RS-12-153, Relief Request Associated with the Third 10-Year Inservice Inspection Program Interval

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Relief Request Associated with the Third 10-Year Inservice Inspection Program Interval
ML12283A084
Person / Time
Site: Braidwood  Constellation icon.png
Issue date: 10/08/2012
From: Gullott D
Exelon Generation Co
To:
Office of Nuclear Reactor Regulation, Document Control Desk
References
RS-12-153
Download: ML12283A084 (29)


Text

RS-12-153 10 CFR 50.55a October 8,2012 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-001 Braidwood Station, Units 1 and 2 Facility Operating License Nos. NPF-72 and NPF-77 NRC Docket Nos. STN-50-456 and STN-50-457 10 CFR 50.55a In accordance with 10 CFR 50.55a, "Codes and standards," paragraph (g)(5)(iii), Exelon NRC approval of the attached relief is requested on the basis that 100% examination coverage of Relief Request Associated with the Third 1 0-Year Inservice Inspection Program

Subject:

Relief Request Associated with the Third 10-Year Inservice Inspection Program The details of the 10 CFR 50.55a request are enclosed. EGC requests approval of this relief Interval There are no regulatory commitments contained within this letter. Should you have any In accordance with 10 CFR 50.55a, "Codes and standards," paragraph (g)(5)(iii), Exelon Generation Company, LLC, (EGC) hereby requests NRC approval of the attached relief request Generation Company, LLC, (EGC) hereby requests NRC approval of the attached relief request associated with the Third 10-year Inservice Inspection (lSI) Program Interval for Braidwood Station, Units 1 and 2. The third interval of the Braidwood Station lSI program complies with the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code, required surfaces and volumes of Class 1 components has been determined to be impractical.

Section XI, "Rules for Inservice Inspection of Nuclear Power Plant Components," 2001 Edition Braidwood Station, Units 1 and 2 with 2003 Addenda.

associated with the Third 10-year Inservice Inspection (ISI) Program Interval for Braidwood NRC approval of the attached relief is requested on the basis that 100% examination coverage of required surfaces and volumes of Class 1 components has been determined to be impractical.

Due to the original design and/or the base metal materials associated with the specified welds, it is not feasible to effectively perform examinations of 100% of the volume of these welds.

Station, Units 1 and 2. The third interval of the Braidwood Station ISI program complies with the Interval Facility Operating License Nos. NPF-72 and NPF-77 The details of the 10 CFR 50.55a request are enclosed. EGC requests approval of this relief Due to the original design and/or the base metal materials associated with the specified welds, it is request by October 8, 2013.

questions concerning this letter, please contact Ms. Dwi Murray at (630) 657-3695.

request by October 8, 2013.

There are no regulatory commitments contained within this letter. Should you have any American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code, questions concerning this letter, please contact Ms. Dwi Murray at (630) 657-3695.

U. S. Nuclear Regulatory Commission Respectfully, NRC Docket Nos. STN- 50-456 and STN-50-457 ATTN: Document Control Desk Section XI, "Rules for Inservice Inspection of Nuclear Power Plant Components," 2001 Edition not feasible to effectively perform examinations of 100% of the volume of these welds.

Manager - Licensing October 8, 2012 Exelon Generation Company, LLC RS-12-153 Washington, DC 20555-001 with 2003 Addenda. Respectfully,

Attachment:

10 CFR 50.55a Relief Request 13R-10

Subject:

cc: NRC Regional Administrator, Region III NRC Senior Resident Inspector, Braidwood Station NRR Project Manager, Braidwood Station Management Nuclear Safety

ATTACHMENT 10 CFR SO.SSa RELIEF REQUEST 13R-10 Relief Requested In Accordance with 10 CFR SO.SSa(g)(S)(iii)

Braidwood Station Third Interval, First Period Limited Examinations Revision 0 Page 1 of 6 1.0 ASME CODE COMPONENTS AFFECTED:

Code Class: 1

Reference:

IWB-2500, Table IWB-2500-1, Code Case N-460 Examination Category: B-D Item Number: B3.110

Description:

Limited Examination Coverage Component Number: See Tables 1 and 2 Drawing Number: See Attachments 1-1, 1-2, 2-1, and 2-3 ASME Section XI, 2001 Edition with 2003 Addenda requires a volumetric and/or surface ASME Section XI, Mandatory Appendix I requires ultrasonic examination of vessel welds Table IWB-2500-1, Examination Category B-D requires volumetric examination of Item The Third Interval Inservice Inspection program is based on the American Society of T-472. 1.1 Beam Angle: The search unit and beam angle selected shall be appropriate 2.0 APPLICABLE CODE EDITION AND ADDENDA:

ATTACHMENT 1

The Third Interval Inservice Inspection program is based on the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code,Section XI, 2001 Edition with 2003 Addenda.

IWB-2500, Table IWB-2500-1, Code Case N-460 B3.1 10 (Pressurizer Nozzle-to-Vessel welds). Figure IWB-2500-7(b) depicts the 10 CFR 50.55a RELIEF REQUEST 13R-10 B-D 3.0 APPLICABLE CODE REQUIREMENT:

ASME Section XI, 2001 Edition with 2003 Addenda requires a volumetric and/or surface examination, which includes essentially 100% of the weld and the applicable base metal, B3.110 greater than 2 inches thick to be conducted in accordance with ASME Section V, Article examination, which includes essentially 100% of the weld and the applicable base metal, Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code,Section XI, for the configuration being examined and shall be capable of detecting the calibration Relief Requested In Accordance with 10 CFR 50.55a(g)(5)(iii) for the affected examination categories of Class 1 components.

required examination volume (A-B-C-D-E-F-G-H) which includes the actual Limited Examination Coverage APPLICABLE CODE EDITION AND ADDENDA:

Table IWB-2500-1, Examination Category B-D requires volumetric examination of Item B3.110 (Pressurizer Nozzle-to-Vessel welds). Figure IWB-2500-7(b) depicts the ASME CODE COMPONENTS AFFECTED:

required examination volume (A-B-C-D-E-F-G-H) which includes the actual See Tables 1 and 2 Braidwood Station Third Interval, First Period Limited Examinations circumferential weld and adjacent base metal on either side of the weld extending to a APPLICABLE CODE REQUIREMENT:

distance of one-half the thickness of the wall from the extremities of the weld crown.

See Attachments 1-1, 1-2, 2-1, and 2-3 circumferential weld and adjacent base metal on either side of the weld extending to a ASME Section XI, Mandatory Appendix I requires ultrasonic examination of vessel welds greater than 2 inches thick to be conducted in accordance with ASME Section V, Article for the affected examination categories of Class 1 components.

4. ASME Section V, Article 4 requires:
4. ASME Section V, Article 4 requires: reflectors, over the required angle beam path.

Revision 0 2001 Edition with 2003 Addenda.

Code Class:

T-472.1.1 Beam Angle: The search unit and beam angle selected shall be appropriate for the configuration being examined and shall be capable of detecting the calibration

Reference:

reflectors, over the required angle beam path.

distance of one-half the thickness of the wall from the extremities of the weld crown.

Examination Category:

Item Number:

Page 1 of 6 T-472.1.2 Reflectors Parallel to the Weld Seam: The angle beam shall be directed at approximate right angles to the weld axis from both sides of the weld (i.e., from two

Description:

directions) on the same surface when possible. The search unit shall be manipulated so Component Number:

that the ultrasonic energy passes through the required volume of weld and adjacent base metal material. Drawing Number:

1.0 2.0 3.0

ATTACHMENT 10 CFR 50.55a RELIEF REQUEST 13R-10 Relief Requested In Accordance with 10 CFR 50.55a(g)(5)(iii)

Braidwood Station Third Interval, First Period Limited Examinations Revision 0 Page 2 of 6 T-472.1.3 Reflectors Transverse to the Weld Seam: The angle beam shall be directed essentially parallel to the weld axis. The search unit shall be manipulated so that the ultrasonic energy passes through the required volume of weld and adjacent base material. The search unit shall be rotated 180 deg and the examination repeated.

Braidwood Station has adopted ASME Section XI Code Case N-460, "Alternative Examination Coverage for Class 1 and Class 2 welds,Section XI Division 1." Code Case N-460 states in part, " ... when the entire examination volume or area cannot be examined ... a reduction in examination coverage ... may be accepted provided the reduction in coverage for that weld is less than 10%."

Pursuant to 10 CFR 50.55a(g)(5)(iii), relief is requested on the basis that conformance T-472. 1.3 Reflectors Transverse to the Weld Seam: The angle beam shall be directed Tables 1 and 2 identify the limitations for examination coverage of the welds NRC Information Notice 98-42, "Implementation of 10 CFR 50.55a(g) Inservice Braidwood Station has adopted ASME Section XI Code Case N-460, "Alternative NRC Information Notice 98-42, "Implementation of 10 CFR 50.55a(g) Inservice ATTACHMENT Inspection Requirements," termed the reduction in coverage of less than 10% to be "essentially 100 percent." Information Notice 98-42 states in part, "The NRC has with the specified Code requirement has been determined to be impractical. Due to the adopted and further refined the definition of "essentially 100 percent" to mean "greater than 90 percent" ... which has been applied to all examinations of welds or other areas Inspection Requirements," termed the reduction in coverage of less than 10% to be required by ASME Section XI."

10 CFR 50.55a RELIEF REQUEST 13R-10 original design and/or the base metal materials associated with these welds, it is not Examination Coverage for Class 1 and Class 2 welds,Section XI Division 1." Code essentially parallel to the weld axis. The search unit shall be manipulated so that the 4.0 IMPRACTICALITY OF COMPLIANCE:

feasible to effectively perform examinations of 100% of the volume of these welds.

Pursuant to 10 CFR 50.55a(g)(5)(iii), relief is requested on the basis that conformance Relief Requested In Accordance with 10 CFR 50.55a(g)(5)(iii) "essentially 100 percent." Information Notice 98-42 states in part, "The NRC has with the specified Code requirement has been determined to be impractical. Due to the encountered at Braidwood Station, Unit 1 and Unit 2, respectively during the first period original design and/or the base metal materials associated with these welds, it is not feasible to effectively perform examinations of 100% of the volume of these welds.

Case N-460 states in part, "...when the entire examination volume or area cannot be Therefore, relief is requested on the basis that the Code requirements to examine Therefore, relief is requested on the basis that the Code requirements to examine essentially 100% of the welds' volume are impractical due to physical obstructions and geometric interference. Attaining the geometry required to achieve the Code required Braidwood Station Third Interval, First Period Limited Examinations adopted and further refined the definition of "essentially 100 percent" to mean "greater ultrasonic energy passes through the required volume of weld and adjacent base IMPRACTICALITY OF COMPLIANCE:

examination coverage would require major modifications to existing components without essentially 100% of the welds' volume are impractical due to physical obstructions and providing a corresponding increase in the level of quality and safety.

examined.. .a reduction in examination coverage... may be accepted provided the Tables 1 and 2 identify the limitations for examination coverage of the welds encountered at Braidwood Station, Unit 1 and Unit 2, respectively during the first period geometric interference. Attaining the geometry required to achieve the Code required Revision 0 than 90 percent"... which has been applied to all examinations of welds or other areas examinations.

material. The search unit shall be rotated 180 deg and the examination repeated. examinations.

examination coverage would require major modifications to existing components without Page 2 of 6 reduction in coverage for that weld is less than 10%." required by ASME Section XI."

providing a corresponding increase in the level of quality and safety.

4.0

Table 1 - Unit I Nozzle -to-Vessel Weld Table 2 - Unit 2 Nozzle-to-Vessel Weld Relief Requested In Accordance with 10 CFR 50.55a(g)(5)(iii)

ATTACHMENT Cumulative Cumulative Reference Reference 10 CFR 50.55a RELIEF REQUEST 13R-10 Examination Examination Relief Requested In Accordance with 10 CFR 50.55a(g)(5)(iii)

Sketch/C Braidwood Station Third Interval, First Period Limited Examinations Sketch/C overage overage Remarks Remarks Coverage Coverage Revision 0 ATTACHMENT Page 30f6 Plot Plot Braidwood Station Third Interval, First Period Limited Examinations Achieved Achieved 56.56% Attachment 1-1 88.5% Attachment 2-1 Pressurizer Spray Nozzle-to-Shel Table 1 - Unit 1 Nozzle-to-Vessel Weld Pressurizer Spray Nozzle-to-Shel I Outage Cumulative recordable indications noted in an recordable indications noted in a Component 10 Reference I Examined Examination Code Category Sketch/Coverage Remarks Month/ Coverage 10 CFR 50.55a RELIEF REQUEST 13R-10 Code Item Plot ultrasonic scans performed.

Revision 0 ultrasonic scans performed.

Year Achieved 1PZR-01-N2 A1R15 56.56% Attachment 1-1 Pressurizer Spray Nozzle-to-Shell Weld. No 60.92% 88.5%

Category B-O (10/2010) recordable indications noted in any of the Item B3.110 ultrasonic scans performed.Attachment 1-2 Pressurizer Relief Nozzle-to-Shel Attachment 2-2 Pressurizer Relief Nozzle-to-Shel 1PZR-01-N3 A1R15 60.92% Attachment 1-2 Pressurizer Relief Nozzle-to-Shell Weld. No recordable indications noted in an recordable indications noted in an Category B-O (10/2010) recordable indications noted in any of the Item B3.110 ultrasonic scans performed.

ultrasonic scans performed.

Page 3 of 6 ultrasonic scans performed.

Table 2 - Unit 2 Nozzle-to-Vessel Weld Outage Cumulative Outage Outage Component 10 Examined Examination Reference Examined Month/ A1R15 Examined Month! A2R15 Code Category Sketch/Coverage YearRemarks Year Month/ Coverage Code Item Year Achieved Plot Al R15 (10/2010) (10/2010) A2R15 (4/2011)

(4/2011) 2PZR-01-N2 A2R15 88.5% Attachment 2-1 Pressurizer Spray Nozzle-to-Shell Weld. No Category B-O (4/2011 ) recordable indications noted in any of the Component ID Category B-D Component ID 1 PZR-01-N2 Item B3.110 ultrasonic scans performed. 2PZR-01-N2 2PZR-01-N3 A2R15 88.5% Attachment 2-2 Pressurizer Relief Nozzle-to-Shell Weld. No Item 83.110 Category B-D Code Category Code Category Category B-O (4/2011 ) recordable indications noted in any of the 1PZR-01-N3 Item B3.110 2PZR-01-N3 Item B3.110 ultrasonic scans performed. Category B-D Code Item Category B-D Item B3.110 Code Item Item B3.1 10

ATTACHMENT 10 CFR 50.55a RELIEF REQUEST 13R-10 Relief Requested In Accordance with 10 CFR 50.55a(g)(5)(iii)

Braidwood Station Third Interval, First Period Limited Examinations Revision 0 Page 4 of 6 5.0 BURDEN CAUSED BY COMPLIANCE:

Compliance with the examination requirements of ASME Section XI would require significant modification of plant components to remove obstructions, redesign of plant systems/components, and/or replacement of components where geometry is inherent to the component design.

The pressurizer vessel spray nozzle-to-vessel weld is approximately 2.7 inches thick.

The pressurizer nozzle and vessel are clad with stainless steel on the inside diameter The pressurizer vessel spray nozzle-to-vessel weld is approximately 2.7 inches thick.

surface. The geometry of the nozzle along with the presence of the cladding on the Compliance with the examination requirements of ASME Section XI would require Attachments 1-1, 1-2, 2-1, and 2-2 provide the basis for the limited examination coverage from the scan directions required by ASME Section V and Section A. These In addition to the completion of required volumetric examination performed to the extent inside diameter of the pressurizer resulted in limited access to the entire examination The nozzle geometry tapers away from the weld resulted in limited scanning surfaces volume. The propagation for the ultrasonic beam was in the shear mode. Normally, this Relief Requested In Accordance with 10 CFR 50.55a(g)(5)(iii) mode would allow the ultrasonic beam to reflect off the inside surfaces and create a two-The pressurizer nozzle and vessel are clad with stainless steel on the inside diameter beam axis at right angles to each other, however, the presence of the stainless steel coverage, which include drawings/sketches, as applicable. The differences between the cladding precludes the ultrasound beams from reflecting at the inside diameter from the shell/cladding interface.

surface. The geometry of the nozzle along with the presence of the cladding on the The nozzle geometry tapers away from the weld resulted in limited scanning surfaces limitations are inherent to the original design of the pressurizer vessel. Conformance aggregate examination coverage achieved and the coverage previously attained during significant modification of plant components to remove obstructions, redesign of plant available for the transducer coupling on the nozzle side of the weld, which resulted in ATTACHMENT additional examination limitations. These factors resulted in limited examination Braidwood Station Third Interval, First Period Limited Examinations coverage from the scan directions required by ASME Section V and Section XI. These practical, numerous system leakage tests (Section Xl Category B-P and Generic Letter inside diameter of the pressurizer resulted in limited access to the entire examination available for the transducer coupling on the nozzle side of the weld, which resulted in limitations are inherent to the original design of the pressurizer vessel. Conformance the Second 10-Year ISI Program Interval examination are due to changes in ASME with the ASME Section XI requirements for essentially 100% of the volumetric coverage would require extensive structural modifications to the pressurizer vessel.

volume. The propagation for the ultrasonic beam was in the shear mode. Normally, this Attachments 1-1, 1-2, 2-1, and 2-2 provide the basis for the limited examination with the ASME Section XI requirements for essentially 100% of the volumetric coverage Section V requirements. While it may be possible to increase the overall coverage using coverage, which include drawings/sketches, as applicable. The differences between the systems/components, and/or replacement of components where geometry is inherent to aggregate examination coverage achieved and the coverage previously attained during BURDEN CAUSED BY COMPLIANCE:

1 0 CFR 50.55a RELIEF REQUEST 13R-10 Revision 0 the Second 10-Year lSI Program Interval examination are due to changes in ASME mode would allow the ultrasonic beam to reflect off the inside surfaces and create a two-Section V requirements. While it may be possible to increase the overall coverage using alternative or additional angles, it would not necessarily increase the level of quality and alternative or additional angles, it would not necessarily increase the level of quality and safety in detecting flaws or relevant conditions, and would increase the radiation dose additional examination limitations. These factors resulted in limited examination 88-05) at nominal system operating pressure (2235 psig) and temperature (557°F) have beam axis at right angles to each other, however, the presence of the stainless steel received by the examiners due to additional time spent to scan the welds.

would require extensive structural modifications to the pressurizer vessel.

In addition to the completion of required volumetric examination performed to the extent safety in detecting flaws or relevant conditions, and would increase the radiation dose the component design.

practical, numerous system leakage tests (Section XI Category B-P and Generic Letter Page 4 of 6 cladding precludes the ultrasound beams from reflecting at the inside diameter from the 88-05) at nominal system operating pressure (2235 psig) and temperature (55rF) have been performed with no evidence of leakage associated with the pressurizer spray nozzle-to-vessel welds. The system leakage tests will continue to be performed received by the examiners due to additional time spent to scan the welds.

throughout the remainder of the interval.

Radiography as an alternative is not feasible because access is not available for film shell/cladding interface.

placement. No alternative examinations are planned for the weld during the current inspection interval. No additional ultrasonic examinations will be completed during the inspection interval for these welds since the examination was performed to the extent 5.0

ATTACHMENT 10 CFR SO.SSa RELIEF REQUEST 13R-10 Relief Requested In Accordance with 10 CFR SO.SSa(g)(S)(iii)

Braidwood Station Third Interval, First Period Limited Examinations Revision 0 Page S of 6 practical. The results of this examination along with the results of the pressure tests and plant monitoring provide reasonable assurance that pressure boundary integrity has been and will be maintained for the components throughout the interval.

6.0 PROPOSED ALTERNATIVE AND BASIS FOR USE:

Braidwood Station proposes to perform the Code required volumetric examinations to the maximum extent possible. Due to the original design of these welds, there are no Braidwood Station proposes to perform the Code required volumetric examinations to practical. The results of this examination along with the results of the pressure tests and alternative examination techniques currently available to increase the examination As a minimum, all components received the required volumetric examination to the In addition to the periodic visual inspections performed under ASME Section XI and volume. There were no cases in any of the listed examination components where outside diameter surface features (Le., weld crowns, weld shrinkage, surface roughness, ATTACHMENT etc.) could have been conditioned to maximize the coverage attained without major extent practical due to limited or lack of access availability. There were no recordable Generic Letter 88-05, reactor coolant pressure boundary leakage is monitored through a modification to the components.

the maximum extent possible. Due to the original design of these welds, there are no As a minimum, all components received the required volumetric examination to the indications requiring further evaluation noted in any of the volumetric examinations extent practical due to limited or lack of access availability. There were no recordable number of other activities, which provide a high level of confidence that in the unlikely indications requiring further evaluation noted in any of the volumetric examinations 10 CFR 50.55a RELIEF REQUEST 13R-10 performed. The examinations were conducted, and satisfactory results were confirmed, performed. The examinations were conducted, and satisfactory results were confirmed, alternative examination techniques currently available to increase the examination even though essentially 100% coverage was not attained. Additionally, multiple VT-2 examinations were and will continue to be performed on the subject components plant monitoring provide reasonable assurance that pressure boundary integrity has event that leakage did occur, it would be detected and proper action taken. Specifically, throughout the interval through the required system pressure tests (examinations even though essentially 100% coverage was not attained. Additionally, multiple VT-2 required by ASME Section XI and Generic Letter 88-05). No evidence of leakage was PROPOSED ALTERNATIVE AND BASIS FOR USE:

observed at these components, providing additional assurance that the structural volume. There were no cases in any of the listed examination components where Relief Requested In Accordance with 10 CFR 50.55a(g)(5)(iii) integrity of the subject components will be maintained throughout the remainder of the system leak rate limitations imposed by Technical Specifications Section 3.4.13, "RCS Page 5 of 6 examinations were and will continue to be performed on the subject components interval.

In addition to the periodic visual inspections performed under ASME Section XI and throughout the interval through the required system pressure tests (examinations Generic Letter 88-05, reactor coolant pressure boundary leakage is monitored through a Operational Leakage," as well as the reactor makeup control system, reactor cavity and outside diameter surface features (i.e., weld crowns, weld shrinkage, surface roughness, number of other activities, which provide a high level of confidence that in the unlikely event that leakage did occur, it would be detected and proper action taken. Specifically, Braidwood Station Third Interval, First Period Limited Examinations system leak rate limitations imposed by Technical Specifications Section 3.4.13, "ReS required by ASME Section XI and Generic Letter 88-05). No evidence of leakage was been and will be maintained for the components throughout the interval.

containment floor drain sump monitoring, containment radiation monitoring, and Operational Leakage," as well as the reactor makeup control system, reactor cavity and containment floor drain sump monitoring, containment radiation monitoring, and etc.) could have been conditioned to maximize the coverage attained without major containment atmospheric monitoring, provide additional assurance that any leakage observed at these components, providing additional assurance that the structural would be detected prior to gross failure of these components.

containment atmospheric monitoring, provide additional assurance that any leakage Revision 0 integrity of the subject components will be maintained throughout the remainder of the 7.0 DURATION OF PROPOSED ALTERNATIVE:

modification to the components. would be detected prior to gross failure of these components.

Relief is requested for the Third i0-Year Inservice Inspection (lSI) Program Interval for interval.

Braidwood Station Units 1 and 2. For the examination categories under this relief, the Third Interval for Braidwood Unit 1 began on July 29,2008 and is currently scheduled to end on July 28, 2018. The Third Interval for Braidwood Unit 2 began on October 17, 2008 and is currently scheduled to end on October 16, 2018.

6.0

ATTACHMENT 10 CFR 50.55a RELIEF REQUEST 13R*10 Relief Requested In Accordance with 10 CFR 50.55a(g)(5)(iii)

Braidwood Station Third Interval, First Period Limited Examinations Revision 0 Page 6 of 6

8.0 PRECEDENTS

A similar relief request was approved for North Anna Power Station, Unit 1 for limited examination coverage for Examination Categories 8-A, 8-0, 8-K, R-A, C-8, C-C, and C-F-1 (NRC Safety Evaluation Report dated January 7, 2011 - ADAMS Accession Number ML110060011).

For 8raidwood Station, limited coverage for these components was identified during the previous inspection interval and relief from Code requirements under Relief Request 12R-50 which was approved by NRC Safety Evaluation Report dated March 8, 2010 For Braidwood Station, limited coverage for these components was identified during the A similar relief request was approved for North Anna Power Station, Unit 1 for limited (ADAMS Accession Number ML100480699).

ATTACHMENT

9.0 ATTACHMENTS

Attachment 1-1: Weld 1PZR-01-N2 (6 pages total) 10 CFR 50.55a RELIEF REQUEST 13R-10 Attachment 1-2: Weld 1PZR-01-N3 (6 pages total) previous inspection interval and relief from Code requirements under Relief Request examination coverage for Examination Categories B-A, B-D, B-K, R-A, C-B, C-C, and Attachment 2-1: Weld 2PZR-01-N2 (3 pages total)

Attachment 2-2: Weld 2PZR-01-N3 (3 pages total)

Relief Requested In Accordance with 10 CFR 50.55a(g)(5)(iii)

Attachment 1-1: Weld 1PZR-01-N2 (6 pages total) Attachment 1-2: Weld 1PZR-01-N3 (6 pages total) Attachment 2-1: Weld 2PZR-01-N2 (3 pages total) Attachment 2-2: Weld 2PZR-01-N3 (3 pages total) 12R-50 which was approved by NRC Safety Evaluation Report dated March 8, 2010 Braidwood Station Third Interval, First Period Limited Examinations C-F-1 (NRC Safety Evaluation Report dated January 7, 2011 - ADAMS Accession Revision 0 Page 6 of 6 PRECEDENTS: Number ML110060011). (ADAMS Accession Number ML100480699). ATTACHMENTS:

8.0 9.0

Weld 1PZR-01-N2 ATTACHMENT 1-1 ATTACHMENT 1-1 Weld 1 PZR-01-N2

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nozzle configuration. See attached pages 3 thru 6 for coverage calculations. Serial No.: Serial No.: SAP 104391

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4.0 div 0 50% CD 0 No. of Probe Delay: ~ Range: 5.cr Probe o.y. _ Range: \

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filter: Fixed Mode: 0U8I Off Filter: Mode: \

fa .. t~ ~^

ExamineB Paul 8Ied\a III Rectify: Fulwave Voltage: 450 Rectify: Voltage: \

lAM! DaCe 10112110 PuIM Width: 220 OS - PuIae WidIh:

~A \

~ NiA DaCe AlA Display Delay: 0 Display DekAy: \

WeaOyne Re'iIewef I Date: - 8..,." & m-Referen ce SendM ty (dB) Referen ce SensitM ty (dB)

I~.I"

\

1 C* L ... Axial: 10.0 dB Cke: NlA Aldet: Cire:

FuI1het Evaludon Reqund 1 FSOH SenIitMty:

.MWW/~

--1"'""'\

. LA . ..- \ . .

i a n

RY D Austen tic imately, 56.56 ACCESS I1 2-06250

c. 0 Both i-210 Sided 0

h-Q-6 071 4'F 105230 8' t 1.0' m: 803.1 10 Type:

T ULTR AGEL it FLAW

~ W~~p'ynii Final Calib. Date Final Cafib. Intermediate intermediate Initial Calib. Date initial Caiib.

Data Sheet 0 Calibration Data She et x No TNo7ct3 COMPONENT TEMP 78'F A W, ~t ,,\*..t h I4l"' 1' '~ * ~UM. C9InpM'l)

Cal. Checks I.

NON RELEVANT l'.n Page

.l.o ..

h:

Piant I Unit 2

Braidwood 11 .,.

Data Sheet , A1R15-UT-022 III Calibration Data Sheet Company E.xeton Page 2 of 8 1]11 ~~

Comp I System N21 RV 09225 Procedure No.

- "l/. T -E n liT .t &

YES (dolt t;uf.)j exe-lSI-210 Rev I Chng. No. 3Ia Cal. Checka TIm. 11 !1'"

Cal. Block No. ewo 071 Al RI 5-UT-022

~4 :t 15:52115:63 13:57/14:39 12:19/12:20 09:22109:2 3 x

Cal. Block Temp. Initial CaIib. 09:22/09:23 1'1 Mdill Thermometer ~ :

Size .-

74-F SAP 105230 10/12/10 10/12110 Time Initial Calib. Date of 6 10112110

  • Inl Intrt UNc ~ i~ ~T I Sch. NlA 12.0825" I "r I Ref 8todS' ' - - - '---

SAP 105220 [!] Ferritic D Au8tenitic Intennediate 12:19/1 2:20 Search Unit 11 Search Unit 12 Type:

Each Major CRT ON. = a.r , 1.fr Wedge Style:

Size: 0.5' x 1.00 Search Unit 01 Shap Manufacture:

-Red e

Intermediate 13:57/14:38 K8A Manufacture: K8A Length: 00B864 Cal. Direction: [!)Axial Cl Cire. 0 Both Serial No.:

No. of EJemenIi: 1 SeriIII No.:

No. of Elemenli:

008X8K Manufacture:

Final CaIib. 15:52115:53 i KBA ShiP8: Rect.

Freq. TEW Style:

Size: 0.5" x 1,(1' Sh8P8: Rect.

Inatr111116/>t f3etLinge Scan Area: I toW" [!] oamma Size: 0.5" X 1.rr Search Unit Cable Gamma 12 Freq. 2:25 URi Styte: Freq. 225 URi Styte: aamma II l!J Final CaIib. Date 10112110 Serial No.:

to Weld An9Ii:

RG-174 Coupla nt Exam Meaaured Angta--:-

45- Mode: SfMNii Exam AIijjIi: eo-Modi: ShUi 45- so-Exam di* -"

Cat89OfY: 8-0 Code Item: 803.110 Type:

Meuur ed Angae:

45' ModeShear ULTRAGEL II Wedge Style: SWS Wedge Styte: --:sws~---

No. of SWS No. of Elements:

Batch: 09225 0 Examin ation AIea I Weld Measured Angle:

45' ACCESS YU FLAW NO ElCAII (a)

Type:

Length:

8ean:h Unit cable 12' R~174 NO. Of con.:

Type:

Search Unit cable R~174 NO. Of con.: --L 1RY01S 11PZR~1-H2 Bematkll BulQO 1m ~ Smnlll Type: Serial No.:

Co.FONeHT TEMP:7a-.=

X X ...

    • Inatrument Setdng e 0 length: 12' lnetnn ent Settings Manufacture:

No rec:0fdab6e Indication.. Approximatety 58.56% ~ IICNIYed due OOW$K Length: to MIke 1 Model: KrautkI8mef I USN 58l SW Make I Model: Krautkremer I USN nozzle configuration. See attached pagel 3 thru 6 b' c:ovwa 58l SW No. of Elemen .

ge Clllcutdona. Serial No.: SAP 104391 SenaI No.: SAP 104381 Cal Chedt: 1.r:r Radius 0 1.25 diY 0 70% 0 22.5 dB; 2.fT Rlldiua Ank 0 2.5 Probe Delay. 12.825 Range: 8.0" Probe o.uy. 18.0784 Range: 10.0" dN @ 25% CD 22.5 dB Size: 0.5' x 1.0' Inet anent Settfnge Shape: Red, s9U!i!

Search Unit Cable 12'

.. 60- Cal Chedc ' 1.r:r RadIU' CD 1.0 diY G 80% CD 2e dB; 2.r:r fUdiuI M'tI Ca 0.1272 Puller: M'tI Call Vel: 0.1272 Puller. sQU!i!

search Unit 02 I

CD 2.0 diY OampiJag: 500 Re;ed: 0% DampIng: 500 Rttect Freq.

0%

@50% @26d B.

No. z Style: mma PRF: AutoHigh Freq: 2.25MHz PRF: Auto High Freq: '"'"2.2S"MHz RG-174 Filler. Fbced Mode: Dual Off Filter:

Exam Anglia:

Flx8d Mode: Dual Off 60' Mode: - ar fQ..L 0 KM Rectify: FuIIMM Voltage: 450 Rectify. FuDwave Voltage: 450 Exanuneta: Paul 8IectIa fi!t..L lewIt III Date 10112110 Pulse Width: 220 ns - PuIIe W6dth: 220 ns -

NlA Measured Angie: 60' fUADeIe

.. - L.e¥eI

- NlA DiIpIay Delay: 0 Display Oe&ay: 0

~#<.. ~,.. ~"IIb Refeten ce Sen8itMty (dB)

Wedge Style:

Referen ce SenIiIM ty (dB)

SWS WeaOyn e Rewtwer I Dat.e: I **,$'-/tl 0 Axial: 37.0 dB Circ: NlA Axial: 42.& dB Circ: NlA Fut1her Evatuatioft RequIred? FSOH SenaN y:

  • t,,- . I
  • FSDH SenaN y:

(DENT. NO.

A1R15-UT"()22 11_. . . . . . .

f" ,.,. It Jir'" Page 3 of6 450,600 and 70° Axial Upstream / Dow LlMIT AnON TO EXAMINATION PROCEDURE Braidwood UNIT 1 SKETCH 1PZR..() 1 SKETCH ON TO EX"' WATION RY/N2 .

PROCEDURE EXE..aSI-210. Rev. 3 DATE A DATE 1011212010 nstream Scans VT

[0 OtSCw&E APPROXIMATE I

RELATED TO: UT x PT MT _ _ VT _ __

(DENT. NO. 1PZR"()1-N2 UNIT PROVIDE GENERAlINFORMATJOH TO DESCRIBE APPROXIMATE SlZE, LOCATJOH AND TYPE OF UUlTAllON.

Inner Radius Examtior 45". 60" and 70" Axial Upstream' Downstream Scans Exam Volume:: length x Width x Height length :: 40" MT SUE, LOCATION AND TYPE OF L1 Width:: 4.1" Height::: 2.52" oia, rmssej volume (Downstream (40" x 4.1" x 2.52")::: 413.28'"

x Height (in cross hatched a to Nozzle Exam.

t Ot3i Achieved coverage (per scan i otai altissea volume (Upstream Area 1: (40" x 1.0" x 0$') 12:::: 16'"

ITO Area 3: (40" x 2.52" x 2.52") 12 :; 127'"

) = T.E.V. - T.M.V. I T.E.V.

scan) = Area 1 + Area 3 + Are PT Area 2: (40" x 1$' x 0.7") 12 :::: 25.2 '"

f:3 Area1:(40"x1Q" x0.8")/2=16" otai Exam Volume = Length x Area 4: (40" x 1.8" x 2.52"):; 181.44"'1 413 28"' - 41.2`3 1413. 28`3 Total missed volume (Upstream scan):::: Area 1 + Area 2 W dth x Height scan) = Area I + Area 2 X

16'" + 252'" :::: 41.2'"

16`4 1- 127"' + 181 44"' z32 a4 THOLE 70° coverage achieved during

= 901(Upstream Scan)

Langtn = 40" Total missed volume (Downstream scan) :::: Area 1 + Area 3 + Area 4 (40' x 4 1" x 2.52") = 413 fvt,ssed Volume = Length x Width 16'" + 127'" + 181.44'" :: 324,44'"

IPHOV Dt c04:R L iPtrOr AT+Oi UT 1 6"' - 252" = 41.

413 28"' - 32444" 141128"' =

Achieved coverage (per scan) ::: T.E.V. - T.MV 1T.E.V. 1<eF II'At! 'AI¢ 1?Eh ,e..,- AIIt1 5-0T "-O.z .O....

4.44"'

Width = 4.1" 413.28fta - 41.2'" 1413.28'" :::: Ir1l (Upstream Scan)

.28"'

"A44 3 ~" Fo.IIl. rNAle"JII. itAd,(/.s .A..r A.

2" 413.28'" - 324.44'" 1413,2 8:: ~ (Downstream Scan) 21 (Downstream Scan)

IO/Z. 2./1D 4 RMEW I OATS IRL ATED T4.

70" coveraae achieved durina Inner Radius Exam Drior to Nozzle Exam, tieoght = 2.52"

'~~

~.QJ?nr 10./,,-*'0 1 l L..J~ l~ll""tl...l

BraKtwood S, L&VOI III RY / N2 IN8P£CT1ON SERVICES , . . 4ofl PROFILE OF THE EXAMINATION VOLUME/ DATA

" ~I. I"'~ .hIIC "",~

PROFILE OF THE EXAMINATION VOLUMEI DATA PLANT Braidwood UNIT

-1 SKETCH lPZR-0 1 DATE SYST ICOMP . RY IN2 PROCEDURE EXE-ISI-21 0. Rev. 3

&~aUtD ~1N. Ir INSPECTION SERVICES EXAMINER DATE 1011212010 IDENT,

. II 1PZR-01-N2 UNIT 10/12/2010 4 I

45-, 60- & 70-Aletal Scans IDENT.

PROCEDURE SKETCH M1.

Tot .. (AD EXE4SI-210, Rev. 3

,~

1PZR-01-N2

  • >'\

(A. IPZR-01 Page 4 of $

J: I <

"'0*

I I

1__=-_--=-_

I ...

1: . s"

^io '.,-

/.-/~... ;.:J ol l-t"""--4._ l.:;) \ \40 \ \. ~

EXE-IS 1P 10' m scan + Downstream scan + CW scan + CCW IDENT. NO.

AfRl5=UT.;Q22 Page 50f6 LIMIT AnON TO EXAMINATION PROCEDURE Braidwood UNIT ..!. SKETCH 1PZR"()1 SKETCH TO EX4A-iiiiATION scan + 0° scan) / 5 45° & 60° CW/CCW Exam & 0° SYST/COMP.

DATE TATTON.

PROCEDURE E.XE-ISI-210IR~  :'! ___ __

EXAMINER ~

DATE 1011212010 1 OF U RELATED TO: UT x PT _ _ VT _ __

AC40SE APPRO)U RATE 8W% LOCATION AND TYPE MT IOENT. NO. 1PZR..()1-N2 UNIT PROVIDE OENERAlINFORMATIOH TO OESCRtBE APPROXlIlllATE SIZE.

LOCATIOH AND TYPE OF LliilTATIOH.

45* & 50* CWICCW Exam & O*

Total Exam Volume =: Length x Width x Height Lliv-a1TATIO length =: 40" riT Width =: 4.1" Height =: 2.52" Nil: ,.,-d volume = Le c, J m x Width x Heigh (40" x 4.1" x 2.52") ;: 413.28"*

T'otai Achieved overage (per scan) = T.E.V Missed Volume;: Length x Width x Height (in cross hatched area)

~ Area 1: (40'" x 1.0" x 0.8") I 2 =: 16"*

RY / N2 Area 2: (40" x1.6"x2.52")=161.28"'

. - T.M.V. / T.E.V.

PT Deal A: t^Iuva i overage (per exam naLo n)

Area1 :(4u"x1.0" x0.8")/2=16"'

A,ea 1 Area 2_ (16 + 161.28") =177.28"'

Area 2: (40" x 1.6" x 2.52") =: 161.28 "*

Total Exam Volume = Length x Width x H Braidwood t (in cross hatched area)

Area 1 + Area 2: (16"* + 161.28"*) =177.28"* X 413.28- 177.28"/ 413.28" = 57.1 % = (Ups Total missed volume =In.28J!It.l '.... III'= 0eIIt 10112110 Rectify.

" . . WidIh:

FuMw Voltage:

220 os -

Rectify:

P&;aeW klh:

Search All: Cable NlA l..eWII 0. NlA Display Delay: 0 ~~-.-----------------~

WesOyne ~ I o.te:

'RJ,ar cS6' : -- J.#.<< / *. (£-~O Reference SentiM y (dB)

Axial: 10.0 dB Cifc: NJA R...... a SenIitM ty (dB)

A>>II:

Fur1her E~ RequIred?~"__ mHo Circ:

ClfWl. *M'WII WJOI\ T(

~ --r-'MTI J 1.8W: *

\ . --, ..

FSOH SenIitMty:

\

m: 803.110 Type:

0 3 Austenitic nts) c. 105230 071 RY /1 0 Both 4'F I.210 imately 2.06W h:

S n / 1.0' T

l1: i t._ti 1.711 1=3 Final Calib. Cate Final Calib. Intermediate Intetnte Initial Catib. Date NO Ini Data Sheet d Calibration Data Sheet X

X .-

Cal. Checks YES >6O% Ret Calib.

I Page

__ .)

Plant I Unit BIaidwood I 1 T .1 r!.1 2

Data Sheet , A1R15-UT..Q23

m FLAW Calibration Data Sheet 06 d8 Compa ny JlII.

ElC860n Page 2 e MON RELEVANT of Ilf II! ~

Comp I System Coupi-ant H31 RV I.

Pro<:edure No. EXE-tS1-21 0 3J~ IT ] 0~

Rev J Chng. No. ULTRAGEL 11 CeI.Ch eGka TIme IJ 'l" A1RI5-UT-023 3/0 COMPONENT TEMP:78'F Cat. 8&cJd( No. BWO 071 ')14 tr 16:52/15:53 13:57114:39 09225 12:191112:20 09:22 / OW23 No Initial CaIib.

10112110 Cal. 8&cJd( Temp. 09:22/09".23 10/12110 746 F Thermometer SIN:

so d8 Size 6- Sc::h.

SAP 105230 NlA 12.Q825-Time initial CUb. Date of 6 10112110 i . - --- - -

l ID~ but c_ 1I~'" .,.tw I ,~ ~T

.,.. - ~

~

~

I Rtf BIoq; SAP',05 220 Type:

I [!J F8fritic DAuatenitic 1ntennediat8 12:19/12:20 8earctI Untt t1

~

- I e.ch Major CRT ON. = Search UM 01 o.r 11 .0" 8eaIch Unit 12 1ntennediat8 13:57/14:39 ManufacIure: KBA ManufacIure: KBA Length: Manufacb e: KBA Serial No.: &alA Cat. Direction: [!)Axial Serial No.:

0 eire. 0 BoIh Fin8I c.Jib. 15:52115:53 No. of EJamenIi: 1 Serial No.:

No. of Elemei\1I:

OOIXBK 1

Sh8P8: ReCt.

Instrument Settings Size: 0.5" x 1.0" Size: 0.5" x 1.0" Sh8P8: Rect.

I No.

Search Unit Cable Sean Area: 12' of Elem en .

toWetd [!]

II to Weld [!J Final CaIib. Date 10112110 Freq. 2:28 MHZ Styte:

Exam AniiI8:

oammii Freq. 2.21 fIIIHi Styte: oamma RG-174 Size: 0.5' x 1.0' sue  : ed. CoupIa nt Measured 45* Mode: §i8i; Atge-:-- 45*

Exam AniiI8: Modi: eo* Sh88i Code Categoty: Freq.

8-0 2. Style : G arnma Code Item: 803.110 Type: ULTRAGEL II Wedge Styte:

Measured Angle: eo*

No. of Exam rW. Batch:

SWS Wedge Style: SWS 45' Moc e:: 0Q225

.: Meas ured Wedge Style:

Angle :

SWS 45' ACCESS FLAW 11011 'Hr. ... IUN~

NOH Rl!LEVAHT ....

EXAII Type:

8eanIh Unit cable RG-174 Type:

Search UnIt CQIe RG-174

=

0 examin ation Area I Wefd VEl NO VII~IW.I NO CdB) Length: .!!,...NO. Olean.: - L LengIh: 12' NO. or con.: - L 1RY01S 11PZR..Q1-N3 X X eo dB

.. dB Instrum ent Sealnge Type:

Ben\8tt(ll Beaaon fg( IncomDlata Sctn(1l Inatrum ent Sealnge COMPONENT TEMP:78" Search Unit 92 No recordable indications. Approximately 60.92% coverage achieve Length: d due to Marwfeckae: Make I Model: Ktautkramer I USN 58L SW Make 1 Model: KrautIuamer' KBA USN 58L SW I

nozzle configuration. See attache d pages 3 Ihru 6 for coverage calcu&ations. Serial No.: SAP 104391 Serial No.: SAP 104391

  • 45" cal Check: 1,(1" Radjus @ 1.25 div @ 70% CD 22.5 dB; 2.0" Serial No.:

Radius CD 2.5 I D K Probe Delay: 12.1I2aO Range: 8.0" Probe Delay: 18.0784 Renge:

Instrument Settings diY @ 25% @ 22.5 dB 10.0" Search Unit Cable 12' M'II Cal 'Vel: 0.1272 NIet: sgui i!

No. of Elements: M'II cat 1 Vel: 0.1272 Puller. sgui i!

.. 60° Cal Check : 1.0" Radius @ 1.0 div 0 90% (0 26 dB; 2.0" Radius CD 2.0 div f Damping: 500 Retect 0% Oamptng; 500 RfIted:

@50% @26d B. 0%

RG-174 Sane: 0.5' x 1.0' speed. PRF: Auto High Freq: 2:2SMHz PRF: Auto High Freq: 2.25'"MHl FIter: Fbcad Mode: Dual Off FItl8r:

No. of Freq. Style :

Fbcad Mode: Dual Off GOM M ExamIne,.: Paul 8IItcha Exam ICN p0'

&+0 SJl l ..Level III DatIl 10112110 Rectify.

Pulse WkIh:

Fullwawe Voltage:

220 na -

450 Rectify. FuIIwa¥e Voltage: 450 HI" Mo ear ~ ~o. N1A PuIIe WidIh: 220 ns -

.: 0tspIay Delay: 0 Display Delay. 0 Meas ured Angie : 60' Referenee SensItivIty (dB)

WeaOy neRewM et/Date :

0 ?j;.,p f"t4 ,.,' 4 ....11[ /o*/,s: ./O AxiII; 37.0 dB Circ: NlA Refef aa SenaiIM ty (dB)

Wedge Style: A*I: 42.8 dB SWS Ckc: NlA Further Evaluation Reqund 1 FSOH SenIN y.

  • FSOH S. ........

I D -II. -, 0 1 L

Width x Height O OEUCRIOE APPROXIMA can) = Area 1 + Area 2 7"x08 )/ 2=32.0"' 0"x0.6')12=14.13"'

x Height (in cross hatche and 1.2" on each side) 64 BraKtwood X

d area)

TE SUM. LOCATM A11O TYP PT RYI N3 A1R 1s: uT.m3 45', 60' and 70' Axial Upstrea Pag e 3 0'6 UMITATION TO EXAIIINAliO N T

LIMITATION TO EXAMINA Braidwood UNIT 1 E OF LWITATION.

SKETCH 1PZR-01 SYST ICOMP .

RY /N3 MT PROCEDURE EXE~St*210. Rev 3

~..&itn EXAMINER Paul B (U,. IS ~..?=== DATE 1011212010 RELATED TO: UNIT UT x H PROVlDE GEJtE.RAL IHFORMATlOH TO EJIlI PT 0UC IU8 e APPROlUIIATE I&ZE.. LOC MT VT IDE NT. NO.

--- 1PZR-01-N3 VT ATlON AHO nPE 0# LlllllTATlOM. I m / Downstream Scans Total Exam Volume ;: len gth x 45-, and 70* Axial Up IbU m 1 00w n1t JUm eo-Area 4: (47 10" x 1.7" x 2.5")

Area 3: (47.10" x2.5"x2 .50)12 Wid th x Height Scans DATE len gth ;: 47.10*

PROCEDURE SKETCH TION Width ;: 4.1" (1 .r weld crown and 1.2" on eac h aide)

Height = 2.5-(47. 10" x 4.1

  • x 25* ) = 482 .8'"

=147.21 IDENT. NO.

Missed Volume = len gth x Width x Height (in aos a hatched

~

area)

Asea 1: (47 10" x 1.0* x 0.6 ")' 2.: 14.1 3'" [ill Area 3: (47. 10" x 2.5

  • x 2.5") 12 =147.2'"

~ Area 2: (47. 10" x 1.lx O.8") /2=

32.0'"

§

= 200.2" Area 4: (47 .10- x 1.1 x 2.5") = 200 Total missed volume (Upstream .2*

scan) = Area 1 + Area 2 EXE-ISI- 210, Rev 3 14 13'" + 3Z"-;: 46.13'"

1011212010 1PZR-01 Toral missed volume (Downstrea m scan) = Ale a 1 + Area 3 + Area 4 Page3of6 AIR1S-UT-023 141 3** + 147 . ~ + 200 .2'" 361 =

1PZR-01-N3

.53 '" 1l~'Pl6NCe R& AL ttr 'li tiS -v r- 02 ',

Total Actlleved coverage (per sca n) T.E.V .

  • T.M .V. I T.E V. = ?A4-e 3 ell& ' ~ ~/II'S ~"..

482 .8" *46 .13 ""4 82.8"' * ~

482 .8"' *36 1 .53 "'4 82.8"* =B" (Upstream Scan) ~~ .. I. ... . ~ 10 '% ..'1 ll (Do wna bum Sca n) -// '

,e actlleved dunna Inner Radius Exa m to NozzJe Elcam.

~ ..... ~"

/0 - /S- IO

/4-1 1..1 () L \- 't l_\ \c. . \'_

C112. LOVOI III Brudwood

,^: 6Ll-,

RY / N3 INSPECTION SERVICES Paae 4of.

PROFILE OF THE EXAMINATION VOLUME! DATA PROFILE OF THE EXAMINATION VOLUMEI DATA PLANT Braidwood UNIT 1 SKETCH 1PZR~1 DATE SYST ICOMP RY I N3 PROCEDURE EXE~SI*210, Rev. 3

~ . ("i' -

!Uf.I^31:S:Iyci^P.

EXAMINER DATE 1011212010 IOENT . 1PZR~1-N3 UNIT 10112/2010 INSPECTION SERVICES 1

45-, SO* & 70*

Axial Scans PROCEDURE IDENT.

SKETCH m's EXE-ISI-210, Rev. 3 IPZR-01-N3 I

Pape 4 o16 1 PZR-01 Tot 1"1..Q~

Ft L's I I'lpitl ~

't..~

"1-

~I

....M-. .. "..:.. }.".J£ - I~ - ~S - ~d

/1-. ~()f)11r no JL .uJ L \-'(,,1. ,,~ \'-\4..,:)

EXE-1S P

I ToLai :.cnievec coverage A1R15-:uT:.023

~"T." ** ' t ( ) " . t Page 5of8

"'W"..~.llod""c:..m_ LIMITATION TO EXAM IHAnO N PROCEDURE PLANT Braidwood UNIT 1 SKETCH 1PZR-01 SKETCH stJ r^AIION SYST.lCOMP.

(per examination) = (Upstreeam scan +

RY I N3 DATE PROCEDURE EXE..fSI-210, J~~,,~ ~. _____ ___

EXAMINER reIl:t: &.n~ ~ ::

Pau l8; ev I DATE 1011212010 1

RELATED TO: UT x PT MT _ _ VT _ __

'DENT. NO. 1PZR-01-N3 PROVIDE GENERAL IHFORMA11OM TO DESCRiBE APPROXIMATE 8Il£,

'i 0 UNIT t, hOJ T E 70` coverage acri ;eved duriri L0CA11OM AND 1YPE Of UIllm'Al1ON.

45° & 80° CWICCW Exam & 0°

=

Total Exam Voiume length x Width x Height Downstream scan + CW scan + CCW

=

length 47.1"

=

Width 4.1" (1.7" weld crown and 1.2" on each side)

(904%+252%+ 63%+63%

=

Height 2.5" tevjht (in cross hatched area)

(47 10" x 4.1" x 2.5") :;: 482.8'*a j"; o:ai Achieved coverage (per scan) :z T.E.

Missed Volume = length x Width x Height (in cross hatched area) 1

~

L ength = 47 1" Area 1: (4710"x 1.0"x0.6")/2 = 14.13"

=14.13'*a Inner Radius Exam rlor to Nox a Exam.

Area 1: (47.10" x 1.0" x 0.6") 12 2: (47.10" x 1.4" x 2.5") = 164.85 "'

scan + 00 scan) / 5

~

16485"')= 179"'

Area 2: (47.10" x 1.4" x 2.5") = 164.8 5*

f otai Exam Volume = Lengtn x W^a V. - TMV. / T.E.V.

+ 63%)/5=

Area 1 .. Area 2: (14.13'*' + 164.as'*a) =17Q"a Total missed voiume =17I Width = 4 1" (11' wt d crown and 1. 2" on Ma sseo Volume = Length x Width x i-tri x H eight (4710"x41"x2. 5")-.482.8"'

TF Achieved coverage (per scan) =T.E.V. - T.M.V.I T.E.V.

452 8" - 179"' 1482 8 W 63%

482.8'" - 179*/4 82.8* = 63%

each side) m 7

Area 1 t- Area 2 (14 1 Achieved coverage =

Total Achieved coverage =

=

Achieved coverage (per examination) (Upstream scan + Downstream Height = 2 5' scan + CW scan + CCW scan + 0" scan) 15 (904% + 25.2% + 63% + 63% + 63%) 15 80.12% =

ita+ misseo volume= C SYS I iCOMf'.

NOTE 70" coveraGe achieved during Inner Radius Exam crior to Nome Exam.

EXAM NErZ L L-....... (...::J\,,-\... o

Braidwood L OVOI III RYIN3 INSPECTION IEJM CEI ,... of.

PROFILE OF THE EXAMINATION VOLUME/

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PROFILE OF THE EXAMINATION VOLUMEI DATA PLANT Braidwood UNIT 1 SKETCH 1PZR-01 DATE SYST/ COMP RY/N3 PROCEDURE EXE~SI-2101 Rev. 3 f~~.~ DATE WSPECTiON SERVICES EXAMINER 1011212010 100NT. 1PZR-01-N3 UNIT 10/12/2010 1

45-, 60* & O*

Cire Scans IDENT.

PROCEDURE SKETCH DATA __ UL~1

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ATTACHMENT 2-1 Weld 2PZR-01-N2 ATTACHMENT 2-1 Weld 2PZR-01-N2

m: B03.110 Type:

CCESS Austenitic

. RY I-210 /2 Single Sld.d C 171 0'F Msy 108888 h:

2.06250 Both " 0.80" T

INNDDICATT W Final Caiib. Date

~ .w_~ ,~ynii Final Calib. Intermediate Intermediate Initial Calib. Date Initial Calib.

NO Page X Data Sheet a Calibration Data Sheet X

Cal. Checks AW..t""V ....... ~ . . Co........

YES (>10% "I 1~_glE Plant I Unit Brai<tNood 1 2 Data Sheet

  • A2R15-UT-034 Calibration Data Sheet 1/ I~ lOIf FLAW Company Exelon 45.4 Page of 1

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Procedure No. 1-EXE-tSI-210 Rev I Chng. No. ULTRAGEL 11 cal. CheGka Time A21415-UT-034 3/1 COMPONENT TEMP:79'F Cal. Bkx:k No. of lJ In IW 10.45110: 60 BWI) 71 09:25110:39 09225E 08:12 / 08:21 4/27/2011 427/2011 Cal. Bkx:k Temp. 70*F IMiaI CaIib. 08:12/ 08:21 It ~ t; t.I t N/A Time Thefmometer 5nII: SAP 106888 .-. tJbIe Size 2ve 91 .5- Sen. NlA 12.0825- .,..

IrWaI CaIib. Date 3 412712011  :- ~~

I ~. : I. [!J F~ nAuat~ Intennediate 09:25/10:3Sl Type:

Size:

o.m 0.60" Search Unit 11 Search Unit 12 No. of Elemen :

Manufacture:

Each Major CRT DiY.

  • 1.0' Shap e:

Manufacture:

Round Intennediate KBA Manufadule:

Length: NlA KBA Cal. Difection: CJAxiaI 0 1 Serial No.: o1BfJV Serial No.: 00B954

[!] Boeh Serial No.:

Cin:.

Freq. 2.25 MHz Style:

Final Calib. 10:45/10:50 I

No. of ElementS: 1 No. of Elemei\tS: 1 Gamma instrument Settings Size: 1.a Shape: Round Size: 0.5- x 1,(1' Shape: Rect.

Search Unit Cable Scan Area: 12' LtoW eid [!] Freq. 2.25 MHz Styte: Gamma Sear Final CaIib. Date Freq. 2.25 MHz Styte:

ch II [!]

Unit i

412712011 Gamma 81 10 Weid Exam Exam Angle: o* Mode: long Exam AilgI8:

Mum-'^ -

45- Mode: Sh88i RG-174 AnfIte:-

Code Category: B-D Code Item: 803.110 Type:

Coupla nt UlTRAGEL II Measured Wedge Style:

NlA MeaauIed AnfIte:- 45*

No. of Integra! Wedge Styte:

KBA SWS Measured Angle:

Batch: 09225e

.. WA 1 Search Unit Cable Search Unit cable Wedge Style:

ACCESS Integral 0 Type: RG-174 Type: RG-17..

EJuunlnaUon Alva I Weld YEI Length: --.!L. NO. 01 con.: 0 Length: --.!L. NO. of con.:

2RY01S I 2PZR~1-N2 I S~ lnetrument SeUtng s 0

Type:

Rematlr.il RealOfl tor IncomDIete Scanta} Search Unit 1112 lnatnun ent Setting s NRI 88 5% Coverage 8CNeved.

Length: Marw Make 1 Modef: KBA I USN 58L SW factu re: KBA Make I Model: KBA I USN 58L SW Serial No.: SAP 106947 Serial No.: SAP 108947 Serial No.: 008954 Probe Delay: 0.9688 Range:

instrument Settings 4.0" Probe DeMay: 12 .* 1~ Range: 6.0" Square-Search Unit Cable 12' No. of Elemen M'U Call Vel: 0.2300 PuMr:

1 ~:

M'1I Call Vel: 0.1254 Pullet: Squa;;-

500 Refect: 0% Damping: 500 Re;ect: 0%

RG-174 Size: 0.5"x 1.0' Shap PRF: Auto High Freq: 2.25"MHz e: Red. PRF: Auto High Freq: 2.2sMHz Filter: Fixed No. of Freq. 2.25 MHz Style :

Mode: Dual Off FiItel: Fixed Mode: Dual Off Gamma Rectify: Fullwave Voltage : 450 Exam levef II Date 412712011 Pulse Wdth:

Rectify: Fulwav e Voltage : 450 N/A 5* Mode: s levef NlA 220 ns - PuIIe Wdth: 220 ns -

.. 0... NlA Disp6ay Delay: 0 Display Oeiay:

Measured Angl 0 e: 45' Reference SenaitM Iy (dB)

WeaOyne Reviewe r/Date:

0 -M4 1f &.. ..... /. ..7!L 0(-30-1/ Axial: 9.0 dB Reference SeoaitMty (dB)

Wedge Style: SWS Cin:: 9.0 dB Axial: 33 .* dB eire: 33.4 dB Further Evaluation Required?

2.5080 %02.0 dB FSDH Sensitivity: 1.8 CD 50'% CD 33.4 dB

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A ITACHMENT 2-2 Weld 2PZR-01-N3 ATTACHMENT 2-2 Weld 2PZR-01-N3

wedge Serest Probe Martu Make 1 No. of M'11 Ca Serial Size: Dampin PRF:

Axial:

Freq. Fitter:

Rectify:

Exam Pulse W Display Retarerc 1.0`

M'U Cal 1 Vel: 0.231 Putow. Square Mod. e: Long Shape: Round KBA / USN 58L SW SAP 106947 Damping:

iiS niS Calibration Data Sheet 500 0%

Search On N/A PRF: Auto High Freq: 2.25 MHz "l.l'II * * ~tOW"'i 4w...t. .~ . . i~~

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- KBA F ullwa ve Voltag e:

Gamma I System N3/RY Exam -

Pulse VAft:

0' 220 ns Serial No.:

Procedure No. EXE-ISI-210

-WaTiv Serial No.:

Rev Chng, No, 3/1 CaI.C heeb Time Display De4aj:

0 Measured Angle:

Cal, Bloc:<< No. BVVO 71 Releverwe Sect i ` (dB)

No. of Ele ments:

Cal, Bloc:<< Temp. 70*F Initial CaIib, 08:12/0 8:21 Axial:

Probe Delay: 0.

9.0 dB 1

Circ:

Wedge Style:

Thermometer SIN: SAP 106888 Size:

Size 91,5" sai, NlA 12,0625- Initial CaIib. Date ~712011 Freq.

..,... 1' Roai 8W. 2 I ~~ I [!] Intennediate 09:25/1 0:3S 08:12/08:21 09:25110:39 10:45/10:50 Fenitic Austenitic Search Unit 11 4127/2011 Search Unit f.2 412712011 ach Major CRT ON, == O.

Time 0.60" Manufacture:

N/A Intermediate NlA KBA Manufacture: KBA CJAxiaI 0 Serial No.: 018TJV at Oirection: Cire, I!l Both Final Caltb. 10:45/1 0:50 No. of Elements: 1 Serial No.:

No. of ElementS: 1 00lJ954 Scan Area: ..L to Weld Size:

Freq, 2.25 MHz ~: Gamma 1,(1 Shape: Round Size: 0,5" x 1,0" Shape: Red.

II toWeId Final CaJib. Date ~712011 Freq. 2,25 MHz Style: Gamma Exam Af\iiI8:

Cal. Checks O* Mode:

Initial Cabb. Date

..- - - - - . - - - - - . - . - - - - - - - --.--. (ong Exam AnQ18: 459 Modi: She8i Fiinal Calib. Date Mgte:-

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Coupia nt Measured NlA Code Category: 8-0 Code Item: Measured Angle: 45*

Intermediate iate 803,11 0 Type: UlTRAG Elll In"l° caw.

\IVedge Style: Integral Wedge Style: -..."S,. ,.,,'WS ,;;:----

Final Calib.

Batch: 09225E Search Unit Cab'e Search Unit Cabte lnte ACCESS fLAW Type:

Eumin atlon ANa , Weld RG-174 Type: RG-174 YES Length: --E:.... No. of con.: - length: --E:.... No. ot con,: - 2RY01S 12PZR..1-N3 "9 Sided 45.4 Instrument SeW .

Blma!!I' BeH90 f9r Incompfete Setn'&) lnatrument SeW .

ACCL.ii COMPONENT TEMP:79°F 6, ndwo:,d/2 i ^! b_!

NRI. 88,5% Covera ge achieve d.

70*F SWD 71 Mae I Model: KBA I USN 58l SW Make/ Model: KBA I USN 58l SW Exekon 3/1 Serial No.: SAP 106947 Serial No.: SAP 106947 nJ9 j 14 P1^ete Scan(5)

N31 RY Probe Delay: 0.9688 Range: 4,0" Probe Delay: 12.41~Range: 6,0" M'tJ Cal I Vel: 0.2300 PWMr. ~

iii4dt]{iiy Aroai I Wald M'U Cal 1 Vel: '0125i PWMr. §qua;;-

2RYOIS 12PLR-01-N3 6E 61-2 10 Damping: 500 Ratact: 0% Damping: 500 Ratact: 0%

PRf: Auto High Freq: 2,25 MHz PRf: Auto High freq: '"'2.'25"MHz INRi 88.5% Coverage achieved.

Filter: fixed Mode: Dual Off filler: fixed Mode: Dual Off Rectify: fuflwave Voltage:

"rom!!! JacKIiOn 450 Rectify: Fulwsve Voltage: 450 bi,xctc T&41, p, Examsnera II level Date NU.

412712011 i5* Pulse'Mdth: 220 ns - PuIae Wdth:

Procoajuie No Cal bk N/A level ~ Date 220 ns -

i cic No, NlA SAP t 34tsit Display Oeiay: 0 Disptay Oeiay:

Rijn ' Chou 0

YWIliIUVrI iI ReVIeWer I Date:

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treat VUli^tt i Reference SenaitMty (dB)

Axial: 9.0 dB Cire: 9.0 dB A.c^l>'

Reference Sensitivity (dB)

Axial: 33.4 dB Cire: 33.4 dB Fuf'ttle( Evaluation Reqund?

Sus 1* Rompu BW: 2,5 G 80% G 2,0 dB FSOH Senlitivity: 1,8 G 50% G 334 dB mONi...I!VIL* * *wTi:l.An r,^,

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