ML063620147

Second Ten-Year Interval ISI Request 2ISI-32

ML063620147
Person / Time
Site:	Columbia
Issue date:	12/14/2006
From:	Oxenford W Energy Northwest
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
GO2-06-156
Download: ML063620147 (155)

Text

%*x ENERGY

'6NORTHWEST Peopge -Vision Sonutinns P.O. Box 968

• Richland, WA 9 99352-0968 December 14, 2006 G02-06-156 10 CFR 50.55a U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001

Subject:

COLUMBIA GENERATING STATION, DOCKET NO. 50-397 SECOND TEN-YEAR INTERVAL ISI REQUEST 21SI-32

Dear Sir or Madam:

In accordance with 10 CFR 50.55a(g)(5)(iii) and 10 CFR 50.55a(g)(5)(iv), Energy Northwest hereby submits the attached request for approval related to the Columbia Generating Station second ten-year interval inservice inspection program. This request pertains to the 1989 Edition, with no Addenda, of Section Xl of the ASME Boiler and Pressure Vessel Code, for examinations which resulted in less than 100% ASME code required coverage. Energy Northwest has determined that conformance with the code requirements described herein is impractical for Columbia Generating Station.

There are no commitments being made to the NRC by this letter. If you have any questions or require additional information regarding this matter, please contact GV Cullen, Licensing Supervisor, at (509) 377-6105.

Respectfully, WSO0 f d Vice Pre dent, Technical Services Mail Drop PE04

Attachment:

Request 21SI-32 Tables and Sections including Attachments A through G cc:

BS Mallett - NRC RIV (w/o)

RF Kuntz - NRC NRR (w/o)

NRC Senior Resident Inspector/988C (w/o)

RN Sherman - BPA/1 399 (w/o)

WA Horin - Winston & Strawn (w/o)

W7

REQUEST 21SI-32 TABLES AND SECTIONS Attachment Page 1 of 12

.10 CFR 50.55a Request Number 21SI-32 Proposed Alternative In Accordance with 10 CFR 50.55a(g)(5)(iii)

--Inservice Inspection Impracticality-Summary This request identifies components whose inspection coverage during the second Inservice Inspection Interval was less than essentially 100% due to impracticality.

Essentially 100% examination coverage is defined in Code Case N-460 (listed in Regulatory Guide 1.147 Revision 14 as acceptable without conditions) as examining greater than 90% of the applicable volume or area.

Tables 1 through 4 list the individual components.

Sections 1 through 7 provide the details of the limitations, alternate examination proposed, and duration of the request.

Attachments A through G provide additional information supporting the request including examination data sheets, coverage plots, and drawings.

Abbreviations RCIC Reactor Core Isolation Cooling RHR Residual Heat Removal MS Main Steam RRC Reactor Recirculation HPCS High Pressure Core Spray SWL Sweep-O-Let RWCU Reactor Water Cleanup RPV Reactor Pressure Vessel IGSCC Intergranular Stress Corrosion Cracking TT Thermal Transient TASCS Thermal Stratification Cycling and Striping SCC Stress Corrosion Cracking

REQUEST 21SI-32 TABLES AND SECTIONS Attachment Page 2 of 12 TABLE 1 Code Category B-D Item Number B3.90

1.

2.

3.

4.

5.

6.

7.

8.

ASME CODE COMPONENT ID APPLICABLE CODE IMPRACTICALITY BURDEN PROPOSED DURATION OF RECORDABLE COMPONENT NO.

REQUIREMENT OF COMPLIANCE CAUSED BY ALTERNATIVE PROPOSED INDICATIONS REQUEST (AREA OR COMPLIANCE AND BASIS FOR ALTERNATIVE FOUND DURING NUMBER WELD TO BE Material

(% COVERAGE USE EXAMINATION?

EXAMINED)

OBTAINED)

(Associated damage mechanism)

Relief Request 21SI-RPV Top Head 24 Figure 21SI-24-1See Paragraph 21SI-32-1 Spare Nozzle SA 508 CL2 (88% volumetric See Paragraph 4.A 5.A 6.A See Paragraph 7 None to RPV Weld(8%vumti5.6A (None) coverage)

Relief Request 21SI-N1824Fgr21-2i RPV Top Head 24 Figure 21SI-24-1 21SI-32-2 Spare Nozzle SA 508 CL2 See Paragraph 4.A See Paragraph See Paragraph See Paragraph 7 None to RPV Weld (85% volumetric 5.A 6.A (None) coverage)

REQUEST 21SI-32 TABLES AND SECTIONS Attachment Page 3 of 12 TABLE 2 Code Category B-F Item Number B5.130

1.

2.

3.

4.

5.

6.

7.

8.

ASME CODE COMPONENT ID APPLICABLE CODE IMPRACTICALITY BURDEN PROPOSED DURATION OF RECORDABLE COMPONENT NO.

REQUIREMENT OF COMPLIANCE CAUSED BY ALTERNATIVE PROPOSED INDICATIONS REQUEST (AREA OR COMPLIANCE AND BASIS FOR ALTERNATIVE FOUND DURING NUMBER WELD TO BE Material

(% COVERAGE USE EXAMINATION?

EXAMINED)

OBTAINED)

(Associated damage mechanism)

HPCS 10HPCS(1)-3 Fig. IWB-2500-8 Discharge to 21SI-32-3 RPV SA 508 CL1 / SB (85% volumetric See Paragraph 4.B See Paragraph See Paragraph See Paragraph 7 None Safe end 166 cvrg)5.A 6.13 extension to coverage) safe end (SCC)

RHR 12RHR(1)A-14 Fig. IWB-2500-8 Shutdown SA-350 GR LF2 See Paragraph See Paragraph None 21SI-32-4 Cooling Return SA-182 TP 304 (26% volumetric See Paragraph 4.B1 5.A 6.13 See Paragraph 7 Valve to Safe coverage) end (IGSCC)

RHR 12RHR(1)B-10 Fig. IWB-2500-8 Shutdown SA -SS 21SI-32-5 Cooling Return SA-350 GR LF2 I (29% volumetric See Paragraph 4.B See Paragraph See Paragraph See Paragraph 7 None SA-182 TP 304 coverage Valve to Safe coverage) end (IGSCC)

REQUEST 21SI-32 TABLES AND SECTIONS Attachment Page 4 of 12 TABLE 3 Code Category B-J Item Number B9.11

1.

2.

3.

4.

5.

6.

7.

8.

ASME CODE COMPONENT ID APPLICABLE IMPRACTICALITY BURDEN PROPOSED DURATION OF RECORDABLE COMPONENT NO.

CODE OF COMPLIANCE CAUSED BY ALTERNATIVE PROPOSED INDICATIONS REQUEST (AREA OR REQUIREMENT COMPLIANCE AND BASIS FOR ALTERNATIVE FOUND DURING NUMBER WELD TO BE Material USE EXAMINATION?

EXAMINED)

(% COVERAGE (Associated damage OBTAINED) mechanism) 6RCIC(1)-40 Fig. IWB-2500-8 RCIC Head 21SI-32-6 Spray SA 106 GR B (86% volumetric See Paragraph 4.C See Paragraph See Paragraph See Paragraph 7 None Pipe to Valve coverage) 5.A 6.C (TT,TASCS) 24RRC(1)A-14 Fig. IWB-2500-8 RRC 21SI-32-7 Discharge SA 358 GR 304 CL 1 (50% volumetric See Paragraph 4.D See Paragraph See Paragraph See Paragraph 7 None Pipe to Valve coverage) 5.A 6.D (IGSCC) 24RRC(1)A-15 Fig. IWB-2500-8 RRC RCSee Paragraph See Paragraph SePrgah7Nn 21SI-32-8 Discharge SA 358 GR 304 CL (50% volumetric See Paragraph 4.D 5.A S

Pg See Paragraph 7 None Valve to Pipe coverage)

(IGSCC)

RRC 24RRC(1)A-18 Fig. IWB-2500-8 21Sl-32-9 Discharge SA 358 GR 304 CL 1 See Pvrorph 4.D See Paragraph See Paragraph See Paragraph 7 None Pipe to Valve (50% volumetric agp 5.A 6.D (IGSCC) coverage) 24RRC(1)A-19 Fig. IWB-2500-8 RRC 21Sl-32-10 Discharge SA 358 GR 304 CL 1 (50% volumetric See Paragraph 4.D See Paragraph See Paragraph See Paragraph 7 None Valve to Elbow coverage) 5.A 6.D (IGSCC)

REQUEST 21SI-32 TABLES AND SECTIONS Attachment Page 5 of 12 TABLE 3 Code Category B-J Item Number B9.11 APPLICABLE CODE REQUIREMENT 4.

IMPRACTICALITY OF COMPLIANCE BURDEN CAUSED BY PROPOSED ALTERNATIVE DURATION OF PROPOSED RECORDABLE INDICATIONS USE EXAMINATION?

(% COVERAGE OBTAINED)

REQUEST 21SI-32 TABLES AND SECTIONS Attachment Page 6 of 12 TABLE 3 Code Category B-J Item Number B9.11

1.

2.

3.

4.

5.

6.

7.

8.

ASME CODE COMPONENT ID APPLICABLE IMPRACTICALITY BURDEN PROPOSED DURATION OF RECORDABLE COMPONENT NO.

CODE OF COMPLIANCE CAUSED BY ALTERNATIVE PROPOSED INDICATIONS REQUEST (AREA OR REQUIREMENT COMPLIANCE AND BASIS FOR ALTERNATIVE FOUND DURING NUMBER WELD TO BE Material USE EXAMINATION?

EXAMINED)

(% COVERAGE (Associated damage OBTAINED) mechanism) 24RRC(2)B-10 Fig. IWB-2500-8 RRC Suction SA 358 GR 304 CL 1 (50% volumetric See Paragraph 4.E See Paragraph See Paragraph See Paragraph 7 None Elbow to Pump coverage) 5.A 6.E (IGSCC) 24RRC(2)B-11/8CAP-1 21SI-32-17 RRC Discharge Cap to Sweep-O-Let SA 403 GR WP 304 with Corrosion resistant clad - CRC Fig. IWB-2500-8 (50% volumetric coverage)

See Paragraph 4.F See Paragraph 5.A See Paragraph 6.F See Paragraph 7 None

REQUEST 21SI-32 TABLES AND SECTIONS Attachment Page 7 of 12 TABLE 3 Code Category B-J Item Number B9.11

1.

2.

3.

4.

5.

6.

7.

8.

ASME CODE COMPONENT ID APPLICABLE IMPRACTICALITY BURDEN PROPOSED DURATION OF RECORDABLE COMPONENT NO.

CODE OF COMPLIANCE CAUSED BY ALTERNATIVE PROPOSED INDICATIONS REQUEST (AREA OR REQUIREMENT COMPLIANCE AND BASIS FOR ALTERNATIVE FOUND DURING NUMBER WELD TO BE Material USE EXAMINATION?

EXAMINED)

(% COVERAGE (Associated damage OBTAINED) mechanism) 24RRC(2)B-RRC Suction 8I4RRC(4)-4S Fig. IWB-2500-8 RR uto /RC4-SSee Paragraph See Paragraph SePrgah7 Nn 21SI-32-20 Pipe to Sweep-SA 358 GR 304 CL 1 (50% volumetric See Paragraph 4.F Se See Paragraph 7 None O-Let coverage)

(IGSCC)

REQUEST 21SI-32 TABLES AND SECTIONS Attachment Page 8 of 12 TABLE 4 Code Category C-F-2 Item Number C5.51

1.

2.

3.

4.

5.

6.

7.

8.

ASME CODE COMPONENT ID APPLICABLE CODE IMPRACTICALITY BURDEN PROPOSED DURATION OF RECORDABLE COMPONENT NO.

REQUIREMENT OF COMPLIANCE CAUSED BY ALTERNATIVE PROPOSED INDICATIONS REQUEST (AREA OR COMPLIANCE AND BASIS FOR ALTERNATIVE FOUND DURING NUMBER WELD TO BE Material

(% COVERAGE USE EXAMINATION?

EXAMINED)

OBTAINED)

(Associated damage mechanism) 6MS(1)B-2 Fig. IWC-2500-7 21SI-32-21 MS line SA 106 GR B (81% volumetric See P h 4G See Paragraph See Paragraph See Paragraph 7 None Cap to Pipe coverage 85%

Paragraph

5.

6.G (None) surface coverage)

REQUEST 21SI-32 TABLES AND SECTIONS Attachment Page 9 of 12

1. ASME Code Components Affected Refer to Tables 1 through 4, Columns 1 and 2

2. Applicable Code Edition and Addenda

ASME Section Xl - 1989 Edition no Addenda ASME Section Xi - 1995 Edition, 1996 Addenda for Appendix VIII

3. Applicable Code Requirement

Refer to Tables 1 through 4, Column 3 All welds receiving a volumetric examination after the implementation dates in 10 CFR 50.55a for ASME Section Xl, Appendix VIII were performed in accordance with Appendix VIII as modified by 10 CFR 50.55a.

4. Impracticality of Compliance

A. Table 1 Code Category B-D weld identification N18. See additional information in attachment A. Examination requirement is per 10 CFR 50.55a request 21SI-24, figure 21SI-24-1. This request was authorized by letter, Nuclear Regulatory Commission to Mr. J. V. Parrish, "Columbia Generating Station - Relief Requests 21SI-21, 21SI-22, 21SI-23, 21SI-24 and Commitment Change (TAC No. MB0686),"

dated April 25, 2001 (reference 1). When applying this requirement, Energy Northwest was only able to obtain 85% examination coverage of the weld due to the configuration of the nozzle. Full code examination volume was obtained in both axial directions and one circumferential direction. The other circumferential direction scan was limited by the nozzle radius configuration.

B. Table 2 Code Category B-F Weld identification 10HPCS(1)-3, 12RHR(1)A-14, and 12RHR(1)B-10. See additional information in attachment B. The reason the examination was limited for 10HPCS(1)-3 was the configuration of the safe end which does not allow full code coverage from the safe end side. The reason the examination was limited for welds 12RHR(1)A-14 and 12RHR(1)B-10 is the configuration of the safe end and valve body did not allow full coverage scanning from both the safe end side and the valve side.

C. Table 3 Code Category B-J support attachment weld configuration Weld identification 6RCIC(1)-40. See additional information in attachment C. The reason the examination was limited for the weld listed above is the support attachment welded to the pipe did not allow full coverage scanning from the attachment side.

REQUEST 21SI-32 TABLES AND SECTIONS Attachment Page 10 of 12 D. Table 3 Code Category B-J Valve configuration Weld identification 24RRC(1)A-14, 24RRC(1)A-15, 24RRC(1)A-18, 24RRC(1)B-12, 24RRC(1)B-16, 24RRC(2)A-10, 24RRC(2)B-8, 24RRC(1)B-17, 24RRC(1)A-19. See additional information in attachment D. The reason the examination was limited for the welds listed above is the configuration of the valve body did not allow full coverage scanning from the valve side.

E. Table 3 Code Category B-J pump configuration Weld identification 24RRC(2)B-

10. See additional information in attachment E. The reason the examination was limited for above weld is the configuration of the pump body did not allow full coverage scanning from the pump side.

F. Table 3 Code Category B-J sweep-o-let configuration Weld identification 24RRC(2)B-8/4RRC(8)-4S, 24RRC(2)B-8/4RRC(4)-4S 24RRC(2)B-1 1/8CAP-1 24RRC(2)B-1 1/4RRC(4)-4S. See additional information in attachment F. The reason the examination was limited for the above welds is the configuration of the sweep-o-let did not allow full coverage scanning from the sweep-o-let side.

G. Table 4 Code Category C-F-2 Weld identification 6MS(1)B-2. See additional information in attachment G. The reason for the limited coverage for this weld is a pipe support attachment welded to the pipe. Transducers were not able to scan from the three areas where the support is welded to the pipe. The surface examination could not examine the pipe that was under the welded attachments.

This resulted in the limitation for this weld.

5. Burden Caused by Compliance

A. To achieve the code required examination volume or area the part would need to be redesigned. This is not a practical action.

6. Proposed Alternative and Basis for Use

A. Table 1 Code Category B-D weld identification N18. The proposed alternative is to examine the weld to achieve at least 85% examination coverage. A significant volume of the weld and base material was examined to provide a reasonable assurance that any service induced flaws would be detected. The weld volume was interrogated using 0, 45, 60, and 70RL transducers. The ultrasonic technique was performed in accordance with ASME Section Xl, Appendix VIII as modified by 10 CFR 50.55a and 10CFR50.55a request 21SI-24. The examinations performed applied all the current knowledge and techniques to obtain the maximum amount of coverage to the extent practical within the limitations of design, geometry and materials of construction of the component.

No indications were detected in the base material nor weld.

REQUEST 21SI-32 TABLES AND SECTIONS Attachment Page 11 of 12 B. Table 2 Code Category B-F Weld identification 10HPCS(1)-3, 12RHR(1)A-14, and 12RHR(1)B-10. The proposed alternative is to examine the welds to achieve at least the examination coverage identified in Table 2, column 3 for each weld.

The examinations performed applied all the current knowledge and techniques to obtain the maximum amount of coverage to the extent practical within the limitations of design, geometry and materials of construction of the component.

The entire weld population Code Category B-F was examined. Of the forty three (43) Code Category B-F welds the three welds listed in Table 2 were the only ones where essentially 100% code coverage was not obtained. This represents a significant total volume of welds examined in this category. No indications were detected in the base material nor welds for all the volume examined in this category.

C. Table 3 Code Category B-J support attachment weld configuration Weld identification 6RCIC(1)-40. The proposed alternative is to examine the weld to achieve at least 86% examination coverage. The examinations performed applied all the current knowledge and techniques to obtain the maximum amount of coverage to the extent practical within the limitations of design, geometry and materials of construction of the component. No indications were detected in the base material nor weld.

D. Table 3 Code Category B-J Valve configuration Weld identification 24RRC(1)A-14, 24RRC(1)A-1 5, 24RRC(1)A-1 8, 24RRC(1)B-1 2, 24RRC(1)B-1 6, 24RRC(2)A-10, 24RRC(2)B-8, 24RRC(1)B-17, 24RRC(1)A-19. The proposed alternative is to examine the weld to achieve at least the examination coverage identified in Table 3, column 3 for each weld. The examinations performed applied all the current knowledge and techniques to obtain the maximum amount of coverage to the extent practical within the limitations of design, geometry and materials of construction of the component. No indications were detected in the base material nor welds.

E. Table 3 Code Category B-J pump configuration Weld identification 24RRC(2)B-

10. The proposed alternative is to examine the weld to achieve at least 50%

examination coverage. The examinations performed applied all the current knowledge and techniques to obtain the maximum amount of coverage to the extent practical within the limitations of design, geometry and materials of construction of the component. No indications were detected in the base material nor weld.

F. Table 3 Code Category B-J sweep-o-let configuration Weld identification 24RRC(2)B-8/4RRC(8)-4S, 24RRC(2)B-8/4RRC(4)-4S 24RRC(2)B-1 1/8CAP-1 24RRC(2)B-1 1/4RRC(4)-4S. The proposed alternative is to examine the weld to achieve at least the examination coverage identified in Table 3, column 3 for each weld. The examinations performed applied all the current knowledge and techniques to obtain the maximum amount of coverage to the extent practical

REQUEST 21SI-32 TABLES AND SECTIONS Attachment Page 12 of 12 within the limitations of design, geometry and materials of construction of the component. No indications were detected in the base material nor welds.

G. Table 4 Code Cateqory C-F-2 Weld identification 6MS(1)B-2 The proposed alternative is to examine the weld to achieve at least the examination coverage identified in Table 5, Column 3. The examinations performed applied all the current knowledge and techniques to obtain the maximum amount of coverage to the extent practical within the limitations of design, geometry and materials of construction of the component. No indications were found with either the surface or volumetric examinations.

7. Duration of Proposed Alternative

The request is for the duration of the second inspection interval which began February 10, 1995 and concluded December 12, 2005.

References

1. Nuclear Regulatory Commission to Mr. J. V. Parrish, "Columbia Generating Station - Relief Requests 21Sl-21, 21Sl-22, 21SI-23, 21SI-24 and Commitment Change (TAC No. MB0686)," dated 4/25/2001, ML011150323

REQUEST 21SI-32 ATTACHMENTS A THROUGH G Attachment Attachment A 21SI-32-1 Weld Identification N7 ISI Diagram RPV-1 11 Figure 21SI-24-1 NDE Data Report R-R13-G17 pages 1, 8, and 9 through 15 21SI-32-2 Weld Identification N18 NDE Data Report R15-109 pages 1, 6, and 7 NDE Data Report R15-109 enlarged page 6 of 7 two pages

0 0

I 2

3 4

S 6

7 e

9 10 1/16' 0

KD 0S 0

0 WELDS N?

0O NiB 180" 6RCIC ()-45 6' SPARE-I RCIC SPARE FLANGE TO NOZZLE WELD DETAIL NOTES CAL BLOCK END EXTENSION UT-15 NOZZLE TO VESSEL HEAD WELD UT-I07 NOZZLE TO FLANGE WELD UT-1 15 NOZZLE INNER RADIUS REFERENCES.

CBI NUCLEAR CO.

205 AE 023 SHT 68 REV 2 N?

NOZZLE g WELD NECK FLANGE SHT 69 REV 4 N?

NOZZLE ASSEMBLY SHT 92 REV 4 NIB NOZZLE & WELD NECK FLANGE SHT 93 REV 6 NIB NOZZLE ASSEMBLY 0I 1 23456 7

8 9 10I IS ISOMETRICS RCIC-102-3 REV 5 RPV-i02 REV 2 QUALITY CLASS, I

ASME CODE CLASS, 1

ENGR, T HOYLE I DRAWN. K-MCA I DATE, 5-17-79 WASHINGTON PUBLIC POWER SUPPLY SYSTEM AICHLAND.

WASHINGTON 935,2 SCALE. 114'

= I' THIS DRAWING IS INTENDED FOR USE IN PRESERVICE AND INSERVICE INSPECTIONS PROGRAMS ONLY.

NOM DIA

, C NOM WALL I MATL CAL WNP-2 PIPING SYSTEM CH MATERIAL SPEC T

BLOCK IRC6 8

0 S

S IYEI NUTBER WELD E

COMAONENT 6"RCIC(l)-4 6

BO 0.432 1SA 108 GR B I

CS ISEE NOTES IDENTIFICATION DIAGRAM WELD NECK FLANGE S

9O#

ISA 508 CL 1 CA SEE NOTES 4 4 4

-I--

TITLE, N7 NOZZLE I

ISAS508 CL 2 CS SEE NOTES CS RCIC / SPARE N? NOZZLE AT O" NIB NOZZLE AT I1O" I

I 2-20-2 I ~AI?-END SAND-~

INCOELII'09tAT6FI I K-ftA~ IJ I SPA NiB8 NOZZLE ISA 508 CL 2 CS APE NOTES 0

7-31-79 ISSUED FOR USE K-ftCA H

LFB RPV 3 5/B ISA 533 OR B CL I CS ISEE NOTES] DWG NO, RPF>_V_

1_ 1_1_REVI NO DATE REVISION BY CI AVD I

I I

I O

5.

iC-o& Ccxnpiance ISI PROGRAM PLAN INTERVAL - 2 REVISION 0-J APRIL, -2001 9,

-ml.

tnI, tR2

" nozzle wall thickness to, shell (or head) thickness ri -

nozzle inside corner radius

-N A

8C D

I Is I

I I

I I

Cladding where present A-B-C-D-E-F-G-H M

Corner flaw EXAMINATION REGION INote fiLL Shell for head) adjoining region Attachment weld region Nozzle cylinder region Nozzle inside cornme region EXAMINATION VOLUME INote (2)1 C-D-E-F B-C-F-G A-B-G-H M-N-O-P NOTES:

I1) Examination regions are identified for the purpose of differentiating the acceptance standards in IW8-3S12.

(2) Examination volumes may be determined either by direct measurements on the component or by measurements based on design drawings.

Figure 21SI-24-1 From ASME Code Case N-613, approval date July 30, 1998 5-4 1xxxii file: CODEI

REQUEST 21SI-32 ATTACHMENTS A THROUGH G Attachment 21SI-32-1

SG Nuclear Energy EXAMINATION

SUMMARY

SHEET REPORT NO.:

R-R13-G17 PROJECT: WNP2 R13 SYSTEM: REACTOR PRESSURE VESSEL WELD NO.: N7 CONFIGURATION-NOZZLE TOP HEAD SPRAY EXAMINER:

J. SIMPSON LEVEL:

i EXAMINER:

K. KIMBALL LEVEL: 1i EXAMINER:

N/A LEVEL:

II DATA SHEET NO.(S): DGR13-07, DGR13-13 PROCEDURE:

UT-WNP2-300V3 REV: N/A FRR: N/A N/A N/A N/A REV:

N/A FRR:

N/A N/A

_N/A N/A REV:

N/A FRR:

NIA N/A N/A El MT El PT E UT E VT WELD TYPE:

El CIRCUMFERENTIAL El LONGITUDINAL U OTHER NZ-VSL HEAD CAL SHEET NO.(S): CGR 09. 10 11 16 Ultrsonc eamiatin rsult wee acepabl totherequremntsof SMESecion l, 989no ddedaCatgoryB-Dwels ad UNRCReg Ultrasonic examination results were acceptable to the requirements of ASME Section XI, 1989 no Addenda, Category B-D welds and USNRC Reg.

Guide 1.150.

Manual exams were performed in accordance with UT-WNP2-300V3.

Manual scans were unrestricted.

Due to the nozzle to vessel weld design it is not feasible to effectively ultrasonically examine 100% of the ASME Code examination volume as defined in Section XI.

EXAM COMPLETE El PARTIALLY EXAMINED (EXPLAIN IN COMMENTS)

ADDITIONAL DATA SHEETS:

NIA COMPARED TO:

El PSI N ISI REPORT NO.(S): 1 RPU-009 NO. OF RECORDABLE INDICATIONS:.

• ] NO CHANGE U~j,,...,,,..PTABLE NO. OF REPORTABLE INDICATIONS:

0*

EXAMINATION RESULTS:

a ACCEPTABLE Fý LUT-M REV 6

4:49 PM 0

0 WNP2 N7 Nozzle 0 wm 45 T-scan 60 T-scan 45 P-scan CW 60 P-scan CW 45 P-scan CCW 60 P-scan CCW 70 T-scan 70 P-scan CW 70 P-scan CCW O wm 45 T-scan 60 T-scan 45 P-scan CW 60 P-scan CW 45 P-scan CCW 60 P-scan CCW 70 T-scan 70 P-scan CW 70 P-scan CCW UNRESTRICTED CROSS SEC TIONAL AREA (per shce)

TOTAL CODE COVERAGE code cross area area

% of code area

% of code area degrees degrees percent percent sectional scanned scanned scanned scanned scanned scanned scanned scanned area automated manually automated manually automated manually automated manually 18.87 0

15.05 0.00 79.76 0.00 360.00 0.00 79.76 18.87 0

17.42 0.00 92.32 0.00 360.00 0.00 92.32 1887 0

17.51 0.00 92.79 0.00 360.00 0.00 92.79 18.87 0

16.32.

0.00 86.49 0.00 360.00 0.00 86.49 18.87 0

16.32 0.00 86.49 0.00 360.00 0.00 86.49 18.87 0

16.32 0.00 86.49 0.00 360.00 0.00 86.49 18.87 0

16.32 0.00 86.49 0.00 360.00 0.00 86.49 4.74 0

4.61 0.00 97.26 0.00 360.00 0.00 97.26 4.74 0

4.06 0.00 85.65 0.00 360.00 0.00 85.65 4.74 0

4.06 0.00 85.65 0.00 360.00 0.00 85.65 Coverages 0.0 87.94 Total coverage 87.94 RESTRICTED CROSS SECTIONAL AREA (per slice)

TAL CODE COVERAGE code cross area area

% of code area

% of code area degrees degrees percent percent sectional scanned scanned scanned scanned scanned scanned scanned scanned area automated manually automated manually automated manually automated manually 18.87 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 18.87 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 18.87 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 18.87 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 18.87 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 18.87 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 18.87 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 4.74 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 4.74 0.00 0.00 0.00 0.00 0.00 0.00 0.00 000 4.74 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 C~overages 0.0 Total coverage Total Composite Coverage =

0.0 0.0 87.94 CJfý

0 WNP

-2 TOP H1EAD~

SPARE N7 Nozzte 0'

W/eld Me8tal examination coverage 0

-i V*

/NP 2

TOP HEAD SPARE N7 NozzLe 45' P-Scan examination coverage

WNP 2

TOP HEAD SPARE N7 NozzWe 45' T-Scn examina-tion coveraoge

0 II

/NP

-9 TOIP HE-AD SPARE N7 NozzLe 60° P-Scan examinati.on coverage

0 WNP 29 T*P HEAD SPARE N7 NozzLe 60~' T-Sccrn exa~minaction coveraxge

0 0

VINP

-92 TOP HEAD SPARE N7 Nozz(e 70' P-Scan examinoition coverage

w WNP TOP HEAD SPARE N7 Nozzte 70' T-Scn examination coverage

-4 L

REQUEST 21SI-32 ATTACHMENTS A THROUGH G Attachment 21SI-32-2

Report No.:

EXAMINATION

SUMMARY

SHEET R5-109 GE NUCLEAR ENERGY Site and Unit:

Columbia Generating Station Component ID:

N18 Outage:

RFO-1 5 SPARE NOZZLE TO TOP HEAD WELD System RPV ASME Cat.:

B-D ASME Item B3.90 Aug Requirements:

N/A Exams Performed!

Data Sheet Cal Sheet Procedure Calibration Block Examination Cert Date 7Q0 Personnel Level 70* RL RPV-R15-C0971 N/A GE-UT-300 Ver. 3 UT-1 15

'KENT MONTGOMERY il 5/30/01 0° Long jRPV-R'15-C0841 N/A j GE-UT-300 Rev. 3 UT-!15u KEVIN LOCKLER II 5/30/01 45° Shear RPV-Ri15-C086 N/A GE-UT-300 Rev. 31 UT-1 15 KEVIN LOCKLER II 5/30/01 60' Shear IRPV-R15-C088 N/A GE-UT-300 Rev. 3 UT-1 15 KEVIN LOCKLER II 5/30/01 Examination Results:

During the manual ultrasonic examination o1 the above referenced weld, no indications were recorded utilizing the 00, 450, 600 and 70° RL search units.

This examination is acceptable per the requirements of ASME Section XI, 1989 Edition, No Addenda and USNRC Regulatory Guide 1.150, Rev.1.

This examination was limited due to the weld Top Head to Nozzle configuration. 85.6% Code coverage was obtained.

Previous data was reviewed prior to this summary.

Examination results were compared to data report 1 RPU-048 from R-4 outage with No Change These examinations were performed under Work Order:

01010463 D

Change This Summary and the following data sheets have been rev'm nd accepted by the following personnel.

RWP:

N/A

~

<~o(

Dose:

N/A mr.

Prepared By:

Level:

Date:

ry Reviewed By:

Title:

Date:

GE Reviewed By:

Level:

Date:

ANII Reviewed By:

Title:

Date:

Page 1

of

C.

/

0'T __

I IER

[

P L!IUS EX.I-I

\\ UDLIJU E =

IR E,

\\E VOLU-IE iI'v1 E TED =

FID. 2I£,-2-4-1 EX:AiM ViDLU!-E V

t

\\EA ]LI-IHE lIISPECTED =

45"T EXlI,' 'i/]LUIE

!NiPDEJTEE 45'P E'-.,r. \\,iLUHE INSPECTED

=0*T EATI-i V'LUI IE !INSPE TED

ýf0°P E'.sA, "VOLUIE iNSPECTED 70 I /VOLULI =

70 rT E; II

'v LIJItiE 'IN

, PE-TED 70°P E KAI- \\ \\

LUIAE iPFECTED t

45-T/P 45-T/P 45* T/P 40 },P INNEP P DIUS EXAI. VOLUIE

=

IR EX`I- \\V'LUJIAE INISPECTED =

FIG.

'ISI-t'4-1 EXAI.I

\\"OLLIUHE c0 E IXI HVOLUME INSPECTED =

45'T EXA,

\\ V]LUIIE INSPECTED 450P EXAII V" LULHE IN'tSPECTED 6,0'T E.AHl VE]LUIIE lIISPECTED 60'P EXAI.I

\\VOLLIIUME INSPECTED 70ý E':.`I. \\"OLUI.IE =

70-T EXAII 'VEILLIIE II.SPECTED 70FP EXAl.

VOELLIUIE INSPECTED 14.1' C.4"

10.5"

=

11.9"

11.6' IQ G E.. NUCLEAR ENERGY ICULUMBIA GEN.

STA.TION WELD 1\\113 EXAIvi VOLUME I SCALE:

NONE DWG.

CG-_--NI8]P\\Eý7 0

I CE NUCLEAR ENERGY COLUMBIA CEN. SIATION WELD I~I15 EXAM VOLUIvIE SCALE:

NONEL DWG.

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=

FIG. 2ISI-24-1 'EXAM V.OLUI.'E 14.t'-

00 EXAM 1,

VOLUME INSPECTED

=

5.0" 45.0T EXAM VOLLUME INSPECTED =10.5" 45'0P EXAM A'OLUME. INSPECTED= 9.9" 600T EXAM VOLUME INSPECTED

.11.8" 6,OP EXAM H VOLUME INSPECTED

=D.

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$1.

Columbia Generating Station N18 -Top Head Spare Nozzle Spring 2001 00 WELD METAL 0' WELD METAL 450 T-SCAN 450 T-SCAN 450 T-SCAN 600 T-SCAN 60° T-SCAN 600 T-SCAN 450 P-SCAN CW 450 P-SCAN CW 600 P-SCAN CW 600 P-SCAN CW 450 P-SCAN CCW 450 P-SCAN CCW 600 P-SCAN CCW 600 P-SCAN CCW 2

2 1

2 1

2 1

2 1

2 1

2 CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE Area Scanned

% of Area Scanned Degrees Scanned

% Scanned Area Inch 2 Auto Manual Auto Manual Auto Manual Auto Manual 14.1 0.0 5.0 0.0 35.5 0.0 180.0 0.0 17.7 13.9 0.0 13.9 0.0 100.0 0.0 180.0 0.0 50.0 14.1 0.0 10.5 0.0 74.5 0.0 180.0 0.0 37.2 13.9 0.0 13.9 0.0 100.0 0.0 180.0 0.0 50.0 14.1 0.0 0.0 0.0 0.0 14.1 0.0 11.8 0.0 83.7 0.0 180.0 0.0 41.8 13.9 0.0 13.9 0.0 100.0 0.0 180.0 0.0 50.0 14.1 0.0 0.0 0.0 0.0 14.1 0.0 9.9 0.0 70.2 0.0 180.0 0.0 35.1 13.9 0.0 13.9 0.0 100.0 0.0 180.0 0.0 50.0 14.1 0.0 11.6 0.0 82.3 0.0 180.0 0.0 41.1 13.9 0.0 13.9 0.0 100.0 0.0 180.0 0.0 50.0 14.1 0.0 9.9 0.0 70.2 0.0 180.0 0.0 35.1 13.9 0.0 13.9 0.0 100.0 0.0 180.0 0.0 50.0 14.1 0.0 11.6 0.0 82.3 0.0 180.0 0.0 41.1 13.9 0.0 13.9 0.0 100.0 0.0 180.0 0.0 50.0 Coverages 0.0 85.6 Total Composite Coverage =

85.6 COMMENTS:

Code examination volume as defined by Relief Request 21Si-24, Figure 21Sl-24-1.

Manual UT scans were not restricted Credit for the initial 114" of material in Code coverage not obtained with the 45° and 60° near field effects is taken with the 70° RL.

Area I is the exam volume calculated at Top Dead Center. Area 2 is the exam volume calculated at 180".

-t 0

CovCa~c.xls 02/29/01

REQUEST 21SI-32 ATTACHMENTS A THROUGH G Attachment Attachment B 21SI-32-3 Weld Identification 10HPCS(1)-3 ISI Diagram HPCS-101-2 ISI Diagram RPV-109 NDE Data Report APR-001 21SI-32-4 Weld Identification.12RHR(1)A-14 ISI Diagram RHR-105 NDE Data Report R17-010 21SI-32-5 Weld Identification 12RHR(1)B-10 ISI Diagram RHR-106 NDE Data Report R17-012 pages 1 through 4

)ages 1 through 4

)ages 1 through 3

REQUEST 21SI-32 ATTACHMENTS A THROUGH G Attachment 21SI-32-3

23 4

5 6

7 8

9 10

• • ý N

0.

90*

• '270' 80O AZ /0 RPV NI (EE NOTE 6) lOHFCS(1)-4 (SEE NOTE 4)

SACRIFICIAL SHEILD WALL op0-3(ENOE)

IOHPCS(1)-2 (SEE NOTE 3)

I2HIPCS(I)-I9/3/4PI ()-4S (SEE NOTE 2)

(EO 212' X 10' RED ELL

//*..12HCS (1)-I1 NOTES

1. DELETED

2. EXTENO VISUAL LEAKAGE EXAM THRlOUGH CONTAINMENT PENETRATION (X-73O) THROUGH EXCESS FLOW CHECK VALVE TO INSTRUMENT TUBING CONNECTION.

3. DISTANCE BETWEEN WELDS 1OHPCS(1)-2 AND 1OHPCS(I)-3 IS LESS THAN 6E.

4. DISSIMILAR METAL WELD, CS TO INCO, USE CAL BLOCK UT-102.

S. DISSIMILAR METAL WELD, CS TO INCO, USE CAL BLOCK UT-iO6.

6. FOR NOZZLE ASSEMBLY DETAILS SEE RPV-109.

7. HPCS-918N & HPCS-919N WERE DELETED PER BDC 86-0525-6E-022.

REFERENCOP ISI - 220-I BOVEE AND CRAIL ISOMETRICS HPCS-630-29-30 REV 11 HPCS-630-31.33 REV 11 EL 561' CS-PWS 2-1 EL 558' EL CONT ON SLC-I01-7 4"SLC(2)-4 (REF)

EL 550" AZ, 2 40; 557' HECS-V-51 12HPCS(1 1-1 6/3/4HeCS-V-3B EL 552' DETAIL A

A 12IfCS(I)-15/4HPGCS1)

-4 SEE DET g0.

0.

160E PLATFORM EL5 li

• --- 12HPCS (1)-16

w HPCS-V-S CONT ON HECS-101-1 12'HPCS (1)-4 (IEF) 270*

QUALITY CLASS.

1 I

ASIE CODE CLASS.

1 ENGR, GA KUGLER IDRAWN, K-MCA IDATE, 11-2-77 ZONE R-43 THIS DRAWING IS INTENDED FOR USE IN PRESERVICE AND INSERVICE INSPECTIONS PROGRAMS ONLY.

WASHINGTON PUBLIC POWER SUPPLY SYSTEM RICHLADH.

WASHINGTON 99352 PIPING SYSTEM NOM DIA (IN)

SCH NGM WALL THK MATERIAL SPECIFICATION MATL TYPE CAL BLOCK NO WNP-2 WELD I COMPONENT IDENTIFICATION DIAGRAM 6

11-13-921 ADDED NOTE 7. MODOIFIED ACCORDINGLY.

K-IMCA I LWR I DRW 5 14-9S'rSTE", CNO AT HPCS-V-7tl. AWOEDONG LINE CONTINUATION.

12-4-B LOCO. MODIFIED EYPLA. REDA LIN K-PIcA DPR TFH 12"HPCS(l)-4 12 ED 0.68E SA 106 GR B CS UT-17

TITLE,

.53AMD 9UMRS gIEN I 919N. REMOVED 3/4L0C. AWED K-MCA OPR TFH IO'HpCS0)-4 10 ED 0.594 SA 106 GR B CS UT-22 4 S-24-B3 4"PCS(1I)-4, ADDXE UT-30 REDRAINM HPCS DISCHARGE TO VESSEL 3

12-2-81 REVISED AS NOTED K-PcA DER TFH 4"HPCS(Il)-4 4

Eo 0.377 SA 106 GR B CS UT-30 2 7-17-79 DELETED NOTE I AND REF TO WREL IN RE DtXIN G K I P

LFB t

6 ELBOW.

AS BUILT FIHE 15 SEAMLESS.

ZN C-5 K-CA LFG

, HPCS-1 01 -- 2R NO DATE REVISION BY CHKD APVD

a 0

I 2

4 5

6 9

10 A

B E

F G

H 0

0 0

0 WELDS N5 120" LPCS N16 240" HPCS I OLPCS(I)-4 1OHPCS(I)-4 IOLPCS(I)-3 A 1OHPCS(1)-3 IOLPCS(1)-2 A IOHPCS(1)-2 SAFE-END EXTENSION WELD DETAIL SAFE-END WELD DETAIL WELD DETAILQ 0 0

0}

0 55 UT-120 UT-102 NOTES EXAMINATION NOZZLE TO SHELL WELD NOZZLE TO SAFE-END WELD SAFE-END TO SAFE-END EXTENSION WELD SAFE-END EXTENSION TO PIPE WELD SAFE-END FORGING (IF EXAMINED)

NOZZLE INNER RADIUS UT-106 UT-22 UT-1O6 UT-1 19

REFERENCES:

CBI NUCLEAR CO.

SHT 60 REV 3 SHT 61 REV 2 SHT 63 REV S SHT 88 REV 4 SHT 89 REV 2 SHT 91 REV S ISl ISOMETRICS LPCS-101-2 REV HPCS-101-2 REV 205 AE 023 NS NOZZLE FORGING N5 SAFE-END & SAFE-END EXTENSION NS NOZZLE ASSEMBLY N16 NOZZLE FORGING N16 SAFE-END & SAFE-END EXTENSION N15 NOZZLE ASSEMBLY I NOZZLE 5' t o10' 0 1 2 3 4 5 6 7 8 9 10 SCALE. 1/4' THIS DRAWING IS INTENDED FOR USE IN PRESERVICE AND INSERVICE INSPECTIONS PROGRAMS ONLY.

QUALITY CLASS, I

I ASM"E CODE CLASS.

I QUALITY CLASS, 1 I

ENGR, T HOYLE I DRAWN, K-McA I DATE, 5-15-79 WASHINGTON PUBLIC POWER SUPPLY SYSTEM

RICHLAND, WASHINGTON 9935 ODIA SCH NON WALL INCH THICKNESS MATERIAL SPEC WNP-2 WELD 2 COMPONENT IDENTIFICATION DIAGRAM 80 0.594 SA IC 80 0.594 SA 106 W0 8 SA 508 CL 1

TITLE, LPCS / I'PCS DISCHARGE N5 NOZZLE AT 120" N16 NOZZLE AT 240" I SB 166 (900)

SA DWGNO, RPV-109 I REV 2 5 11/15 SA

/ I0 4 1

. Report No.:

EXAMINATION

SUMMARY

SHEET APR-001 GE NUCLEAR ENERGY Site:

Columbia Generating Station Component ID:

1 OHPCS(1 )-3 Outage:

R17 SE EXT TO SE System HIGH PRES CORE SPRAY ASME Cat.:

B-F A ASME Item B5.130 Aug Req Exams Data Sheet Cal Sheet Procedure Calibration Block Examination Cert Level Date Performed Personnel 45*/RL N/A APC-001 GE-UT-209 UT-106 Kevin Fish II 5/16/2005 450/S N/A APC-002 GE-UT-209 UT-106 Kevin Fish II 5/16/2005 45°/S N/A APC-005 GE-UT-209 UT-106 Kevin Fish II 5/16/2005 60*/RL N/A APC-006 GE-UT-209 CAL-DPTH-068 Kevin Fish II 5/16/2005 600/RL N/A APC-003 GE-UT-209 CAL-DPTH-068 Kevin Fish II 5/16/2005 45°/RL N/A APC-004 GE-UT-209 UT-106 Kevin Fish II 5/16/2005 N/A APD-008 N/A GE-UT-209 N/A Kevin Fish II 5/16/2005 Examination Results:

During the automated examination of the above referenced component, the Smart 2000 system recorded no indications associated with IGSCC utilizing 450 shear wave, 450 and 600 refracted longitudinal wave search units.

The 450 shear wave examinations were performed from both the upstream and downstream sides of the weld and recorded non-relevant indications, acoustic interface, inside surface geometry, outside surface geometry, root geometry, and beam re-direct.

The 450 refracted longitudinal wave examinations were performed from both the upstream and downstream sides of the weld and recorded non-relevant indications, acoustic interface, inside surface geometry, and root geometry.

The 600 refracted longitudinal wave examinations were performed from both the upstream and downstream sides of the weld and recorded non-relevant indications, acoustic interface, inside surface geometry, and root geometry.

Previous data was reviewed prior to this examination.

Pictures, thickness and contours were taken in accordance with BWRVIP 2005-14.

No counterbore was detected.

Examination coverage achieved utilizing a composite of the 450 shear, 450 RL and 600 RL search units.

85% code coverage achieved.

81%

procedural coverage achieved.

This examination meets the requirements of ASME Section Xl, 1989 Edition, no Addenda, and Appendix VIII, up to, and including 1998 Edition, with the 2000 Addenda.

Examination results were compared to data report R-R 10-016 from 1995 outage with

[]

No Change These examinations were performed under Work Order:

10853480 01 El Change This Summary and the following data sheets have been reviewed and accepted by he following personnel:

5 Dose:

181 mr.

Prellred By:

Level:

Date:"

Uti* eview:

Date, GE Review By:

Level:

Date:

ANII Revi w:

Date:

Page 1

of 15

Wall Thickness Site:

Columbia Generating Station Unit:

2 Report No.:

GE NUCLEAR ENERGY Profile Sheet Project:

16423 APR-001 System:

HIGH PRES CORE SP Y

Component ID Number:

IOHPCS(1)-3

-1.5 1.5" Position W0 90*

1800 270M 1

80 NA A

A Crown Height:

FLUSH 2

.80 IA WIA N/A Crown Width:

0.87 3

.82 WA NWA N/A SAFE END EXT.

SAFE END IIUPST Component:

DNST Component:

Nominal Diameter:

10.0..

4

.80 WA

/A N/A 5

Weld Length:

36.5" 5

N/A NA iN/A N/A FO =.

FLOW 1415 WJ40 U/~T6*

JO LPC.S(I) p p

(

Justin Lehmann II 5/15/2005 TV13A2 lnitials:

Drawn by:

Level:

Date:

.G eviewed By:

Level:

Date:

Page 2

of 1.

CF~)

10 HPCS(1)-3 45*S, 45° & 6(r RL.

430S, 45* & 6V RL Code Required Inspection Volume -

85%

Procedura( Required Inspection Volume -

81%

Circ Sc ca

Ultrasonic Data / Scan Parameter Sheet GE Nuclear Energy (Automated with Micro TomoScan)

Site:

Columbia Generatinq Station Procedure:

GE-UT-209 System:

HIGH PRES CORE SPRAY Report No.:

APR-001 Unit:

2 Version/ Revision:

17 Weld No.:

1OHPCS(lI-3 Data Sheet No.:

APD-008 Project No.:

16423 DRR:

N/A Configuration:

SE EXT TO SE Calibration Sheet No.

APC-O01 to 006 Scanner Information Weld Reference, (GE-ADM-1005):

Lo:

Too Dead Center Wo:

Weld Centerline Motor Steps:

Cir:

96.125 Tra:

98.3 Examination Surface:

OD Exam Surface Temperature:

90o F

Thermometer S/N:

241942 Exam Start:

5/16/2005 2:30:00 AM Exam End:

5/16/2005 8:51:00 PM Nominal Pipe Size:

10 in.

Nominal Thickness:

.8 in.

Weld Width:

.875 in.

Weld Length:

36 in.

Scanner:

NOVA Track Diameter:

16 in.

Arm Length:

12 in.

Track Location:

UPSTREAM 12" X Positive Scan Direction:

DOWNSTREAM Y Positive Scan Direction:

CW Resolution:

.036" Index Ax / Circ:

.18"

.047" Axial Scan Speed:

< 2.0 in./Sec.

Circ Scan Speed:

9 1.0 in./Sec.

Scanner Zero Positions:

CIR:

TOP DEAD CENTER TRA:

WELD CENTERLINE ROT Zero:

LOOKING DOWNSTREAM Scan Parameters and Results Scan:

Skew:

File ID:

Disk:

X-Start:

X-Stop:

Y-Start:

Y-Stop:

Gain:

Results:

Comments:

Z31 0

N16 3Z31 01 8.0mm

-49.0mm O.Omm 950.Omm Loi Z41 180 N16 3Z41 01 7.0mm

-49.0mm O.Omm 950.Omm LO" CD Z0o 0

N16 3Z10 01

-53.0mm 14.6mm O.Omm 950.0mm Ln C D E F H Z_11 N16 3Z11 01

-53.0mm 14.6mm O.Omm 950.0mm Lo" C.D.E.F.H 720 180 N16 3Z20 01

-48.2mm

17. 1mm O.Omm 950.Omm L"0 Q D, E F.

EXAMINATION RESULTS LEGEND A - NO RECORDABLE INDICATIONS B - NON-GEOMETRIC INDICATIONS C - NON-RELEVANT INDICATIONS D - ACOUSTIC INTERFACE E - INSIDE SURFACE F - OUTSIDE SURFACE G - WELD DISCONTINUITY H - ROOT GEOMETRY I - COUNTERBORE J - SHEAR COMPONENT K - BEAM RE-DIRECT Comments:

Exam limited to 17 mm downstream due to safe end taper.

Exam limited to 53 mm upstream due to location of weld 1OHPCS(1)-2.

• Configuration was not as designed. Load modified DXF.

Kevin Fish 5/1612005 s4"J '

Examiner:

Level:

Date:

GE Revie.

/

Level:

Date:

Page 4

of 15 Page _4 of

1.

I

REQUEST 21SI-32 ATTACHMENTS A THROUGH G Attachment 21SI-32-4

1 2

3 4

5

-6 7

8 9

10 I

II II CL 2 CLOTESi.

1. ACCESS TO WELD 12EHR(1)A-18 REQUIRES REMOVAL 1-RHR-V-53A/3/4 CAP OF RHR-PWS 6-1.

A 12RHR Ii)A-2/3/4V-602

2. WELD 12RHR(A)-5 IS FITTINGO TO FITTING.

-*3.

DISS IllILAR MElTAL WELD, CS TO SS. USE CAL CONT ON RHR-201-11 BLOCK UT-19.

2 (4.

ACCES TO WELD 12RHR(1)A-1O REQUIRES REMOVAL Z

Z

/

cOF RHP-SA-38.

RHR-V-53A(

R 12RHR(1)A-ILUO 12R I)A-L2RHR()A-4

5. DELETED.

12RHR(1) A-LU 12RI(1)A-1L 1(SEElA NOTE 7)"

EL5096.

CONDUIT 2 1/2' ABOVE WELD 12RHR(I1)A-12.

AZ 85'7.

WELD 12R14R(1)A-1 WAS REPLACED BY 12R1EI1C)A-lD WElfN RIHl-V-53A WAS REPLACED.

B. RHR-SA-35, RHR-SA-36, RHR-SA-37, RHR-SA-39, PRIMARY CONTAINMENT 12RHR(1)A-4/3/4V-59A RFR-SA-40 WERE DELETED PER BDC 87-0244-OJ-025.

12RHR(1)A-17LUI-

"2RHR(1)A-IGLOI

/12RM(I)A-?

X-1A,*12R'(I)A-5

9.

ACCESS TO WELD 12RHRI()A-17 REQUIRES REMOVAL (SEE NOTE 2)

OF RHR-SA-34.

RI-P-50410.

ACCESS TO WELDS 12RHR11)A-17LLIO.

12RFIR(I)A-17LU].

12RHR(1)A-16LUO AND 12RIR(1)A-1ILUI REQUIRES

(<

/

12RH A-O "REMOVAL OF RHlR-OlD.

11.ACCESS TO WELDS 12RHR(1)A-16 REQUIRES REMOVAL OF RHR-SA-33.

D REFERENCEoS,_,-s-.° vRV11 IS] - 221-1 RFP-510BOVEE

& CRAIL ISCBETRICS l

A(SEE NOTE IRHR-81-14 REV 10 12RH(1)-17RtR-B51-15.16 REV 110

• ~

~ CE DEAL RHI SA-33S,**

_/

(ST SSE OE3

\\,

y

\\

'2-SE NOT-45 REV1)

R0"/

990, QUALITY CLASS, 1

ASME CODE CLASS.

/2

• ENGR, 0 PORTER D RAWN. K-RcA

DATE, 12-14-77 WASHINGTON PUBLIC POWER THIS DRAWING IS INTENDED FOR R A__

EUSE IN PRESERVICE AND INSERVICE1)

SUPPLY SYSTE INSPECTIONS PROGRAMS ONLY.

RICILAND. WASHINGTON 9932 5

9-22-94 ADDED NOTE 8, MODIFIED ACCORDINGLY.

K-MCA OPR DW WNP-2 NOM NOM MATERIAL MATL CAL 4

12-9-92 ADDED NOTE 7, 101 DWG REF a O LINE CONT. MODIFIED LOGO

1.

KR NOTES 1 3, RR SA-32 Z RHR SA-59 EDRAWN K-MCA DPR DPW PIPING SYSTEM DIA SCH WALL BLOCK WELD 6 COMPONENT 3

9-26-83 REVISED AS NOTED, ADDED KEYPLAN K-MCA DPR TFH (IN)

THK SPECIFICATION TYPE NO IDENTIFCATION DIAGRAM 1

12-2-81 REVISED AS NOTED K-MCA DPR TFH 12"RHR(1)-4 12 100 0.844 SA 106 GR B CS UT-16

__________________T I___

TTLE.

o e-3-?-* ADDED LON SEAM DOWNSTREAMl FROM' WELDS 12RMt(1)A-1S. 115 ZI 17 K_

TH _.

P9ER A-EULT. ADDEO DETAIL FOR CLARITY Z

)A-a K-C3CA uw1 LEB 12'RHR{1)-4S 12 Bo 0.688 SA 312 GR B SS UT-19 RNR SHUTDOWN COOLING RETURN LOOP "A 6

1-24-96 ADDED NOTES 9, 10 a 11, RELOCATED RHR-PWS-6-1 SRP DPR CH' aRI91-SA-34 N&

RHE-SA-3 DWG NO. RHR-1 05 REV 6

NO.DATE IREVISION By-CHKD

ý APVDI H

0 I

GE NUCLEAR ENERG

)

I Site:

Outage:

System Columbia Generating Station R17 SHUTDN COOL RET LP-A Component ID:

12RHR(1)A-14 VALVE TO SE F

A ASME Item B5.130 Aug Req ASME Cat.:

B-Exams Data Sheet Cal Sheet Procedure Calibration Block Examination Cert Level Date Performed Personnel 45 RL UT-033 N/A PDI-UT-10 8746 George DuBose, IlII Il 5/11/2005 450 RL UT-034 N/A PDI-UT-10 8746 George DuBose, III Il1 5/11/2005 60 RL UT-035 N/A PDI-UT-1 0 8746 George DuBose, III Il1 5/11/2005 450 Shear UT-036 N/A PDI-UT-1 0 8746 George DuBose, III III 5/11/2005 Examination Results:

During the manual examination of the above referenced dissimilar metal weld, no reportable indications were detected utilizing a 450 Shear wave, 450 and 600 Refracted Longitudinal wave search units.

The 450 Shear did record root'and counterbore geometry.

No upstream examination was performed due to valve configuration.

31% Procedural coverage achieved 26% Code coverage achieved This examination meets the requirements of ASME Section Xl, 1989 Edition, no Addenda and 1995 Edition, 1996 Addenda, as modified by the Performance Demonstration Initiative (PDI) program description.

Examination results were compared to data report R-R8-136 from These examinations were performed under Work Order:

01082543 01 1993 outage with

[]

No Change Change This Summary and the following data sheets have been reviewed and accepted by the followi g Prepared By:

100, Level:

Date:

ilityRReview:

R =Ie ve

I Level:

Date:

Aý eview.

t 0

GE NUCLEAR ENERGY Wall Thickness Site:

Columbia Generating Station Unit:

2 Report No.:

Profile Sheet Project:

16423 R17-010 System:

SHUTDN COOL RET LP-A 1.5"-

1.5" Component ID Number:

12RHR(1)A-14 M

4 Position 0° 900 1800 2700 1

NA NA

/A

/A Crown Height:

0.15",

2 1.4 N/A N/A N/A Crown Width:

1.65" 3VALVE SAFE END Nomna Dimeer 12A N"

UPST Component:

iDNST Component:

Nominal Diameter:

12.0" 4

1.22 N/A N/A N/A Weld Length:

43.0" 5

1.3 N/A N/A N/A

.FLOW George DuBose, III III 511/2005 2

IffI

/PI&/u3 Drawn by:

Level:

Date:

Reviewed Level:

Date:

eview:

Date:

i-X,-

ew:.

Date:

Page 2

of Z C>)

F _

[Ultrasonic Examinati W

GE NUCLEAR ENERGY on Indication Report Data Report Number:

R17-010 Cal/Data Sheet Number UT-036

'dil Orlllrflf I A /AIIA V,.

Ul,,

llllUlf.

CW" U

U*Ula&i ul I

VI"

. F i

-. p i iv il-IIl Weld ID:

12RHR(I)A-14 Drawing:

RHR-105 Rev. 8 Size:

12" Thickness:

1.22" Exam Start:

0240 Lo Location: TDC Wo Location:

Weld Centerline Weld Width:

1.65" Weld Height:

0.15.

Exam End:

0410 Ind [Angle

% of Indication Length W Distance Metal Path Ax/

Upst/

No.

Used DAC L1 LMax L2 WI W Max W 2 MP 1 MP Max MP2 Circ Dnst Comments:

1 45° 112 1 N/A I 5.0 N/A N/A N/A I/A 1.9 N/A Ax Dnst IRoot geometry observed 360°.

2 1 45' 141 N/A I 31.0 W/A N/A 1.9 I WNA N/A 1.75 N/A I

Ax I Dnst iCounterboregeometryobserved360o.

Sketch

.George DuBose., Ill It 5/11/2005 d

R Level:

Date:

ReDReview:

Date:

Examiner Level:

Date:

Page 3

of 7

GE NUCLEAR ENERGY

[u Site/Unit: Columbia Generating Station /2 Outage:

R17 Iltrasonic Calibration and Examination Record Manual Piping and Components I

Report Number:

R17-010 Data Sheet Number:

UT-033 Linearity Sheet:

L-006 Calibration Data for Block: 8746 SS N/A 1.50" to 2.0 Calibration Cal Time Material Size Thick Initial Cal:

2201 Ulr e I 00325 Cal Check:

N/A Couplant:

Couplant batch 2417 72F Cal Check:

N/A Thermometer S/N Cal Temp.

Final Cal:

0456 Scan Direction Cal Reflector Signal Amplitude Signal Sweep:

Signal dB:

DAC Construction N/A 1.5 Notch 80%

5.2 Div 59.0 dB Procedure: PDI-UT-10 Ver/Rev: A DRR: N/A Search Unit Data RTD 04-301 2(10x18) mm/Rect.

Manufacturer:

Serial Number Size/Shape:

0.55 in.

45 450 Incident Point:

Nominal Angle:

Measured Angle:

2.0 MHz 450TRL 2-Aust RL 2

Frequency:

Style:

Mode:

Elements:

Search Unit Cable 2(RG-174) 6' 0

Cable Type:

Length:

Connectors:

Instrument Settings Staveleyf Sonic 136P 136P1106C031373 Maufacturer/Model:

Serial Number:

1.0 in.

0.227 inJusec.

2 4 KHz Delay:

Velocity:

Filter:

Rep Rate:

4.0 in.

250 500 Ohms Range:

Pulser:

Damping:

Off 2.25 MHz Dual Reject:

Frequency:

Mode:

Exam Comments / Limitations:

Sweep 0-10 =

4.0 in.

Metal Path Calibration Verification Field Simulator Block S/N:

N/A Reflector N/A NIA Amplitude N/A N/A Gain (dB)

N/A N/A Sweep (SD)

N/A N/A Acceptable Linearity performed :

4/20/2005 Exam Data for Weld: 12RHR(1)A-14 VALVE TO SE Configuration:

84'F 241783 Exam Surface:

Exam Temp.

Exam Thermometer Axial 1

UPST I Scan dB Recordable Exam Circ DNST 6

Indications Angle A

Dnst NRI f 45' Exams performed to maintain 5% to 20% ID roll.

No upslteam exam performed due to valve configuration.

4---

~-

-f Exam Start:

0240 Exam End:

0410 George DuBose, Ill Ill

-//__/0 Iniial:

Examiner:

Level:

eview By:

Level:

Date:

Initials:

Examiner 2:

Level:

Ilty view:

Date:

Initial Cal/Exam Date:

5/11/2005 A

ew Date Page 4 of 7

REQUEST 21SI-32 ATTACHMENTS A THROUGH G Attachment 21SI-32-5

2 34 SS 8

1 2

3 4

5 7

8 9

10 4 N PLATFORM EL 513'

NOTES, I. WELD 12RHR(1)B-1 IS FITTING TO FITTING.

2. WELD 12R1HR(1)B-11 IS FITTING TO FITTING.

3. ACCESS TO WELD 12RHR(1)8-11 RESUIRES REMOVAL OF RHR-SB-32 I RHR-SB-33.

4. DISSIMILAR METAL WELD, CS TO SS, USE CAL BLOCK UT-19.

5. ACCESS TO WELD 12RHR(I1)-6 REQUIRES REMOVAL OF RWE-514.

6. RHR-SB-40 CHANGED FROMI SNUBBER TO STRUT PER BDC-E6-0525-OA.

7. RHR-V-53B WAS REPLACED WITH A GATE VALVE AT OUTAGE RF BSA PER BDC-Br-0323-OA.

8. RHR-SB-32, RHR-SB-34, RHR-SB-3S. AHR-SB-36 &

RHR-SB-39 WERE DELETED PER BDC 07-0244-OJ-025.

REFERENCEGS-ISl

- 221-2 BOVEE & CRAIL ISOMETRICS RHR-B99-46.47 REV 12 RHIR-89-4B REV 10 90W CF TP AN

100, 270' DUAL I

ENGR, THIS DRAWING IS INTENDED FOR USE IN PRESERVICE AND INSERVICE INSPECTIONS PROGRAMS ONLY.

TY CLASS, 1

I ASME CODE CLASS.

1 D PORTER I DRAWN. K-McA I DATE, 12-15-77 WASHINGTON PUBLIC POWER SUPPLY SYSTEM RICILAND, WASHINGTON 952 WNP-2 WELD & COMPONENT IDENTIFICATION DIAGRAM ADDED NOTE 8. MODIFIED ACCORDINGLY.

ADDED RHR-PWE ?-1 ZONE C-?.

ADDED IS) DWG REF DW LINE CON[, LOGO, NOT1S 6 I LUGS. CORRECTED RHR-V-528 9 CONN. a rUEYPtAN.

REVISED AS NOTED.

ADDED KEYPLAN & LUGS.

REVISED AS NOTED SHUTDOWN COOLING RETURN LOOP 'B' REVISION

D / ::

// t-) Cý-'

, /

a GE NUCLEAR ENERGY EXAMINATION

SUMMARY

SHEET Site:

Outage:

System Columbia Generating Station Comp R17 SHUTDN COOL RET LP-B

'onent ID:

12RHR(1)B-10 VALVE TO SAFE END A ASME Item B5.130 Aug Req ASME Cat.:

B-F Exams Data Sheet Cal Sheet Procedure Calibration Block Examination Cert Level Date Performed Personnel 450 Shear UT-091 N/A PDI-UT-10 8746 George DuBose, Ill III 5/21/2005 450 Long.

UT-092 N/A PDI-UT-10 8746 George DuBose, III III 5/21/2005 600 Long.

UT-093 N/A PDI-UT-10 8746 George DuBose, III III 5/21/2005 450 Long.

UT-094 N/A PDI-UT-10 8746 George DuBose, III III 5/21/2005 Examination Results:

During the manual examination of the above referenced dissimilar metal weld, no reportable indications were detected utilizing a 450 Shear wave, 450 and 600 Refracted Longitudinal wave search units.

The 450 Shear did record counterbore geometry.

The 450 RL did record counterbore geometry.

No upstream examination was performed due to valve configuration.

16% Procedural coverage achieved 29% Code coverage achieved This examination meets the requirements of ASME Section Xl, 1989 Edition, no Addenda and 1995 Edition, 1996 Addenda, as modified by the Performance Demonstration Initiative (PDI) program description.

No previous data was available prior to this examination.

Examination results were compared to data report N/A from N/A outage with

[ No Change These examinations were performed under Work Order:

01082186 D

Change This Summary and the following data sheets have been reviewed and accepted by the following personnel:

RWP:

NA 4

-'.j-2-3-T 4

Dose:

N/A mr.

Prepared By:

Level:

Date:

LiIi View:

Date:.

GE Review By:

Level:

Date:

AN(I Revi#w:

Date:

Page 1

of 7

I U

vWall Thickness Site:

Columbia Generating Station Unit:

2No.:

GE NUCLEAR ENERGY Profile Sheet Project:

16423 R17-012 System:

SHUTDN COOL RET LP-B C.o" I

N 1.1"

-Component ID Number:

12RHR(1)B-10 1.

r 1.5" Position 0

900 1800 2700

[_*

Crown Height:

Flush 2

N/A N/A N/A N/A Crown Width:

1.7 Valve Safe End 3

1.34 N/A N/A N/A UPST Component:

DNST Component:

Nominal Diameter:

12.0" 4

1.30 N/A N/A N/A Weld Length:

42.0" 5

1.36 N/A N/A N/AFLW Ge DuBose I II 5/21/2005 Initials:

Drawn by:

Level:

Date:

GE Reviewed By:.-/"

Level:

Date:

Page 2

of Z i

II-

GE NUCLEAR ENERGY Ultrasonic Examination Indication Report Data Report Number:

R17-012 Cal/Data Sheet Number UT-091 and 092 Site: Columbia Generatinq Station Procedure: PDI-UT-10/A Weld ID:

12RHR(1)B-10 Drawing:

RHR-106 Size:

N/A Thickness:

0.50" to 2.0" Exam Start:

1450 Lo Location: Top Dead Center Wo Location:

Weld Centerline Weld Width:

1.70 in Weld Height:

Flush Exam End:

1555 Ind Angle I% of Indication Lentth W Distance Metal Path Ax/

Upst/

No. ! Used DAC ! Li I L Max L

L2 ! W1 I W Max I W2 ! MPi I MP Max I MP2 Circ Dnst I Comments:

1 45' 200 28.5 1.9 1.8 AX I DNST 145 Shear - Counterbore Geometry observed 360 1

450 159 29.0 19 I

1.8 AX DNST 145 RL - Counterbore Geometry observed 360 Sketch George DuBose, Ill LIl 5/21/2005 GE Reviewed By:

Level:

Date:

LiReview:

Date:

A/11 Re/ew:

Date:

Examiner Level:

Date:

Page 3 of 7

REQUEST 21SI-32 ATTACHMENTS A THROUGH G Attachment Attachment C 21SI-32-6 Weld Identification 6RCIC(1)-40 ISI Diagram RCIC-102-3 Construction Drawing RCIC-129 (CVI 02-215-008, 203) sheets 2, 4, and 5 NDE Data Report R15-086 pages 1, 4, and 5

10 0

2 4

5 7

8 9

N 6RC IC (1 6ElC IC I. WELD 6RCIC(l)-45 UTILIZED CAL BLOCK UT-lOT.

2. FOR DETAILS OF NOZZLE ASSEMBLY SEE RPV-111.

3. TEMPORARY SUPPORTS INSTALLED WAEN OISCOFNECTED FROM RPV.

4. ACCESS TO WELD ERCIC(l)-37 REQUIRES REMOVAL OF RRC-940N.

5. RCIC-934N & RCIC-936N CHANGED FROM SNUBBER TO STRUT PER SOC-86-0525-SC-024.

6. RCIC-128, RCIC-931N.

RCIC-932N, RCIC-933N g RCIC-935N WERE DELETED PER BOC-86-0525-SC-024.

IS] - 219-1 BOVEE I CRAIL ISOMETRIC RCIC-659-27.29 REV 12 6RCIC(1) (SEE NOTE 4)

~ RPV

,,-EL 593' EL 592' RETURN 0.

270*

KEYPLAN 180O

-6RCIC(l)-34 PLATFORM EL 583' QUALITY CLASS, i

ASME CODE CLASS.

1 ENGR, D PORTER I DRAWN, K-McA I DATE, 4-26-78 WASHINGTON PUBLIC POWER SUPPLY SYSTEM RICHILAND, WASHINGTON 993M2 THIS DRAWING IS INTENDED FOR USE IN PRESERVICE AND INSERVICE INSPECTIONS PROGRAMS ONLY.

1 r-,

1 r-r 4

PIPING SYSTEM NOM DIA (IN)

SCH NOM WALL TI-K MATERIAL SPECIFICATION MATL TYPE CAL BLOCK NO WNP-2 WELD & COMPONENT IDENTIFICATION DIAGRAM 7

9-22-941 DELETED RCIC-941N PER BDC 86-0525-5C.

IK-ICAI DPR I DW 6

12-9-92 ADDED NOTES S It 6.

DELETED UT-45.

K-NCA DPR DRW 6RCIC(Il)-4 A

BO 0.432 SA 106 GR 8 CS UT-28 TITLE.

'10-16-7 CWNED RCiC-129 O SPRINg. ADDD ISi OW REF, DW C041 K-RCA D

T_

RESIDUAL HEAT REMOVAL /

LINE Z LOGO. MIOIFIED WDYPLAN. REDRAWN jPR T RESIDUALHEATREOVAL_/

4 1-23-86 REVISED AS NOTED ADDED KEYPLAN & LUGS K-RCA OPR TFH REACTOR CORE ISOLATION COOLANT HEAD SPRAY 3

11-5-M0 REDRAWN, CONFIGLURATION CHANSE, ADDED HANGERS.

K-RCA TFH OWP NO DATE REVISION BY CHKD APVD R

C WASHINGTON PUBLIC POWER SUPPLY SYSTEM HANFORD NO.2 MARK NO. RC/C- /Z9 BURNS AND ROE, INC.

Engineers and Constructors New Jersey

• New York e Connecticut e California W.0.3808 DWG. P C/C-/Z'2""*

ENGINEER I

U)

C 0

ca"Rclc 60-4 Z/4'%o Q)

II

.2-i U-S~2 a

WASHINGTON PUBLIC POWER SUPPLY SYSTEM HANFORO NO.2 REV NO REVISION IDATE I APVO OWN t'

rCHKDpF40

/

9A I

SCALE 1,75 MR SL/LDE

%\\bf-JDATE N-/7-o. PC, / C 251 ENGINEERING REVIEW BURNS AND ROE, INC.

MECH CIVIL *.

Engineers and Constructors ELEC New Jerseys New York 6 Connecticut

• California

• E'VTg61 P

3*¢.A OATE V

7,I a-ý NIER'ýS.

ý;z/a/&t W -

.380T(DWG. R ICf/C / 2

C UAAJ SIZE- ~EC~P'A I

/0 2

/20

/A./F//C~

}

/

~~/",q t-74.,

~6 c/- 6716 0/~

M

/4 x 3& 77/v

)

ý-

/

) 9 4 STIFF R-318"x

-"3~

Ila-' (CU-T T0 SUrF SEE SE-CT. E-E)

A-3co I

?- V ViV ELDED BEAMA A-TTACHMEN7 FKG. 14DA 22 Z

V2a"Ox P-711 LQj, HANGERI ROD) FIG. 165 2-4 a 1CNSTANT SUPPOR~T 'tVA-9O5-3OO9 TOTAL LOAD= 554"CALCO.

-__ 4

___TFRAVELIz2-5/A')

HP TOTAL TRAVE.L 73 V?-"

UP 25:2

/"

TURNBUCK~LE, 3'" OPENING Firl. )64 2C~ c I

/

x0-C"(a~m oR,1s6" lp 4

I__ De 7--=

/ 7-,--Ai5

/

,7,/1,5,2 p

.3 7T0 74-AWX

.3w_

N DELETED DETAIL k~Y m w?/coep.

I 0-I'rA IfE-/,C-0 25o 0 8aIFb/-

WASHINGTON PUBLIC POWER SUPPLY SYSTEM HANFORD NO.2 REV NO REVISION DATE 1 APvo OWN CNKDFeOF4AJek

!SCALE MR O

ANLE

-NIE-MUC

/2/3 W..

DG. 1C C- / 2li.

C Report No.:

EXAMINATION

SUMMARY

SHEET RIS-086 GE NUCLEAR ENERGY Site and Unit:

Columbia Generating Station Component ID:

6RCIC(1 1-40 Outage:

RFO-15 PIPE TO VALVE System:

RCIC ASME Cat:

B-J ASME Item B9.1_1 Aug Requirements:

N/A Exams Performed Data Sheet Cal Sheet Procedure Calibration Block Examination Cert Date Personnel Level 60° Shear UT-R1 5-067 N/A PDI-UT-1 UT-28 DREW PETERSON II 5/28/01 450 Shear UT-R15-068 N/A PDI-UT-1 UT-28 DREW PETERSON I1 5/28/01 Examination Results:

During the manual ultrasonic examination of the above referenced weld, no reportable indications were recorded utilizing the 45' and 60' search units. Root geometry was recorded by the 60° search unit.

This examination is acceptable per the requirements of ASME Section Xl, 1989 Edition, no Addenda and the 1995 Edition, 1996 Addenda with modifications as stated in 10CFR50.55.

The examination was limited from 8" to 14" due to a support. 86% Code coverage was obtained.

Previous data was reviewed prior to this summary.

Examination results were compared to data report RIU-080 from 1980 outage with No Change These examinations were performed under Work Order:

01010463 ED Change This Sfll?'nd the following data sheets have been reviewaend accepted by the following personnel:

RWP:

N/A 5__3,0___

-1 i

Dose:

N/A mr.

Prepared By:

Level:

Date:

UtihtbReviewed By:

Title:

Dte:

GE Reviewed By:

Level:

Date:

ANII Reviewed By:

Title:

Date; Page 1

of K'1'

O P

GE NUCLEAR ENERGY Ultrasonic Ex Site: Columbia Generating Station amin;ation Indication Report Data Report Number:

R15-086 Procedure" PDI-UT-1 / 8/Site Specific Rev. 0 Cal / Data Sheet Number UT-R15-067 Weld ID: 6RCIC(1)-40 Lo Location: TOP DEAD CENTER Drawing:

RCIC-102-3 Wo Location:

WELD CENTERLINE Size:

6 Thickness:

0.432 Weld Width:

1.0" Weld Height:

FLUSH Exam Start:

2105 Exam End:

2155 Ind Angle

% of Indication Length W Distance Metal Pa Ax Upst/

No.

Used DAC LI L'Max I L2 W1 W Max W2 MP1 MPMax IMP2 Circ Dnst Comments:

1 so 80 NA I 7".CW [ N/A.

N.A.

.87" I NAI

-- LAx Upst Root geometry seen 360" Intermittent -d Sketch DREW PETERSON Examiner It 5/28/01 GER ie Level:

Date:

Level:

Date:

Date:

Page ~lof£ ANII Reviewed By:

GE NUCLEAR ENERGY System:

RCIC Wall Thickness Profile Sheet RFO-15 Component ID Number:

6RCIC(1).40 1.5" 1 Crown Height:

Crown Width:

Nominal Diameter Weld Length:

FLUSH 1.0" 6.0" 21.5" PIPE VALVE UPST Component:

DNST Component C1 (

Div DREW PETERSON II 5128/01 Initials: Examiner:

Level:

Date:

GE Reviewed By:

Level:

Date:

Page S-

REQUEST 21SI-32 ATTACHMENTS A THROUGH G Attachment Attachment D 21SI-32-7 Weld Identification 24RRC(1)A-14 ISI Diagram RRC-101-2 NDE Data Report R15-053 21SI-32-8 Weld Identification 24RRC(1)A-15 ISI Diagram RRC-101-2 NDE Data Report R15-054 21SI-32-9 Weld Identification 24RRC(1)A-18 ISI Diagram RRC-101-2 NDE Data Report R15-057 21SI-32-10 Weld Identification 24RRC(1)A-19 ISI Diagram RRC-101-2 NDE Data Report R15-058 21SI-32-11 Weld Identification 24RRC(1)B-12 ISI Diagram RRC-102-2 NDE Data Report R16-060

REQUEST 21SI-32 ATTACHMENTS A THROUGH G Attachment 21SI-32-12 Weld Identification 24RRC(1)B-16 ISI Diagram RRC-102-2 NDE Data Report R16-062 21SI-32-13 Weld Identification 24RRC(1)B-17 ISI Diagram RRC-102-2 NDE Data Report R16-063 21SI-32-14 Weld Identification 24RRC(2)A-10 ISI Diagram RRC-101-2 NDE Data Report R15-049 pages 1 and 6 21SI-32-15 Weld Identification 24RRC(2)B-8 ISI Diagram RRC-102-2 NDE Data Report R16-066

REQUEST 21SI-32 ATTACHMENTS A THROUGH G Attachment 21SI-32-7

2 4

5 7

8 9

10 I

II II I

6 X 12' RED (REF)

CONT ON RRC-101-3 NDTEi.

112RRC(l)-4S (REF)

1.

SEE RRC-P-1A DETAIL DWG RRC-103 FOR PUMP SUPPORT DETAILS.

NR r2.

EXTEND LEAKAGE EXAM THROUGH CONTAINOIENT A

N K_ EL 528' (REF)

PENETRATION (X-?Oe) THROUGH EXCESS FLOW 24' X 1 CROSS (REP)

CHECK VALVE TO INSTRUMENT TUBING CONNECTION.

3. DELETED CONT ON RRC-101-3

4. SPECIAL CLAMP WITH HA-7 I SA-7 ATTACHMENTS.

6 E RRCI,)-4s (REF)

. WELD 24.RCCl)A-13/BCAP-,

IS PITTING TO FITTING.

24-RC1)A-21

5. WELD 24RRC ()A-20/IOCAP-1 IS FITTING TO FITTING.

9*

4 U

P. EXTENO LEAKAGE EXAM THRODUGH CONTAINIENT ILUPENETRATIO (X-P7Ao)

THROUGH VALVE RRC-V-20.

B. WELD 24RRC(I)A-19 IS FITTING TO FITTING.

29.

RRC-V-EDA HAS TWELVE (121 2 3/4' X 1iS' BDY V

24RRC(A-2/3/400-14

10. CAP TO NOZZLE WELDS ARE CLAD ON THE ID IN RE-NA

• -~

(SEE NGTE 7)

THE WELD AREAS.

SEE REF DUOS 131 C 7588,

131 C 7589.

A*

,11.

PIPING FROM PMPP DISCHARGE TO RRC-V-67A HAS 24RRCl BIN WALL OF 1.218.

PIPING FROM RRC-V-67A HAS EL 512 't-24RRCO*iA-2D/,2CAP 2MIRC,,-A-UOO EEC-A-ES N WALL OP 1.140.

EL 51-24RRC(1)A-20/12CAP-1 24RRC()A-P NRC-HA-?

2. DELETED

/ * /

(SEE NOTES 6 2 10) 24RRC(l)A-17D *2 A-

13. DELETED CO(T ONO TES R\\C1)XC)

-/

,-I4 A-16.O0

14. RRC-SA-B. RRC-SA-9, RRC-SA-iS. RRC-SA-17.

RC(?-45--7 RRC-SA-18 & R-SA-66 WERE DELETED PER 12'RC(?I-4S(RE)_X 4RRO)A-6 BC 8?-0244-OJ-024.

24RRC(I)A-20/121RC-1-40 244RCCI)(1) 24R(1A20' RR--O034-E IS] - 230-1 24RRC(I)A-2OLUOD-I (SEE NOTE 4)

VA_ A/

GENERAL ELECTRIC DRAWINGS 24RRCLX)A-2DLU I

,i/

-V-761 E 424 REV 2 (ENO* *

,SEE NOTE )

762EE 538 SNI REV 12 04R()AIL N1RC-V-B0A/I V-94A 762 E 538 SM 2 REV 11 D

)-824RRC(1)A-1471E 3RV EL50'761 E735 REVB6

-RC-V-67A/3/4V-7A

(,SEE NOTE 12) 131 C 7588 REV 3 RC-V-Bg 7A/3/4V-69A 24RRC(I)A-14LU 131 C 7588 REV S 24RCIA-9131 C 7582 REV 3 (1

1BOVEE CRAIL/GERI 24I 24A-,1

-1BC/G-216 REV 8 24RRC(I)A-19LD 24RRCI1)A-13/OCAP-1 90' i /p~j.(SEE NOTES~

1 0)

E 4RRC (B)

(

A-?

PLt0 24RRC(IlA-i3/

(B)

PLATFORM (SEE NOTE 12)

EL 501" 24RRC (1)A-1-3/3/4APT-HO1SA 0.)

160*

(SEE NOTE 2) 6 24RRC (1)A-13LD 270' QUALITY CLASS, 1

I ASME CODE CLASS, 2

CONT ON)NRC-lOT-i NR IMNS JR

-C 67 24'RRCC2ENR TI INS DRAWN, K-o I DATE, 4-6-76 WASHINGTON PUBLIC POWER EL 503' (REF) V THIS DRAWING IS INTENDED FOR G

USE IN PRESERVICE AND INSERVICE SUPPLY SYSTEM INSPECTIONS PROGRAMS ONLY.

RICHLAND, WASHINGTON 99352 5

8-22-94 ADD NOTE 14. MOD ACCORDINGLY. DEL NOTES 12. 13 K-MCA DPR DW NOM NOM MATERIAL MATL CAL WNP-2 4

6-7-94 CORRECTED PENETRATION NUMBER IN NOTES 2 & 7.

K-McA DPR DW PIPING SYSTEM 0IA SCH WALL BLOCK WELD It COMPONENT

• o SI )W*RIF D* LNE OMT LOO [ ""

T I R*-9.

IN)THK SPEIFCATION TYPE IO Owe (IN)*TS I

ATFI K-ICA DPR TFH IDENTIFICATION DIAGRAM 2

10-13-83 REVISED AS NOTED.

ADDED KEYPLAN K-BcA DPR TFH 24"RRC(l)-4S 24 XXX SEE NOTE 11 I SA 358 GR 304 CL 1 0S UT-?

TITLE, 1

11-5-80 REVISED AS NOTED K-MCA TFH DWP 4*RRC(8)-4S 4

60 0.337 SA 376 TP 304 SS UT-29 REACTOR RECIRCULATION LOOP A 0

11-27-78 ISSUED FOR USE K-MCA LFB CAP 12 80 0.688 SA 403 GR WP 304 SS UT-19 5-19-76 ISSUED FOR INFORMATION ONLY K-HcA NCH DWP CAP 6

80 0.50 GSA 403 GR UP 304 GO UT-26 DWG NO, RPC--1 0 1 - 2 REV 5 NO DATE REVISION BY CEND APVD I

H

GE NUCLEAR ENERGY EXAMINATION

SUMMARY

SHEET Site and Unit:

Columbia Generating Station Component ID:

24RRC(1)A-14 PIPE TO VALVE Outage:

RFO-15 System:

RRC ASME Cat:

B-J ASME Item B9.11 Aug Requirements:

N/A Exams Performed Data Sheet Cal Sheet Procedure Calibration Block Examination Cert Date

!L!

Personne Level I

600 RL I UT-R15-046 PDI-UT-2 UT-7 JACK REISEWITZ II 5/24/01 450 SHEAR UT-R15-045 PDI-UT-2 UT-7 JACK REISEWITZ II 5/24/01 Examination Results:

During the manual ultrasonic examination of the above referenced weld, no reportable indications were recorded utilizing the 450 and 60° search units.

This examination is acceptable per the requirements of ASME Section X1, 1989 Edition, no Addenda and the 1995 Edition, 1996 Addenda with modifications as stated in 10CFR50.55.

Examined from pipe side only due to valve configuration. 50% code coverage obtained.

Previous data was reviewed prior to this summary.

. Xaminatlon results were compared to data report RRU-240 from 1979 outage with

[

No Change LI Change These examinations were performed under Work Order:

01011024 This Summary and the following data sheets have been reviewejd accepted by the following personnel:

RWP:

N/A

.o__

Dose:

N/A mr.

GPrepared By: '

Level:

Date:

AI Reviewed By:

Title:

DateP GE Reviewed By: L 7 Level:

Date:

ANII Reviewed By:

Title:

Date:

Page 1 of 4

Ultrasonic Calibration and Examination Record I

GE NUCLEARl ENERGY Manual Piping and Components Data Report Number: R15-053 Site/Unit: Columbia Generatinq Station IN/A Data Sheet Number:

UT.R15.045 Outage:

RFO-15 Linearity Sheet:

L-004 Calibration Uata or ~lock: U7-1 Proceaure: rL-u -'

Rev _

DRR: Site Specitic Rev. 0 ss Material ULTRAGEL Couplant:

213183 Thermometer SIN 24 1.14 Size Thick 97425 Couplant batch

70. F Cal Temp.

Calibration Initial Cal:

Cal Check:

Cal Check:

Final Cal:

Cal Time 2030 N/A NA_

2354 DAC Construction Search Unit Data KBA 003R18 0.50"/Round Manufacturer:

Serial Number Size/Shape:

0.55 In.

450 45.

Incident Point: Nominal Angle: Measured Angle:

1.5 MHz Como-G SHEAR Frequency:

Style:

Mode:

Search Unit Cable RG-174 6-0 Cable Type:

Length:

Connectors:

Instrument Settings Scan Direction Cal Reflector Signal Amplitude Signal Sweep:

Signal dB:

Ax Circ ID Notch ID Notch 80%

5.2 Div 37.2 dB 80%

5.3 Div 42.0 dB Sweep 0-10 =

4.0 In.

Metal Path Calibration Verification Field Simulator Block SIN:

N/A Staveley / Sonic 136P Maufacturer]Model:

0.48 In.

0. 1221n./usec.

Delay:

Velocity:

Reflector N/A N/A Amplitude NIA NIA Gain (dB)

NIA N/A Sweep (SD)

N/A N/A Acceptable Linearity performed:

5/16/01 136991A091220 Serial Number:

2 4 KHz Filter:

Rep Rate:

500 Ohms Damping:

P/E Mode:

4.0 In.

Range:

Off Reject:

334 ns Pulser:

2.25 MHz Frequency:

Exam Data for Weld. 24RRC(!)A-14

---.. PIPETO VALVE Configuration:

.CxamComments

/Umitations:

No axial exams performed on downstream valve surface.

Counterbore observed below recordable level.

O_

Exam Surface:

92°.F 213183 Exam Temp.

Exam Thermometer RRC-101-2 Drawing:

Circ DNST Scan dBI Recordable I

L!

I.n:*i{Jdicationls Exam Angle Axial UI'st 51._2 NRI 45_

Axial Dnst NIA I

N/A CIrc Upst 56.0 NRI 45_

Exam Start:

2100 Exam End:

2215 Clrc Dst NIA NRI JACK REISEWITZ It

~

j/-/

Initials:

Examiner:

Level:

GE Rev*

d By:

Level:

Date:

N/A N/A 0

eV

&40 1Ji evi~ewed B:5'e1 1WI Initi.als:

Examiner 2.evwedB

.:aeFrPlpeweld Cal/Exam.Date.

24/01N "By:

Date.

PRecord # 67 Cal/Exam Date:

5,124101 NIRvee y

ae Page 2 of 4

-NIRveedB:Dt:-

Ultrasonic Calibration and Examination Record GE NUCLEAR ENERGY Manual Piping and Components Data Report Number: R15-053 lSite/Unit: Columbia Generating Station /N/A Data Sheet Number:

UT-R15-046 Outage: RFO-15 Linearity Sheet:

L-004 Calibration Data for Block: UT-.7 Procedure: PDI-UT-2 S 24 1.14 ~C~libratitnn 1 c* Tim* 1 Rev A DRR: Site Specific Rev. 0 Material Size Thick Initial Cal:

2045 ULTRAGEL 97425 Cal Check:

N/A C ouplant:

C ouplant batch C

C h eck:

NIA 21383 0F Cal Check:

N/A 213183 70S F T

F Th~ermometer S/N Cal Temp.

IFinal Cal:

2357__

I Scan Direction Cal Reflector Signal Amplitude Signal Sweep:

Signal dB:

Sweep 0-10 =

...*0 DAC Construction Search Unit Data RTD 92-894 2(10x18) mm/Rect.

Manufacturer:

Serial Number Size/Shape:

0.5 In.

60_

60.

Incident Point: Nominal Angle: Measured Angle:

2.0 MHz TRLA RL Frequency:

Style:

Mode:

Search Unit Cable RG-174 6-0 Cable Type:

Length:

Connectors:

Instrument Settings Ax ID Notch 80%

5.9 Div 76.0 dB In.

Metal Path Calibration Verification Field Simulator Black SIN:

N/A 1 Reflector NIA N/A Amplitude N/A N/A Gain (dB)

N/A N/A Sweep (SD)

N/A N/A Acceptable Linearity performed:

5/16/01 StaveleV/ Sonic 136P Maufacturer/Model:

136991A091220 Serial Number:

0.85 In.

0.231n./iusec.

2 4 KHz Delay:

Velocity:

Filter:

Rep Rate:

5.0 In.

Range:

250 ns Pulser:

500 Ohms Damping:

Exam Data for Weld: 24RRC(1)A-14 PIPE TO VALVE..

Configuration:

OD Exam Surface:

Drawing:

92E F 213183 Exam Temp.

Exam Thermometer RRC-101-2 Off 2.25 MHz Dual Reject:

Frequency:

Mode:

Exam Comments I Limitations:

No scans possible from downstream valve surface.

Exam Start:

2100 Exam End:

2215

~e~2

-/

Level:

Date:

Date:

Date:

Form: Pipe Weld Record # 62 Page 3 of 4

GE NUCLEAR ENERGY Wall Thickness Profile Sheet F

Site:

Columbia Generatinq Station Unit:

N/A Report No.:

Project:

RFO-15 R15-053 I

System:

RRC Component ID Number:

24RRC(1)A-14 Position 0° 90° 180I 2700 1.5" 1.5"

!--,-l L--2 4,.t, 1

N/A N/A 1.03 1

WA N/A N/A 1.10 N/A 2

N/A N/A 1.21 N/A 3

N/A NA 1.32 NA 4

Crown Height:

Crown Width:

Nominal Diameter Weld Length:

FLUSH 1.1" 24.0" 75.0" PIPE i

VALVE UPST Component:

DNST Component

/

.\\

5 N/A N/A N/A I

WA

REQUEST 21SI-32 ATTACHMENTS A THROUGH G Attachment 21SI-32-8

0 066 1) 10 2

3 4

7 a

9 1' X 12' RED <RNF)

CON ON RRC-101-3 12'SRCfl)-45 (SEF)

,t EL 528' (REF) 2 iN' CROSS (REE)

CONT ON RRC-101-3 16"RRC(l)-4S CREP)

-24RRCCI)A-21

90.

24RRC (1) A-21LU

1. SEE RRC-P-lA DETAIL OWG RRC-103 FOR PUMP SUPPORT DETAILS.

2. EXTEND LEAKAGE EXAM THROUGH CONTAINMENT PENETRATION (X-?7e) THROUGH EXCESS FLOW CHECK VALVE TO INSTRUMENT TUBING CONNECTION.

3. DELETED

4. SPECIAL CLAMP WITH HA-? It SA-7 ATTACHMENTS.

5. WELD 24RRC1)WA-13/BCAP-I I5 FITTING TO FITTING.

6. WELD 24RRC(I)A-20/IOC AP-1 I5 FITTING TO FITTING.

7. EXTEND LEAKAGE EXAM THRIO.UGH CONTAINMENT PENETRATION (X-7?AO) THROUGH VALVE RRC-V-20.

8. WELD 24RRC(I)A-19 IS FITTING TO FITTING.

g. RRC-V-NOA HAS TWELVE (12) 2 3/4" X 15' BODY TO BONNET STUDS.

0 o.>2 f RPV BC oo-9C A

D

ý 4R()-034O7 12' 24RC C1IIA L

A 24RRC(I)A-1?LUI EL 512' ".

24RRC(1)A-2D/i2CAP 24RRCi1) A-'LuO REC-SA-E5 24RRC(I)A-20/i2CAP-1 24RRC(I)A-7-HT\\

FRC-A-?

(SEE NOTES 6 & 10) 24RRC(I)A-17LD 24RRC)A-16LDI CONT ON REC-106

/\\

V

\\7A

/

2ONRC(IA-I-_O0 RRC(7T-4 S

(SEP) 24RRC(ITA -20/12RECIT)-45 2RCIA1L RCR-.A I,24RRC(IA--

24RRC (i)TA-20LD---

RRC-;A-7 (SEE NOTE 3) 24RRC 1T)

A-20 ---

24R/C\\1)A-2L-(SEE N--*TE

\\

,' R RC-V-NOA/3/4V-66A 24RLC(/)A-20LIII----..

A SEC -V0A

(

SEC VNO/TE V SEC-V-6TA/3/4V-69A 245EC(I)A-14LU 2455CClT-T3/BCA 2

C24RRC (1) N-1 3/BAP-T 245RC ( I I A-13/1/4dPT-NOI 5k" (SEE(SE NOTE 212)/*

~4?R(OA 24BD 1A113"'"i 24RRC..... 3/BCAP-,

24RO)-34"R(83-4S PLATFORM>

EL 503 (REP) A THIS DRAWING IS INTENDED FOR USE IN PRESERVICE AND ]NSERVICE INSPECTIONS PROGRAMS DNLY.

10. CAP TO NOZZLE WELDS ARE CLAD ON THE ID IN THE WELD AREAS.

SEE REF DWGS 131 C 7588E 131 C 7589.

II.

PIPING FROM PUMP DISCHARGE TO RRC-V-ETA HAS MIN WALL OF 1.218.

PIPING pROM RRC-V-ETA HAS MIN WALL OF 1.140.

12. DELETED

13. DELETED

14. RRC-SA-8, RRC-SA-9, RRC-SA-15, RRC-SA-17, RRC-SA-18 & SRC-SA-66 WERE DELETED PER DOC MT-0244-OJ-024.

RFRE

NCES, ISI - 230-1 GENERAL ELECTRIC DRAWINGS 761T E 424 REV 2 762 E 53W SH 1 SEW 12 762 E 538 SH 2 REV 11 761 E 735 REV 131 C 7588 REV 3 131 C 7589 REV S 131 C 7582 REV 3 BOVEE CRAIL/GERI BC/G-216 REV 9 0*

GO*

270*

1 so*

QUALITY CLASS, I

ASME CODE CLASS.

2 ENGR, D TIMMINS I DRAWN. K-McA I DATE, 4-6-78 WASHINGTON PUBLIC POWER SUPPLY SYSTEM RICHLAND, WASHINGTON 9935 5

9-22-94 ADD NOTE 14, MOD ACCORDINGLY. DEL NOTES 12, 13 K-McA DPR DW_

NO NOM MATERIAL MATL CAL WNP-2 4

6-7-94 CORRECTED PENETRATION NUMBER IN NOTES 2 & 7.

K-McA DPR ODW PIPING SYSTEM DIA SCH WALL BLOCK WELD I COMPONENT

-- W0 ISI 0% 5F, WINE toRT,.55O "A' TM SW'S I

Re" MH.

(IN)

THK SPECIFICATION TYPE NO 3

12-4-89 WATL.

& Wt NO48 FOR 4"LGMIT-WI.

tMOIFIED IKIYI'KMt OR K-McA DPR TFH IDENTIFICATION DIAGRAM 2

10-13-83 REVISED AS NOTED. ADDED KEYPLAN K-mcA DPR TFH 24"RRC(I)-4S 24 XXX SEE NOTE II SA 358 GR 304 CL 1 SS UT-?

TITLE, 1

11-5-80 REVISED AS NOTED K-M.A TFH DWP 4SRRC(B)-4S 4

BO 0.337 GA 3'6 TP 304 SS UT-29 REACTOR RECIRCULATION LOOP A 0

11-27-78 ISSUED FOR USE K-MCA 0

LFB CAP 12 BO 0.56 SA 403 GR WP 304 SS UT-19 A

SSUED FOR INFORMATION ONLY K-McA NCH DWP CAP 8

BO O,

S A 403 GR WP 304 SS UT-26 ONG NO, RRC-1 0

-- 2 REVA5 NO IDATE IREVISION BY CHKD APVO II

Report No.:

EXAMINATION

SUMMARY

SHEET R1 5-054 GE NUCLEAR ENERGY Site and Unit:

Columbia Generating Station Component ID:

24RRC(1)A-15 Outage:

RFO-15 VALVE TO PIPE System:

RRC ASME Cat.:

B-J ASME Item B9.11 Aug Requirements:

N/A Exams Performed Data Sheet Cal Sheet Procedure Calibration Block Examination Cert Date Personnel Level 450 Shear UT-R15-047 N/A PDI-UT-2 UT-7

JACK REISEWITZ II 5/24/01 600 RL UT-R1 5-048 N/A PDI-UT-2 UT-7 JACK REISEWITZ II 5/24/01 Examination Results:

During the manual ultrasonic examination of the above referenced weld, no reportable indications were recorded utilizing the 450 and 60° search units.

This examination is acceptable per the requirements of ASME Section Xl, 1989 Edition, no Addenda and the 1995 Edition, 1996 Addenda with modifications as stated in 10CFR50.55.

Examined from the pipe side only due to valve configuaration. 50% code coverage was obtained.

Previous data was reviewed prior to this summary.

Examination results were compared to:dith report, RRU-174 from 1979 outage with W1 No Change These examinations were performed under Work Order:

01011024 El Change This Summary and the following data sheets have been reviw nd accepted by the following personnel:

RWP:

N/A

~

2~Dose:

N/A mr.

Prepared By:

Level:

Date:

R.* eviewed By:

Title:

'e.

GE Reviewed By,-'"

Level:

Date:

ANII Reviewed By:

Title:

Date:

Page 1 of 4

[-Ultrasonic Calibration and Examination Record GE NUCLEAR ENERGY Manual Piping and Components Data Report Number R15-054 Site/Unit: Columbia Generating Station IN/A Data Sheet Number, UT-R15-047 Outage:

RFO-15 Linearity Sheet:

L-004 Calibration Data for Block: UT-r Procedure:

PDI-UT-2 ss Material ULTRAGEL Couplant:

213183 Thermometer S/N Scan Direction Cal Reflector Signal Amplitude Signal Sweep:

Signal dB:

Rev _

DRR: Site Specific Rev. 0 24 1.14 Size Thick 97425 Couplant batch 70° F Cal Temp.

Calibration Cal Time Initial Cal:

2030 Cal Check:

N/A Cal Check: ! N/A Final Cal:

I2354 DAC Construction Ax Circ ID Notch ID Notch Search Unit Data KBA 003R18 0.50"/Round Manufacturer:

Serial Number Size/Shape:

0.55 in.

450 450 Incident Point: Nominal Angle: Measured Angle:

1.5 MHz cp..

Shear Frequency:

Style:

Mode:

Search Unit Cable RG.174

6.

0 Cable Type:

Length:

Connectors:

80%

5.2 Div 37.2 dB 80%

5.3 Div 42.0 dB JSJ Sweep u-i u =

.u in.

moral rmn Calibration Verification Field Simulator Block SIN:

N/A Reflector N/A N/A

[

Amplitude N/A N/A

• Gain (dB)j NI Sweep (SD)

N/A NIA Acceptable Linearity performed:

5/16/01 Instrument Settings Staveley /Sonic 136P Maufacturer/Model:

0.48 In.

0. 1221nl/sec.

Delay:

Velocity:

136991A091220 Serial Number:

2 4 KHz Filter:

Rep Rate:

500 Ohms Damping:

PIE Mode:

Range:

Off Reject:

.334 ns Pulser:

2.25 MHz Frequency:

Exam Data for Weld: 24RRC(1)A-15 O0 Exam Surface:

Drawing:

VALVE TO PIPE.

Configuration:

92 0F 213183 Exam Temp.

Exam Thermometer

.. Exam Comments I Limitations:.

No Axial exams performed on upstream valve surface.

Counterbore observed below recordable level.

RRC-101-2 2220 Exam End:

2335 Level:

Date:

U Date:

Forn:Pi~e WeId Record # 63 Page 2 of 4

Ultrasonic Calibration and Examination Record i

GE NUCLEAR ENERGY Manual Piping and Components Data Report Number. R15-054 Site/Unit: Columbia Generating Station /N/A Data Sheet Number:

UTR15.048 Outage:

RFO-15 Linearity Sheet:

L-004 Calibration Data for Block: UT-7 SS 24 1.14 Material Size Thick ULTRAGEL 97425 Couplant:

Couplant batch 213183 70° F Thermometer S/N Cal Temp.

DAC Construc Scan Direction Ax Cal Reflector ID Notch Signal Amplitude 80%

Signal Sweep:

5.9 Div Signal dB:

76.0 dB Sweep 0-10 =

5.0 In.

Metal Path Procedure:

Rev B PDI-UT-2 DRR: Site Specific Rev. 0 Calibration Cal Time Initial Cal:

2045 Cal Check:

N/A Cal Check:

N/A Final Cal:

235.7 tion Search Unit Data RTD 92.894 2(10x18) mm/Rect.

Manufacturer:

Serial Number Size/Shape:

0.5 In.

60.

60.

Incident Point: Nominal Angle: Measured Angle:

2.0 MHz TRLA RL Frequency:

Style:

Mode:

Search Unit Cable RG-174 6'

0 Cable Type:

Length:

Connectors:

Instrument Settings Calibration Verification Field Simulator Block SIN:

N/A Reflector MI A N/A Amplitude N/A N/A Gain (dB)

N/A N/A Sweep (SD)

N/A NIA Acceptable Linearity performed:

5/16/01 Staveley/ Sonic 136P Maufacturer/Model:

0.85 In.

0.231n/usec.

Delay:

Velocity:

5.0 in.

250 ns Range:

Pulser:

Off 2.25 MHz Reject:

Frequency:

136991A091220 Serial Number:

2 4 KHz

- Filter:

Rep Rate:

500 Ohms Damping:

Dual Mode:

Exam Data for Weld: 24RRC(1)A-15 VALVE TO PIPE Configuration:

OD 92".F 213183 Exam Surface:

Exam Temp.

Exam Thermometer Drawing:

RRC-101-2 Exam Comments I Limitations:

No exams performed on upstream valve surface.

2220 Exam End:

2335 Level:

Date:

Date:

FoWnpei W

RecPrd e

69 Date:

Page 3 of 4 0

Cal/Exam Date:

5/24/01 ANII Reviewed By:

GE NUCLEAR ENERGY System:

RRC Wall Thickness Profile Sheet C-1 I -

Site:

Columbia Generating Station Unit:

Project:

RFO-15 N/A C

Report No.:

R15-054 I

I Component ID Number:

24RRC(1JA-15 Position 1.5" 1.5" W

2:4 90*

180, 270° 4-.

4.-.---

4.-

4

.4 I

N/A N/A N/A N/A N/A N/A 1.35 N/A 2

N/A N/A 1.40 N/A 3

N/A N/A 1.35 N/A 4

Crown Height:

Crown Width:

Nominal Diameter:

Weld Length:

FLUSH 1.5" 24.0" 75.0" VALVE iPIPE UPST Component

. DNST Component i1 'A 5

N/A N/A 1.35 N/A b6_e DREW PETERSON I

5/23/01I Initials: Examiner:

Level:

Date:

GER By:

Level:

Date:

R Reviewed By:

REQUEST 21SI-32 ATTACHMENTS A THROUGH G Attachment 21SI-32-9

I - 0 5

06 10 2

3 4

8 2

3 4

5@

7 8

9 10@

1l X 12' RED..R.)

CONT ON RRC-101-3 r 12"RRC(I)-4S (REF) k EL 528' (REE) 24' X 16' CROSS (REF)

CONT ON RRC-101-3 1 "RRC(1)-4S (REF) 0'24RRC()A-21 90, 24RRC (1)A-21LU N

27Žt*'980 "1(

t 8VFCA-9A I A D

12' 24RRClI)A-

"I A

EL 512' $

24R C(1)A-20/12CAP 24RRC(l)A-7LUO RC-SA-6S "N

24RRC(1)A-20/12CAP-1 24RRC(l)A-17

-HA-7

/

//

(SEE NOTES 6 I 10) 24RRC(1)A-17LD 24RRC1A-1LOI

-ONT ON RRC-1,5-" -/

24R (

1)A-16 u RRC,7)-4S (PEE)A 24RRCCI)A-1 5

-20

,24RRCC

]A 24*

{1 RRA-2OAD t

244RRC Cl)1 24RRC(1)A-20----

RC SA-7 (SEE NOTE 3)

A A"

RC-V-60A

-6 24CRC(1)A-2-LDO-,

V BA "3/L 24RRC(I)A (SE/

/

NOTE 4)\\

-y RCA 1-

.U 3\\V-6/C-PA 24RC(IA-2LUIRC-(11 A-3/0AE-24RRRC (1 A-1 3/RRC V

6)-4S FATFOR EL 50B'

--24RRC(1)-18

\\4RLCS1)A14

/

/

/

\\

• '-RRC-*'-67A/3/40-71A

/(SEE NOTE 12) 24RC(1RA-3//4dT-N1S (SEENOTE N2E 4RRC< B)IA-*

I SEE NOTES 5 & 10) 2*R AC (1-A-1*L 24DRK(lIA-13/3/4dPT-NDI5AJ (SE NOTE

2)

/*

CONT ON RRC-1O1-1 24"RKC(2)-4S (REF)

EL 503' (REF) V THIS DRAWING IS INTENDED FOR USE IN PRESERVICE AND INSERVICE INSPECTIONS PROGRAMS ONLY.

1. SEE RRC-P-lA DETAIL DWG RRC-103 FOR PUMP SUPPORT DETAILS.

2. EXTEND LEAKAEE EXAM THROLUGH CONTAINMENT PENETRATION (X-7O.)

THROUGH EXCESS FLOW CHECK VALVE TO INSTRUMENT TU1BING CONNECTION.

3. DELETED

4. SPECIAL CLAMP WITH HA-7 I SA-7 ATTACHMENTS.

5. WELD 24RRC(1)A-13/BCAP-1 IS FITTING TO FITTING.

6. WELD 24RRC(1)A-20/IOCAP-1 IS FITTING TO FITTING.

7. EXTEND LEAKAGE EXAM THROUGH CONTAINMENT PENETRATION (X-77Aa) THROUGH VALVE RRC-V-20.

B. WELD 24RRC(1)A-19 IS FITTING TO FITTING.

9. RRC-V-bOA HAS TWELVE (12) 2 3/4' X 15' BODY TO BONNET STUDS.

10. CAP TO NOZZLE WELDS ARE CLAD ON THE ID IN THE WELD AREAS.

SEE REF DWGS 131 C 7588 9 131 C 7589.

11. PIPING FROM PUIP DISCHARGE TO RRC-V-67A HAS PIN WALL OF 1.218.

PIPING FROM RRC-V-67A HAS HIN WALL OF 1.140.

12. DELETED

13. DELETED

14. RRC-SA-8, RRC-SA-9, RRC-SA-1S, RRC-SA-17.

RRC-SA-19 I RRC-SA-66 WERE DELETED PER BDC g7-0244-OJ-024.

REFERENCES, ISI - 230-1 GENERAL ELECTRIC DRAWINGS 761 E 424 REV 2 762 E 538 SH 1 REV 12 7E2 E 538 SH 2 REV 11 71 E 735 REV 8 131 C 75 REV 3 131 C 7589 REV S 131 C 7582 REV 3 BOVEE CRAIL/GERI BC/G-216 REV 9 go.

I.

1EY AN 0.

2?0' QUALITY CLASS, 1

ASME CODE CLASS, 2

ENGR. D TIMMINS IDRAWN. K-McA I DATE. 4-6-78 a

WASHINGTON PUBLIC POWER SUPPLY SYSTEM

RICHLAND, WASHINGTON 9j92 5

9-22-94 ADD NOTE 14, MOD ACCORDINGLY. DEL NOTES 12, 13 K-MCA DPR OW NO" NOM MATERIAL WATL CAL VNP-2 4

6-7-94 CORRECTED PEN4ETRATION NUMBER IN NOTES 2 & 7.

K-McA DPR DW PIPING SYSTEM DIA SCH WALL BLOCK WELD I COMPONENT

___ I_ 151 RKF -,LINE

" To_ _

-M tFH (IN)

THK SPECIFICATION TYPE NO IDENTIFICATION DIAGRAM 3

12-4-89

• *A TL

&T ND OR44-

-4S =IFED EY'PL

-PICA DPR TN 2

10-13-63 REVISED AS NOTED. ADDED KEYTP.AN C-McA DPR TFH 24'RRC(1)-45 24 XXX SEE NOTE 11 SA 358 GR 304 CL 1 SS UT-7

TITLE, 1

11-5-P0 REVISED AS NOTED K-HeA TFH DWP 4'RRC(8)-4S 4

80 0.337 SA 376 TP 304 SS UT-29 REACTOR RECIRCULATION LOOP A 0

11-27-78 ISSUED FOR USE K-RcA LFO CAP 12 80 O.5EB SA 403 SR WE 304 55 UT-I9 A

5-19-?8 ISSUED FOR INFORMATION ONLY K-,IcA NCHI DWP CAP P

E 0.50D0 SA 403 SR WP 304 55 UT-2 N-N ATE RVSONY DHD DDG NO.

C-101 -2R NO DATE REVISION BY CHCD APYD

Report No.:

EXAMINATION

SUMMARY

SHEET R15-057 GE NUCLEAR ENERGY Site and Unit:

Columbia Generating Station Component ID:

24RRC(1)A-18 Outage.:

RFO-1 5 PIPE TO VALVE System:

RRC ASME Cat:

B-J ASME Item

@2gW 5/t*/'4Aug Requirements:

Exams Performed Data Sheet Cal Sheet Procedure Calibration Block Examination Cert Date I

Personnel Level 45' Shear UT-R15-051 N/A PDI-UT-2 UT-7 CHAD OLSON II 5/25/01 60° RL UT-R15-0521 N/A PDI-UT-2 UT-7 CHAD OLSON II 5/25/01 Examination Results:

During the manual ultrasonic examination of the above referenced weld, no indications associated with IGSCC were recorded utilizing the 45° search unit. Root geometry was recorded by the 600 RL:

This examination is acceptable per the requirements of ASME Section X1, 1989 Edition, no Addenda and the 1995 Edition, 1996 Addenda with modifications as stated in 10CFR50.55.

The examintion was performed from the pipe side only due to valve configuration, 50% Code coverage was obtained.

Previous data was reviewed prior to this summary.

Examination results were compared to data report RRU-157 from 1979 outage with

[

No Change These examinations were performed under Work Order:

01011024 El Change This Summary and the following data sheets have been review nd accepted by the following personnel:

RWP:

N/A e zz sh 4 Dose:

N/A mr.

Prepared By:-

Level:

Date:

.Ut

.eviewdy TitleV Pate GE Reviewed By:

Level:

Date:

AN1I Reviewed By:

Title:

Date:

Page 1 of 5

C.

0 GE NUCLEAR ENERGY Ultrasonic Calibration and Examination I Manual Piping and Components Data Report Number:. R15o057 Data Report Number. R15-057 Site/Unit: Columbia Generating Station / NIA Outage: RFO-15 Calibration Data for Block: UT-7 SS 24 1.14 Calibration Cal Time Material Size Thick Initial Cal:

0938 ULTRA_

9412_.5 Cal Check:

N/A Couplant:

Couplant batch 213067 71*F Cal Check:

N/A Thermometer SIN Cal Temp.

Final Cal:

1135 Data Sheet Number UT-R15-051 Linearity Sheet:

L-004 Procedure:

PDI-UT-2 Rev B DRR: Site Specific Rev. 0 Search Unit Data KBA OOLI8D 0.3 75"/Round Manufacturer:

Serial Number Size/Shape:

0.4 In.

45o 450 Incident Point: Nominal Angle: Measured Angle:

1.5 MHz Como-G Shear Frequency:

Style:

Mode:

Search Unit Cable RG.174 6'

0 Cable Type:

Length:

Connectors:

Scan Direction Cal Reflector Signal Amplitude Signal Sweep:

Signal dB:

DAC Construction Ax ID Notch 80%

5.0 Div 38.2 dB Sweep 0-10 =

4.0 In.

Metal Path Instrument Settings Calibration Verification Field Simulator Block SIN:

N/A Reflector N/A N/A Amplitude NIA N/A Gain (dB)

N/A N/A Sweep (SD)

N/A N/A Acceptable Linearity performed:

5/16/01 Staveley / Sonic 136P Maufacturer/Model:

0.426 In.

0.123nJtusec.

Delay:

Velocity:

136991A091220 Serial Number 2

4 KHz Filter:

Rep Rate:

500 Ohms Damping:

PE Mode:

4.0 In.

Range:

Off Reject:

334 ns Pulser:

2.25 MHz Frequency:

Exam D*

Exam Drawing:

ata for Weld: 24RRC(I)A-18 OD Surface:

PIPE TO VALVE Configuration:

85._F 213067 Exam Temp.

Exam Thermometer RRC-101-2 Exam Comments I Limitations:

EXAMINED FROM PIPE SIDE DUE TO VALVE CONFIGURATION. ACHIEVED 50% CODE COVERAGE.

Axial UPST Scan dB Recordable Exam Circ DNST Indications Angle AXIAL mUPST 50._2 NRI 450 CIRC UPST 50.2 NRI 45_*

, Exam Start:

1040 Exam End:

1125 CHAD OLSON II Initials:

Examiner:

Level:

GE Reviewed By:

Level:

Date:

Initials:

Examiner 2:

Level:

M eviewed By:

ate:

Form:PipeWeld Racora # 66 CalExa Dae:

/2501ANII Reviewed By:

Date:

Pa

-2 f

S GENULER G

Ultrasonic Calibration and Examination Record i

GE NUCLEAR ENERGY Manual Piping and Components Data Report Number: R15-057 Site/Unit: Columbia Generatin-a Station / N/A Data Rept Number:

R15-052 Data Sheet Number:

Ue-R15-052 Outage:

RFO015 Linearity Sheet:

L-004 Calibration Data for Block: UT.7

! S...SS 24 1.14 Calibration Cal Time Material Size Thick Initial Cal: 1 0950 ULTRAGEL 94125 ClCek

/

Couplant:

Couplant batch Cal Check:

N/A Thermometer SIN Cal Temp.

Final Cal:

1138 Procedure:

PDI-UT-2 Rev B DRR: Site Specific Rev. 0 Scan Direction Cal Reflector Signal Amplitude Signal Sweep:

Signal dB:

Sweep 0-10=

DAC Construction Ax ID Notch 80%

5.6 Div 76.2 dB Search Unit Data RTD 92-893 2(10x18) mm/Rect, Manufacturer.

Serial Number Size/Shape:

0.5 In.

60_

60.

Incident Point: Nominal Angle: Measured Angle:

2.0 MHz TRLA RL Frequency:

Style:

Mode:

Search Unit Cable RG-174 6'

0 Cable Type:

Length:

Connectors:

5.0 In.

Metal Path Instrument Settings Calibration Verification Field Simulator Block S/N:

N/A Reflector N/A N/A Amplitude N/A N/A 1

Gain (dB)

N/A N/A Sweep (SD)

IA N/A Acceptable Linearity performed:

5/16/01 Exam Data for Weld: 24RRC(1)A-18 PIPE TO VALVE Configuration:

Staveley /Sonic 136P Maufacturer/Model:

1.08 In.

0.2371nJ/sec.

Delay:

Velocity:

136991A091220 Serial Number:

2_

4 KHz Filter:

Rep Rate:

500 Ohms Damping:

DUAL Mode:

5.0 In.

Range:

off Reject:

250 ns Pulser:

2.25 MHz Frequency:

Exam Comments f Limitations:

EXAMINED FROM PIPE SIDE DUE TO VALVE CONFIGURATION. ACHIEVED 50% CODE COVERAGE, MAINTAINED 5% TO 20% NOISE LEVEL AT REFERENCE dB.

OD Exam Surface:

Drawing:

85°_F 213067 Exam Temp.

Exam Thermometer RRC-101-2 UPST Scan dB Recordable Exam DNST Indications Angle UPST 76.2 YES 60.

Exam Start:

1040 Exam End:

1125 WCHAD OLSON Initials:

Examiner:

Level:

Date:

Level:

Level:

U Initials:

Examiner 2:

IDate:

Date:

Forrn:Pipe Weld Record # 67 Page I of 6 Cal/Exam Date:

5/25/01 ANII Reviewed By:

0 C.

GE NUCLEAR El Ultrasonic Examr JIERGY Site: Columbia Generating Station Drawing:

RRC-101-2 Wo Location:

WELD CL ination Indication Reiport C

Data Report Number R15-057 Cal / Data Sheet Number UT-R15-052 Exam Start:

1040 Procedure: PDI-UT-2 / B / Site Specific Rev. 0 Size:

24 Thickness:

1.14

--I Weld ID:

24RRC(I)A-18 Lo Location: TDC Weld Width:

1.5 Weld Height:

FLUSH Exam End:

1125 Ind Angle

% of Indication Length W Distance Metal Path Ax tI Upso No.

Used DAC Li L Max L 2 Wi W

WMax W2 MP MP Max MPT2 Cir3 Dnst Comments:

I 60 "

100'__

69 "0 N /A j _. _2.25 W*

A.j WN/A J --2.70 _.-

L

,W A

AX

.ZLu _PS I".CAN BE SEEN INTERMITTENTLY 360 " ROOT GEOMETRY Sketch ro CHAD OLSON II 5/25/01 GE Reviewed. B Examiner Level:

Date:

Level:

Date:

eviewed By:

/ AN'I Reviewed By:

Page 4

Date:

of 5

Q NUCLEAR ENERGY Wall hickness C Profile Sheet Site:

Columbia Generating Station Unit:

-- C N/A Report No.:

R15-057 Project:

RFO-15 System:

RRC Crown Height:

FLUSH Crown WVidth:

1.5" PIPE VALVE UPST Component:

DNST Component:

Nominal Diameter:

24.0" Weld Length:

75.0" M1 I'*\\A/ W

-j41 JACK REISEWlTZ II 5-24-01 we L

Initials: Examiner:

Level:

Date:

GE Reviewed Be Level:

D'ate Ulki evewed-By ate ANII Reviewed By:

Page 4

Date:

F of s

REQUEST 21SI-32 ATTACHMENTS A THROUGH G Attachment 21SI-32-10

5 6

9 10 2

3 4

7 8

CONT ON RRC-IO1-3 IS 12 RED IREF)-

12'RRC(I)-4S (REF)

,V EL 528' (REF) 24 X 16' CROSS (REF)

-CONT ON RRC-101-3 16'RRCI1I-4S (RSF)

-24RRC C1) A-21 "S-24RRCC1I)A-21LU 0.

-20

,*10 RPV RCR-EL 512' '1 CONT ON RRC-1

'ý;SA-65 C_.._,

I)A-20/12CAP

NOTES,

1. SEE RRC-P-1A DETAIL DWG RRC-103 FOR PUMP SUPPORT DETAILS.

2. EXTEND LEAKAGE EXAM THROUGH-I CONTAINMENT PENIEIRAit (CA)t-TC0) ISOUITA EXCIESS FLOWD CHECK VALVE TO INSTRUMENT TUBING CONNECTION.

3. DELETED

4.

SPECIAL CLAMP WITH HA-? I 5A-? ATTACHMENTS.

5. WELD 24RRC(1)A-13/BCAP-1 IS FITTING TO FITTING.

6. WELD 24RRC(I)A-20/IOCAP-1 IS FITTING TO FITTING.

7.

EXTEND LEAKAGE EXAM THROUGH CONTAINMENT PENETRATION (X-77Ao) THROUGH VALVE RRC-V-20.

8. WELD 24RRC(1)A-19 IS FITTING TO FITTING.

9. RRC-V-SOA HAS TWELVE (12) 2 3/4" X 15' BODY TO BONNET STUDS.

IO. CAP TO NOZZLE WELDS ARE CLAD ON THE ID IN THE WELD AREAS.

SEE REF DWGS 131 C 7588 I 131 C 7589.

11. PPING FROM PUMP DISCHARGE TO RRC-V-6?A HAS RIN WALL OF 1.218.

PIPING FROS RRC-V-67A HAS MIN WALL OF 1.140.

12. DELETED

13. DELETED

14. RRC-SA-8, RRC-SA-g, RRC-SA-15. RRC-SA-17.

RRC-SA-18 I RRC-SA-E6 WERE DELETED PER BDC 87-0244-0.1-024.

REFERENCES, IS] - 230-1 GENERAL ELECTRIC DRAWINGS 761 E 424 REV 2 762 E 538 SH 1 REV 12 762 E 538 SH 2 REV 11 7E1E 735 REV 8 131C 7588 REV 3 131 C 7589 REV 5 131 C 7582 REV 3 BOVEE CRAIL/GERI BC/G-216 REV N KEETLAN 9°180 REACTOR FI00 270" QUALITY CLASS, 1

ASME CODE CLASS, 2

ENGR, D TIMMINS I DRAWN. K-PCA I DATE.

4-6-78

/ /

L24RRC(1)A-19.../.

/

(SEE NOTES 8 I 13)

/

24~~RRC11)

A-lg!.DO.,*"

L24RRC (1) A-1I (SEE NOTE 2) 24RRC (1)A-13LD-SEE NOTE CONT ON RRC-1O1-1 24 RRC(2)-4S (REF).

EL 503' (REF) &

THIS DRAWING IS INTENDED FOR USE IN PRESERVICE AND INSERVICE INSPECTIONS PROGRAMS ONLY.

WASHINGTON PUBLIC POWER SUPPLY SYSTEM

RICHLAND, WASHINTON 899352 5

9-22-94 ADD NOTE 14. MOD ACCORDINGLY. DEL NOTES 12, 13 K-McA OPR DW WNP-2 NOR NOM MATERIAL MATL CAL 4

6-7-94 CORRECTED PENETRATION NUMBER IN NOTES 2 & 7.

K-McA DPR OW PIPING SYSTEM DIA SCH WALL TYPE BLOCK WELD & COMPONENT 3

12-4-69 M

s. sL It oF NO Lir I 'M * "

TO KM-o F S.

K-MCA DPR TFH (IN)

THK SO IDENTIFICATION DIAGRAM SWP*tZU PR F(R AtWPCW-S. rODIFIEX 5001.')N OCRI C-RCTFICAION8DTPRA 2

10-13-83 REVISED AS NOTED. ADDED KEYPLAN K-RcA DPR TFH 24"RRC(I)-4S 24 XXX SEE NOTE 11 SA 358 GR 304 CL I SS UT-?

TITLE, 1

11-5-80 REVISED AS NOTED K-RCA TFH DWP 4"RRC(8)-4S 4

80 0.337 SA 376 TP 304 SS UT-29 REACTOR RECIRCULATION LOOP A 0

11-27-78 ISSUED FOR USE K-RcARECO RCRC..TINLPA 1

7 E

S LFB CAP 12 80 0R68E SA 403 GR VP 304 SS UT-19 A

5-19-78 ISSUED FOR INFORMATION ONLY K-MCA NCH DWP CAP 8F B

80 0.500 SA 403 DR WP 304 SS UT-26

____NO,

______01_-2_

REV_5 O DWANO, RRC-lOO? -2 REV 5

NO GATE REVISION BT CHCD APVD

e EXAMINATION

SUMMARY

SHEET GE NUCLEAR ENERGY Site and Unit:

('nhlmhia renartinn St2tinn Comnnnent I:

Outage:

ystem RRC RFO1_5 ASME Cat.:

B-J VALVE TO ELBOW ASME Item B9,34

)*4k, Aug Requirements:

NIA Exams Performed Data Sheet Cal Sheet Procedure Calibration Block Examination Cert Date Personnel Level 45° Shear UT-R15-036 N/A PDI-UT-2 UT-7 CHAD OLSON 1II 5/24/01 60* RL UT-R1i5-037 N/A PDI-UT-2 UT-7 CHAD OLSON*

II 5/24/01 Examination Results:

During the manual ultrasonic examination of the above referenced weld, no reportable indications were recorded utilizing the 45° search unit, root geometry was seen by the 600 search unit.

This examination is acceptable per the requirements of ASME Section Xl, 1989 Edition, no Addenda anl the 1995 Edition, 1996 Addenda with modifications as stated in 10CFR50.55.

Exam performed from the elbow side only due to valve configuration, 50% Code coverage was obtained.

Previous data was reviewed prior to this summary.

Examination results were compared to data report RRU-524 from 1982 outage with V

No Change These examinations were performed under Work Order:

01011024 D

Change This Summary and the following data sheets have been reviewed and accepted by the following personnel:

RWP:

N/A AV/.* **4 Dose:

NIA mr.

Prepared By:

Level:

Date:

@ p eviewed By:

Title:

Date:

GE Reviewed By:

Level:

Date:

ANII Reviewed By:

Title:

Date:

Page I of 5

(.

___Ultrasonic Calibration and Examination Record GE NUCLEAR ENERGY Manual Piping and Components St t CData Report Number R15.058

ý;Site/Unit: Columbia Generat/n-q Station/INIA Data Sheet Number:

UT-R15-036 I Outage:

RFO-15 Linearity Sheet:

L-002 Calibration Data for Block: UT-_.Z Procedure:

PDI.U T-2 SS 24 1.14 Calibration Cal Time Material Size Thick Initial Cal:

0946 ULTRAGEL 94125 C C N

Cal Check: iNIA Couplant:

Couplant batch Cal Check: I N/A 213067 73a Fm Fi

_a__

Thermometer S/N Cal Temp.

Final Cal:

1610 Rev B DRR: Site Specific Rev. 0 Cal Reflector:

Signal Amplitude Signal Sweep:

Signal dB:

DAC Construction b*i'"Yehr/o I ID Notch LoY.%

5.0 Div 44.2 dB Sweep 0-10 =

4.0 In.

Search Unit Data KBA OOL18D 0.375"/Round Manufacturer:

Serial Number Size/Shape:

0.4 in.

450 45_

Incident Point: Nominal Angle: Measured Angle:

1.5 MHz Comp-G Shear Frequency:

Style:

Mode:

Search Unit Cable RG-174 6'

0 Cable Type:

Length:

Connectors:

Instrument Settings STAVELEYV/Sonlc 136P 7701 Maufacturer/Model:

Serial Number 0.426 in.

0. 123inlysec.

2 4 KHz Delay:

Velocity:

Filter:

Rep Rate:

4.0 In.

334 ns 500 Ohms Range:

Pulser:

Damping:

Off 2.25 MHz PIE Reject:

Frequency:

Mode:

Exam Comments / Limitations:

Maintained 5% to 20% ID roll.

Examined from downstream side due to valve configuration.

Achieved 50% code coverage.

Calibration Verification Field Simulator Block SIN:

N/A Reflector N/A N/A Amplitude N/A N/A Gain (dB)

N/A N/A Sweep (SD)

N/A N/A Acceptable Linearity performed:

4/12/01 Exam Data for Weld: 24RRC(1)A-19 VALVE TO ELBOW Configuration:

O0 Exam Surface:

930°F 213067 Exam Temp.

Exam Thermometer Drawing:

RRC-101-2 UPST DNST A..

CCH, Initials:

Examiner:

4D OLSON If Level:

Level:

Date:

L)

N/A Initials:

Examiner 2:

N/A Level:

late4 Date:

Form:Pipe Weld Record # 49 Page 2 of 5 Cal/Exam Date:

5124/01

GE NUCLEAR ENERGY Ultrasonic Calibration and Examination I Manual Piping and Components

.Site/Unit: Columbia Generating Station / N/A Outage:

RFO-15 Data Report Number: R15-058 Data Sheet Number.

UT-R15-037 Linearity Sheet:

L-002 Calibration Data for Block: UT-7 SS 24 1.14 Calibration Cal Time Material Size Thick Initial Cal:

1023 ULTRA GEL 94125 ULTRAGEL Cal Check:

N/A Coupiant:

Couplant batch Cal Check:

N/A 213067 73S F I

Thermometer S/N Cal Temp.

IFinal Cal:

161..66 Procedure:

Rev B PDI-UT-2 DRR: Site Specific Rev. 0 Cal Reflector:

ID

• Signal Amplitude Signal Sweep:

, Signal dB:

Sweep 0-10 =

5.0 In.

AC Construction

'Notch 80%

.6 Div 1.2 dB Search Unit Data RTD 92-893 2(10x18) mm/Rect.

Manufacturer:

Serial Number Size/Shape:

0.5 In.

600 60_

Incident Point: Nominal Angle: Measured Angle:

2.0 MHz TRLA RL Frequency:

Style:

Mode:

Search Unit Cable RG-174 6'

0 Cable Type:

Length:

Connectors:

Calibration Verification Field Simulator Block SIN:

N/A Reflector N/A N/A Amplitude N/A N/A Gain (dB)

N/A N/A Sweep (SD)

N/A N/A Acceptable Linearity performed:

4/12/01 Instrument Settings STAVELEY/ Sonic 136P 7701 Maufacturer/Model:

Serial Number:

1.08 In.

0.237inJpsec.

2 4 KHz Delay:

Velocity:

Filter:

Rep Rate:

5.0 In.

250 ns 500 Ohms Range:

Pulser:

Damping:

Off 2.25 MHz Dual Reject:

Frequency:

Mode:

Exam Data for Weld: 24RRC(I)A-19 VALVE TO ELBOW Configuration:

OD 930

.F Exam Surface:

Exam Temp.

E Drawing:

RRC-101-2 213067 xam Thermometer Exam Comments I Limitations:

Maintained 5% to 20% ID roll.

Examined from downstream side due to valve configuration.

Achieved 50% code coverage.

Axial Circ AX Exam Start:

1500 Exam End:

1545 eCHAD OLSON Initials:

Examiner:

ii Level:

N/A Level:

N/A Level:

Date:

aForm:Pipe Weld Record # 50 Date:

Page 3 of 6 Initials:

Examiner 2:

Cal/Exam Date:

5/24/01._./

ANII Reviewed By:

I

GE NUCLEAR ENERGY Weld ID:

24RRC(1)A-19 Lo Location: TDC Ultrasonic Examin-r C

Site: Columbia Generating Station Drawing:

RRC-101-2 Wo Location:

Weld Centerline ation Indication Report.

Data Report Number.

R1S-0S8 Procedure: PDI-UT-2 / B / Site Specific Rev. 0 4 Cal/ Data Sheet Number TR

_3 Size:

24" Thickness:

1.14" Weld Width:

1.50" Weld Height: Flush Exam Start:

1500 Exam End:

1545 Ud Angle

% of Indication Length W Distance Metal Path Ax /

Upst/

No.

Used DAC L1 LMaxI L2 WI WMax W 2 MP1 1MPMaxI MPp2 Circ Dnst Comments:

I 60*

100 1

10.5 A

2.35 -

I A

-A 2.?

W Ax Dnst Can beseen Intemttently 36**. Rootgeometry.

Sketch CO CHAD OLSON It 5/24/01 GE Reviewed By:

Examiner Level:

Date:

Level:

Date:

Reviewed By:

Date:

Page 4 of 5 ANII Reviewed By:

GEUNUCLEAR ENERGY Wall ThicneSess C Profile Sheet Site:

Columbia Generating Station Unit:

N/A Project:

RFO-15 Report No.:

R15-058 System:

RRC Component ID Number 24RRC(1)A-19 Position 0O 90*

1 80*

270*

1 N/A N/A I

AVAj N/A WA N/A 1.40 N/A 2

WA N/A 1.320 WA 3

WA N/A 1.28 N/A 4

Crown Height Crown Width:

FLUSH 24.0" 75.0" VALVE ELBOW UPST Component:

DNST Component Nominal Diameter 1 5 NAV N/A 1.360 I. IVA Weld Length:

FLOW A0141 JACK REISEWI7TZ I1 5-24-01 Initials: Examiner:

Level:

Date:

GE Reviewed By:

Level:

Date: /

at.k19iT, Oil Date:

PageT of 05

REQUEST 21SI-32 ATTACHMENTS A THROUGH G Attachment 21SI-32-11

'T.~

@6

/

2 4

5 7

a 10 CNY ONIECI 02I

• N CONT ON RRC-102-6 12'RCC(1)-4S (REF) 24' X 12' RED (REF)

CONY ON RRC-102-3 I6'RRCI

) -4S (REF) 24' X 16' CROSS (REF)!

0.

90" 27O~i 15O

~

RPV EL 528' (REF) 24RRC (1)6-19 24RRC C1) B-19LU RC-SB-8

-,24RBM ()B-1B/12RRC(?)-4S CONT ON REC-10?

12"RRC(7)-4S CREF)

EL.

EL.512" RCR-B8

_-24RRC1)B-I1BLD 24RRC(I)B-10

,,-24RRC(I)B-IBLUO

,.,-24RRC(I)B-1BLUI EL 506 '

B

'-24RRC(1)-17LDI (SEE NOTE 7)

?4RRC(1)8-17LDO 4RRC (1)6-i?

'3/4V-69B THIS DRAWING IS INTENDED FOR USE IN PRESERVICE AND INSERVICE INSPECTIONS PROGRAMS ONLY.

1. SEE RRC-P-lB DETAIL, OWG RRC-I03, FOR PUMIP SUPPORT DETAILS.

2. EXTEND LEAKAGE EXAM THROUGH CONTAINMENT PENETRATION (X-41d) THROUGH EXCESS FLOW CHECK VALVE TO INSTRUMENT TUBING CONNECTION.

3. ACCESS TO WELD 24RRCI1)B-13 REQUIRES REMOVAL OF RCR-6B.

4. SPECIAL CLAMP WITH NB-?* S-? ATTACHMENTS.

S. WELD 24RRCCI)8-1/BCAP-1 IS FITTING TO FITTING.

6. WELD 24RRC(I)B-18/12CAP-1 IS FITTING TO FITTING.

7.

WELD 24RRC(1)B-l1 IS FITTING TO FITTING.

B. RRC-V-EON HAS TWELVE (12) 2 3/4' X 15' BODY TO BONNET STUDS.

g. CAP TO NOZZLE WELDS ARE CLAD ON THE ID IN THE WELD AREA. SEE REFERENCE DWGS 131 C 7586 I 131 C 7569.

10. PIPING FROM PUMP DISCHARGE TO RRC-V-67B IS MIN WALL 1.21B.

PIPING FROM RRC-V-76B TO WELD 24RRC(1)6-I9 IS MIN WALL 1.140.

11. RRC-SB-IS, RRC-SB-17, RRC-SB-18 & RRC-SB-66 WERE DELETED PER BOC 87-0244-OJ-026.

ISI -

230-2 GENERAL ELECTRIC DRAWINGS 761 E 424 REV 2 762 E 538 SH 1 REV 3 762 E 538 S 2 REV 3 761 E 735 REV 6 131 C 7588 REV 3 131 C 7589 REV 5 131 C 7592 REV 3 CB NUCLEAR CO.

48 REV 4 NT NOZZLE ASSEMBLY BOVEE CRAIL/GERI BC/G-21B REV 9 90" YPLA 0.

160" 270' QUALITY CLASS, 1

ASME CODE CLASS, I

ENGR, D TIMMINS IDRAWN, K-McA I DATE, 3-30-78 WASHINGTON PUBLIC POWER SUPPLY SYSTEM

RICHLAND, WALSIINGTON 99352 PIPING SYSTEM NOM DIA (IN)

SCH NOM WALL THK MATERIAL SPECIFICATION MATL TYPE CAL BLOCK NO WNP-2 WELD 9 COMPONENT IDENTIFICATION DIAGRAM 6

19-22-941 ADDED NOTE 11. MODIFIED ACCORDINGLY.

IK-MCAJ DPR I DW 5

12-9-92 ADDED 'B' TO ALL RCR'S.

K-KCA DPR DRW 24'"RC(1)-4S 24 XXX SEE NOTE 10 SA 358 GR 304 CL 1 SS UT-7 TITLE.

4 10-16-97 AOIED EEC-TB-AR.

1' COWN I C(RT AT ARC-V-A08. CAR AR-HB-? TO 4S10-16-6 TPR, ARC-TB-W ARC-TB-TO SNUBES.

O AYPLON. ETAWO K-MCA EPR TFH 4*RRC(B)-4S 4

60 0.337 SA 312 TP 304 SS UT-29 REACTOR RECIRCULATION LOOP B 3

10-13-831 REVISED AS NOTED ADDED KEYPLAN K-MCA DPR TFH CAP 12 60 0.699 SA 403 GR WP 304 SS UT-19 2

11-5-BO REVISED AS NOTED K-RCA TFH DWP CAP 6

60 0.500 SA 403 GR WP 304 SS UT-26 DWG NO.

ZRC-1 02-2R NO DATE REVISION BY CHKO APVO

Report No.:

EXAMINATION

SUMMARY

SHEET R

16-060 GE NUCLEAR ENERGY Site and Unit:

Columbia Generating Station Component ID:

24RRC(I)B-12 Outage:

R16 PIPE TO VALVE System RRC ASME Cat.:

B-J ASME Item B9.11 Aug Requirements:

N/A Exams Performed Data Sheet Cal Sheet Procedure Calibration Block Examination Cert Level Date I

~Personnel I

450 Shear UT-O71 NIA PDI-UT-2/Site Specific UT-7 Dickey Michael II 5/1912003 600 Long UT-072 NIA PDI-UT-2/Site Specific UT-7 Dickey Michael II 5/19/2003 Examination Results:

During the manual ultrasonic examination of the above referenced weld, no reportable indications were recorded utilizing the 450 and 600 search units.

This examination is acceptable per the requirements of ASME Section XI, 1989 Edition, no Addenda and the 1995 Edition, 1996 Addenda with modifications as stated in 10CFR50.55.

50% Code coverage was obtained.

Previous data was reviewed prior to this summary.

Examination results were compared to data report RRU-1 06 from PSI (1979) outage with El No Change These examinations were performed under Work Order:

01044925-01 Change This Summary and the following data sheets have been reviewed and accepted by the following personnel:

P ar*

Level:

Date:

40 evewed By:

ate:

Reviewed By:

Level:

Date:

ANII Reviewed By:

Date:

Page 1 of 5

Q GE NUCLEAR ENERGY Ultrasonic Examination Indication Report Data Report Number:

R16-060 Cal / Data Sheet Number UT-072 Qifo*

flMlf hin f2an.ýPinn Prnp~r~gar~ DfILI/T..9IQIts~ ~na#ifip / (~/1

• .rn.a sra.

Dn,,,t Q.I1.e e..c 1- / f'1 Weld ID:

24RRC(I)B-12 Drawing:

RRC-102-2 Size:

24" Thickness:

1.350" Exam Start:

2343 Lo Location: Too Dead Center Wo Location:

Weld Centerline Weld Width:

1.80" Weld Height: Flush Exam End:

2351 Ind Angle

% of Indication Length W Distance Metal Path Ax I Upst I No.

Used DAC Li L Max L 2 W1 I W Max W 2 MP I MP MaxI MP 2 Circ Dnst Comments:

1 600 250 N/A 8"

N/A N/A 2.1" NIA N/A 2.4 N/A

" Ax Upst Root geometry seen 360' at varying amplitudes.

Sketch

\\\\

//

.!/

D4Oickey Michael 11 5/1/ On GE Reviewed By:

Level:

Date:

t eviewed By:Date:

ANII Reviewed By:

Date:

Examiner Level:

Date:

Page 4

of

Wall Thickness Profile Sheet Crown Height:

Crown Width:

FLUSH 1.8" 24.0" 75.5'.

PIPE VALVE UPST Component:

DNST Component:

Nominal Diameter:

Weld Length:

0 "4ý

/

/

\\

/

'I

1 GE NUCLEAR ENERGY Ultrasonic Calibration and Examination Record l

Manual Piping and Components I

I Site/Unit: Columbia Generating Station Outage:

R16 Data Report Number: R16-060 Data Sheet Number:

UT-071 Linearity Sheet:

L-04 Calibration Data for Block: UT-7 Procedure: PDI-UT-2/Site Specific Ver / Rev: 21 DRR: NIA SS 24" 1.140" Calibration Cal Time Material Size Thick Initial Cal:

2154 Ultracel 00325 Cal Check:

2321 Couplant:

Couplant batch 225291 72'F Cal Check:

N/A Thermometer SIN Cal Temp.

Final Cal:

0028 KBA Manufacturer:

0.35 in.

Incident Point:

1.5 MHz Frequency:

Search Unit Data 00H8Y3 Serial Number 45_

Nominal Angle:

Comp-G Shear Style:

Mode:

0.50"/Round Size/Shape:

460 Measured Angle:

I Elements:

DAC Construction Scan Direction Ax Cal Reflector ID Notch Signal Amplitude 80%

Signal Sweep:

5.1 Div Signal dB:

32.2 dB Sweep 0-10 =

4.0 in.

Metal Path Search Unit Cable RG-174 6-0 Cable Type:

Length:

Connectors:

Calibration Verification Field Simulator Block S/N:

CAL-RHIOM-066 Reflector 2" Radius N/A Amplitude 80%

N/A Gain (dB) 20.4 N/A Sweep (SD) 5.0 N/A Acceptable Linearity performed:

417/2003 Instrument Settings Stavelev /Sonic 136P 707H Maufacturer/Model:

Serial Number:

0.279 in.

0.126iniusec.

1 4 KHz Delay:

Velocity:

Filter:

Rep Rate:

4.0 in.

334 ns 500 Ohms Range:

Pulser:

Damping:

Off 2.25 MHz PIE Reject:

Frequency:

Mode:

Exam Data for Weld: 24RRC(1)B-12 PIPE TO VALVE Configuration:

OD 72=F Exam Surface:

Exam Temp.

E)

Exam Comments I Limitations:

225291 xam Thermometer Exams perfonned to maintain 5% to 20% ID rol.

ID geomety observed below recordable levels.

No exam performed from downstream side due to component configuratifon.

Actual Cal Block 7"Tis 1.410."

Axial UPST Scan dB Recordable Exam Circ DNST Indications Angle Axial UPST 44.2 NRI 46" Circ UPST 46.2 NPJ 46" 4

-4

-4 ---

4 Exam Start:

2322 Exam End:

2341 u

l \\

Dickey Michael Initials:

Examiner:

N/A

/I Level:

N/A Level:

GE Re v ed By.

Kd

~By ANII Reviewed By:

?Leve Date:

Date:

Date:

6 Initials:

Examiner 2:

Page 2 of 5 Cal/Exam Date:

5/19/2003

Ultrasonic Calibration and Examination Record GE NUCLEAR ENERGY Manual Piping and Components Site/Unit: Columbia Generating Station Outage:

R16 Data Report Number: R16-060 Data Sheet Number:

UT-072 Linearity Sheet:

L-04 Calibration Data for Block: UT-7 Procedure:

PDJ-UT-2/Site Specific SS 24-1.140 Calibration Cal Time Material Size Thick Initial Cal:

2136 Ultragel 00325 Cal Check:

2342 Couplant:

Couplant batch 225291 72'F Cal Check:

N/A Thermometer S/N Cal Temp.

Final Cal:

0030 Ver / Rev: cL/

DRR: NIA Search Unit Data RTD 00-407 Manufacturer:

Serial Number 2(10x18) mm/RecL Size/Shape:

60*

Measured Angle:

DAC Construction 0.45 in.

Incident Point:

2.0 MHz Frequency:

60 _

Nominal Angle:

TRL 2-Aust Style:

Long Mode:

2 Elements:

Scan Direction Cal Reflector Signal Amplitude Signal Sweep:

Signal dB:

Sweep 0-10 =

5.0 i Ax ID Notch 80%

5.2 Div 71.0 dB in.

Metal Path Search Unit Cable RG-174 6'

Cable Type:

Length:

Connectors:

Instrument Settings Calibration Verification Staveley / Sonic 136P Maufacturer/Model:

707H Serial Number:

Field Simulator Block S/N:

CAL-RHOM-066 Reflector 2" Radius N/A Amplitude 80%

N/A Gain (dB) 40.0 N/A Sweep (SD) 4.0 N/A Acceptable Linearity performed :

4/7/2003 Exam Data for Weld: 24RRC(1)B-12 PIPE TO VALVE Configuration:

1.08/n.

0.24inlusec.

1 4 KHz Delay:

Velocity:

Filter:

Rep Rate:

5.0 in.

Range:

Off Reject:

250 ns Pulser:

2.25 MHz Frequency:

500 Ohms Damping:

Dual Mode:

Exam Comments I Limitations:

OD Exam Surface:

72"_F 225291 Exam Temp.

Exam Thermometer Exams performed at reference sensiivt to maintain 5% to 20% noise level.

ID root geometry recorded. See attached data sheet Supplemental 60' RL examination due to single side access.

No exam performed from downstream side due to component configuration.

Actual Cal Block "T"is 1.410."

Axial UPST Scan dB Recordable Exam Circ i

DNST Indications Angle Axial UPST 71 Yes 600 Exam Start:

&3 r74 Exam End:

2351

/7 C ___________ a I -~-.~---

a ODEM Dicke Initials:

Examiner:

Initials:

Examiner 2:

ey Michael iH Level:

N/A Level:

N/A GE R *wed By:

I ity Reviewed By:

ANII Reviewed By:

Level:

Date:

Date:

Page 3 of 5 Date:

Cal/Exam Date:

5/19/2003

REQUEST 21SI-32 ATTACHMENTS A THROUGH G Attachment 21SI-32-12

g 7

8 9

10 SIII I

I CONT ON RRC-102-6 NOE 12RRC(1)-4S REF)--."

9'0

1. S0E REC-P-lB DETAIL. ODG RRC-103, FOR 12 SC ISREPPUMP SUPPORT DETAILS.

2. EXTEND LEAKAGE EXAM THROUGH CONTAINMENT 24' 12'RED(REF 2 ý.

'Oý'

PENETRATION (X-41d) THROUGH EXCESS FLOW C R-CHECK VALVE TO INSTRUMENT TUBING CONNECTION.

IRORCN1)-4 (REF) 0 RPY

3. ACCESS TO WELD 24RRC(I)B-13 REQUIRES REMOVAL 0OF RCERS-.

4 IEL 528' (REF)

4.

SPECIAL CLAMP. WITH NB-7 gI SE-? ATTACHNENTS.

24' X 16' CROSS (REF)

5. WELD 24RRC(1)B-11/BCAP-1 IS FITTING TO FITTING.

6. WELD 24RRC(I)B-18/12CAP-1 IS FITTING TO FITTING.

7. WELD 24RRC(1)B-17 IS FITTING TO FITTING.

BB.

ERRC-V-6RO HAS TWELVE (12) 2 3/4" X 15' BOOT TO BONNET STUDS.

C LU

. CAP TO NOZZLE WELDS ARE CLAD ON THE ID IN THE WELD AREA. SEE REFERENCE OWGS 131 C 758B t 131 C 758B.

1G. PIPING FRON PUMP DISCHARGE TO RRC-V-RIB IS RCR-9B*

RMIN WALL 1.218.

PIPING FROM RRC-V-7RB TO WELD 24RRC(1)B-1I IS MIN WALL 1.140.

c D1.

RORC-Sa-15, RRC-SB-17, RRC-SE-18 I RRC-SB-66 WERE DELETED PER BDC B7-0244-OJ-026.

SEE NOTE 1 RC-SE--

RRC-SB-8 RRC--

1824RR(I)B11/34dPTNO1IS15

- 2301-2 SGEERAL ELECTRIC DRAWINGS 761 E 424 REV 2 24RRCI1)B-lB/12RRC(?)-4S 762 E 538 SH 1 REV 3 CONT ON RRC-lD?

762 E 538 SO 2 REV 3 4RRC(B)IB-2BO 12.RRC(7)-4S (REF) 761 E 735 REV B

\\

/C(CIB-2 B4R,,,6-1-/12C"P-_

131 C 7588 REV 3 D CNONRC121(SEE NOTES B It B)

'.131 C 7589 REV 5 24"IC)-4S (RF(

EL 512' 131 C 7592 REV 3 4RC(B)IB-1 24RRC(1)B-1/12CAP CBI NUCLEAR CO.

24RC(

B-11 24RC (1)8-11/4R0C(8)-4S 48 REV 4 NI NOZZLE ASSEMBLY 24RRC(1)8-I1LD*

/

• 24RR*(1)6-1,*U R C BOVEE CRAIL/GERI S24RRC()6-11CP-J 2BIRRC(R)B-12 B-."

REV B 24RRCC1 B-11/AP-1 RRC-V-ROB/1V-948 (SEE NOTES 5 I 9)

'T SEE SN-RRC-102

.-- 24RRC(1)8-18LD 90" 3/4 RC5) -45 (REF) 24RRC

-o)B-1B E

RRC-V-6I

<(E 4RRC(1)8-13

• IR1-L24R8C(1)B 12LU0 (SEER NOT T8'N (SE NOTEN 3)*

i24DATE, 3-30-P8 U

NC-V-EE/3/4V-6B C

AND NERRCV()

B-U1P3LD SSTE S EL 506'

0.

180" RRC HS 7 24REC

( ) 8-1 7LD100 OM NOMA(SEE NOTE 7) 24RR(I)B14LU24RCC I)8-1LDOREACROE BLD F24RRC (1)8-14

-4R 1 -

F 24 01C THI DR1 AWIN ISINTENDEDPOCEWELD O

S9-22-94( ADDED NOTE 1 MODIFED ACCORDINGLY.

4 K-McA OR W(IN)

PIPINGB-1 SYSTEM D TIMAN IC WALLN K-.

BLC WELDE 3-COONEN INII(N)T-C SPECIPCTIONS TRGAM NYPE NOHAD AHIrO 95 H4 5

12-9-92 ADDED 'B' TO ALL RCE'S.

K-ECA DPR DRlW 24'RRC(1)-45 24 XXX SEE NOTE 10 SA 358 GR 304 CL 1 SS UT-?

TITLE, 4

10-16-87 W DRP O -eE --T'-

Kt, rT Al SO-V-TGA OH SO-4 e-1 (0

PRE, BlC-S O-8 I

R E- - TO SNUBBERS

, I OO KEYPLM N. REARA K-RcA OP R T FH 4 *RRC(B) 4 80 0,337 SA 312 TP 304 SS UT-9 REACTOR RECIRCULATION LOOP B 3

10-13-83 REVISED AS NOTED ADDED KEYPLAN K-McA DPR TFH CAP 12 80 01188 SA 403 GR WP 304 55 UT-19 2

11-S-80 REVISED AS NOTED K-McA TFH DWP CAP 8

80 0.500 SA 403 GR WP 304 S

j DAD ND, RRC-1 02-2 REV S

NO DATE REVISION BY CHKD APVD DWN.R C

10 E

Report No.:

EXAMINATION

SUMMARY

SHEET R16-062 GE NUCLEAR ENERGY Site and Unit:

Columbia Generating Station Component ID:

24RRC(1)B-16 Outage:

R16 PIPE TO VALVE System.

RRC ASME Cat.:

B-J ASME Item B9.11 Aug Requirements:

NIA Exams Performed Data Sheet Cal Sheet Procedure Calibration Block Examinatirsonnel Cert Level Date 450 Shear UT-077 N/A PDI-UT-21Site Specific UT-7 Chares Barrett II 5/19/2003 60" Long UT-078 N/A PDI-UT-2/Site Specific UT-7 Chades Barrett II 5/19/2003 Examination Results:

During the manual ultrasonic examination of the above referenced weld, no reportable indications were recorded utilizing the 450 and 600 search units.

This examination is acceptable per the requirements of ASME Section XI, 1989 Edition, no Addenda and the 1995 Edition, 1996 Addenda with modifications as stated in 10CFR50.55.

50% Code coverage was obtained.

Previous data was reviewed prior to this summary.

Examination results were compared to data report RRU-1 58 from PSI (1979) outage with

[I No Change These examinations were performed under Work Order:

01044925-01 W

Change This Summary and the following data sheets have been reviewed and accepted by the following personnel:

Level Date:

eviewed By:

P Date:

Reviewed By:

Level:

Date:

ANII Reviewed By:

Date:

Page 1

of 5

aGE NUCLEAR ENERGY Ultrasonic Calibration and Examination Record Manual Piping and Components I

Site/Unit: Columbia Generating Station Outage:

R16 I

I Data Report Number: R16-062 Data Sheet Number:

UT"077 Linearity Sheet:

L-02 Calibration Data for Block: UT-7 Procedure:

PDI-UT-2/Site Specific SS 24_

1.140" Material Size Thick Couplant:

2250ee Thermometer SIN 00325 Couplant batch 77° F Cal Temp.

Calibration Cal Time Initial Cal:

1913 Cal Check:

2250 Cal Check:

N/A Final Cal:

0132 Ver /Rev:

W KBA Manufacturer:

0.3 in.

Incident Point:

1.5 MHz Frequency:

DRR: NIA Search Unit Data OOL6YV 0.50"/Round Serial Number Size/Shape:

450_

45_

Nominal Angle:

Measured Angle:

Comj-G Shear I

Style:

Mode:

Elements:

DAC Construction Scan Direction Cal Reflector Signal Amplitude Signal Sweep:

ID Notch 80/1 5.1 DB 35.0 dB Search Unit Cable RG-174 6"

0 Cable Type:

Length:

Connectors:

Instrument Settings.

Signal dB:

Sweep 0-10 =

4.0 in.'

Metal Path Calibration Verification Staveley /Sonic 136P Maufacturer/Model:

136P1106C031364 Serial Number:

Field Simulator Block SIN:

CAL-RHOM-068 Reflector 1-Radius 2-Radius Amplitude 80%01 72%

Gain (dB) 25.0 25.0 Sweep (SD) 1__5 5.0 Acceptable Linearity performed :

4/7/2003 0.265 in.

0.12,nlitsec.

I 4KHz Delay:

Velocity:

Filter:

Rep Rate:

4.0 in.

Range:

Off Reject:

334 ns Pulser:

2.25 MHz Frequency:

500 Ohms Damping:

PIE Mode:

Exam Data for Weld: 24RRC(1)B-16 PIPE TO VALVE Configuration:

OD Exam Surface:

750 F 22508 Exam Temp.

Exam Thermometer Exam Comments I Limitations:

Exams perhomed to maintain 5% to 20% ID rag.

ID root geometry observed below recordable levels.

No exam perflnned from downstream side due to component configuraton.

Actual Cal Block 7'is 1.410".

Axial UPST Scan dB Recordable Exam Circ DNST Indications Angle Axial UPST 49.0 NPI 450 45 UPST 52.0 NRJ 45.*

Exam Start:

._2, Exam End:

2320 Initials:

Examiner:

Level:

GE Reviewed By:

Level:

Date:

N/A N/A i - Lz/3 Initials:

Examiner 2:

Level:

.=viewed By:

Date:

Cal/Exam Date:

5/19/2003 ANII Reviewed By:

Date:

Page 2 of 5

G Ultrasonic Calibration and Examination Record GE NUCLEAR ENERGY Manual Piping and Components I-Site/Unit: Columbia Generatin-g Station Outage:

R16 Data Report Number: R16-062 Data Sheet Number:

UT-078 Linearity Sheet:

L-02 Calibration Data for Block: UT-7 Procedure:

PDI-UT-2/Site Specific S

24" 1.140" Calibration Cal Time Material Size Thick Initial Cal:

1937 QJ1rgei 00325 Cal Check:

2322 Couplant:

Couplant batch 225088 77 F Cal Check:

N/A Thermometer S/N Cal Temp.

Final Cal:

0140 Ver /Rev:

DRR: NIA Search Unit Data RTD Manufacturer:

Serial Number

0. 6 in..

600 Incident Point:

Nominal Angle:

2.0 MHz TRL 2-Aust Lon Frequency:

Style:

Modi 2(15x25N mm/Rect.

Size/Shape:

62" Measured Angle:

-2 Elements:

DAC Construction Scan Direction Cal Reflector Signal Amplitude Signal Sweep:

Signal dB:

Sweep 0-10 =

6.01 AX ID Notch 80%

4.3 Div 80.8 dB in.

Metal Path Search Unit Cable RG-174 f

Cable Type:

Length:

Connectors:

Instrument Settings Calibration Verification Field Simulator Block SIN:

CAL-RHOM-068 Reflector 1" Radius 2J Radius Amplitude 30%

80%

Gain (dB) 47.4 47.4 Sweep (SD) 1.6 11 Acceptable Linearity performed :

4171200 Exam Data for Weld: 24RRC(1)B-16 PIPE TO VALVE Configuration:

Stavelev / Sonic 136P Maufacturer/Model:

1.33 in.

0.231inlysec.

Delay:

Velocity:

136P1106C031364 Serial Number:

2 4KHz Filter:

Rep Rate:

50 Ohms Damping:

Dual Mode:

6.0 in.

Range:

Off Reject:

250 ns Pulser.

2.25 MHz Frequency:

OD Exam Surface:

75 F

°225088 Exam Temp.

Exam Thermometer Exam Comments I Limitations:

Exams perfwmed at below reference sensiftii to maintain 5%

to 20% noise level.

ID root geometry recorded. See attached data sheeL No exam perbonred from downsrearn side due to valve configuration.

Axial Circ UPST DNST Scan dB Recordable Indications Exam Angle I

I Actual Cal Block "T"is 1.410'.

Axial UPST

7. 8 Yes Exam__

Starrt:

12322 Exam End:

2350

ý *nitials:

Charles Barrett Examiner:

H Level:

N/A Level:

~l22~ 1~~?

GE Reviewed By:

Level:

LtttRevieweL y

Date:

Date:

N/A 6

Initials:

Examiner 2:

ANII Reviewed By:

Date:

Cal/Exam Date:

511912003 Page 3_ of 5

Ultrasonic Ex=

GE NUCLEAR ENERGY U

Site: Columbia Generating Station amination Indication Report Procedure: PDI-UT.2/Site Specific / C/I Size:

24" Thickness:

1.45" Data Report Number:

R16-062 Cal / Data Sheet Number UT-078 Weld ID:

24RRC(IJB.16 Drawing:

RRC.102-2 Wo Location:

Weld Centerline Exam Start:

2322 Exam End:

2350 Lo Location: Top Dead Center Weld Width:

1.1" Weld Height: Flush Ind Angle

% of Indication Length

,W Distance Metal Path I Ax/

Upst/

No.

Used I DAC

-Lij L Max L2 Wv i Wmax 1W2 MID~ I MPMax IMP 2 Circ IDnst IComments:

t 60° 125 N/A 6.5" N/A N/A 2.6" NIA N/A 3.1" N/A Ax Upet IDroatgeometry observed intermttanfly 360° thmughout exam.

Sketch oplo

/

CII/2003 GE Reviewed By Level:

Date:

eviewed By Date:

ANII Reviewed By:

Date:

Examiner Level:

Date:

I Page 4

of 5

Wall Thickness Profile Sheet i

Crown Height:

Crown Vidth:

Nominal Diameter:

FLUSH 1.1"_.*

24.0" 75.5,,

PIPE VALVE UPST Component:

DNST Component:

Weld Length:

Pow, I

I r

\\

I/

Charles Barrett Examiner:

REQUEST 21SI-32 ATTACHMENTS A THROUGH G Attachment 21SI-32-13

S

/

2 3

4 5

7 8

9 10 I

I I_

II

• N 12'RRC01)-4S CREP) 24' X 12' RED (REF)

CONT ON RRC-1O2-3 1

2RRC

°I R (3

-REREF) 24" X 16' CROSS (REF)-

I-,'I

{RPV t "EL`28' I

1. SEE RRC-P-18 DETAIL. DWG RRC-103, FOR PUMP SUPPORT DETAILS.

2. EXTEND LEAKAGE EXAM THROUGH CONTAINMENT PENETRATION (X-41d)

THROUGH EXCESS FLOW CHECK VALVE TO INSTRUMENT TUBING CONNECTION.

3. ACCESS TO WELD 24RRC(I)B-13 REQUIRES REMOVAL OF RCR-68.

4. SPECIAL CLAWP WITH HB-7 & S-? ATTACHMENTS.

S. WELD 24RRCI)8-11/BCAP-1 IS FITTING TO FITTING.

S. WELD 24RRC(1)B-18/12CAP-1 IS FITTING TO FITTING.

7. WELD 24RRC(I)B-17 IS FITTING TO FITTING.

8. RRC-V-60B HAS TWELVE (12) 2 3/4' X IS" BODY TO ONNWET STUDS.

9. CAP TO NOZZLE WELDS ARE CLAD ON THE ID IN THE WELD AREA. SEE REFERENCE DWGS 131 C 7588 I 131 C 75AR.

10. PIPING FROM PUIMP DISCHARGE TO RRC-V-6?B IS MIN WALL 1.218.

PIPING FROM RRC-V-76B TO WELD 24RRC(1)E-19 IS NIN WALL 1.140.

11. RRC-SB-1S, NRC-SB-I?,

RRC-SR-18 I RRC-SB-66 WERE DELETED PER BDC 87-0244-0J-026.

REPEARENCES, ISt -

230-2 GENERAL ELECTRIC DRAWINGS 761 E 424 REV 2

?62 E 538 SH ; REV 3 782 E 538 SR 2 REV 3 751E735 REV6 131 C 75 REV 3 131 C 75B9 REV S 131 C 7592 REV 3 CBI NUCLEAR CO.

48 REV 4 NI NOZZLE ASSEMBLY BOVEE CRAIL/GERI BC/G-218 REV 9 90.

I I

0..9 1 80" 270*

QUALITY CLASS.

1 I ASHE CODE CLASS, 1

ENGR, D TIMMINS I DRAWN, K-McA I DATE, 3-30-78 THIS DRAWING IS INTENDED FOR USE IN PRESERVICE AND INSERVICE INSPECTIONS PROGRAMS ONLY.

WASHINGTON PUBLIC POWER SUPPLY SYSTEM

RICHLAND, WASHINGTON 99352 PIPING SYSTEM NOM DIA (IN)

SCH NON WALL THK MATERIAL SPECIFICATION MATL TYPE CAL BLOCK NO WNP-2 WELD & COMPONENT IDENTIFICATION DIAGRAM 6

19-22-941 ADDED NOTE 11. MODIFIED ACCORDINGLY.

K-McA DPR I DW 5

12-"-62 ADDED 'N' To ALL RCR'S.

K-McA DPR DRW 24RREC(l)-45 24 XXX SEE NOTE 10 SA 358 GR 304 CL 1 59 UT-?

TITLE, 4

10-16-87 A

9 O-M-

. 1' CONN It CNT AT RIC-V-HAN. ORI BG-?A TO 4 1-1 It87 RRC-S-9 TO sNmRS.

KEypLAN. REDIAj K-McA DPR TFH 4NRRC(8)-4S 4

80 0.337 SA 312 TP 304 55 UT-29 REACTOR RECIRCULATION LOOP B 3

10-13-83 REVISED AS NOTED ADDED KEYPLAN K-McA DPR TFH CAP 12 80 0.888 SA 403 GR WP 304 55 UT-19 2

11-5-E0 REVISED AS NOTED K-McA TFH DWP CAP a

80 0.500 SA 403 GR WP 304 SS UT-26 NO DATE REVISION-E CHED APVO DWG NO, RRRC-1 02-2 REV S

GE NUCLEAR ENERGY EXAMINATION

SUMMARY

SHEET Report No.:

R16-063 Site and Unit:

Outage:

System Columbia Generatina Station Component ID.

R16 RRC 24RRC(1)B-17 VALVE TO ELL I

Aug Requirements:

Examination Results:

During the manual ultrasonic examination of the above referenced weld, no reportable indications were recorded utilizing the 45°and 60=RL search unit.

This examination is acceptable per the requirements of ASME Section Xl, 1989 Edition, no Addenda and the 1995 Edition, 1996 Addenda with modifications as stated in 10CFR10.55 50% Code coverage was obtained.

Previous data was reviewed prior to this summary.

Examination results were compared to data report RRU-140 from These examinations were performed under Work Order:

01044925 PSI(1 979) outage with 0]

No Change Change This Summary and the following data sheets have been reviewe and accepted by the following personnel:

Prepared By:

Level:

Date:

evi wed By:

Date:

Reviewed By:

Level:

Date:

ANII Reviewed By:

Date:

Ultrasonic Calibration and Examination Record GENUCLEARENERGY Manual Piping and Components Site/Unit: Columbia Generating Station Outage:

R16 Data Report Number: R16-063 Data Sheet Number:

UT-087 Linearity Sheet:

L-O6 Calibration Data for Block: UT-Z Procedure:

PDI-UT-2/Site Specific Ver / Rev: _l!

DRR: !WA SS 24-1.140" Material Size Thick Couplant:

22531h Thermometer SIN 00325 Couplant batch 75* F Cal Temp.

Calibration Initial Cal:

Cal Check:

Cal Check:

Final Cal:

Cal Time 1148 1315 N/A 1505 DAC Construction Search Unit Data KBA OOMPX8 0.50'/Round Manufacturer:

Serial Number Size/Shape:

0.5 in.

45' 450 Incident Point:

Nominal Angle:

Measured Angle:

1.5Mý Comp-G Shea I

Frequency:

Style:

Mode:

Elements:

Search Unit Cable RG-174 6"

Cable Type:

Length:

Connectors:

Instrument Settinas Scan Direction Cal Reflector Signal Amplitude Signal Sweep:

Signal dB:

Ax ID Notch 80%

5.0 Div 31.4 dB N/A N/A N/A N/A

.0 Div

.O0dB

.0 Div

.0 dB Sweep 0-10 =

4.0 in.

Metal Path Calibration Verification Field Simulator Block SIN:

CAL-RHOM-009 Reflector 1 " Radius 2a Radius Amplitude 8001 MO Gain (dB) 20.6 20.6 Sweep (SD) 2.5 5.0 Acceptable Linearity performed :

417/2003 Exam Data for Weld: 24RRC(1)B-17 VALVE TO ELL Configuration:

Staveley / Sonic 136P MaufacturertModel:

0.408 in.

0.124in Jusec.

Delay:

Velocity:

717H Serial Number:

4KHz Filter:

Rep Rate:

500 Ohms Damping:

P/E Mode:

4.0 in.

Range:

Off Reject:

334 ns Pulser:

2.25 MHz Frequency:

Exam Comments / Limitations:

Exams performed to maintaIn 5% to 20% ID roll.

ID geometry observed below recordable levels.

No exam performed from upst side due to component configuration.

Actual Cal block 7"is 1.410' O0 Exam Surface:

72°.F 225316 Exam Temp.

Exam Thermometer Axial UPST Scan dB Recordable Exam Circ DNST Indications Angle Axial DNST 47.0 NRI 450 Circ DNST

ýf.0 1

NRI 4r t

Exam Start:

1317 Exam End:

1330 Initials:

Andre' Rachal Examiner:

I!

Level:

Level:

Gl~evewed9By:

, R~ee~

Level:

Date:

Date:l Date:

Page I of N/A Initials:

Examiner 2:

6 Cal/Exam Date:

5121/2003 ANII Reviewed By:

Ultrasonic Calibration and Examination Record

_GE NUCLEAR ENERGY Manual Piping and Components LC Site/Unit: Columbia Generating Station Outage:

R16 Data Report Number. R16-063 Data Sheet Number:

UT-088 Linearity Sheet:

L-06 Calibration Data for Block: UT-7 Procedure:

PD/-UT-2ISite Specific Ver / Rev:.91 DRR: NIA sS Material UQrgeU Couplant:

24' 1.140" Size Thick 00325 Couplant batch ZE F Cal Temp.

Calibration Initial Cal:

Cal Check:

Cal Check:

Final Cal:

Cal Time 1133 1332 N/A 1500 225316 Thermometer S/N DAC Construction Search Unit Data RTD 98-172 2(10x18) mm/Rect Manufacturer:

Serial Number Size/Shape:

0.45 In.

60o 590 Incident Point:

Nominal Angle:

Measured Angle:

2.0 MHz TRL 2-Aust Long 2

Frequency:

Style:

Mode:

Elements:

Search Unit Cable RG-1 6-0 Cable Type:

Length:

Connectors:

Scan Direction Cal Reflector Signal Amplitude Signal Sweep:

Signal dB:

Ax ID Notch 80%

4.7 Div 69.2 dB N/A N/A

.0 Div

.0 dB N/A N/A

.0 Div

.0 dB Sweep 0-10 =

6.0 in.

Metal Path Instrument Settings Calibration Verification Field Simulator Block S/N:

CAL-RHOM-069 Reflector 1" Radius 2" Radius Amplitude 34%

80%

Gain (dB) 39.6 39.6 Sweep (SD) 1.7 3.33 Acceptable Linearity performed Staveley / Sonic 136P Maufacturer/Model:

1.2in.

0.233in.J/sec.

Delay:

Velocity:

717H Serial Number.

2 4KHz Filter:

Rep Rate:

500 Ohms Damping:

Dual Mode:

6.0in.

Range:

Off Reject:

250 ns Pulser:

,Z25cMHz Frequency:

c'Adl1l Udai lUf VVIrIU.

c4frtrL(j(

10o I1 VALVE TO ELL Configuration:

Exam Comments I Limitations:

OD Exam Surface:

72°_F 225316 Exam Temp.

Exam Thermometer Exams perfermed to maintain 5% to 20% noise level.

Supplemental 60°RL examination due to single side access.

No exam performed from upst side due to component configuration.

Scanned at reference dB to maintain 5% to 20% noise level.

ID root geometry 3600 intermittently above and below recorded levels.

Actual Cal block "T"is 1.410" Exam Start:

1334 Exam End:

1354 Andre" Rachal IH Initials:

Examiner:

Level:

N/A Initials:

Examiner 2:

Level:

Level:

I Date:

)ate:

Reviewed By:

Cal/Exam Date:

5/21/2003 wl__6'ý Date:

ANII Reviewed By:

Page I of 5_

0 0,

F Ultrasonic Examination Indication Report Data Report Number:

R16-063 GE NUCLEAR ENERGY Site: Columbia Generating Station Procedure: PDI-UT-2/Site Specific / C/1 / N/A Cal / Data Sheet Number UT-088 Weld ID:

24RRC(1)B-17 Drawing:

RRC-102-02 Size:

24" Thickness:

1,58._

Exam Start:

1334 Lo Location: TDC Wo Location:

WELD CL Weld Width:

1.15 Weld Height: FLUSH Exam End:

1354 Ind Angle I%of Indication Length j

WDistance Metal Path I Ax/ I Upst/

No.-

Used

)DACI Li L Max L2 W1 WMax I W2 MP I MPMax I MP2 Circ I Dnst Comments:

1 1 600 1 200 1 NIA 58.0" 1 N/A N/A 2.25 N/A NIA 2.76 1 N/A I

Ax I Dnat tID Root Geomely 360* Intemilttendy above and below recorded levels.

Sketch

/

/

\\/

\\ /

AVAV Andre' Rachal Examiner Rev Level:

Date:

4iReviewe y

Date:

Date:

II 5/21/2003 Level:

Date:

ANII Reviewed By:

Page 4 of 5

+/- _____________________

Wall Thickness Profile Sheet Crown Height:

Crown Width:

Nominal Diameter:

FLUSH 24.0" VALV ELBOW UPST Component:

DNST Component:

Weld Length:

I

/

\\ /

-- /

REQUEST 21SI-32 ATTACHMENTS A THROUGH G Attachment 21SI-32-14

1 2

6 9

10 N*ý

0.

90 A

B c

24"X 2 CON 20°RM D

I 24RAC (2).

0 SACRIEICAL I~RPV

./

SHIELD WALL

• 0 24RRC (2) A-SLUO --.... ~*

>~*

24RRC(2N A

22RRA-(2U 24RRC (2) A-SL 24RR

-2A-3L5

-L 24"RRC (2) A-2) 24R2C-(2)DA-SLD 4 RD4R A UR R(2 A3 eL 5350"AZ 2T4NRRC()-5L 24RR (2) 24A-(3A-3LU*L L

" /

1I 0

24--

4 R

RC2)A

)-1tL 3

CE-*IA LA1D-R 24RRC(2)A-4LUI N,4 AC -N1-I TO EL 541I 24IIC EL A-4 (4 WETE LUGS)

(SEE NOTE 2) 24R-C(2)A-4A P-2F 24IRC(2)A-4LD I

2(ERC~)-4SR(EF)

A

~~COE4T ON RRC-101-2 3CI 4X 20' RED TEE I

2/RRC (2) A-ELU V

530 2499K (2) A-B1)IDx I4R()-

(SEE NOTE )

24 C

-]-2 A-T RIC-1 24RRC (2) A-D002 24-RC(2)A-7LUE 4RRC.(6) 2A-2BD o

24RRC-(2)PA-12 4RRC (B) 2A-2 (SEE NOTE 8) 4 AEL 517' 24RRC2)A-7 24ARRC(2)A-_2LU1 4 A24BRCC2)A-7LD 24RRC(2)A-R2LUI 24ERC (2)A-LUI 4RRCC (B) 2A-i

/

NOTE

( 2)EA-4i D/

ELRR(8)"-

2RC2)ABIEC2)-iL 2499K (2) A-i O/3/4PLUG (2)RRC-2--11UO3T S

RTG SIT E

C2A-/

FELU--I (SEEp NOT 6)NEVCO*

O 24RRC (2) A-IO/3/4TE-N023A 24RRC (2) A-B/i FIll)-4SO 2499K (2) A-iO/3/4TE-ND12BA RCR-3A--,_24RRC (2) A-1O/4RRC (4)-4S R

2RC()AB 4.RCENT -4 (NR-iEF) 24R l(2)A-B/IPI~

24R()-

-24RRCC2)A-IOLD 24RRCI2)A-B/lFI (1)-4S,-""'

2ARC2A-B/il 24R9C2)-S HR--3 TPFR4 24RKE (2) A-BD :

L ý RRC-V-23A/3/4V-26A SEE DETAIL 1"'\\RRC-V-23A/3/4V-2BA ZONE F-7 SEE SN-RRC-101 3/4(R9C(Si)-4S (REF)

DT I

.4 L 503' 24RRC(2)A-9 PLATFORMI (SEE NOTE 7)

EL 501' 24RRC (2) A-BLUO A

24RRC (2) A-gLUI THIS DRAWING IS INTEND FE-14 USE IN PRESERVICE AND INSPECTIONS PROGRAMS C

1BO*

LUO

1.

WELD 24RRC(2)A-1 UTILIZES CAL BLOCK UT-101.

2. ACCESS TO WELD 24RRC(2)A-4 REQUIRES REMOVAL OF RCR-lA.

3. EXTEND LEAKAGE EXAM THROUGH CONTAINMENT PENETRATION (X-78)

THROUGH EXCESS FLOW CHECK VALVE TO INSTRUMENT TUBING CONNECTION.

4. ACCESS TO WELD 24RRC(2)A-B REQUIRES REMOVAL OF RCR-3A.

S. EXTEND LEAKAGE EXAM THROU-GH CONTAINMENT PENETRATIONS (X-40c),

(X-40d),

(X-610)

(X-61b) THROUGH EXCESS FLOW CHECK VALVES TO INSTRUMENT TUBING CONNECTION.

6. EXTEND LEAKAGE EXAM THROUGH CONTAINNENT PENETRATION (X-?OF) THROUGH EXCSS FLOW CHECK VALVE TO INSTRUMENT TUBING CONNECTION.

7.

WELD 24RRC(2)A-9 IS FITTING TO FITTING.

B. WELD 24RRC(2)A-12 IS FITTING TO FITTING.

9. LONGITUDINAL WELDS LOCATED INBOARD I OUTBOARD ON THE RED TEE, WITH RESPECT TO THE RPV, ARE 90" FROM THE BRANCH CONNECTION.

i1. FOR NOZZLE ASSEMBLY DETAIL SEE DWG RPV-lOS.

ii.

PIPING PURCHASED TO MIN WALL SPEC - 0.910'.

12. RRC-SA-1, RRC-SA-2, RRC-SA-16, RRC-SA-19, RRC-SA-20 I RRC-SA-25 WERE DELETED PER BOC BT-0244-OJ-024.

13. ADDED FE-14 PER BDC $5-0753-OA-302.

REFERENCES,.

ISI - 230-1 GENERAL ELECTRIC DRAWINGS 761 E 424 REV 2 762 E 538 SH 1 REV 3 762 E 538 SN 2 REV 3 761 E 73S REV 6 131 C 7599 REV 4 131 C 7587 REV 3 CBI NUCLEAR CO.

48 REV 4 NI NOZZLE ASSEMBLY BOVEE CRAIL/GERI BC/G-215 REV 910 g0.

E F

G KYPYLAN 24RRI (l)-45C PI (1)-4Sd 10s REACTOR BLDG 270*

270" 1

ENGR, D TIMMINS I DRAWN, K-McA I DATE, DED FOR INSERVICE ONLy.

WASHINGTON PUBLIC POWER SUPPLY SYSTEM

RICHLAND, WASHINGTON 99352 MATERIAL SPECIFICATION MATL CAL BLOCK TYPE NO WNP-2 WELD I COMPONENT IDENTIFICATION DIAGRAM REACTOR RECIRCULATION LOOP A

I 1GE NUCLEAR ENERGY Site and Unit:

Columbia Generating Station Component ID:

24RRC(2)A-10 VALVE TO PIPE Outage:

RFO-15 System:

RRC ASME Cat.:

B-J ASME Item B9.11 Aug Requirements:

NIA Exams Performed Data Sheet Cal Sheet Procedure Calibration Block Examination Cert Date Personnel Level 600 RL UT-R15-042 N/A PDI'UT-2 UT-7 BRET FLESNER 11 5(24/01 45° Shear UT-R15-041 N/A PDI-UT-2 UT-7 BRET FLESNER II1 5/24101 60' Shear UT-R15-044 NIA PDI-UT-2 I

UT-7 BRET FLESNER 11i 5/24/01 Examination Results:

During the manual ultrasonic examination of the above referenced weld, no reportable indications were recorded utilizing the 450 shear wave search unit. Root geometry was recorded with the 600 RL and confirmed using a 60° shear wave.

This examination is acceptable per the requirements of ASME Section X1, 1989 Edition, no Addenda and the 1995 Edition, 1996 Addenda with modifications as stated in 10CFR50.55.

Examined from the pipe side only due to valve configuration. 50% code coverage obtained.

Previous data was reviewed prior to this summary.

Examination results were compared to data report RRU-078 from 1979 outage with W

No Change These examinations were performed under Work Order 01011024 77 Change This Summary and the following data sheets have been reviewe d accepted by the following personnel:

________Dose:

N/A mr.

Prepared By:

Level:

Date:

i eviewed By:

Title:

Date:

GE Reviewed By: t Level:

Date:

ANII Reviewed By:

Title:

Date:

Page 1

of 7

a (I*-

GE NUCLEAR ENERGY System:

RRC F

Indication / Coverage Plot Sheet Site:

Columbia Generating Station Unit:

NIA Project:

RFO-15 Report No.:

R15-049 Component ID Number 24RRC(2)A-10 Configuration:

19 Valve VALVE PIPE COVEA&E PL bT Intas BRETaFLESNER Initials: Exam~iner

!I Level:

Level:

REQUEST 21SI-32 ATTACHMENTS A THROUGH G Attachment 21SI-32-15

1 2

3 4

5 6

?

8 9

10

"*ýN 24E5C (2) W-4LUI 24RRC 12) 6-4LU()

24RC (2) B-4 (SEE NOTE 2) 24RRC(2) B-4LD-EL 3'r 24RRC (2) B-BLU---

24RRC(2) B-5--

24RRC (2) B-SLD --,,

EL 524' 24RRC (2.) B-5/3/4PS-N088 (SE NOTE 3)*

24RRC(2)B-5/3/4PX-1B eý-24RC 124)R B-2L I-.

2RC2)RR-3L01-24O 2) 6-(21003 24RRC(2)B-2LD (SEE NOTE 12) 24ERC(2)B-2 (SEE NOTE 1) 24- -(2)8-1 (SEE NOTE 1)

SHIELD WALL RPV

NOTES,

1. WELD 24RMC(2)8-1 UTILIZES CAL BLOCK UT-101.

2. ACCESS TO WELD 24RRC(2)B-4 REQUIRES REMOVAL SE 5CR-lW.

3. EXTEND LEAKAGE EXAM THROUGH CONTAINHENT PENETRATION (SX-ROW) THROUGIH EXCESS FLOW CHECK VALVE TO INSTRUMENT TUG ING CONNECTION.

4. ACCESS TO WELD 24RRC(2)B-E REQUIRES REMOVAL OF RRC-SE.

S. EXTEND LEAKAGE EXAM THROUGH CONTAINMENT PENETRATIONS (X0-62C), (-62d),

C(-75W) I (X-?SF) THROUGH EXCESS FLOW CHECK VALVES TO INSTRIUENT TUBING CONNECTION.

6. EXTEND LEAKAGE EXAM THROUGH CONTAINMENT PENETRATION (X-41c) THROUGH EXCSS FLOW CHECK VALVE TO INSTRUMENT TUBING COWNNECTION.

?. WELD 24RRC(1)B-7 IS FITTING TO FITTING.

W. NELD 24RRC(1)B-10 IS FITTING TO FITTING.

6. FOR NOZZLE ASSEMBLY DETAIL SEE DOW RPV-lO5.

10. PIPING PURCHASED TO MIN WALL SFEC-0.910.

11. WELD IS STAMPED 24RRC(1)R-2.

12. WELD IS STAMPED 24RRC(1)B-2LD.

13. RRC-5B-1, RRC-S8-2, RRC-SR-16 I RRC-SB-25 WERE DELETEO PER BOC B?-O244-OJ-026.

14. ADOED FE-24 PER BOC 55-0753-0A-303.

ISI - 230-2 GENERAL ELECTRIC DRAWINOS

?61 E 424 REV 2 72 E5sm 5H1 REV3 7?2 E 538 SH 2 REV 3 761 E 73 REV 6 131 C ?5 REV 4 131 C 7S7 REV 3 CB1I NUCLEAR CO.

46 REV 4 N1 NOZZLE ASSEMBLY BOVEE CRAIL/GERI 6C/G-21?

REV 10 go.

A A

RCR-3BPLATFORM 24RR C2)8-6/IFI(I)-4S5 Nc D:..ý-Z4RRC(22R-0i.I (SEE NOTE 4)

EL 501, 24RRC(2)-6/lFPI (1)-40F 24 (2)R-W 4RRC CB)2B-224RRC (2) B-6/11 (1)-4S.

4RO~mB-y-(SEE NOTE 5) CTYP FOR 4)

" (EE NTE

)

\\

\\J*

/.,,

)

\\

24 OR0(C2)p-R1.U I

_c * *\\

\\

\\

\\/

..4"*

'I

\\

,-24 2

E-2 (4E NTE IR2ý 22 6-(-LU I

I/24 24RRC (226

-B/3/4~T-NO288N.

24ORC(22RB-01f1 I1 -5 24660(233/dP-N15 24RRC' 22)RC(6/WI P314(E)

-236 (SEE NOTE 5

24) (2) B--/3/4PL 24ORR(2)B-LOL T ON R-

-24ORC(2).-)-

THIS DTAWIN I EL 503 24 600(226-6,. 0 55 IN P5E0RV 24ERCC2 IIN1SPECTIONS FE I

I 270" QUALITY CLASS, 1I AMSE COOS CLASS, 1

ENGEI, 0 TIMMINS I DRAWN K-CA I DATE, 3-29-78 S INTENDED FOR ICE AND INSERVICE EOGRAMIS ONLY.

WASHINGTON PUJBRLIC POWER SUPPLY SYSTEM RICH.ANO, WASHINGTON 99352 PIPING SYSTEM NOM CIA (IN)

SCH NOM WALL MATERIAL SPECIF ICAT ION MATL TYPE CAL BLOCK NO WNP-2 WELD & COMPONENT 5

9-22-941 ADDED NOTES 13 & 14. MODIFIED ACCORDINGLY.

IK-M.AI DPR I0O A[W*O 6B" (S

-I-s IDENTIFICATION DIAGRAM 4 11-13-92 WEET W6.'

'Ai lT-.7. K-RA 6PM REW_____________

OFE SVW 6LOE16 24ORRC12)-4S 24 SSX ISEE NOTE tR SA 35W OR 30.4 C1 55

-2

TITLE, MODIFIED

• IEYP'Mt 2 LOGO. REORA*

ITE 3

10-16-"? AWE*D ISI DVW REFER.

CKAIýO lt-HB-l TO SPR IN*

KHA F

CO3RECT6ED 10 T

a

)

P' CEWCTIO0 g" EONW ZN E-5.

K-cA DR TF 4"RRC(W)-4S 4

No 0.33?

SA 312 TP 304 SS UT-29 REACTOR RECIRCULATION LDDP 8 2

11-14-63 REVISED AS NOTED. ADDED KEYPLAN I

LUGS.

K-RcA DPR TFH I

11-5-80 ADDED NOTE 9 K-MCA DA I

ONE N.

I No OWE NO, RRC-R102-- 1B REV S

No DATE REvIsION OT CHD WV I__

Report No.:

GE EXAMINATION

SUMMARY

SHEET R16-066 GE NUCLEAR ENERGY Site and Unit:

Columbia Generating Station Component D:

24RRC(2)B-8 Outage:

R16 VALVE TO PIPE System.

RRC ASME Cat:

B-J ASME Item B9.11 Aug Requirements:

N/A Exams Performed Data Sheet Cal Sheet Procedure Calibration Block Examination Cert Level Date I

I I

Personnel 45° Shear UT-119 N/A PDI-UT-2/Site Specific UT-7 Charles Barrett II 5/21/2003 60° Long UT-120 N/A PDI-UT-2/Site Specific UT-I Chades Barrett.

II 5/2112003 Examination Results:

During the manual ultrasonic examination of the above referenced weld, no reportable indications were recorded utilizing the 450 and 60" search units.

This examination is acceptable per the requirements of ASME Section XI, 1989 Edition, no Addenda and the 1995 Edition, 1996 Addenda with modifications as stated in 10CFR50.55.

50% Code coverage was obtained.

Previous manual UT data and construction radiographs were reviewed prior to this summary.

This weld was identified during construction as BC/G 217 Weld B-4.

Examination results were compared to data report RRU-069 from PSI (1979) outage with

[]

No Change These examinations were performed under Work Order.

01044925-01

[]

Change This Summary and the following data sheets have been reviewed and accepted by the following personnel:

I

Ultrasonic Calibration and Examination Record GE NUCLEAR ENERGY Manual Piping and Components Site/Unit: Columbia Generating Station Outage:

R16 Data Report Number: R16-066 Data Sheet Number:

UT-119 Linearity Sheet:

L-02 Calibration Data for Block: UT-7 Procedure:

PDI-UT-2/Site Specific SS W

1.140 Calibration Cal Time Material Size Thick Initial Cal:

1901 ltai I

00325 Cal Check:

2202 Couplant:

Couplant batch 2208 7rCal Check:

N/A Thermometer S/N Cal Temp.

Final Cal:

2308 Ver /Rev: c/.

DRR: NIA DAC Construction Search Unit Data KBA OOL6YV 0.50"/Round Manufacturer:

Serial Number Size/Shape:

0-35 in.

45_

45_

Incident Point:

Nominal Angle:

Measured Angle:

1.5 MHz Com.-G Shear 1

Frequency:

Style:

Mode:

Elements:

Search Unit Cable RG-174 6_

0 Cable Type:

Length:

Connectors:

Instrument Settings Scan Direction Cal Reflector Signal Amplitude Signal Sweep:

Signal dB:

AxY ID Notch 600%

5.1 Div 35.0 dB Sweep 0-10 =

4.0 in, Metal Path Calibration Verification Field Simulator Block SIN:

CAL-RtIOM-068 Reflector 1" Radius 2" Radius Amplitude 80%

76%

Gain (dB) 24.0 24.0 Sweep (SD) 2.5 5.0 Acceptable Linearity performed 41712003 Exam Data for Weld: 24RRC(2)B-8 VALVE TO PIPE Configuration:

Staveley / Sonic 136P MaufacturerlModel:

136PI106C031364 Serial Number:

0265 in.

0. 12inse.

4KHZ Delay:

Velocity:

Filter:

Rep Rate:

4.0 in.

Range:

off Reject:

334 ns Pulser 2.25 MHz Frequency:

500 Ohms Damping:

PIE Mode:

Exam Surface:

Ea p

E 22508 t

Exam Temp.

Exam Thermometer Exam Comments I Limitations:

Exams perotmed to maintain 5% to 20% ID roll.

No exam performed from upstream side due to valve configuration.

Actual Cal Block "T"is 1.410.'

Axial UPST Scan dB Recordable Exam Circ DNST Indications Angle Axial DNST 49-0 NRI 45° Circ ONST 53.0 NRI 45W 4

I-

-I-4

~.

I-Exam Start:

/9 2202 Exam End:

2222

,/Y Charles Barrett Initials:

Examiner:

N/A Initials:

Examiner 2:

Cal/Exam Date:

5/21/2003 Level:

N/A Level:

(

GE Reviewed By:

Utility Reviewed By:

ANII Reviewed By:

Level:

Date:

Date:

Date:

Page 2 of 5

Ultrasonic Calibration and Examination Record GE NUCLEAR ENERGY Manual Piping and Components Site/Unit: Columbia Generating Station Outage:

R16 Data Report Number: R16-066 Data Sheet Number:

UT-120 Linearity Sheet:

L-02 Calibration Data for Block: UT-7 Procedure:

PDI-UT-2/Site Specific SS 24'

1. 140' Calibration Cal Time Material Size Thick Initial Cal:

1915 Ultraael 00325 Cal Check: 2224 Couplant:

Couplant batch 22087r" Cal Check:

N/A Thermometer S/N Cal Temp.

Final Cal:

2310 DAC Construction Scan Direction Ax Cal Reflector ID Notch Signal Amplitude 8".

Signal Sweep:

4.6 Div Signal dB:

80.4 dB Sweep 0-10 =

.in.

Metal Path Ver / Rev: c/.

DRR: W/A Search Unit Data RTD 00-369 2(15x25) mm/Rect.

Manufacturer:

Serial Number Size/Shape:

0.6 In.

6_

600 Incident Point:

Nominal Angle:

Measured Angle:

2.0 MHz TRL 2-Aust Lo 2

Frequency:

Style:

Mode:

Elements:

Search Unit Cable RG-174

6.

0 Cable Type:

Length:

Connectors:

Instrument Settings 0,

Calibration Verification Field Simulator Block S/N:

CAL-RHOM-058 Staveley / Sonic 136P Maufacturer/Model:

1.33 in.

0.231inJusec.

Delay:

Velocity:

Reflector 1 Radius 2 Radius Amplitude 30%

Gain (dB) 46.8 46,8 Sweep (SD) 1.6 3.3 Acceptable Linearity performed :

4/7/2003 Exam Data for Weld: 24RRC(2)B-8 VALVE TO PIPE Configuration:

136PI106C031364 Serial Number 2

4KHz Filter.

Rep Rate:

500 Ohms Damping:

Dual Mode:

6.0 In.

Range:

Off Reject:

250 ns Pulser:

2.25 MHz Frequency:

OD Exam Surface:

81°_F 225088 Exam Temp.

Exam Thermometer Exam Comments / Limitations:

Exams perfonned at reference sensitivity to maintain 5% to 20% noise level.

No exam pednnred from upstream side due to valve conflguration.

Reference attached indication report lbr examination results Actual Cal Block 7Tis 1.410.

Axial Circ UPST DNST Scan dB Recordable Indications Exam Angle Axial DNS]

j0.Ye

~

____}Exam Start:

Z 2224 Exam End:

2255 Initials:

Charles Barrett Examiner:

I1 Level:

NIA Level:

Zt7

- /o~z N/A Initials:

Examiner 2:

6 GER~ed By:

iit'ii Reviewed By:

ANII Reviewed By:

Level:

Dat a

e:

Cal/Exam Date:

5/21/2003 P

2n f

nf Date:

0GE NUCLEAR ENERGY Ultrasonic Examination Indication Report I

0 Data Report Number:

R16-066 Cal / Data Sheet Number UT-120 Q4 rM-f-f-,.-

P1rnari rom DrlI 9I I7.Cl#a 4

^Qarjfio / I1 Weld ID: 24RRC(2)B-8 Lo Location: Top Dead Center Drawing:

RRC-102-01 Wo Location:

Weld Centerline Size:

W Weld Width:

Thickness:

1._0" 1.20" Weld Height: Fius. h Exam Start:

2224 Exam End:

2255 Ind Angle

% of Indication Lengh W Distance Metal Path AxI UpstI No.

Used DAG L1 LMax L 2 W1 WMax I W2 MP IMP MaxI MP2

Circ, Dnst Comments:

1 60' 125 NIA 72.0" NIA N/A

'1.7" NIA NIA 2.2" NIA Ax Dnst ID mot geometry observed Intarmlttentlyl3O0 thmu*gut exam.

Sketch Charles SO&Of HII 5/21/2003 GE Reviewed By:

Level:

Date:

U eviewed By:

Date ANII Reviewed By:

Date:

Examiner Level:

Date:

Page of 5

Wall Thickness Profile Sheet I 1.5" I

Crown Height:

Crown Width:

Nominal Diameter:

Weld Length:

FLUSH 1.0" 24.0" 75.5" VALVE UPST Component:

PIPE DNST Component:

0O

/

r I

/

V LAýR~evlwed By:Dt NI Date:

ANII

REQUEST 21SI-32 ATTACHMENTS A THROUGH G Attachment Attachment E 21SI-32-16 Weld Identification 24RRC(1)B-10 ISI Diagram RRC-101-2 NDE Data Report R16-064

1 2

3 4

5 6

7 8

9 10 CONT ON REC-102-6

'-...O 12ORRCR1)-4C (10E) 0 9

1.

SEE RRC-P-1B DETAIL, DWG REC-103, FOR 12'RC~l-45(RE)

-PUMP' SUPPORT DETAILS.

A 24" X 12' RE(

)

(.PE>,2.

EXTENO LEAKAGE EXAM THROUGH CONTAINMENT 270' PENETRATION 1X-41d) THCRIOUGH EXCESS FLOW CHECK VALVE TO INSTRUIMIENT TUBING CONNECTION.

CONT ON REC-102-3

,1s 1EF)

V

3. ACCESS TO WELD 24REC(1)B-13 REODIRES REMOVAL 16'RC~l)AS CEF)OF RCR-68.

EFEL 528' (REF)

4. SPECIAL CLAMP WITH HB-7 SB-? ATTACHBENTS.

24' X 16' CROSS (REF)

5. WELD 24RRCI1)B-11/8CAP-1 IS FITTING TO FITTING.

6. WELD 24RRC(1)B-B/12CAP-1 IS FITTING TO FITTING.

7. WELD 24RRC(1)R-17 IS FITTING TO FITTING.

BB.

ERC-V-ROB HAS TWELVE (12) 2 3/4' X 15' BOOT TO BONNET STUDS.

tB

9. CAP TO NOZZLE WELDS ARE CLAD ON THE ID IN THE

-:24RRCO)B-1BLU WELD AREA. SEE REFERENCE DOGS 131 C 7588 &

131 C 7589.

10. PIPING FROM PUMP DISCHARGE TO REC-V-6BI IS RCR-9B EMIN WALL 1.21B.

PIPING FROM RRC-V-FBB TO WELD 24RRC(1)9-19 IS MIN WALL 1.140.

11. RRC-SB-iS. EEC-SB-I?,

RRC-SB-B8 I RRC-SB-66 C

WERE DELETED PER BDC E7-0244-0J-026.

GEE NOTE 1 EEC-SB-B EEC-SB-B B8C, J 1f 24RRC(1)B-I11/3/4dPT-NO1SB 151 -

230-2

/

SEE NOTE 2 GENERAL ELECTRIC DRAWINGS 761 E 424 REV 2 24REC(1)B-1B/12RRC(7)-4S 762 E 538 SH 1 REV 3 CONT ON EEC-iD?

762 E 538 SH 2 REV 3 I2E41CC(B)IB-2BD 12'RRC(7)-4S CREF) 761 E 735 REV 6 D

4RRC(B)0B-2 24RRC(1)B-1B/12CAP-1 131 C 7%88 REV 3 CONT ON RRC-102-1 (SEE NOTES 6 I 9)

EL 2

131 C 7589 REV 5 24'RRC(2)-4S (REF) 4.EL 512-131 C 7592 REV 3 4R24RECBlB-18/12CAP

'z.

CBI NUCLEAR CO.

24*C(1)B-11 24RRC(1I)B-11/4EEC(B)-45 48 REV 4 NI NOZZLE ASSEFBLT 24RR(1)8 11 D

2RRC

1) 8..)BOVEE CRAIL/GERI

-. 24RRC( 1 )B-11L/A

• 241C(1)B-1U 4C/G-218 REV 9 24RRCC I)B-11/SCAP-RRC-V-BDB/1V-948 (SEE NOTES 5 It 9

/SEE SNRRC-102 24RRC(l) 1 D

90

.. 24EEC I1)B-1BLDIMO 4

3/4RRC(5))-4S 14EF)

.f-24

-(C41)VB-1 8

(

N

8)

(SEE 4

T 3) 24RRC (1 4B-IS1-L K

270" RRC-V-BOBi/3/4V-BRB

/

24RRC CITB-l 3LD RR-VET3,,

AN RRC-V B4B-.

(1)

0.

1 0 RR24EEC I1 -i ILDI0 C-SEENOTE7)

OUALITT CLASS, 1

B ASII CODE CLASSD ENGR, 0 TIFMIINS DRAWN. K-MoEA DATE.

3-30-IB FOR 1WASHINGTON PUBLIC POWER GUSE IN PRESERVICE AN(D INSERVICE ISUPPLY SYSTEM INSPECTIONS PROGRAMS ONLY.

E-CI.A O, WAS46NGTON RE392 NON NNO MATERIAL MATL CAL WNP-2 1 T ~

~

~

~

~

~

4R (i~

1

) B-IN I

TH5PEIICTONN PIPING SYSTEM DIA SCH WALL BLOCK WELD & COMPONENT 6

9-22-94 ADDED NOTE 11. MODIFIED ACCORDINGLY.

K-McA DPR DW (IN)

THK SPECIFICATION TYPE NO IDENTIFICATION DIAGRAM H

5 12-9-92 ADDED "B' TO ALL RCR'S.

K-McA OPR DRW 24'RR(C1)-4S 24 XXX SEE NOTE 10 SA 358 GR 304 CL 1 SS UT-I TITLE.

410-16-87 A"".

-S8--8 9 RC-S--9 TO ENESIRS. "DO KEYPLAN. REDRAWN K-McA DPR TFH 4*RRC[B)-4S 4

Ro 0.337 SA 312 TP 304 SS UT-29 REACTOR RECIRCULATION LOOP B 3

10-13-83 REVISED AS NOTED ADDED KEYPLAN K-RCA DPR TFH CAP 12 R

0 S0EBB GA 403 GR WP 304 SS UT-19 2

11-5-80 REVISED AS NOTED K-RCA TFH DWP CAP I

B BO 0.500 SA 403 GR NP 304 SS UT-RD NO DATE REVISION BY CHKD APVD

Report No.:

EXAMINATION

SUMMARY

SHEET R16-o04 GE NUCLEAR ENERGY Site and Unit:

Columbia Generating Station Component ID:

24RRC(2)B-10 Outage:

R16 ELL TO PUMP System.

RRC ASME Cat.:

B-J ASME Item B9.11 Aug Requirements:

NIA Exams Performed Data Sheet Cal Sheet Procedure Calibration Block Examination Cert Level Date Personnel 450 Shear UT-117 N/A PDI-UT-2/Site Specific UT-7 Dickey Michael II 5/21/2003 60' Long UT-118 N/A PDI-UT-2/Site Specific UT-7 Dickey Michael II 5/21/2003 0

Examination Results:

During the manual ultrasonic examination of the above referenced weld, no reportable indications were recorded utilizing the 45° and 60' search units.

This examination is acceptable per the requirements of ASME Section Xl, 1989 Edition, no Addenda and the 1995 Edition, 1996 Addenda with modifications as stated in 10CFR50.55.

50% Code coverage was obtained.

Previous data was reviewed prior to this summary.

Examination results were compared to data report R-R8-127 from These examinations were performed under Work Order:

01044925-01 R-8 outage with W

El No Change Change This Summary and the following data sheets have been reviewed and accepted by the following personnel:

P red y:

Level:

Date:

eviewed By:

Date:

Reviewed By:

Level:

Date:

ANII Reviewed By:

Date:

Ultrasonic Calibration and Examination Record GE NUCLEAR ENERGY Manual Piping and Components Site/Unit: Columbia Generating Station Outage:

R16 Data Report Number: R16-064 Data Sheet Number:

UT-117 Linearity Sheet:

L-04 Calibration Data for Block: UT-7 Procedure:

PDI-UT-21Site Specific Ver / Rev: 91 DRR: N(A SS 24_*

1.140" Calibration Cal Time Material Size Thick I

C Initial Cal:

1910 l00325 Cal Check: 2204 Couplant:

Couplant batch 225291 72*F Cal Check:

N/A Thermometer SIN Cal Temp.

Final Cal:

2354 KBA Manufacturer.

0.35 In.

Incident Point:

1.5 MHz Frequency:

Search Unit Data 00H8Y3 Serial Number 45.

Nominal Angle:

Comp-G Shei Style:

Mod(

DAC Construction Scan Direction Ax Cal Reflector ID Notch Signal Amplitude 80%

Signal Sweep:

5.1 Div Signal dB:

31.0 dB Sweep 0-10 =

4.0 in.

Metal Path 0.50"/Round Size/Shape:

46.

Measured Angle:

or1 Elements:

n Connectors:

Search Unit Cable RG-174 6.

Cable Type:

Length:

Calibration Verification Field Simulator Block SIN:

CAL-RHOM-066 Reflector 2" Radius N/A Amplitude 80%

MIA Gain (dB) 19.4 N/A Sweep (SD) 5.0 N/A Acceptable Linearity performed :

4/7/2003 Instrument Settings Staveley / Sonic 136P 707H Maufacturer/Model:

Serial Number:

0.221 in.

0.126ini/usec.

1 4KHz Delay:

Velocity:

Filter:

Rep Rate:

4.0 In.

334 ns 500 Ohms Range:

Pulser:

Damping:

Off 2.25MHz PIE Reject:

Frequency:

Mode:

Exam Data for Weld: 24RRC(2)B-1O ELL TO PUMP Configuration:

OD 76°F 225291 Exam Surface:

Exam Temp.

Exam Thermometer Exam Comments / Limitations:

Exams performed to maintain 5% to 20% ID roll Previously recorded geometry observed below recordable levels.

No exam performed fom downstream side due to component configuratbon.

Actual Cal Block "T is 1.410".

Axial UPST Scan dB Recordable I Exam Circ DNST Indications Angle Axial Circ UPST 45 NRI 45o UPST 48 NRI 450 Exam Start:

12205 Exam End:

A4 2222 Initials:

Dickey Michael Examiner:

iH Level:

NIA Level:

N/A Initials:

Examiner 2:

K GE Reviewed By:

ANII Reviewed By:

Level:

DatE Date:

Date:

e:

Cal/Exam Date:

5/21/2003 Page 2 of 4

Ultrasonic Calibration and Examination Record GE NUCLEAR ENERGY Manual Piping and Components Site/Unit: Columbia Generating Station Outage:

R16 Data Report Number: R1-064 Data Sheet Number:

UT-118 Linearity Sheet:

L-04 Calibration Data for Block: UT-7 Procedure:

PDI-UT-2/Site Specific ss Material Ultrapel I Couplant:

225291 Thermometer S/N 2_

S CA

!4 1.140 ize Thick 00325 ouplant batch 72°F Cal Temp.

Calibration Initial Cal:

Cal Check:

Cal Check:

Final Cal:

Cal Time 1924 2223 rN/A 2355 Ver / Rev: 9._

DRR: NIA DAC Construction Search Unit Data RTD 00-407 2(10x18) mm/RecL Manufacturer:

Serial Number Size/Shape:

0.45 in.

60.

W00 Incident Point:

Nominal Angle:

Measured Angle:

2.0 MHz TRL 2-Aust Long 2

Frequency:

Style:

Mode:

Elements:

Search Unit Cable RG-174 6_

0 Cable Type:

Length:

Connectors:

Instrument Settings Scan Direction Cal Reflector Signal Amplitude Signal Sweep:

Signal dB:

Ax ID Notch 80%

5.2 Div 64.0 dB Sweep 0-10 =

5.0 in.

Metal Path Calibration Verification Field Simulator Block S/N:

CAL-RHOM-066 Reflector 2" Radius N/A Amplitude 80%

N/A Gain (dB) 33.4 NIA Sweep (SD) 40

_N/A Acceptable Linearity performed :

4/7/2003 Exam Data for Weld: 24RRC(2)B-1O ELL TO PUMP Configuration:

Staveley / Sonic 136P Maufacturer/Model:

1.08 in.

0.244inJusec.

Delay:

Velocity:

707H Serial Number:

I 4KHz Filter:

Rep Rate:

500 Ohms Damping:

Dual Mode:

5.0 in.

Range:

Off Reject:

250 ns Pulser:

2.25 MHz Frequency:

Exam Comments I Limitations:

OD Exam Surface:

76*F 225291 Exam Temp.

Exam Thermometer Exams perfomed at reference sensifviWly to maintain 5% to 20% noise level.

Previously reconred geometry observed below recordable levels.

No exam performed from downstream side due to component configuration.

Actual Cal Block "T'is 1.410W Axial UPST Scan dB ý Recordable Exam Circ DNST Indications Angle Axial UPST 64 ti!

for 4

4 4

4-4 4

Exam Start 2224 Exam End:

2236 In0M E

Dicke Initials:

Examiner:

Initials:

Examiner 2:

y Michael Level:

NIA Level:

NIA K

GE Reviewed By:

Rev ed y:

2-N7 0/-, /1 Level:

Date:

Date:

Date:

Page 3 of 4 Cal/Exam Date:

5/21/2003 ANII Reviewed By:

Wall Thickness Profile Sheet Crown Height:

Crown Width:

.1.£ 1.8'..*

24.o" 77.5..

ELBOW PIPE UPST Component:

DNST Component:

Nominal Diameter:

Weld Length:

C6Mroj2O) f-AA~AdA C*A" Pat.Wooui PArRf.

/_

~

N

~

\\

I Date bwei By:

Date:

ANII I

REQUEST 21SI-32 ATTACHMENTS A THROUGH G Attachment Attachment F 21SI-32-17 Weld Identification 24RRC(2)B-i 1/8CAP-1 ISI Diagram RRC-101-2 NDE Data Report R17-014 21SI-32-18 Weld Identification 24RRC(2)B-1 1/4RRC(4)-4S ISI Diagram RRC-101-2 NDE Data Report R16-058 21SI-32-19 Weld Identification 24RRC(2)B-8/4RRC(8)-4S ISI Diagram RRC-101-1 NDE Data Report R16-068 21SI-32-20 Weld Identification 24RRC(2)B-8/4RRC(4)-4S ISI Diagram RRC-101-1 NDE Data Report R16-067

REQUEST 21SI-32 ATTACHMENTS A THROUGH G Attachment 21SI-32-17

2

3 4

5 7

B 9

10

1. SEE RRC-P-IB DETAIL, DWG RRC-TO3, FOR PUTMP SUPPORT DETAILS.

2. EXTEND LEAKAGE EXAM THROUGH CONTAINMENT PENETRATION (X-41d) THROUGH EXCESS FLOW CHECK VALVE TO INSTRUMENT TUBING CONNECTION.

3. ACCESS TO WELD 24RRCI1)B-13 REQUIRES REMOVAL OF RCR-SE.

4. SPECIAL CLAMP WITH HB.-? & SB-7 ATTACHMENTS.

S. WELD 24RRC(1)B-1/SfBAP-I IS FITTING TO FITTING.

6. WELD 24RRC(1)9-18B12CAP-1 IS FITTING TO FITTING.

7. WELD 24RRC(I)B-I? IS FITTING TO FITTING.

B. RRC-V-SOB HAS TWELVE (12) 2 3/4' X 15' BODY TO BONNET STUDS.

B. CAP TO NOZZLE WELDS ARE CLAD ON THE ID IN THE WELD AREA. SEE REFERENCE DWGS 131 C 758B 2 131 C 7O89.

10. PIPING FRO" PUMP DISCHARGE TO RRC-V-STB IS MIN WALL 1.21B.

PIPING FROM RRC-V-TBB TO WELD 24RRC(1)B-19 15 MIN WALL 1.140.

11. RRC-SB-1S, RRC-SB-T?.

RRC-SB-lB & RRC-SB-66 WERE DELETED PER BDC B7-0244-OJ-026.

REFERENCES, 151 - 230-2 GENERAL ELECTRIC DRAWINGS 761 E 424 REV 2 762 0 538 SH 1 REV 3 762 E 538 S

2 REV 3 761 E 735 REV 6 131 C 7588 REV 3 131 C 7589 REV S 131 C 7592 REV 3 CBI NUCLEAR CO.

48 REV 4 NT NOZZLE ASSEKBLY BOVEE CRAIL/GERI BC/G-218 REV B 90" KEYPLAN IBSO 270" QUALITY CLASS.

I ASME CODE CLASS.

ENGR D TIMMINS IDRAWN.

K-McA I DATE, 3 WASHINGTON PUBLIC POWER SUPPLY SYSTEM THIS DRAWING IS INTENDED FOR USE IN PRESERVICE AND INSERVICE INSPECTIONS PROGRAMS ONLY.

MATERIAL HATL CAL TYPE BLOCK SPECIFICATION TYPE Nn RICHL.AND),

WAS*HINGTON 99352 WNP-2 WELD 2 COMPONENT ENTIFICATION DIAGRAM REACTOR RECIRCULATION LOOP B H

j)'Ic' i/C44'1 AReport No.:

EXAMINATION

SUMMARY

SHEET R17-014 W

GE NUCLEAR ENERGY Site:

Columbia Generating Station Component ID:

24RRC(1)B-11/8CAP-1 Outage:

R R17 SWL TO CAP System REACTOR RECIRC LOOP B ASME Cat.:

B-J A ASME Item B9.31 Aug Req N/A Exams Data Sheet Cal Sheet Procedure Calibration Block Examination Cert Level Date Performed Personnel 600 RL UT-037 N/A GE-UT-105 8746 James Bullen II 5/12/2005 450 Long.

UT-038 N/A GE-UT-105 8746 James Bullen II 5/12/2005 Examination Results:

During the manual ultrasonic examination of the above referenced weld, no reportable indications were recorded utilizing 450 and 600 refracted longitudinal wave search units.

This examination meets the requirements of ASME Section XI 1989 and 1995 Edition with the 1996 Addenda.

50% Code coverage was achieved.

Examination results were compared to data report N/A from N/A outage with D

No Change These examinations were performed under Work Order:

01082497 01 ED Change This Summary d the following data sheets have been reviewed and accepted by the following personnel:

tRWP:

NIA 0t; Dose:

N/A mr.

re ared By:

Level Date:

eview:

D GE Review By:

Level:

Date:

ANIII Reviee:

Date:

Page 1 of 4

1:7

Ultrasonic GE NUCLEAR ENERGY Me Calibration and Examination Record inual Piping and Components Site/Unit: Columbia Generating Station /2 Outage:

R17 Report Number:

R17-014 Data Sheet Number:

UT-037 Linearity Sheet:

L-002 Calibration Data for Block: 8746 SS304 N/A 0.50" to 2.0" Material Size Thickness OOltraael 00325 Couplant:

Couplant batch 241980 78' F Thermometer S/N Cal Temp.

DAC Construction Scan Direction Ax Cal Reflector 1,0 Signal Amplitude 80%

Signal Sweep:

4.5 Div Signal dB:

36.8 dB Sweep 0-10 =

4.0 in Metal Path Calibration Initial Cal:

Cal Check:

Cal Check:

Final Cal:

Cal Time 1022 N/A N/A 1340 Procedure:

GE-UT-105 Ver /Rev: _

DRR: NIA Search Unit Data RTD 04-304 2(10x18) mm/Rect.

Manufacturer:

Serial Number Size/Shape:

0.5 in.

60.

60.

Incident Point:

Nominal Angle:

Measured Angle:

2.0 MHz 60 °TRL 2-Aust RL 2

Frequency:

Style:

Mode:

Elements:

Search Unit Cable RG-174 6-0 Cable Type:

Length:

Connectors:

Instrument Settings Calibration Verification Field Simulator Block S/N:

N/A Panametrics / Epoch 4 Maufacturer/Model:

0.2334 in/usec Velocity:

Reflector N/A N/A Amplitude N/A N/A Gain (dB)

NIA N/A Sweep (SD)

NIA N/A 11.88us Zero:

Auto Rep Rate:

400 Oh, Dampin ns g:

031573011 Serial Number:

0.8 - 3.0 MHz Narrowband Filter:

So./Max Pulser/Energy:

P/E y:

Mode:

Fullwave Rectification:

Off Reject:

4.0 in Range:

2.0 MHz Frequency Acceptable Linearity performed :

4/18/2005 Exam Data for Weld: 24RRC(1)B-11/8CAP-1 SWL TO CAP Configuration:

OD 82' F 241980 Exam Surface:

Exam Temp.

Exam Thermometer Exam Comments / Limitations:

Exams perfomied to maintain 5% to 20% noise IWal.

No exam performed from upstream side due to component configuration.

Achieved 50% Code coverage.

1210 Exam End:

1220 iW__ oil,4l6S Level:

Date:

Date:

Date:

Page 2 of 4

Ultrasonic Calibration and Examination Record GE NUCLEAR ENERGY Manual Piping and Components Report Number:

R17-014 Site/Unit: Columbia Generatinq Station /2 Data Sheet Number:

UT-038 Outage:

R17 Linearity Sheet:

L-002 Calibration Data for Block: 8746 Procedure:

GE-UT-105 Ver/Rev: f DRR: NIA SS304 Material Ultragel I Couplant:

241980 Thermometer S/N N/A 0.50" to 2.0" Size Thickness 00325 Couplant batch 78°F Cal Temp.

Calibration Initial Cal:

Cal Check:

Cal Check:

Final Cal:

Cal Time 1020 N/A NIA 1342 RTD Manufacturer:

0.5 in.

Incident Point:

1.0 MHz Frequency:

Search Unit Data 98-228 2(10x18) mm/Rect Serial Number Size/Shape:

45.

45.

Nominal Angle:

Measured Angle:

45°TRL 1-Aust Long.

2 Style:

Mode:

Elements:

DAC Construction Scan Direction Cal Reflector Signal Amplitude Signal Sweep:

Signal dB:

Sweep 0-10 =

Ax

/.0 80%

5.0 Div 38.1 dB 2.0 in Search Unit Cable RG-174 6'

0 Cable Type:

Length:

Connectors:

fetal Path Calibration Verification Field Simulator Block S/N:

N/A Reflector N/A N/A Amplitude N/A N/A Gain (dB)

NIA N/A Sweep (SD)

N/A N/A Acceptable Linearity performed :

4/18/2005 Instrument Settings Panametrics /Epoch 4 Maufacturer/Model:

0.2316 in/usec Velocity:

10.09 us Zero:

Auto Rep Rate:

400 Ohn Dampin IS g:

Fullwave Rectification:

off Reject:

2.0 in Range:

1.0 MHz Frequency:

031573011 Serial Number:

0.8 - 3.0 MHz Narrowband Filter:

S. /Max Pulser/Energy:

PIE Mode:

Exam Data for Weld: 24RRC(1)B-118/CAP-1 SWL TO CAP Configuration:

OD 82* F 24198 Exam Surface:

Exam Temp.

Exam Therm

'0 ometer Exam Comments / Limitations:

Exams performed to maintain 5% to 20% noise level.

No exam performed upstream side due tD component configuradon.

Achieved 50% code coverage.

1224 Exam End:

1232 Level:

Date:

ate Date:

Pag e 3

of 4 t

Wall Thickness Profile Sheet S 1.5" Crown Height:

Crown Width:

Nominal Diameter:

Weld Length:

FLUSH 1.3" 8.0,"

27.5" SWL CAP UPST Component:

DNST Component:

/

\\

S \\N/L 0 vroj C/ AP

/

-I---

/L

REQUEST 21SI-32 ATTACHMENTS A THROUGH G Attachment 21SI-32-18

4 7

8 9

10 CONT ON RC-102-6 12"RRC(l)-45 CREF) 0 9

1. SEE RRC-P-1A DETAIL. DWG RRC-103.

FOR A24 X 12

- RED (REF))~>

2. EXTEND LEAKAGE EXAM THROUGH CONTAINMENT 2

PENETRATION (X-Aid) TIQOUGH EXCESS FLOW CENT OH RRC-102--3

-CHECK VALVE TO INSTRUJMENT TUBING CONNECTION.

16RRC(I1-4S (REP)

3. ACCESS TO WELD 24RRC(I)B--13 REOUIRES REMOVAL OF RCR-6E.

t EL 521 (REP)

4. SPECIAL CLAMP WITH HB-? I SB-? ATTACHMENTS.

24 X 16' CROSS (REF)-"

5. WELD 24RRC(I1)B-I1/8CAP-1 IS FITTING TO FITTING.

6. WELD 24RRC(1)B-1B/12CAP-1 IS FITTING TO FITTING.

7.

WELD 24RRC(I)B-17 IS FITTING TO FITTING.

B. RRC-V-608 HAS TWELVE (12) 2 3/4' X 15I BODY TO BONNET STUDS.

ý 24RRC(1)8-lgLU

9. CAP TO NOZZLE WELDS ARE CLAD ON THE ID IN THE WELD AREA. SEE REFERENCE OWGS 131 C

--r8 I.

131 C 7589.

10. PIPING FROM PUMP DISCHARGE TO RAC-V-67B IS RrE.gs-Ct MIN WALL 1.218.

PIPING FRON RRC-V-76B TO WELD 24RRC(1)8-I8 IS MIN WALL 1.140.

C

11. RRC-SO-15. RRC-SB-I7, RRC-SB-18 X RRC-SB--6i SEE NOTE 1 REC-SB-B-,ý S-WERE DELETED PER BOC 97-0244-OJ-026.

REFERENCES.

.24RRlIB--11/3/4dPT-NOISS IS 230-2 SEENOTE2GENERAL ELECTRIC E

RAWINGS 761 E 424 REV 2

"./-24RRC(,)B.-18/,2RRC()-,S 762 E 538 SN 1 REV 3

(

1 B I-,

CONT ON ARC-10?

7626 E3M 9H2 REV 3

\\

(8) 1

)r, 112*RRC.7)-4S RE) 761 E 735 REV 6 CONT ON RRC-102-1 24RRC(1)8-18/12CAP-1 131 C 7588 REV 3 24'REC(2)-4S (REP)

(SEE NOTES 6 9 )

1'.131 C 7589 REVS5 EL S12-131 C 7592 REV 3 4RRC(8 18-1 24RRCC()B-16/12CAP

'_1 CSI NUCLEAR CO.

P 24 RRC 4) -

"1' L

-z 24 RR!c(1) 8-11/4RRC(R)-4S

,C l M.E C.

224RRC)B-11LC

-24CR(1)8-12LU 46 REV 4 NI NOZZLE ASSEMBLY 24RC(1)-11/BCAP-24RRC(1)B-12

-,.OVEE CRAIL/GERI 24RC0)-II8CA-I f

R'-'-W/'-4'BC/G-218 REV B (SEE NOTES 5 9 9)

SEE SN --

102

• 24RR C(I )&-1BLD 90" "E*,

RRCV..6O00.

(

24RRC I)S'-1I3

/

• -24 AR(1)B-181.UO E

A:

RC-V-B B34"4 1

4U (SO)

-4S24RR(E)P-8LO

-4 R2\\ARC81)3-I

/I v180 RCR-?

"0I270"

- IQU AL ITY CLASS.

1 A SME.

CO DE CL AS S,

WENG.

0 TiMSIN DRAWN,,-MeA NTATE 3-30-7 P4ATFO3*-

24 B-5*FRWASHINGTON PUBLIC POWER USE IN PRESERVICE AND INSERVICE SUPPLY SYSTEM INSPECTIONS PROGRAMS ONLY.

R LANO, NWASINETON 52 NO(

NONOT MATERIAL 4 MATL CAL WNP-2 MPiPiNG SYSTEM DIA CH WALL BLOCK WELD I COMPONENT H

6 9-22-94 ADDED NOTE 11. MODIFIED ACCORDINGLY.

K-MCA DPR DDW (IN)

THK SPECIFICATION TYPE NO IDENTIFICATION DIAGRAM 5

12-9-92 ADDED 'B' TO ALL RCR'S.

K-cA EPAR DRW 24"RRC(1)-45 24 XXX SEE NOTE 10 SA 358 GR 304 CL 1 5S UT-7 TITLE?

4 10-16-87 I'0 C.-O(-WE.

1" C916I(1 AT 9(C-V-589. 0 C-IU-7 TO 9

SPRRRC-93-8 t 58-SB-U TO S RS.

88 RESPU.W.

M M A' W K-McA OPR TFH 4"RCCB)-45 4

80 0.337 SA 312 TP 304 S

, :1-29 REACTOR RECIRCULATION LOOP B 3

10-13-93 REVISED AS NOTED ADDED CEYPLAN K-McA OPR TFH CAP I2 GO 0.088 SA 403 GR WP 304 5

UT-19 2

11-5-60 REVISED AS NOTED K-lcA TFH DWP CAP 6

60 0.5 SA 403 OP WP 304 55 UT-25 NO,_

_-2 NO DATE REVISION BY CH-D APVD IRRC-102-2 REV 5

Report No.:

EXAMINATION

SUMMARY

SHEET R16-058 GE NUCLEAR ENERGY Site and Unit.

Columbia Generating Station Component ID:

24RRC(1)B-1114RRC(8)-4S Outage:

R16 PIPE TO SWL System.

RRC ASME Cat.:

B-J ASME Item B9.31 Aug Requirements:

NIA Exams Performed Data Sheet Cal Sheet Procedure Calibration Block Examination Cert Level Date Personnel 45° Shear UT-069 N/A PDI-UT-2/Site Specific UT-7 Dickey Michael II 5/119/2003 600 Long UT-070 N/A PDI-UT-2/Site Specific UT-7 Dickey Michael II 5/19/2003 Examination Results:

During the manual ultrasonic examination of the above referenced weld, no reportable indications were recorded utilizing the 450 and 60' search units.

This examination is acceptable per the requirements of ASME Section Xl, 1989 Edition, no Addenda and the 1995 Edition, 1996 Addenda with modifications as stated in 10CFR50.55.

50% Code coverage was obtained.

Previous data was reviewed prior to this summary.

Examination results were compared to data report 1 RRU-079 from R-1 outage with W

No Change These examinations were performed under Work Order:

01044925-01 Li Change This Summary and the following data sheets have been reviewed and accepted by the following personnel:

f Date:

Ut y-Date:

Reviewed By:

Level:

Date:

ANII Reviewed By:

Date:

Page 1

of 4

G Ultrasonic Calibration and Examination Record SGE NUCLEAR ENERGY Manual Piping and Components Data Report Number: R16-058 Site/Unit: Columbia Generatinq Station Data Sheet Number:

UT-069 Outage:

R16 Linearity Sheet:

L-04 Calibration Data for Block: UT-7 Procedure:

P01-UT-21Site Specific SS 24" 1.140" Material Size Thick Ultra gel I Couplant:

225291 Thermometer S/N 00325 Couplant batch 720 F Cal Temp.

Calibration Initial Cal:

Cal Check:

Cal Check:

Final Cal:

Cal Time 2154 2352 N/*

0028 Search Unit Data Ver /Rev: 2-1 DRR: NIA KBA Manufacturer:

0.35 in.

Incident Point:

OOH8Y3 Serial Number 45' Nominal Angle:

O.50"/Round Size/Shape:

46_

Measured Angle:

I Elements:

DAC Construction 1.5 MHz Comn-G Frequency:

Style:

Shear Mode:

Scan Direction Cal Reflector Signal Amplitude Signal Sweep:

Signal dB:

Sweep 0-10 =

4.0 i Ax ID Notch 80%

5.1 Div 32.2 dB In.

Metal Path Search Unit Cable RG-174 6'

0 Cable Type:

Length:

Connectors:

Instrument Settings Calibration Verification Field Simulator Block S/N:

CAL-RHOM-066 Reflector 2" Radius N/A Amplitude 8091 N/A Gain (dB) 20.4 N/A Sweep (SD) 1.0 N/A Acceptable Linearity performed :

4/7/2003 Exam Data for Weld: 24RRC(1)B-11/4RRC(8)-4S PIPE TO SWL Configuration:

Staveley / Sonic 136P Maufacturer/Model:

0.279 in.

0.126in./usec.

Delay:

Velocity:

707H Serial Number:

I 4KHz Filter Rep Rate:

500 Ohms Damping:

PIE Mode:

4.0 in.

Range:

Off Reject:

334 ns Pulser:

2.25 MHz Frequency:

Exam Comments I Limitations:

o0 Exam Surface:

720 F 225291 Exam Temp.

Exam Thermometer Exams performed to maintain 5% to 20% ID roll.

ID geometry observed below recordable levels.

No exam performed from downstream side due to component configuration.

Actual Cal Block "Tris 1.410."

2353 Exam End:

0004 D£M Initials:

Li Level:

Level:

Date:

Examiner:

N/A Initials:

Examiner 2:

N/A Level: 6 GE Reviewed By:

itR ed By:

"7// I'm~

Date:

Cal/Exam Date:

5/19/2003 Page 2 of 4 ANII Reviewed By:

G Ultrasonic Calibration and Examination Record GE NUCLEAR ENERGY Manual Piping and ComponentsI Site/Unit: Columbia Generating Station Outage:

R16 Data Report Number: R16-058 Data Sheet Number:

UT-070 Linearity Sheet:

L-04 Procedure:

PDI-UT-2/Site Specific Ver / Rev: C/1 DRR: NIA Calibration Data for Block: UT-7 SS 24-1.140" Calibration Cal Time Material Size Thick Initial Cal:

2136 ltaeII0032_55 Cal Check:

0005 Couplant:

Couplant batch 225291 72*F Cal Check:

N/A Thermometer S/N Cal Temp.

Final Cal:

0030 RTD Manufacturer:

0.45 in.

Incident Point:

2.0 MHz Frequency:

Search Unit Data 00-407 Serial Number 60.

Nominal Angle:

TRL 2-Aust Lon Style:

Modi 2(10x18) mm/Rect Size/Shape:

W._

Measured Angle:

Een 2

B:

Elements:

Scan Direction Cal Reflector Signal Amplitude Signal Sweep:

Signal dB:

Sweep 0-10 =

DAC Construction Ax ID Notch 130%

5.2 Div 71.0 dB 5.0 in.

Metal Path Search Unit Cable RG-174 6'

0 Cable Type:

Length:

Connectors:

Calibration Verification Field Simulator Block S/N:

CAL-RHOM-066 Reflector 2" Radius N/A Amplitude 80%

N/A Gain (dB) 40.0 N/A Sweep (SD) 4.0 N/A Acceptable Linearity performed :

4/7/2003 Exam Data for Weld: 24RRC(1)B-11/4RRC(8)-4S PIPE TO SWL Configuration:

OD 72°F 225291 Exam Surface:

Exam Temp.

Exam Thermometer 1.01 De 5.

Ri R*

Instrument Settings Staveleyv Sonic 136P Maufacturer/Model:

8 in.

0.24inJusec.

I lay:

Velocity:

Filter:

.0 in.

250 ns ange:

Pulser:

Off 2.25 MHz eject:

Frequency:

70711 Serial Number:

4KHz Rep Rate:

500 Ohms Damping:

Dual Mode:

Exam Comments I Limitations:

Exams perfomed at reference senstvity to maintain 5% to 20% noise leveL Supplemental 600 RL examination due to single side access No exam performed from downstream side due to component configuwaton.

Actual Cal BIock "T"is 1.410."

Axial UPST Scan dB I Recordable Exam Circ DNST Indications Angle Axial UPST 71 1

NRI

-_60.

+

t Exam Start:

Exam End:

0015 A1 OEM Dickey Michael Initials:

Examiner:

N/A Initials:

Examiner 2:

Y Level:

N/A Level: 6 GE Reviewed By:

Level:

Date KUt ty Reviewed By:

Zate:

ANII Reviewed By:

Date:

Cal/Exam Date:

511912003 Page 3 of 4_

Wall Thickness Profile Sheet Crown Height:

Crown Width:

Nominal Diameter:

Weld Length:

FLUSH 1.4" 24.0" 48.0" PIPE SWEEPOLET UPST Component:

ONST Component:

46 ss L4SS OL' I

\\

/

j -

REQUEST 21SI-32 ATTACHMENTS A THROUGH G Attachment 21SI-32-19

',**TI

/

I 2

3 4

5 6

7 8

9 10 tI

'11ýN 24RRC 1216-31.0!

24RRC (2) &-4LU I

-24R1C (2)8-3LDO0 24RRC (239 5-EUOS ý

/

24Rt)-

24EEC123B-4

-L (SEE NOTE 2) 241SEC(236-2L0 (SEE NOTE 12) 24RR(2)84LD24E1C(236-1 (SEE GE NOT 1

ý24ERC(216-2 (SEE NOTE 1)

PLATFOR SHIELD WALL EL 530(E'NTE9 2AIEC 2 14 WELDED LUGIS) -Ael A

90' PLATFORM EL 524' C

24RRC (2) B-S/3/4PS-NOI 68 (SEE N

-itE 3-24RRC(2)0-S/3/4PX-t FlV NOTESý

1. WELD 24RACC2)B-1 UTILIZES CAL BLOCK UT-lOT.

2. ACCESS TO WELD 24RRC(2)B-4 REQUIRES REMOVAL OF RCR-lB.

3. EXTEND LEAKAGE EXAM THROUGH CONTAINMENT PENETRATION (X-690) THROUGH EXCESS FLOW CHECK VALVE TO INSTRUMENT TUBING CONNECTION.

4. ACCESS TO WELD 24REC(2)-E6 REQUIRES REMOVAL OF ARC-38.

S. EXTEND LEAKAGE EXAM THROUGH CONTAINMENT PENETRATIONS (X-62').

(0-62d), (C-75.) 9 CX-TSF) THROUGH EXCESS FLOW CHECK VALVES TO INSTRUM.ENT TUBING CONNECTION.

6. EXTEND LEAKAGE EXAM THROUGH CONTAINMENT PENETRATION (X-41c) THROUGH EXCSS FLOW CHECK VALVE TO INSTRUMENT TRING CROlNECT ION.

7. EELD 24RRECI1)-7 IS FITTING TO FITTING.

8. EELD 24RRC(1)B-10 IS FITTING TO FITTING.

N. FOR NOZZLE ASSEM13LY ETAIL SEE DUG RPV-IOS.

10. PIPING PURCHASED TO HIM WALL SPEC-O.10.

11. WELD IS STAMPED 24RRCI1)B-2.

12. WELD IS STAMPEO 24RC (1)B-2LD.

13. NRC-SB-I, RRC-SB-2, RRC-SB-16 & RRC-SB-25 WERE DELETED PER BDC 67-0244-UJ-02E.

14. ADDED FE-24 PER QOC 55-0753-OA-303.

GERNC S,

ISI - 230-2 GENERAL ELECTRIC DRAWINGS 761 E 424 REY 2 E62 E 538 SH1 REV3 762E 538 5H2 REV3

?61 E 73S REV 6 131 C 85 REV 4 131 C 757 REV 3 C81 NUCLEAR CO.

48 REV 4 N1 NOZZLE ASSEMBLY QOVEE CRAIL/G*RI BC/G-21?

REV 10 E0" A

A A

RCR-3BPLATFORM 24RRCC23B6E/IPI (1)-4Eco

.~--24RRC(2)9-S.U (SEE N0TE 4)

EL 501' 24RRC(2)B-6/TPICI-S

ý 4R()-

ERECCB(WI 280-ZG

~

24R5C (2) B6-9.0

\\,....44RCI2)B6G/FIP (11-40.

y (SEE NOTE 5) (TX? FOR 4)

-24R "21p-LDI 4RC(D2-F 24j 24RCC2B-83/4E-N288RRC2Y

-LU 24RR C2)B-B3/4dT-MQ 582

=C.2 I

-R/TFI 1) -A d (SEE2410 NOTE E-OCD(28-L 2424R (21I-4 DIE4RR 1 6 -4S

ý23 EEC~RR 238/3/0-28B43-

!..24D~lC2IB46/C(2H NRC-3B COINSPECTIO NS1F9 0.

p1-:

IB" AN 100O' OUALITY CLASS, 1

1 ASME CODE CLASS, I

S INTENDED FOR ICE AND INSERVICE OGRAIS ONLY.

ENGR. D TIMIMINS I DRAWN, K-MCA I DATE, 3-29-?6 WASHINGTON PUBLIC POWER SUPPLY SYSTEM

RICHLAND, WASHINGTON 99352 5 19-22-941 ADDED NOTES 13 & 14. MODIFIED ACCORDINGLY.

IK-McAj DPR I DW PIPING SYSTEM NOR DIA (IN)

SCH NoH WALL THK MATERIAL MATL SPECIFICATION TYPE CAL BLOCK NO WNlP-2 EELD & COMPONENT IDENTIFICATION DIAGRAM 4 111-13-921 ¶(..O h~i-jIMMATI MiW-I?.

IK-VAA I SEE1 R

24'RRC (21-4S 24 000 SEE NOTE 101 55 35 SE 304 C3 1 SS UT-? I...

3 X-l-7j fýO11 REFEGK E. (0165 M1-HR-1 TO

-M

~

CRA~

F 3

OTE 5St PI CONNECTION ON N0' ELBOW MTE K

DAI FH1 4RCB -4S80 1

.37 IA 12 T 30 TITLE.

REACTOR RECIRCULATION LOOP 6 2

111-14-831 REVISED AS NOTED. ADDED KEYPLAN I LUGS.

I K-GA D

I TFH 1

I1-5-80 ASDED NOTE 9 1.--Kc rFj T OH 1

2 NO DATE REVISION BY CHl I APVD

Report No.:

EXAMINATION

SUMMARY

SHEET R16-068 GE NUCLEAR ENERGY Site and Unit:

Columbia Generating Station Component ID:

24RRC(2)B-8/4RRC(8)-4S Outage:

R16 PIPE TO SWL System RRC ASME Cat.:

B-J ASME Item B9.31 Aug Requirements:

NIA Exams Performed Data Sheet Cal Sheet Procedure Calibration Block Examination CertDate Personnel 45' Shear UT-1 13 N/A PDI-UT-2/Site Specific UT-7 Michael Kemp II 5/21/2003 60' Long UT-114 N/A PDI-UT-2/Site Specific UT-7 Michael Kemp II 5/21/2003 Examination Results:

During the manual ultrasonic examination of the above referenced weld, no reportable indications were recorded utilizing the 450 and 600 search units.

This examination is acceptable per the requirements of ASME Section Xl, 1989 Edition, no Addenda and the 1995 Edition, 1996 Addenda with modifications as stated in 10CFR50.55.

50% Code coverage was obtained.

Previous data was reviewed prior to this summary.

Examination results were compared to data report 1RRU-082 from R-1 outage with

[

No Change These examinations were performed under Work Order:

01044925-01 Ii Change This Summary and the following data sheets have been reviewed and accepted by the following personnel:

r*

• /eB Level:

Date:

Uti I eviewed By Date:

Reviewed By:

Level:

Date:

ANII Reviewed By:

Date:

Page 1 of 4

Ultrasonic Calibration and Examination Record GE NUCLEAR ENERGY Manual Piping and Components I

I Site/Unit: Columbia Generating Station Outage:

R16 Data Report Number: R16-068 Data Sheet Number:

UT-113 Linearity Sheet:

L-12 Calibration Data for Block: UT-7 SS 24' 1.140' Calibration Cal Time Material Size Thick Initial Cal:

204__

7 Ultragel 00325 Cal Check:

0030 Couplant:

Couplant batch 280504 0.F Cal Check:

N/A Thermometer SIN Cal Temp.

Final Cal:

0146 DAC Construction Scan Direction Ax Ax Cal Reflector ID Notch OD Notch Signal Amplitude 80%

15%

Signal Sweep:

5.1 Div 10.0 Div Signal dB:

29.8 dB 29.8 dB Sweep 0-10 =

4.0 in.

Metal Path Procedure:

PDI-IUT-2Site Specific Ver / Rev: 2_1 DRR: NIA Search Unit Data KBA OOMPX8 0.507/Round Manufacturer:

Serial Number Size/Shape:

0.4 in.

45o 45' Incident Point:

Nominal Angle:

Measured Angle:

1.5 MHz Comn-G Shear I

Frequency:

Style:

Mode:

Elements:

Search Unit Cable RG.174 6-0 Cable Type:

Length:

Connectors:

Calibration Verification Field Simulator Block S/N:

CAL.-RHOM-069 Reflector 1" Radius 2" Radius Amplitude 60%

60Y Gain (dB) 22.0 22.0 Sweep (SD) 2.S 5.0 Acceptable Linearity performed:

515/2003 Instrument Settings Staveley / Sonic 136P Maufacturer/Model:

0.342 in.

0.12lnlusec.

1 Delay:

Velocity:

Filter:

4.0in 334 ns 5

Range:

Pulser:

Off 2.25 MHz Reject:

Frequency:

136-7661 Serial Number:

4KHz Rep Rate:

o00 Ohms Damping:

PIE Mode:

Exam Data for Weld: 24RRC(2)B-8/4RRC(8)-4S PIPE TO SWL Configuration:

OD 780 F 225045 Exam Surface:

Exam Temp.

Exam Thermom eter Exam Comments I Limitations:

Exams performed to maintain 5% to 20% ID roll.

ID geometry observed below recordable levels.

No exam perforned from downstream side due to component colrgurawln.

No countetbom detected.

Actual Cal Block 'T"is 1.410."

31 Exam End:

0040 Level:

Date:

Date:

tOýý4ý0_

Page 2 of 4 Date:

Cal/Exam Date:

5/21/2003 4-

G Ultrasonic Calibration and Examination Record "0

GE NUCLEAR ENERGY Manual Piping and Components Sit6'Qjir: Columbia Generating Station Outage:

a'16 Data Report Number: R16-068 Data Sheet Number:

UT-114 Linearity Sheet:

L-12 Calibration Data for B1o3...UT-.7 SS 24" 1.140_.

Material Size Thick 11ltragel 00325 Couplant:

Couplant batch 225048 Thermometer S/N Cal Temp.

Procedure: PDI.UT-2/Site Specific Ver / Rev: W/_

DRR: NIA q-alibration Cal Time lnit4*,Cl:

2122 Cal Chieu,..

0042 Cal Check:

Final Cal:

0147 RTD Manufacturer:

0.45 in.

Incident Point:

2.0 MHz

\\requency:

Search Unit Data 98-172 Serial Number two Nominal Angle:

TRL 2-Aust Lon Style:

Mod 2(10x18) mm/Rect Size/Shape:

6.0 Measured Angle:

g2 e:

Elements:

DAC Construction Scan Direction Ax Cal Reflector ID Notch Signal Amplitude 80%

Signal Sweep:

5.2 Div Signal dB:

71.2 dB Sweep 0-10 =

5.0 in.

Metal Path Calibration Verification Field Simulator Block S/N:

CAL-RHOM-069 Search Unit Cable I.N_--174 6_'

Cable ")Yne:

Length:

Connectors:

Instrument Settings Staveley / Sonic 136P 136-7661 Maufacturer/Model:

Serial Number:

1.21 In.

0.239in.$usec.

1 4KHz Delay:

Velocity:

Filter:

Rep Rate:

5.0 in.

250 ris 500 Ohms Range:

Pulser.

Damping:

Off 2.25 MHz Dual Reject:

Frequency:

Mode:

Acceptable Linearity performed:

V512 Exam Data for Weld: 24RRC(2)B-8/4RRC(8)-4S PIPE TO SWL Configuration:

OD 78* F 225046 Exam Surface:

Exam Temp.

Exam Thermometer Exam Comments I Limitations:

Exams performed at reference sensitvify to maintain 5% to 20% noise level.

ID geometry observed below recordable levels.

No exam performed from downstream side due to component configuration.

No counterbore detected.

Actual Cal Block 7" is 1.410."

/

0042 Exam End:

0051 Level:

Date:

Date:

Page 3 of 4 Cal/Exam Date:

V/21/2003 ANII Reviewed By

Wall Thickness Profile Sheet Crown Height:

Crown Width:

1.11 0.0's 32.0' PIPE SWL UPST Component:

ONST Component:

Nominal Diameter:

Weld Length:

REQUEST 21SI-32 ATTACHMENTS A THROUGH G Attachment 21SI-32-20

6 a

I 2

4 5

7 8

9 10 N

24ENC (2)B-4LUI-1 24RRC (2) B-4LU]

(SEE NOTE 2) 24RRC (2) B-4LD.

(

4 CR-10 24RRC (2) B-S.OL -....

24RRC (2)B-24RRC (21BSL RRC46-1-,

(4 WELDED LUG(S) )

PLATFORM EL 524' 24K C(2) B-S/3I4PS-NO1 868 (SEE NOTE 3)~C 24RRC (2) B8-310 I 24E 2) 6-31003L 24RRC(2)B-2LO (SEE NOTE 12) 24REC(2)B-2 (SEE NOTE 11) 24EEC(2)8-1 (SEE NOTE 1)

- ~

SHIELD WALL NIB (SEE NOTE 9) 27 0-".0 wE' N

A A

1. WELD 24RRC(2)B-I UTILIZES CAL BLOCK UT-101.

2. ACCESS TO WELD 24REC(2)B-4 REQUIRES REMOVAL OF RCR-10.

3. EXTEND LEAKAGE EXAM THROUGH CONTAINMENT PENETRATION (X-S9e) THROUGH EXCESS FLOW CHECK VALVE TO INSTRUMENT TUBING CONNECTION.

4. ACCESS TO WELD 24RRC(2)B-6 REOUIRES REMOVAL OF RRC-38.

S. EXTEND LEAKAGE EXAM THROUGH CONTAINWEHT PENETRATIONS (X-62c).

(X-62d),

CS-75.) I CO-iSF) THROUGH EXCESS FLOW CHECK VALVES TO INSTRUMENT TUBING CONNECTION.

6. EXTEND LEAKAGE EXAM THROUGH CONTAINMENT PENETRATION (X-41C) THROUGH EXCSS FLOW CHECK VALVE TO INSTRUMENT TUBING CONNECTION.

?. WELD 24RRC(1)8-7 IS FITTING TO FITTING.

a. WELD 24RRC(1)8-10 IS FITTING TO FITTING.

9. FOR NOZZLE ASSEMBLY DETAIL SEE DWG RPV-lO5.

10. PIPING PURCHASED TO MIN WALL SPEC-O.IO.

11. WLD IS STAMPED 24RRC(1)D-2.

12. WELD IS STAMPED 24REC(IB-2LO.

t3. EEC-Sm-i, RRC-SB-2, RRC-SB-16 9 RRC-SB-25 WERO DELETED PER SDC 87-0244-OJ-02W,

14. ADEED FE-24 PER 8OC SS-0753-0A-303.

REFERENCPES IS

- 230-2 GENERAL ELECTRIC DRAWINGS 761 E 424 REV 2

?62 E 539 DM1 REV 3 762 E 53.

SH 2 REV 3 761 E r35 REV 6 131 C 7586 REV 4 131 C 7587 REV 3 Cll NUCLEAR CO.

46 REV 4 NI NOZZLE ASSEMBLY BOVEE CRAIL/rERI BC/6-217 REV 10 go.

KE BL AN

1. ný1)

A

,-.-RCR-30 PLATFORM R C2......

- 5

....- -24RRC (2 8.6--L U

(SEE NOTE 4)

EL 501' 24 B24FJEC 2)E-A/1F1 B--2 24RR(2)-6/~l(I-4S E:-:24RR 12)

.6 4RRC (8)2Bý2O 24RRC(2)B-SLDO 4

24R (2)

B -

6/P 1 -4S CONE ON 80-102-2 A

24ERC(2)6-7 (SEE NOTE 7) 4*4RC (4)-45 (REP) 24RRCC8)8-(2

-O-

?R C()l/

3 RP 24RCC)B8/34T-% 2 4RR (2).

B-_3/ALI 24RRC(2)E-/B/Ud-"-N I B

24RRCC2)8-ITHIS DRAWING (SEEUS NOTE P)24 RCRT W

NINSPECTIONS PO2 270' QUALITY CLASS.

1 I ASHE CODE CLASS, I

ENGR. D TIMMINS I DRAWN, K-McA I DATE, 3-29-76 S INTENDED FOR VICE AM INSERVICE ROGRAIS ONLY.

WASHINGTON PUBLIC POWER ESUPPLY SYSTEM I CHLAND, WAHINGTON 99M 5 1PIPING SYSTEM 5

9-22-94 ADDED NOTES5 13,& 14. MODDIFlED ACCORDINGLY.

E-IMoA DPR DWN mom DIA (IN)

SCH NOm WALL TI-H MATERIAL RATL CAL BLOCK SPECIFICATION TYPE NO WNP-2 WELD I COMPONENT IDENTIFICATION DIAGRAM AED -I 0

EC-S 1 I C

EIT 4

11-13-92 O1 F' WI IEL tC-S-.

AtE

.MN M

.11-47. I-RCA I ON I DRW I

IMODIFED MY"LA t LOGO. ERLMWtN I

I 24 ERC(2)-4S 24 XXX SEE NOTE 0 1SA 358 RR 304 CL I S

I UT-TITLE 3

10t-ir-e D

IsD m "FEIWECE. CK94ED REC-HN-i X 6I P

4'RC(B)-4S TO "IA" 1 -

C TED NO15 t Pt CO*INECTIOI I

E5'6.50 EOI T-5 K-RcA D A

i 0.37 S 312 TP 304ELBOI vrE-5 lllL*l REACTOR RECIRCULATION LOOP B 2

111-14-831 REVISED AS NOTED. ADDED KEYPLAN I LUGS.

I Kl-fA DPR 1 TFH 1 I11-s-8o iADDE NOTE A K-tA, 4

ow up No.

RRC-"I_02-'!

REV_5 NO DATE REVISION WY CHI-II APVD DWG I

N

4 I

Report No.:

EXAMINATION

SUMMARY

SHEET R16-067 GE NUCLEAR ENERGY Site and Unit:

Columbia Generating Station Component ID:

24RRC(2)B-814RRCf4)-4S Outage:

R16 PIPE TO SWL System RRC ASME Cat.:

B-J ASME Item 89.31 Aug Requirements:

NIA Exams Performed Data Sheet Cal Sheet Procedure Calibration Block Examination Cert Level Date Personnel 450 Shear UT-111 N/A PDI-UT-2/Site Specific UT-7 Michael Kemp II 5/21/2003 60' Long UT-112 N/A PDI-UT-2/Site Specific UT-7 Michael Kemp II 5/21/2003 Examination Results:

During the manual ultrasonic examination of the above referenced weld, no reportable indications were recorded utilizing the 45° and 600 search units.

This examination is acceptable per the requirements of ASME Section X1, 1989 Edition, no Addenda and the 1995 Edition, 1996 Addenda with modifications as stated in 10CFR50.55.

50% Code coverage was obtained.

Previous data was reviewed prior to this summary.

Examination results were compared to data report 1RRU-081 from R-l outage with No Change These examinations were performed under Work Order:

01044925-01

[

Change This Summary and the following data sheets have been reviewed and accepted by the following personnel-Pr ared B Level:

Date:

at Reviwed By:

Reviewed By:

Level:

Date:

ANII Reviewed By:

Date:

Page 1

of 4

4 GE NUCLEAR ENERGY Ultrasonic Calibration and Examination Record Manual Piping and Components 1

Site/Unit: Columbia Generating Station Outage:

R16 Data Report Number: R16-06 Data Sheet Number:

UT-111 Linearity Sheet:

L-12 Calibration Data for Block: UT-7 SS 24' 1.140" Calibration Cal Time Material Size Thick Initial Cal:

2047 Initiall 00325 20.

Q~

i00325 Cal Check:

0059 Couplant:

Couplant batch 22W4 801F Cal Check:

N/A Thermometer S/N Cal Temp.

Final Cal:

0146 DAC Construction Scan Direction Ax Ax Cal Reflector ID Notch OD Notch Signal Amplitude 80%

15%

Signal Sweep:

5.1 Div 10.0 Div Signal dB:

29.8 dB 29.8 dB Sweep 0-10 =

4.0 in.

Metal Path Procedure:

PDl-UT-2/Site Specific Ver / Rev: _1-DRR: NIA Search Unit Data KBA QOMPX8 0.50 /Round Manufacturer:

Serial Number Size/Shape:

0.4 In.

450 450 Incident Point:

Nominal Angle:

Measured Angle:

1.5 MHz Com-c Shear I

Frequency:

Style:

Mode:

Elements:

Search Unit Cable RG-174

6.

0 Cable Type:

Length:

Connectors:

Instrument Settings Staveley / Sonic 136P 136-7661 Maufacturer/Model:

Serial Number 0.342 in.

0. 12in.lusec.

1 4KHz Delay:

Velocity:

Filter:

Rep Rate:

4.0 in.

334 ns 500 Ohms Range:

Pulser:

Damping:

Off 2.25 MHz PIE Reject:

Frequency:

Mode:

Exam Comments I Limitations:

Exams performed to maintain 5% to 20% ID roff.

ID geometry observed below recordable levels.

No exam performed frm downstream side due to component configuration.

Calibration Verification Field Simulator Block S/N:

CAL-RHOM-069 Reflector I Radius 2" Radius Amplitude K%

60%

Gain (dB) 22.0 22.0 Sweep (SD) 2-5 5.0 Acceptable Linearity performed :

512003 Exam Data for Weld: 24RRC(2)B-8/4RRC(4)-4S PIPE TO SWL Configuration:

OD 78_ F 225046 Exam Surface:

Exam Temp.

Exam Thermometer No counterbore detected.

Actual Cal Block 'T"is 1.410."

0059 Exam End:

0112 Level:

Date:

Date:

Cal/Exam Date:

5/21/2003 ANII Reviewed By:

Page 2 of 4

Ultrasonic Calibration and Examination Record GE NUCLEAR ENERGY Manual Piping and Components Site/Unit: CData Report Number: R16-067 S tColumbia Generatin Station Data Sheet Number:

UT-112 Outage:

R16 Linearity Sheet:

L-12 Calibration Data for Block: UT-7 Procedure:

PDI-UT.2/Site Specific SS 24" 1.140" Calibration Cal Time Material Size Thick Initial Cal:

2122 nit2Cal Check:

0114 Couplant:

Couplant batch

__44_

225046 601*F Cal Check:

N/A Thermometer S/N Cal Temp.

Final Cal:

0147 Ver /Rev: 2/11 DRR: NIA Search Unit Data RTD 98-172 Manufacturer:

Serial Number 2(10x18) mm/Rect Size/Shape:

a r' Measured Angle:

DAC Construction 0.45 in.

Incident Point:

20MHz Frequency:

60_

Nominal Angle:

TRL 2-Aust Style:

Lamn Mode:

2 Elements:

Scan Direction Cal Reflector Signal Amplitude Signal Sweep:

Signal dB:

Sweep 0-10 =

5.0i Ax ID Notch 80%A 5.2 Div 71.2 dB in.

Metal Path Search Unit Cable RG-174 6"

0 Cable Type:

Length:

Connectors:

Instrument Settings Calibration Verification Field Simulator Block S/N:

CAL-RHOM-069 Stavelev /Sonic 136P Maufacturer/Model:

1.21 in.

0.239inJlsec.

Delay:

Velocity:

Reflector 2" Ra'iu$

N/A Amplitude 80%

N/A 136-7661 Serial Number:

4KHz Filter:

Rep Rate:

500 Ohms Damping:

Dual Mode:

Gain (dB) 43.4 N/A Sweep (SD) 4,0 N/A Range:

Reject:

250 ns Pulser:

2.25 MHz Frequency:

Acceptable Linearity performed:

5/5/2003 Exam Data for Weld: 24RRC(2iB-8/4RRC(4)-4S PIPE TO SWL Configuration:

Exam Comments I Limitations:

OD Exam Surface:

786 F 22°04 Exam Temp.

Exam Thermometer Exams performed at reference sensitivity to maintain 5% to 20% noise level.

ID geometry observed below recordable levels.

No exam performed from downstream side due to component configuration.

Exam End:

0125 Initials:

Michael Kemp I/

Examiner Level:

GE Reviewed B Level:

D*

tyReviewed By:

Date:

ate:

N/A Initials:

Examiner 2:

NIA Level:

C ANII Reviewed By:

Date:

Cal/Exam Date:

512112003 Page 3_ of 4

Wall Thickness Profile Sheet Crown Height:

Crown Width:

FLUSH 1,2" 44.0" PIPE SWL UPST Component:

DNST Component:

Nominal Diameter:

Weld Length:

F/a..

REQUEST 21SI-32 ATTACHMENTS A THROUGH G Attachment Attachment G 21SI-32-21 Weld Identification 6MS(1)B-2 ISI Diagram MS-202-4 Construction Drawing MS-529-1.3 (CVI 215-00, 14362) sheet 2 NDE Data Report 2MSU-005 NDE Data Report 2MSM-002

5 10 6

2 3

7 a

9 I

2

5 5

5 7

6 S

A B

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1. DELETED.

2. SCAFFOLDING IS REQUIRED.

3. VIBRATION DAMPER PREVENTS FULL ASME SECTION XI CODE EXAMINATION COVERAGE OF WELD 6PE(1)B-2.

REFERENCES, ISI - 229-IA I 229-4 BOVEE & CRAIL ISOMETRICS MS-529-12 REV 8 MS-529-13 SH 1 REV 12 MS-529-13 SH 2 REV 1 I)B-25LDO AA CIl rAT~r)KM I nnkTN1(-

MtnDTW-S(1)B-24/1TE-1B EMS()9B-i/IL CONT ON MS-202-3 30"MSC1)-4 (REF) 6MS(1) 9-2/1 30MS(1)1 7ýý 6MS(1)B-1/2MS(50)-

CONT ON MS-226 2°MS(SO)-4 (REF)

VRE N*

SFYPLAN TURBINE GENrRATOR RUILDING 120" 6MS(I)B-2/3/4CAP-SECTION A

A VIBRATION DAMPER DETAIL ZONE T-23 THIS DRAWING IS INTENDED FOR USE IN PRESERVICE AND INSERVICE INSPECTIONS PROGRAMS ONLY.

QUALITY CLASS, 1

ASME CODE CLASS, 2

ENGR. O TIMMINS DRAWN, K-McA I DATE. 1-30-78 WASHINGTON PUBLIC POWER SUPPLY SYSTEM RICHLAND, WASHINGTON 9935:2 NOM NOM MATERIAL MATL CAL WNP-2 PIPING SYSTEM DIA SCH WALL BLOCK WELD & COMPONENT (IN)

THK SPECIFICATION TYPE NO IDENTIFICATION DIAGRAM S

WLLBLCKWEDENTIFCOMPONENTGRA 30MS (1)-4 30 XXX 1.250

!SA 155 CL 1 KCF 70 CS UT-1 ITITLEc 30 Dxx 1.250 SA 155 CL 1 ECF 70 CS UT-l I 6M5(1)-4 S

80 3 0.432 ISA 106 GR B

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DESCRIPTION IlOWN I CHK I Avo EVI BAEI I OW CH APV

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31 TYP 2 Typ 4 PL NOTES OE "3 PCS) HAS BEEN CUT DOWN IN FIELD PER POC. IMMEDIATE D. O*SIO OF.[E.R. 293-102.

BILL OF MATERIALS EDESCRIPTIO MATERIAL CODE A

2 1 9/16 61THCK CUT TO T0 3/4 DIA (SEE DTA. I SA-A 36 2

B 13

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SA-3

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