to DAC) Scan Direction to Weld:90 TO WELD Notch dB (Piping): N/A i- ( to WRV; 0 to Material; 90 to Weld; to Weld) 50--
Notch dB (Vessels): N/A 4 Recordable Geometry (Yes / No): NO CALIBRATION CHECK 30 - _ _ _ _ _ _ _ _ Recordable Indications (Yes / No): NO Time OK Initials 20 _ _ _ _ _ _ Limited Exam (Yes I No): YES Initial Cal: 0310 OK TLK 10 - Percent Scan Completed: 84.21%
InM.Sim.Cal: 0312 OK TLK 0 _ Percent Exam Completed: 84.21%
Intermediate: 0320 OK TLK 0 1 2 3 4 5 6 7 8 9 10 0 DEG. WELD THICKNESS ONLY Intermediate: NIA N/A N/A Comp.: N/A Intermediate: N/A N/A N/A Amplitude vs. Range BM: N/A HAZ: N/A Intermediate: . NtA N/A N/A Signal to NoiseRatio: 8 TO I C/L Weld: N/A Intermediate: NWA N/A N/A Comp: N/A Final Cal.: 0510 OK nK BM: N/A HAZ: N/A Scan Direction on Cal. Block 0 Deg. Axial Circ Crown HT.: N/A (Yes / No) NO YES NO Weld Width: N/A Refledor NOTCH NIA NWA N/A N/A N/A N/A N/A Sweep Pos. / Depth in Inches 6.61/.50 N/A N/A N/A NIA N/A N/A NWA Amplitude in % 80% N/A N/A N/A N/A N/A N/A N/A Gain in dB 53.0 N/A N/A N/A N/A N/A N/A NIA Notes: Performed a 60 shear, axial (perpendicular to weld) examination of Pipe to Elbow WeId (RVD-B.-17)_
No recordable indications were noted. Limited exam due to weld crown height, 84.21% code volume achieved.
INCD' i ID roll 20% @ 3.0 sweep divisions. ~~~J L2 Z- -I - a Examiner: Examiner: N/A Sign: / Level: 11 Date: 01/26/05 Level: N/A Date: N/A
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AREVA ULTRASONIC EXAMINATION SCAN LIMITATION REPORT Customer Cooper Nudear station, NPPD Component: 2" PIPE TO ELBOW Summary No.: B9.21.0032.R1 Weld No.: RVD-BJ-1T Percent Of Exam Completed (Calculations Or Conmnents Below)
Reference Point MA
- 1) Interfering Condition AS WELDED WELD CROWN 84.21% code volume acbleve4 Distance From Centerline NIA TO WA Total coverage missing .0151' Distance From Ref. Point WA To NIA
- 2) Interfering Condition WA .095"I total area of lower % =
Distance From Centerline WA To NtA
.095"' - .015"' = .080 Distance From Ref. Point NtA To WA
- 3) Interfering Condition WA .080"` +.095"2 - 0.8421 Distance From Centerline NtA To WA Distance From Ref. Point NIA To tA 0.4U21 x 100 - 4.21% total coverage obtained (For All Measurements Indicate: US, DS, CW. CCW)
Sketch Of Urmitation(s):
Limited exam due to Weld crown heih.
ELZOW FL OW 1-1-06 INCLUDED THE EXTENT 0F % CWMPLETED OF EXAM AND REASON FOR UMITED REPORT, AND SKETCH SIJOWNG AREA OF UMITAT1CW)
Level III Date: Examiner Date: 16/05 Reviewer: Date: )
Cust r _Date:
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AREVA Areva CR # 2005-497 NPPDCR# Gf-c!st Z{) O/9/
Table of search units used for examinations referenced by above CR's. This table will be attached to each data report affected by these CR's.
Data Base# Manufacturer Model Shape Manu. Serial#
N/A RTD TRLA RECT 00-737 34570 KBA COMP-G ROUND M16422 34639 RTD TRLA RECT 98-272 34735 KBA COMP-G ROUND OOCR3D 34739 KBA COMP-G ROUND 0OCRF5 34784 KBA COMP-G ROUND A10524 34785 KBA COMP-G ROUND A10535 34790 KBA COMP-G ROUND 007R5M 35000 KBA COMP-G ROUND 00PVX1 35265 RTD TRLA RECT 03-334 35394 KBA COMP-G ROUND OOXR3V 35398 KBA COMP-G ROUND 0OXWKC 35487 RTD TRLA RECT 03-843 35488 RTD TRLA RECT 03-844 1-1-0s-Date Z- i-o0i--
ievel III Date h;S Hc /- - ,67a/&&
CNS ISI Engineer Z- 7 -:5 Date ZD/7/at-Aut onzed Nuclear Inservice Inspector Date
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ARE VA EXAMINATION
SUMMARY
Summary No.: B9.21.0033.RI Data Package: CNSDPO71-RF022 Exam Date: 01-26-2005 Customer: Cooper Nuclear Station, NPPD Examination Methods: UT System I Component ID: NBDR I RVD-BJ-18 Examination Procedures: 544SI-836-08 Component
Description:
ELBOW TO PIPE Calibration Sheets No(s): CNS-05-059 &
CNS-05-060 Examination 1 No Reportable Indications Examination Category: R-A Results:
O Reportable Indications ISO I Drawing: X-2512-200 1 Geometric Summary:
This examination was done to ASME section Xl appendix Vil, 1995 edition with editions and addenda through 2000.
The 45- shear and the 60' shear were used for optimum flaw detection. A 70' shear was not used due to high signal to noise ratio.
No recordable indication noted with either 45' or 60- shear.
84.85% code required volume achieved using the 45' and 60' transducers, due to the as welded weld crown height gd'ft(~/oj, 'f5g4&9P.
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,41'9ge -7ef A0 Af~ ;) UT CALIBRATION DATA SHEET Customer: Cooper Nuclear Station, NPPD Exam Date: 01/2612005 Summary No.: B9.21.0033.R1 System I Component l.D.: NBDR I RVD-BJ-18 Calibration No.: CNS 05.059 Component
Description:
2.fr ELBOW TO PIPE WELD ISO/ Drawing No.: X-2512-200 Procedure No. IRev.: 54-ISI36-08 Code I Accept. Criteria: IWB-3514 Material: STAINLESS STEEL Diameter 2.fr Thickness: .218' INSTRUMENT SETTINGS SEARCH UNIT CALIBRATION STANDARD Mfg: KBA Model: USN 58L DB / Serial No.: 34570 Cal. Block No.: 7500285 Serial / MT&E #: VH-9074 Size: .25" Cal. Block Thickness (in): .50r Mat. Cal. I Velocity: 0.1212 Freq. (MHz): 2.25 MHZ Cal. Block Dia. (in): N/A Delay: 0.000 Zero Oftwet 6.5W8 Long I Shear /Single /Dual: SHEAR / SINGLE Temp (F) Block: 74' Cornp.: 84 Each Major Screen Div. #: .1' Nominal Angle: 45' Measured: 45' Therm. No.: VH-8043 Channel #: N/A Fixture / Size: MSWQC Couplant Type: EXOSEN 30 Range: 1ff Freq (MHz): 2.25 Cable Type & Length: RG-174 Couplant Batch No.: 32104301 Damping: 1000 Reject: OFF No. of Connectors: 0 CALIBRATION STD. SIMULATOR Rep. Rate:AUTOHIGH Pulse: HIGH DAC PLOT Serial No.: N/A Gate: NIA Display: FULLWAVE Sweep Position I Depth: N/A Mode: P.E. Jack: T 100 __
- - Signal Amp. (%): N/A Ref.Sensitivity: 31.0 dB90 - _ Gain DB(dB): N/A Scan Sensitivity: 37.0dB EXAM DATA (Amt. DB to bring Notch to DAC) 70 - _ Scan Direction to Weld:90TOWELD;-TOWELD 60--------
Notch dB (Piping): NIA 5 __ (0 to WRV; 0 to Material; 90 to Weld; = to Weld) s 0 - - - - - - - -_ _ _ _ _ _ _ _ _
Notch dB (Vessels): N/A 4 _ _ _ _ _ _ _ _ RecordableGeometry(YesINo): NO CALIBRATION CHECK 30 _ _ _ _ _ _ __ Recordable Indications (Yes I No): NO Time OK Initials -_ - - _ _ _ __ Limited Exam (Yes/ No): YES Initial Cal: 0300 OK TLK 10 - - - - - - _ i Percent Scan Completed: 84.85%
Init. Sim. Cal: N/A N/A N/A 0 - _
- - -_ Percent Exam Completed: 84.85%
Intermediate: N/A N/A N/A 0 1 2 3 4 5 6 7 8 9 10 ODEG. WELD THICKNESS ONLY Intermediate: N/A N/A NIA Comp.: N/A Intermediate: N/A N/A NIA Amplitude vs. Range BM: NA HAZ: NIA Intermediate: N/A N/A N/A Signal to Noise Ratio: 8 TO I C/L Weld: N/A Intermediate: N/A NMA N/A Comp: N/A Final Cal.: 0505 OK TLK BM: N/A HAZ N/A Scan Direction on Cal. Block 0 Deg. Axial Circ Crown HT.: N/A (Yes / No) NO YES - NO Weld Width: N/A ReNectorNOTCH NIA N/A N/A N/A N/A N/A NIA Sweep Pos. I Depth In Inches 7.0/.50" N/A WA NIA N/A N/A N/A N/A Amplitude in % 80% NA N/A NMA N/A N/A N/A N/A Gain indB 31.0 NA N/A N/A N/A NA N/A [N/A Notes: Performed a 45 shear, circumferential (parallel to weld) and axial (perpendicular to weld) examination of Elbow to Pipe Weld RVD.BJ-18).
No recordable indications were noted. Limited exam due to weld crown height, 84.85% code volume achieved.
'NCD' Cog -
ID fol 20% @ 3.0 sweep divisions.
Examine; Terry KobeLeelrnuat:sz26V Examiner: N/A Lvl / ae /
Sign:L Sign: _ -
Reviewed: Level: Da ANII Review:
Sign: _ a L C Date:S-ig: Date:P Customer:
7 Date 4~ jPage Z- of Framatorne ANP, Inc., an AREVA and Siemens company
aFs- t - .. UT CALIBRATKOA DATA SHEET Customer: Cooper Nuclear Station, NPPD Exam Date: 0112612005 Summary No.: B9.21.0033.Rl System I Component I.D.: NBDR I RVD-BJ-18 Calibration No.: CNS-05406D Component
Description:
2.ff ELBOW TO PIPE WELD ISOI Drawing No.: X-2512-200 Procedure No. I Rev.: 54-SI;-836-08 Code I Accept. Criteria: IWB-3514 Material: STAINLESS STEEL Diameter. 2.0 Thickness: .218w INSTRUMENT SEtTINGS SEARCH UNIT CALIBRATION STANDARD Mfg: KBA Model: USN 58L DB I Serial No.: 34790 Cal. Block No.: 7500285 Serial I MT&E #: VH-9074 Size: .25' Cal. Block Thickness (in): .50' Mat. Cal. I Velocity: 0.1247 Freq. (MHz): 2.25 MHZ Cal. Block Dia. (in): N/A Delay: 0.000 Zero Offset: 8.5269 Long I Shear I Singlet Dual: SHEAR I SINGLE Temp (F) Block: 74 Comp.: 84 Each Major Screen Div. #: .16" Nominal Angle: 60 Measured: 60- Therm. No.: VH-8043 Channel #: NWA Fixture I Size: MSWQC Couplant Type: EXOSEN 30 Range: 1.5' Freq (MHz): 2.25 Cable Type & Length: RG-174 /12' Couplant Batch No.: 32104301 Damping: 10000 Reject: OFF No. of Connectors: 0 CALIBRATION STD. SIMULATOR Rep. Rate:AUTOHIGH Pulse: HIGH DAC PLOT Serial No.: 7500772 Gate: NWA Display: FULLWAVE Sweep Position I Depth: 7.0 Mode: P.E. Jack: T 100 - _ Signal Amp. (%): 40%
Ref. Sensitivity: 53.0 dB -90 _ Gain DB (dB): 34.0 dB Scan Sensitivity: 53.0 dB0 - EXAM DATA (Amt. DB to bring Notch to DAC) 70 Scan Direction to Weld:90 TO WELD 60 -
Notch dB (Piping): N/A (0 to WRY; 0 to Material; 90 to Weld; to Weld) 50 Notch dB (Vessels): N/A 40 Recordable Geometry (Yes ( No): NO CALIBRATION CHECK _- _ _ _ _ _ _ _ _ Recordable Indications (Yes / No): NO Time OK Initials 20 _- _ _ - _ _ I Lmited Exam (Yes / No): YES Initial Cal: 0310 OK TLK 10 -_ _ _ _ _ _ Percent Scan Completed: 84.85%
Init. Sim. Cal: 0312 OK TLK 0 - _ Percent Exam Completed: 84.85%
Intermediate: 0320 OK TLK 0 1 2 3 4 5 6 7 8 9 10 0 DEG. WELD THICKNESS ONLY Intermediate: MIA N/A N/A Comp.: N/A Intermediate: NWA N/A NA Amplitude vs. Range BM: N/A HAZ: NWA Intermediate: NMA N/A N/A Signal to Noise Ratio: 8 TO I C/L Weld: N/A Intermediate: NWA NIA NIA Comp: NIA Final Cal.: 0510 OK TLK BM: N/A HAZ: N/A Scan Direction on Cal. Block 0 Deg. Axial Circ Crown HT.: N/A (Yes / No) NO YES NO Weld Width: N/A ReecIorANOTCH N/A N/A N/A NIA N/A Sweep Pos. / Depth in Inches 6.6 N.50T N/A J A N/A N/IA N/A N/A WA Amplitude in 9 80% N/ NM N/ANIA N/A N/A Gain in dB 53.0 NA NIA N/A N/A N/A N/A Notes: Performed a 60 shear, axial (perpendicular to weld) examination of Elbow to Pipe Weld (RVD-EJ-1 8).
No recordable indications were noted. Limited exam due to weld crown height, 84.85% code volume achieved.
NCDb ID roRl 20% @ 3.0 sweep divisions. /d 4AD Z- I a-Examiner TIMy Kobernusz A is
. . A I Examiner: N/A , **,*
PdIM Level.LaVW."I.-
n Uale.e r41P Date:oftq 5 of 5-
,V,LS> 0l'c5/E2 /d*'sirC 7>D
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AREVA ULTRASONIC EXAMINATION SCAN LIMITATION REPORT Customer: Cooper Nuclear Station, NPPD Component: 2" ELBOW TO PIPE Summary No.: B921.0033.R1 Weld No.: RVD-BJ-18 Percent Of Exam Completed (Calculations Or Corments Below)
Reference Point NIA 84.85% code volume achieved.
- 1) Interfering Condition AS WELDED WELD CROWN Distance From Centerline NIA To NIA Total coverage missing .015"z Distance From Ref. Point NIA To NIA
- 2) Interfering Condition WA .099"' total area of lower s =
Distance From Centerline NIA To NIA
.099" -.015S2 =.084w2 Distance From Ref. Point NWA To NIA
- 3) Interfering Condition WA .084"2 + .099`2 = .8485 Distance From Centerline WA To N/A Distance From Ref. Point NIA To WA .8485 x 100 84.85% total coverage obtained (For All Measurements Indicate: US, DS, CW, CCW)
Sketch Of Limitation(s):
P1 P6 4 ELBOW P4P - i-~
ONCLUDED THETENT COM OF EXAM AN REASON FOR LUMITED REPORT, AND SKETCH SHOMNG AREA OF LIMITATION.)
Level IlI: Date: Examiner: Terry Kobernz Date: 105 Reviewer: Date:
Customer: 7 Date:
Framatome ANP, Inc., an AREVA and Siemens company
J/-6~&2d5/2 6g/e- , e /pe9, J° AREVA Areva CR # 2005-497 NPPDCR# - c' ls'J/ 'S Table of search units used for examinations referenced by above CR's. This table will be attached to each data report affected by these CR's.
Data Base # Manufacturer Model Shape Manu. Serial #
N/A RTD TRLA RECT 00-737 34570 KBA COMP-G ROUND M16422 34639 RTD TRLA RECT 98-272 34735 KBA COMP-G ROUND OOCR3D 34739 KBA COMP-G ROUND 00CRF5 34784 KBA COMP-G ROUND A10524 34785 KBA COMP-G ROUND A10535 34790 KBA COMP-G ROUND 007R5M 35000 KBA COMP-G ROUND OOPVXI 35265 RTD TRLA RECT 03-334 35394 KBA COMP-G ROUND OOXR3V 35398 KBA COMP-G ROUND 00XWKC 35487 RTD TRLA RECT 03-843 35488 RTD TRLA RECT 03-844 Date
I ATTACHMENT 3 LIST OF REGULATORY COMMITMENTSl Correspondence Number: NLS2005105 The following table identifies those actions committed to by Nebraska Public Power District (NPPD) in this document. Any other actions discussed in the submittal represent intended or planned actions by NPPD. They are described for information only and are not regulatory commitments. Please notify the Licensing Manager at Cooper Nuclear Station of any questions regarding this document or any associated regulatory commitments.
COMMITMENT COMMITTED DATE COMMITMENT NUMBER OR OUTAGE NONE 1 4
.1. I 4 I 4 4 I 4 I 'I.
PROCEDURE 0.42 l REVISION 18 l PAGE 19 OF 25 l