ML082550270

Response to Request for Additional Information Concerning Relief Requests Associated with the Second Inservice Inspection (ISI) Interval

ML082550270
Person / Time
Site:	Limerick
Issue date:	09/08/2008
From:	Cowan P Exelon Generation Co, Exelon Nuclear
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML082550270 (356)

Text

Exelon Nuclear www.exeloncorp.com Exek~n 200 Exelon Way Nuclear Kennett Square, PA 19348 10 CFR 50.55a September 8, 2008 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 Limerick Generating Station, Units 1 and 2 Facility Operating License Nos. NPF-39 and NPF-85 NRC Docket Nos. 50-352 and 50-353

Subject:

Response to Request for Additional Information Concerning Relief Requests Associated with the Second Inservice Inspection (ISI) Interval

References:

1) Letter from P. B. Cowan (Exelon Generation Company, LLC) to U.

S. Nuclear Regulatory Commission, "Submittal of Relief Requests Associated with the Second Inservice Inspection (ISI) Interval,"

dated January 28, 2008

2) Letter from P. J. Bamford (U. S. Nuclear Regulatory Commission) to C.

G. Pardee (Exelon Generation Company, LLC), "Limerick Generating Station, Unit Nos. 1 and 2 - Request for Additional Information Regarding Relief Requests Associated with the Second Inservice Inspection Interval," dated August 8, 2008 In the Reference 1 letter, in accordance with 10 CFR 50.55a, "Codes and standards," Exelon Generation Company, LLC (EGC), requested relief from the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI, "Rules for Inservice Inspection of Nuclear Power Plant Components." These reliefs apply to the second 10-year interval inservice inspection program, which concluded on January 31, 2007.

/ 47

Response to Request for Additional Information Submittal of Relief Requests Associated with the Second Inservice Inspection (ISI) Interval Page 2 In the Reference 2 letter, the U. S. Nuclear Regulatory Commission requested additional information. Attached is our response to this request.

No commitments are contained in this letter.

Should you have any questions concerning this letter, please contact Tom Loomis at (610) 765-5510.

Sincerely, Pamela B. Cowan Director - Licensing & Regulatory Affairs Exelon Generation Company, LLC Attachments: 1) Response to Request for Additional Information Regarding Relief Requests Associated With the Second Inservice Inspection Interval - Limerick Generating Station, Units 1 and 2

2) Revised Request for Relief RR-35

3) Relief Request 34 - LGS, Unit 1 Second Ten-Year Inservice Inspection Interval Component NDE Exam Limitations

4) Relief Request 34 - LGS, Unit 2 Second Ten-Year Inservice Inspection Interval Component NDE Exam Limitations

5) Relief Request 35 - LGS, Unit 1 Second Ten-Year Inservice Inspection Interval Component NDE Exam Limitations

6) Relief Request 35 - LGS, Unit 2 Second Ten-Year Inservice Inspection Interval Component NDE Exam Limitations cc: S. J. Collins, Regional Administrator, Region I, USNRC E. M. DiPaolo, USNRC Senior Resident Inspector, LGS P. Bamford, Project Manager [LGS] USNRC

1 Attachment Information Request for Additional With the to Associated

Response

Relief Requests Interval Regarding Inservice Inspection Second 1 and 2 Station, Units Limerick Generating

Response to Request for Additional Information Submittal of Relief Requests Associated with the Second Inservice Inspection (ISI) Interval Attachment 1 Limerick Generating Station, Units 1 and 2 Page 1 Question:

RR-34

1) Provide further detailed information to support the basis for each limited examination in RR-34, and therefore, demonstrate impracticality. This information should include detailed descriptions (with sufficient explanation, and lay-out or cross-sectional drawings/sketches) to enable the staff to fully understand the causes of ultrasonic scan limitations and their impact on examination volume coverage.

Response

The basis for each limited examination in RR-34, including detailed descriptions and drawings/sketches to enable the staff to fully understand the causes of ultrasonic scan limitations and their impact on examination volume coverage is contained in Attachment 3 "Relief Request 34 - LGS, Unit 1 Second Ten-Year Inservice Inspection Interval Component NDE Exam Limitations," and Attachment 4, "Relief Request 34 - LGS, Unit 2 Second Ten-Year Inservice Inspection Interval Component NDE Exam Limitations."

Question:

Background for RR-34, RAI number 2:

The submittal states the following regarding the scheduling and completion of examinations for LGS, Unit 2, RPV shell welds and nozzle-to-vessel welds:

The Unit 2 inspection interval was reduced to three outages to align the start of the Unit 2 interval with the Unit 1 interval. The remainderof the second interval inspections for Unit 2 will be completed during the first period of the third interval, per Relief Request 13R-01, Request for Relief for Alternative Requirements for the Synchronization of Ten-Year ISI Intervals Between Units 1 and 2 for [ASME Code] Class 1, 2, 3, MC [metal containment vessel], and CC [concrete containment] Components, which was approved in accordance with 10 CFR 50.55a(a)(3)(i).

2) Considering this realignment of the LGS Unit 2 schedule, confirm that all ASME Code-required RPV shell and nozzle weld examinations will be completed within 10 code years of the time when the exams were previously performed.

For example, the Unit 2 inspections, which were performed in the first period of the second ISI interval, should be performed again no later than the second period of the third ISI interval. Likewise, inspections which they performed in the second period of the second ISI interval should be performed no later than the third period of the third ISI interval.

Response

The ASME Code-required RPV shell and nozzle weld examinations will be completed within 10 code years from the time when the exams were previously performed to the extent practical in accordance with code rules, but not necessarily within the corresponding period of the third interval.

Response to Request for Additional Information Submittal of Relief Requests Associated with the Second Inservice Inspection (ISI) Interval Attachment 1 Limerick Generating Station, Units 1 and 2 Page 2 Question:

3) State whether the methods used for the RPV shell weld and nozzle-to-vessel weld inspections in RR-34 have been qualified in accordance with performance demonstration requirements per ASME Code, Section Xl, Appendix VIII.

Response

The examination methods used for the various vessel welds in RR-34 (i.e., ASME Section XI, Appendix VIII qualification or other method) are identified for each weld in Attachments 3 and 4.

We note that many of these welds were performed prior to the requirements of Appendix VIII.

Question:

4) Provide descriptions of the ultrasonic techniques deployed for each weld examination volume (near surface, inner 15%, and full volume), and the amount of coverage obtained for each of these techniques. Also, please provide cross-sectional drawings showing scanning angle coverage. List the materials for the base metal and welds.

Response

The ultrasonic techniques deployed for each weld examination volume, the amount of coverage obtained for each of these techniques, cross-sectional drawings showing scanning angle coverage, and the materials for the base metal and welds are contained in Attachments 3 and 4.

Question:

5) As applicable, describe nondestructive examination (NDE) equipment, show accessibility limitations, and discuss whether alternative methods or advanced technologies could be employed to maximize ASME Code coverage.

Response

The limited examinations listed in Relief Request 34 were completed using automated and/or manual techniques. The responses to questions 3 and 4 have shown the limitations of these examinations. As new ultrasonic techniques and tooling are qualified to ASME Section Xl, Appendix VIII the station reviews the new tooling and techniques to maximize the inspection coverage.

An example is the use of the phased array technology. Phased array search units are longer than those used in conventional examination techniques. In certain configurations, the search unit length actually reduces exam coverage. In those situations, the station continued to perform examinations using conventional examination techniques.

Several examinations are limited because there is no approved qualified method to perform the examination. Once a technique is qualified for this type of examination the station will implement this technology.

Response to Request for Additional Information Submittal of Relief Requests Associated with the Second Inservice Inspection (ISI) Interval Attachment 1 Limerick Generating Station, Units 1 and 2 Page 3 Question:

RR-35 RR-35 actually contains two requests, based on impracticality. Part 1 of the submittal states:

Pursuantto 10 CFR 50.55a(g)(5)(iii), relief is requested from the new examination coverage requirementsfor austeniticpiping welds with single side access as requiredin 10 CFR 50.55a(b)(2)(xv)(A)(2), on the basis that conformance with these Code requirements is impracticaldue to the fact that procedures were not available at the time of the examination of the welds to perform a single-sidedAppendix VIII demonstration using flaws on the opposite side of the weld.

Part 1 refers to the 10 CFR 50.55a requirement that, when applying ASME Section XI, Appendix VIII, Supplement 2, for ultrasonic procedures qualified by performance demonstration, full coverage credit on austenitic welds may only be claimed after a successful single-side demonstration has been performed with flaws located on the opposite side of the weld.

However, 10 CFR 50.55a(g)(5)(iii) only pertains to when ASME Code inservice inspection requirements are found to be impractical, not 10 CFR 50.55a rules. Based on this discussion the NRC staff has the following RAI:

1) Please either withdraw part 1 of RR-35, or re-submit it so that it reflects an ASME code requirement for which relief is being sought.

Response

RR-35 has been revised (see Attachment 2) to delete reference to 10 CFR 50.55a(b)(2)(xv)(A)(2). The relief request has also been revised to correct minor typographical errors.

Question:

Part 2 of the RR-35 submittal states:

Pursuantto 10 CFR 50.55a(g)(5)(iii), relief is also requestedfrom the 100% volumetric examination requirementsof Class 1 and 2 piping welds as defined by Table IWB-2500-1, Table IWC-2500- 1, and the Limerick Risk Informed Inservice Inspection Program, on the basis that conformance with these [ASME] Code requirementsis impracticaldue to component configurationand access restrictions.

Part 2 summarizes limited examinations performed during the second 10-year interval, and provides estimated coverage for each component. Some specific limitations, or causes, for less than ASME Code-required (100%) coverage are briefly listed in Tables RR-35-01 and RR 02, but these are insufficient to demonstrate impracticality.

Other diagrams are included in RR-35 to show typical pipe-to-valve and valve-to-flued head weld configurations, however, these also do not provide sufficient information to enable the staff to evaluate the welds under a basis of impracticality.

Response to Request for Additional Information Submittal of Relief Requests Associated with the Second Inservice Inspection (ISI) Interval Attachment 1 Limerick Generating Station, Units 1 and 2 Page 4 For RR-35, Part 2, the NRC staff requests the following (RAIs 2-5):

2) Provide further detailed information to support the basis for each limited examination in RR-35, and therefore, demonstrate impracticality. This information should include detailed descriptions (with sufficient explanation, and lay-out or cross-sectional drawings/sketches) to enable the staff to fully understand the causes of ultrasonic scan limitations and their impact on examination volume coverage.

Response

The basis for each limited examination in RR-35, including detailed descriptions and drawings/sketches to enable the staff to fully understand the causes of ultrasonic scan limitations and their impact on examination volume coverage is contained in Attachment 5, "Relief Request 35 - LGS, Unit 1 Second Ten-Year Inservice Inspection Interval Component NDE Exam Limitations," and Attachment 6, "Relief Request 35 - LGS, Unit 2 Second Ten-Year Inservice Inspection Interval Component NDE Exam Limitations."

Question:

3) Provide descriptions of the ultrasonic techniques deployed for each weld examination volume, and the amount of coverage obtained for each of these techniques. Also, please provide cross-sectional drawings showing scanning angle coverage. List the materials for the base metal and welds.

Response

The ultrasonic techniques deployed for each weld examination volume, the amount of coverage obtained for each of these techniques, cross-sectional drawings, the scanning angles, and the materials for the base metal and welds are contained in Attachments 5 and 6.

Question:

4) As applicable, describe NDE equipment, show accessibility limitations, and discuss whether alternative methods or advanced technologies could be employed to maximize ASME Code coverage.

Response

The limited examinations listed in Relief Request 35 were completed using manual techniques.

The responses to questions 2 and 3 have shown the limitations of these examinations. As new ultrasonic techniques and tooling are qualified to ASME Section XI, Appendix VIII the station reviews the new tooling and techniques to maximize the inspection coverage.

An example is the use of the phased array technology. Phased array search units are longer than those used in conventional examination techniques. In certain configurations, the search unit length actually reduces exam coverage. In those situations, the station continued to perform examinations using conventional examination techniques.

Response to Request for Additional Information Submittal of Relief Requests Associated with the Second Inservice Inspection (ISI) Interval Attachment 1 Limerick Generating Station, Units 1 and 2 Page 5 Several examinations are limited because there is no approved qualified method to perform the examination. A number of examinations were limited at Limerick because there is no qualified technique to perform a single sided examination of cast stainless steel. Once a technique is qualified for this type of examination the station will implement this technology.

Question:

5) State whether the methods used for the various piping welds in RR-35 have been qualified in accordance with performance demonstration requirements per ASME Section XI, Appendix VIII.

Response

The examination methods used for the various piping welds in RR-35 (i.e., ASME Section Xl, Appendix VIII qualification or other method) are identified for each weld in Attachments 5 and 6.

We note that many of these welds were performed prior to the requirements of Appendix VIII.

Attachment 2 Revised Request for Relief RR-35

Request for Relief (RR-35) for Limited Code Coverage on Piping Weld Examinations In Accordance with 10CFR50.55a(g)(5)(iii)

(Page 1 of 5) 1.0 ASME CODE COMPONENTS AFFECTED:

Code Class: 1 and 2

Reference:

Table IWB-2500-1 Table IWC-2500-1 Risk Informed ISI Program Examination Category: B-J, C-F-1, C-F-2, and R-A Item Number: B9.11, C5.11, C5.51, R1.11, R1.18, and R1.20

Description:

Limited Code Coverage on Piping Weld Examinations Component Number: Various Drawing Number: Various 2.0 APPLICABLE CODE EDITION AND ADDENDA:

The Second Interval Inservice Inspection program was based on the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code,Section XI, 1989 Edition, no Addenda.

3.0 APPLICABLE CODE REOUIREMENT:

ASME Section XI, 1989 Edition, required 100% volumetric examination of Class 1 and 2 piping welds as defined by Table IWB-2500-1, Table IWC-2500-1, and the Limerick Risk Informed Inservice Inspection Program.

4.0 IMPRACTICALITY OF COMPLIANCE:

Request for Relief (RR-35) for Limited Code Coverage on Piping Weld Examinations In Accordance with 10CFR50.55a(g)(5)(iii)

(Page 2 of 5)

Pursuant to 10 CFR 50.55a(g)(5)(iii), relief is requested from the 100% volumetric examination requirements of Class 1 and 2 piping welds as defined by Table IWB-2500-1, Table IWC-2500-1, and the Limerick Risk Informed Inservice Inspection Program, on the basis that conformance with these Code requirements is impractical due to component configuration and access restrictions.

Table RR-35-01 Unit 1 Limited Code Coverage on iping Weld Examinations Welds Name Class Coverage Item Notes CSB 015 12" Flued Head X- 16B to 1 50% R1.20 Austenitic material - Single sided exam due to Valve HV-52-108 valve to pipe flued head configuration.

DCA-101- I SW2402 6" Pup Piece to Valve HV- 1 50% R1.20 Austenitic material - Baseline examination 100%

44-1FOOI PT and 50% UT single sided examination due to valve to pipe configuration DCA-101-I SW2403 6" Valve HV-44-IFOO to 1 50% R1.20 Austenitic material - Baseline examination 100%

6" Pup Piece PT and 50% UT single sided examination due to valve to pipe configuration DCA-101-1 SW2406 6" Pup Piece to Valve HV- 1 50% R1.20 Austenitic material - Baseline examination 100%

44-1F004 PT and 50% UT single sided examination due to valve to pipe configuration.

DCA- 104-2 SW501 12" Pipe to Valve HV-5 1- 1 50% R .11 Austenitic material - Baseline exam - Single sided IF050A exam due to valve to pipe configuration.

DCA-104-4 SW1702 12" Valve HV-5 I-IF050A 1 50% R1.1 I Austenitic material - Baseline exam - Single sided CI to Pipe exam due to valve to pipe configuration.

GBB-105-2 FW 5 16" Valve HV-51-1FO16B 2 69.5% R1.20 Carbon Steel - Baseline examination limited due to to Pipe the valve configuration.

RH 004 20" Pipe to Valve 51-1F077 1 50% B9.11 Austenitic material - Single sided exam due to valve to pipe configuration.

RH 007 20" Pipe to Valve HV-5 1- 1 50% B9.11 Austenitic material - Single sided exam due to IF009 valve to pipe configuration.

RH 008 20" Valve HV-5 I- IF009 to 1 50% B9.11 Austenitic material - Single sided exam due to Pipe valve to pipe configuration.

RH 015 20" Flued Head X-12 to 1 50% R1.20 Austenitic material - Single sided exam due to Valve HV-5 I-I F008 valve to pipe flued head configuration.

RHA 002 12" Elbow to Valve 51- 1 50% B9.11 Austenitic material - Single sided exam due to 1F065A valve to pipe configuration.

RHA 003 12" Pipe to Valve 51- 1 50% B9.11 Austenitic material - Single sided exam due to IF065A valve to pipe configuration.

RHB 002 12" Elbow to Valve 51- 1 50% B9. 11 Austenitic material - Single sided exam due to IF065B valve to pipe configuration.

RHB 003 12" Valve 51-1 F065B to 1 50% B9.11 Austenitic material - Single sided exam due to Pipe valve to pipe configuration.

RRB 004 28"X28"X20" Tee to 28" 1 50% B9.11 Austenitic material - Single sided exam due to Pipe ipe to pipe tee configuration.

RRB 013 28" Pump IBP201 to Pipe 1 50% B9.11 Austenitic material - Single sided exam due to p ump to pipe configuration.

RRB 016 28" Pipe to Valve HV 1 50% B9.11 Austenitic material - Single sided exam due to IF031B valve to pipe configuration.

Request for Relief (RR-35) for Limited Code Coverage on Piping Weld Examinations In Accordance with 10CFR50.55a(g)(5)(iii)

(Page 3 of 5)

Table RR-35-01 Unit 1 Limited Code Coverage on Piping Weld Examinations Welds Name Class Coverage item Notes RW 020 6" Valve HV-44-IF004 to 2 50% C5.1I Austenitic material - Single sided exam due to 6" Pipe valve to pipe configuration.

Table RR-35-02 Unit 2 Limited Code Coverage on Piping Weld Examinations Welds Name Class Coverage Item Notes DBB-203-1 FW2 Valve HV-41-2F032A to 2 81.5% RI.1 I Carbon Steel - Limited examination due to angle 24"x24"xl 6" Reducing Tee R1.18 between the valve and the reducing tee.

DBB-204-1-1A SW7 24" Pipe to 24"x 6" 2 89% R .11 Carbon Steel - Limited examination due to weld Sweepolet RI. 18 geometry due to the severe angle between the 24-inch pipe and the 6-inch sweepolet.

DCA-201-1 FW 10 6" Pipe to Valve HV 1 50% B9.11 Austenitic material - Single sided exam due to 2F105 valve to pipe configuration.

DCA-201-1 SW 1402 6" Pipe to Valve HV-044- 1 50% B9.11 Austenitic material - Baseline exam - Single sided 2F001 exam due to valve to pipe configuration.

DCA-201-1 SW1403 Valve HV-044-2F001 to 6" 1 50% B9.11 Austenitic material - Baseline exam - Single sided Pipe exam due to valve to pipe configuration.

DCA-201-2 SW702 6" Pipe to HV-044-2F004 1 50% B9.11 Austenitic material - Baseline exam - Single sided exam due to valve to pipe configuration.

DCA-204-2 FW 1101 12" Pipe to Valve HV-05 1- 1 50% B9. 11 Austenitic material - Baseline exam - Single sided 2F050A exam due to valve to pipe configuration.

DCA,204-4 FW701 Valve HV-05 I-2F050A to 1 50% B9.11 Austenitic material - Baseline exam - Single sided 12" Pipe exam due to valve to pipe configuration.

DCA-205-1 FW9 Flued Head (X-12) to Valve 1 75% RI.20 Austenitic material - Limited examination due to HV-51-2F008 weld geometry DCB-202-1 FW 1002 6" Pipe to Pipe 2 50% C5.51 Austenitic material - Baseline exam - Single sided exam due to location of the weld. This weld is located very close to DCB-202-1 FWI003. The welds are so close that the area between the two welds cannot be examined.

DCB-202-1 FWI003 6" Pipe to Pipe 2 50% C5.51 Austenitic material - Baseline exam - Single sided exam due to location of the weld. This weld is located very close to DCB-202-1 FW 1002. The welds are so close that the area between the two welds cannot be examined.

DCB-202-1 SW1001 HV-044-2F004 to 6" Pipe 2 50% C5.11 Austenitic material - Baseline exam - Single sided exam due to valve to pipe configuration.

DLA-210-1 FW1 Valve HV-52-208 to Flued 1 71% R1.20 Austenitic material - Limited examination due to Head X- 16B weld geometry GBB-220-1 FW2 12" Pipe to Valve HV 2 50% C5.1 I Austenitic material - Single sided exam due to 2F0 15A valve to pipe configuration.

GBB-220-2 FW2 12" Pipe to Valve HV-5 1- 2 50% C5.11 Austenitic material - Single sided exam due to 2F015B valve to pipe configuration.

HBB-218-1 FW7 Valve HV-51-2F008 to 20" 2 50% C5.1 I Austenitic material - Single sided exam due to Pipe valve to pipe configuration.

Request for Relief (RR-35) for Limited Code Coverage on Piping Weld Examinations In Accordance with 10CFR50.55a(g)(5)(iii)

(Page 4 of 5) 5.0 BURDEN CAUSED BY COMPLIANCE The required ASME Code coverage is impractical for the subject welds since the components would require design modifications that would impose a significant burden to Exelon.

If access is available, the weld shall be ultrasonically scanned in both directions parallel to the weld and both directions perpendicular to the weld, where required. Full credit for examination coverage may be claimed for single side exams on ferritic piping welds.

However, for austenitic piping welds, an ultrasonic examination procedure must be qualified with flaws located in the inaccessible side of the weld.

There were no known qualified PDI ultrasonic examination procedures available for single side coverage that demonstrates equivalency to ultrasonic examination two-sided coverage on austenitic piping welds at the time of the examinations for the welds above.

At Limerick, qualified PDI ultrasonic examination techniques have been used since 2000.

However, qualified PDI procedures were not available at the time of the examination of the welds above to perform a single-sided Appendix VIII demonstration using flaws on the opposite side of the weld.

The table above provides the weld, the code required volume achieved, and the basis for not achieving full coverage. Figure 1 shows a typical configuration of a pipe to valve weld. Due to the valve taper, the examination is only acceptable from the piping side for austenitic piping welds. Figure 2 shows a typical configuration of a valve to flued head.

Due to the taper of the valve and flued head, only a limited examination can be performed.

Figure 1 Typical Pipe to Valve Weld Configuration Pipe valve

Request for Relief (RR-35) for Limited Code Coverage on Piping Weld Examinations In Accordance with 10CFR50.55a(g)(5)(iii)

(Page 5 of 5)

Figure 2 Typical Flued Head to Valve Valve Flued Head The inspection results for the limited weld examinations listed in tables RR-35-01 and RR-35-02 did not identify any reportable indications.

6.0 PROPOSED ALTERNATIVE AND BASIS FOR USE No alternate provisions are practical for the subject welds. Examinations were performed to the maximum extent practical.

7.0 DURATION OF PROPOSED ALTERNATIVE End of Interval relief is requested for the Second Ten-Year Inspection Interval for Limerick Generating Station Units 1 and 2, which ended on January 31, 2007.

8.0 PRECEDENTS

Similar relief requests have been approved for:

1. Oyster Creek Nuclear Generating Station (OCNGS) third inspection interval Relief Request OC-35 was approved in an NRC Safety Evaluation Report dated February 2, 2005. OCGNS Relief Request OC-35 also concerns compliance with Supplement 2 of Appendix VIII.

2. Browns Ferry Nuclear Plant, Unit 3 second inspection interval Relief Request 3-ISI-12 was approved in an NRC Safety Evaluation Report dated August 3, 2006.

The Browns Ferry Nuclear Plant, Unit 3 Relief Request 3-ISI-12 also concerns compliance with Appendix VIII for risk-informed welds examinations.

Attachment 3 Relief Request 34 - LGS, Unit 1 Second Ten-Year Inservice Inspection Interval Component NDE Exam Limitations

Weld: N1A Summary Number: 600640 Unit: 1 Item Number: B3.90 Outage: 1R10 (Spring 2004)

Coverage: 75.6%

Base Metal and Weld Materials: Carbon Steel Examination Volume: Full penetration coverage per figure IWB-2500-7 "Nozzle in Shell or Head" UT Exam Type: Automated UT Examination 0°L, 450 S, 60°RL, and 70°RL Performed per the requirements of ASME Code,Section XI, Appendix VIII:

Yes, the examination was in accordance with ASME Section XI Appendix VIII as modified by the PDI program.

Limitation

Description:

The completed examination was limited to 75.6% Code required coverage due to the design of the reactor vessel nozzle. The following coverage calculation sheet and the drawings contain the limitations. No unacceptable indications were noted. A system pressure test was also completed with no unacceptable indications observed.

Summary No.: 600640 Limerick Unit-1 Weld NiA Spring 2004 CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE Percent Weld Length = 360. Required Exam Area Scanned of Area Weld Length Percent Exam Volume = 58.7 Area Sq. In. Auto Auto Auto Auto 70' T-Scan A 11.1 6 10.2% 360 5.1%

45'. T-Scan A 39.2 34.4 58.6% 360 29.3%

60' T-Scan A 8.4 8.4 14.3% 360 7.2%

70ý P-Scan A 11.1 4.8 8.2% 360 4.1%

45' P-Scan A 392 28 47.7% 360 23.9%

IRS P-Scan A 8.4 7.2 12.3% 360 6.1%

70' T-Scan .. ..

45-' T-Scan 600 T-Scan 70' P-Scan 45' P-Scan '

IRS P-Scan 70' T-Scan 45" T-Scan 60_ T-Scan 70' P-Scan 45' P-Scan IRS P-Scan mI otal Composite Coverage= (n.tio76 Comments: A - Scanned 360 deg., Scanning limited due to nozzle configuration.

Note - Rounding methods may affect calculated values.

(D Limerick Unit-1 Recirc Outlet - N1 700 Exam Volume = 11.1 Sq. In.

450 Exam Volume = 39.2 Sq. In.

Inner 15%T Exam Volume (IRS & 60'T) = 8.4 Sq. In.

70° T-Scan achieved = 6.0 Sq. In.

450 T-Scan achieved = 34.4 Sq. In.

60° T-Scan achieved = 8.4 Sq. In.

-0.301, 70'T 45°T 60'T CD I 0

-h

--- I I

CDI 50.

Limerick Unit-1 Recirc Outlet - N1 70' Exam Volume = 11.1 Sq. In.

450 Exam Volume = 39.2 Sq. In.

Inner 15%T Exam Volume (IRS & 60'T) 8.4 Sq. In.

70' P-Scan achieved = 4.8 Sq. In.

450 P-Scan achieved = 28.0 Sq. In.

IRS P-Scan achieved = 7.2 Sq. In.

45'P1 D /-0.30 45'P2 CD

)-*-. ---

I __

Weld: N1B Summary Number: 600670 Unit: 1 Item Number: B3.90 Outage: 1R07 (Spring 1998)

Coverage: 60%

Base Metal and Weld Materials: Carbon Steel Examination Volume: Full penetration coverage per figure IWB-2500-7 "Nozzle in Shell or Head" UT Exam Type: Automated UT Examination 0°L, 450S, and 60°S Performed per the requirements of ASME Code, Section Xl, Appendix VIII:

No, the examination was performed to requirements contained in ASME Section XI, Section V, and Reg Guide 1.150. This was the approved technical guidance at the time of the examination.

Limitation

Description:

The completed examination was limited to 60% Code required coverage due to the design of the reactor vessel nozzle. The following coverage calculation sheet and the drawings contain the limitations. No unacceptable indications were noted. A system pressure test was also completed with no unacceptable indications observed.

Limerick Unit I NIB Nozzle CROSS SECTIONAL AREA (per slice) 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 O Wm 58.61 24.64 0 42.04 0.00 360 0.0 42.0 0.0 45 T-scan 58.61 45.69 0 77.96 0.00 360 0.0 78.0 0.0 60 T-scan 58.61 49.69 0 84.78 000 360 0.0 84.8 0.0 45 P-scan CW 58.61 28.71 0 48.98 0.00 360 0.0 49.0 0.0 60 P-scan CW 58.61 34.43 0 58.74 0.00 360 0.0 58.7 0.0 45 P-scan CCW 58.61 28.71 0 48.98 0.00 360 0.0 49.0 0.0 60 P-scan CCW 58.61 34.43 0 58.74 0.00 360 0.0 58.7 0.0 Coverages 60.0 0.0 Total coverage 60.0 Automated scans were not restricted No credit taken for initial 1/4" of materialin Code co verage calculationsdue to near field effects.

4,3r C>.

Limerick 1 Recirculation Outlet NiB Nozzle 0OL-wave weld metal exam coverage m-m -~

Limerick 1 Recirculation Outlet N1B Nozzle 45" and 60" T-Scan exam coverage

-o 0 _

60'T

~ C~)

p

(

Limerick 1 Recirculation Outlet N1 B Nozzle 45" and 60' P-Scan exon coverage

0 r- 45" CD

Weld: N2A Summary Number: 600700 Unit: 1 Item Number: B3.90 Outage: 1R07 (Spring 1998)

Coverage: 61.9%

Base Metal and Weld Materials: Carbon Steel Examination Volume: Full penetration coverage per figure IWB-2500-7 "Nozzle in Shell or Head" UT Exam Type: Automated UT Examination 0L, 451S, and 60°S Performed per the requirements of ASME Code, Section Xl, Appendix VIII:

No, the examination was performed to requirements contained in ASME Section XI, Section V and Reg Guide 1.150. This was the approved technical guidance at the time of the examination.

Limitation

Description:

The completed examination was limited to 61.9% Code required coverage due to the design of the reactor vessel nozzle. The following coverage calculation sheet and the drawings contain the limitations. No unacceptable indications were noted. A system pressure test was also completed with no unacceptable indications observed.

Limerick Unit I N2A Nozzle CROSS SECTIONAL AREA (perslice) 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 o wm 59.43 27.33 0 45.99 0.00 360 0.0 46.0 0.0 45 T-scan 59.43 45.87 0 17.18 0.00 360 0.0 772 0.0 60 T-scan 59A43 4982 0 83.83 0.00 360 0.0 83.8 0.0 45 P-scan CW 59.43 32.84 0 55.26 0.00 360 0.0 55.3 0.0 60 P-scan CW 59.43 34.36 0 57.82 CCW 0.00 360 0.0 578 0.0 45 P-scan 59.43 32.84 0 55.26 CCW 0.00 360 0.0 55.3 0.0 60 P-scan 59.43 34.36 0 57.82 0.00 360 0.0 578 0-0 Coverages 61.9 0.0 Total coverage 61.9 Automated scans were not restricted No credit taken for initial 1/4'o materialin Code coverage calculationsdue to nearfield effects.

V110L 6Ur-'1--0h*f ý3HGUPý APR 2 0 SA

A~EVir2WED PECGO EnfgY GO' APR 2 0 '98 WNiE SUJPPORT GROup~6 &b Limerick 1 RECIRCULATION INLET N2A 0' L-wave weld metal exam coverage

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0! L-wove t >

EV'iV4ED PECO Enr W~ESUFP~O rQT f A-' OR Limeric k 1 RECIRCUL.ATION INLET N2A 45' and 60 T-scon s examination coverage S ,0.,

REV IE EDPiz-GO .

G.a,* r . /t -*I7K kIEV1Efl ~ ~~OO 276aAPR 2 0' Limeric k 1 RECIRCUL .ATION INLET N2A 60" and 45" P- -scan exam coverage

/I 60 45" 5!-'-

1 A6!P-scanI 60" P-scan M-*o *_ in C-)

Weld: N2B Summary Number: 600730 Unit: 1 Item Number: B3.90 Outage: 1R09 (Spring 2002)

Coverage: 59.3%

Base Metal and Weld Materials: Carbon Steel Examination Volume: Full penetration coverage per figure IWB-2500-7 "Nozzle in Shell or Head" UT Exam Type: Automated UT Examination 0°L, 450S, 60 0 S and 70°RL Performed per the requirements of ASME Code, Section Xl, Appendix VIII:

No, the examination was performed to requirements contained in ASME Section X1,Section V and Reg Guide 1.150. This was the approved technical guidance at the time of the examination.

Limitation

Description:

The completed examination was limited to 59.3% Code required coverage due to the design of the reactor vessel nozzle. The following coverage calculation sheet and the drawings contain the limitations. No unacceptable indications were noted. A system pressure test was also completed with no unacceptable indications observed.

Limerick Unit I N2B Spring 2002 CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE Area Scanned  % of Area Scanned Degrees Scanned  % Scanned 2

o Area Inch Auto Manual Auto Manual Auto Manual Auto Manual 0' WELD METAL N 63.21 27.33 0.0 43.2 0,0 360.0 0.0 43.2 0.0 45' T-SCAN N 63,21 45.87 0.0 72 6 00 360.0 0.0 72,6 0.0 60' T-SCAN Y 63.21 49.84 0.0 78.8 0.0 360.0 0.0 78.8 0.0 450 P-SCAN CW N 63.21 32.76 0.0 51.8 0.0 360.0 0.0 51.8 0.0 60' P-SCAN CW N 63.21 36.97 0.0 58.5 0.0 360.0 0.0 58.5 0.0 45' P-SCAN CCW N 63.21 32.76 0.0 51.8 0.0 360.0 0.0 51.8 0.0 60' P-SCAN CCW N 63.21 36.97 0.0 58.5 0.0 360.0 0.0 58.5 0.0 59.3 0.0 Total 0', 450 and 60° Coverage = 59.3 70ý T-SCAN N 22.67 10.53 0.0 46.4 0.0 360.0 0.0 46.4 0.0 7(Y P-SCAN CW N 22.67 7.82 0.0 34.5 0.0 360.0 0.0 34.5 0.0 70* P-SCAN CCW N 22.67 7.82 0.0 34 5 0.0 360.0 0.0 34.5 0.0 38.5 00 Total 700 Coverage = 38.5 COMMENTS:

Automated UT scans were limited due to the nozzle radius.

Credit for the initial 114" of material in code coverage taken with the 700 I 02.....1 02/29101 2

-I

Limerick 1 Recirculation Inlet Code Required Exam Volume - 63.21 Sq. In.

0* L-Wave Exam Volume - 27.33 Sq. In.

vi rn,

Limerick 1 Recirculation Inlet Code Required Exam Volume - 63.21 Sq. In.

450 T-Scan Exam Volume - 45.87 Sq. In.

60* T-Scan Exam Volume - 49.84 Sq. In.

-n

)

Limerick 1 Recirculation Inlet Code Required Exam Volume - 63.21 Sq. In.

455 P-Scan Exam Volume - 32.76 Sq. In.

60* P-Scan Exam Volume - 36.97 Sq. In.

I

~2

Limerick 1 Recirculation Inlet Code Required Exam Volume - 22.67 Sq. In.

70' T-Scan Exam Volume -10.53 Sq. In.

70' P-Scan Exam Volume -7.82 Sq. In.

70'P

• 1

Weld: N2C Summary Number: 600760 Unit: 1 Item Number: B3.90 Outage: 1R09 (Spring 2002)

Coverage: 51.9%

Base Metal and Weld Materials: Carbon Steel Examination Volume: Full penetration coverage per figure IWB-2500-7 "Nozzle in Shell or Head" UT Exam Type: Automated UT Examination 0°L, 450S, 60 0 S and 70°RL Performed per the requirements of ASME Code,Section XI, Appendix VIII:

No, the examination was performed to requirements contained in ASME Section Xl,Section V and Reg Guide 1.150. This was the approved technical guidance at the time of the examination.

Limitation

Description:

The completed examination was limited to 51.9% Code required coverage due to the design of the reactor vessel nozzle and the location of the N8A nozzle. The following coverage calculation sheet and the drawings contain the limitations. No unacceptable indications were noted. A system pressure test was also completed with no unacceptable indications observed.

Limerick Unit I N2C Spring 2002 CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE Area Scanned  % of Area Scanned Degrees Scanned  % Scanned 2 Auto Manual 0 Area Inch Auto Manual Auto Manual Auto Manual 0° WELD METAL N 63.21 27.33 0.0 43.2 0.0 360.0 0.0 43.2 0.0 45' T-SCAN N 63 21 45.87 0.0 72.6 00 360.0 0.0 72.6 0.0 60' T-SCAN Y 63.21 49.84 0.0 78.8 0.0 321.0 0.0 70.3 0.0 60' T-SCAN Y 63.21 48.18 0.0 76.2 0.0 39.0 0.0 8.3 0.0 45Y P-SCAN CW N 63.21 32.76 0.0 5118 0.0 360.0 0.0 51.8 0.0 60' P-SCAN CW N 63.21 36.97 0.0 58.5 0.0 360.0 0.0 58.5 0.0 45' P-SCAN CCW N 63.21 32.76 0.0 51.8 0.0 360.0 0.0 51.8 0.0 60' P-SCAN CCW N 63.21 36.97 0.0 58.5 0.0 360.0 0.0 58.5 0.0 51.9 0.0 Total 0, 450 and 600 Coverage = 51.9 70 T-SCAN N 22.67 10.53 0.0 46.4 0,0 360.0 0.0 46.4 0.0 70' P-SCAN CW N 22.67 7.82 0.0 34.5 0.0 360.0 0,0 34 5 00 70' P-SCAN CCW N 22,67 7.82 0.0 34.5 0.0 360.0 0.0 34.5 0 0 38.5 0.0 Total 70' Coverage 38.5 0.

COMMENTS:

utou*aIed Credit for the scans114" u Iinitial were iitleg of material due to thet*nvernan in icoda nozzle radius.

t=.,n .,,ifkh. -7fhl lCredit for the initial 1/4" of material in code covera e taken with Ih 7n- I

=1

N2C Exam Limited Due to N8A Nozzle 45°/60° Transverse Scan Area Scanned Without Limitation 321" 163* az.

Short arm scan in limited area only -

124" az.

N

Limerick 1 Recirculation Inlet Code Required Exam Volume - 63.21 Sq. In.

0* L-Wave Exam Volume - 27.33 Sq. In.

/

(

J

Limerick 1 Recirculation Inlet Code Required Exam Volume - 63.21 Sq. In.

450 T-Scan Exam Volume - 45.87 Sq. In.

60* T-Scan Exam Volume - 49.84 Sq. In.

III I 60'T I

0:

-c

Limerick 1 Recirculation Inlet Code Required Exam Volume - 63.21 Sq. In.

45* P-Scan Exam Volume - 32.76 Sq. In.

60* P-Scan Exam Volume - 36.97 Sq. In.

I' 0-

Limerick 1 Recirculation Inlet N2C 600 T-Scan exam area limited due to N8A nozzle Code Required Exam Volume - 63.21 Sq. In.

60* T-Scan Exam Volume - 48.18 Sq. In.

-13.35" .1

Limerick 1 Recirculation Inlet Code Required Exam Volume - 22.67 Sq. In.

70* T-Scan Exam Volume -10.53 Sq. In.

70° P-Scan Exam Volume -7.82 Sq. In.

-0* 70'T 1707' 0*

Weld: N2D Summary Number: 600790 Unit: 1 Item Number: B3.90 Outage: 1R07 (Spring 1998)

Coverage: 61.9%

Base Metal and Weld Materials: Carbon Steel Examination Volume: Full penetration coverage per figure IWB-2500-7 "Nozzle in Shell or Head" UT Exam Type: Automated UT Examination 0°L, 450S, and 60 0 S Manual UT Examination was performed in area obstructed by the N8A nozzle.

This was performed to increase code coverage.

Performed per the requirements of ASME Code, Section Xl, Appendix VIII:

No, the examination was performed to requirements contained in ASME Section Xl,Section V, and Reg Guide 1.150. This was the approved technical guidance at the time of the examination.

Limitation

Description:

The completed examination was limited to 61.9% Code required coverage due to the design of the reactor vessel nozzle and the location of the N8A nozzle. The following coverage calculation sheet and the drawings contain the limitations. No unacceptable indications were noted. A system pressure test was also completed with no unacceptable indications observed.

Limerick Unit I N2D Nozzle CROSS SECTIONAL AREA (per slice) 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 0 wm 59.43 27.33 0 45.99 0.00 360 0.0 46.0 0.0 45 T-scan 59.43 45.87 0 77.18 0.00 360 0.0 7.2 0.0 60 T-scan 59.43 49.82 49.82 83.83 83.83 300 60.0 69.9 14.0 45 P-scan CW 59.43 32.84 0 55.26 0.00 360 0.0 55.3 0.0 60 P-scan Cw 59.43 34,36 0 51.82 0.00 360 0.0 5Z8 0.0 45 P-scan CCw 59.43 32.84 0 55.26 0.00 360 0.0 55.3 0.0 60 P-scan CCw 59.43 34.36 0 57.82 0.00 360 0.0 57.8 0.0 Co verages 59.9 2.0 Total coverage 61.9 No credit taken for initial 14' of materialin Code coverage calculations due to near field effects.

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• reca due NBA 750 710 N84 N r.

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14" j PAPR? 72 Limeric k 1 RECIRCUL ATION INLET N2D 45" and 60" T-scans examination coverage 6V 60" T I 4 T 45"TI

'TJ, "- *Z .. .

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-lEV1EWD Supp oeftf~Ener,';CO.."

PECO GROUP'-'-,c APR P 2 7.'98 9

LimE,rick 1 RECIR CULATION INLET N2D 60' and 415 P-scan exam coverage I

I60 P-scan I 4q~-A

Weld: N2E Summary Number: 600820 Unit: 1 Item Number: B3.90 Outage: 1 R09 (Spring 2002)

Coverage: 59.3%

Base Metal and Weld Materials: Carbon Steel Examination Volume: Full penetration coverage per figure IWB-2500-7 "Nozzle in Shell or Head" UT Exam Type: Automated UT Examination 00 L, 450S, 600S and 70°RL Performed per the requirements of ASME Code,Section XI, Appendix VIII:

No, the examination was performed to requirements contained in ASME Section XI, Section V and Reg Guide 1.150. This was the approved technical guidance at the time of the examination.

Limitation

Description:

The completed examination was limited to 59.3% Code required coverage due to the design of the reactor vessel nozzle. The following coverage calculation sheet and the drawings contain the limitations. No unacceptable indications were noted. A system pressure test was also completed with no unacceptable indications observed.

Limerick Unit I N2E Spring 2002 CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE Area Scanned  % of Area Scanned Degrees Scanned  % Scanned M 2 0 Area Inch Auto Manual Auto Manual Auto Manual Auto Manual 0: WELD METAL N 63.21 27.33 0.0 43.2 0.0 360.0 0.0 43.2 0.0 45ý T-SCAN N 63 21 45.87 0.0 72 6 0.0 360.0 0.0 72 6 0 0 60' T-SCAN Y 63.21 49.84 0.0 78,8 0.0 360.0 0.0 78.8 0.0 Y 0.0 45Y P-SCAN CW N 6321 32.76 0.0 51.8 0.0 360.0 0.0 51.8 0.0 60' P-SCAN CW N 63.21 36.97 0.0 58,5 0.0 360.0 0.0 58.5 0.0 45' P-SCAN CCW N 63.21 32.76 0.0 51.8 0.0 360.0 0.0 51.8 0.0 60' P-SCAN CCW N 63.21 36.97 0.0 58.5 0.0 360.0 0.0 58.5 0-0 59.3 0.0 Total 00, 45* and 600 Coverage 59.3 70° T-SCAN N 22.67 10.53 0.0 46.4 0.0 360.0 0.0 46.4 0.0 7G' P-SCAN CW N 22.67 7.82 0.0 34.5 0.0 360.0 0.0 34.5 0.0 70' P-SCAN CCW N 22.67 7.82 0.0 34.5 0.0 360.0 0.0 34.5 0.0 38.5 0.0 Total 700 Coverage 38.5

• 1 1~ V

~1..D COMMENTS:

Automated UT scans were limited due to the nozzle radius.

Credit for the initial 1/4" of material in code coverage taken with the 700 = .......

102/29/01

Limerick 1 Recirculation Inlet Code Required Exam Volume - 63.21 Sq. In.

0* L-Wave Exam Volume - 27.33 Sq. In.

/

N

Limerick 1 Recirculation Inlet Code Required Exam Volume - 63.21 Sq. In.

45* T-Scan Exam Volume - 45.87 Sq. In.

60* T-Scan Exam Volume - 49.84 Sq. In.

60"T I 2; 1 ~.D n

'1 C -~

3..

,3

,4

Limerick 1 Recirculation Inlet Code Required Exam Volume - 63.21 Sq. In.

45* P-Scan Exam Volume - 32.76 Sq. In.

60° P-Scan Exam Volume - 36.97 Sq. In.

/

(

Limerick 1 Recirculation Inlet Code Required Exam Volume - 22.67 Sq. In.

70" T-Scan Exam Volume -10.53 Sq. In.

70" P-Scan Exam Volume -7.82 Sq. In.

• 707 70*

Weld: N2F Summary Number: 600850 Unit: 1 Item Number: B3.90 Outage: 1R07 (Spring 1998)

Coverage: 61.9%

Base Metal and Weld Materials: Carbon Steel Examination Volume: Full penetration coverage per figure IWB-2500-7 "Nozzle in Shell or Head" UT Exam Type: Automated UT Examination 0°L, 450S, and 60 0 S Performed per the requirements of ASME Code,Section XI, Appendix VIII:

No, the examination was performed to requirements contained in ASME Section Xl,Section V, and Reg Guide 1.150. This was the approved technical guidance at the time of the examination.

Limitation

Description:

The completed examination was limited to 61.9% Code required coverage due to the design of the reactor vessel nozzle. The following coverage calculation sheet and the drawings contain the limitations. No unacceptable indications were noted. A system pressure test was also completed with no unacceptable indications observed.

Limerick Unit I N2F Nozzle CROSS SECTIONAL AREA (perslice) 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 0 wm 59.43 27.33 0 45.99 0.00 360 0.0 46.0 0.0 45 T-scan 59.43 45.87 0 77.18 0.00 360 0.0 772 0.0 60 T-scan 59.43 49.82 0 83.83 0.00 360 0.0 83.8 0.0 45 P-scan CW 59.43 32.84 0 55.26 0.00 360 0.0 55.3 0.0 60 P-scan CW 59.43 34.36 0 5782 0.00 360 0.0 578 0.0 45 P-scan CCW 59.43 32.84 0 55.26 0.00 360 0.0 55.3 0.0 60 P-scan CCW 59.43 34.36 0 57.82 0.00 360 0.0 57.8 0.0 Coverages 61.9 0.0 Total coverage 61.9 S Automated scans were not restricted No credit taken for initial I/4' of materialin Code coverage calculationsdue to nearfield effects.

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&PRT 0.,. QR0U P I{y ,- APR 2 7 '98 Limerick 1 RECIRCULATION INLET N2F O" L-wave weld metal exam coverage I

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0O L-wave Fn

P~7CO ~y,.

I~-,IIJII APP~2 Limerick 1 RECIRCULATION INLET N2F 45" and 60" T-scons examination coverage

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...... XiýAPR*2 7 '98 Lim( rick 1 RECIR CULATION INLET N2F 60' and 4 5" P-scan exam coverage II 45" PL-scan 60" P-scan 1 60P-scan

Weld: N2J Summary Number: 600940 Unit: 1 Item Number: B3.90 Outage: 1R10 (Spring 2004)

Coverage: 77.0%

Base Metal and Weld Materials: Carbon Steel Examination Volume: Full penetration coverage per figure IWB-2500-7 "Nozzle in Shell or Head" UT Exam Type: Automated UT Examination 0°L, 451S, 60°RL, and 70°RL Performed per the requirements of ASME Code,Section XI, Appendix VIII:

Yes, the examination was in accordance with ASME Section XI Appendix VIII as modified by the PDI program.

Limitation

Description:

The completed examination was limited to 77.0% Code required coverage due to the design of the reactor vessel nozzle and the location of the N8B nozzle. The following coverage calculation sheet and the drawings contain the limitations. No unacceptable indications were noted. A system pressure test was also completed with no unacceptable indications observed.

Summary No.: 600940 Limerick Unit-1 Weld N2J Spring 2004 CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE Percent Weld Length = 360. Required Exam Area Scanned of Area Weld Length Percent Exam Volume = 59.7 Area Sq. In. Auto Auto Auto Auto 70Q'T-Scan A 12 5.8 9.7% 360 4.9%

45' T-Scan A 39.2 33.5 56.1% 360 28.1%

600 T-Scan B 8.5 8.5 14.2% 312.8 6.2%

70' P-Scan A 12 4.5 7.5% 360 3.8%

45' P-Scan A 39.2 31,3 52.4% 360 26.2%

IRS P-Scan A 8.5 8.5 14.2% 360 7.1%

70' T-Scan 450 T-Scan 60" T-Scan B 8.5 7.2 12.1% 47.2 0.8%

70' P-Scan 45' P-Scan IRS P-Scan 70' T-Scan __

45' T-Scan 60" T-Scan 70' P-Scan 45' P-Scan _

IRS P-Scan

%/Total Composite Coverage = 77.0%

Comments: A - Scanned 360 deg., Scanning limited due to nozzle configuration.

B - 60'RL limited due to the proximity of the N8B nozzle.

iNote - Rounding methods may atiect calculated values.

/

/

'7 1~

/

rea scanned~ 31?.So 120 limitec4 47,2'

/

/,

60' RL Uieited due to proximity of N8B CIO Z-7 (e

-7

Limerick Unit-1 Recirc Inlet - N2 N70' Exam Volume = 12.0 Sq. In.

45' Exam Volume = 39.2 Sq. In.

Inner 15%T Exam Volume (IRS & 60'T) 8.5 Sq. In.

70ý T-Scan achieved = 6.1 Sq. In.

45' T-Scan achieved = 34.5 Sq. In.

60' T-Scan achieved = 8.5 Sq. In.

7T 45-T

/I

'.7.-.-"/y"_ .,/ I _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _

Limerick Unit-1 Recirc Inlet - N2 700 Exam Volume = 12.0 Sq. In.

450 Exam Volume = 39.2 Sq. In.

Inner 15%T Exam Volume (IRS & 60T) = 8,5 Sq. In.

70o P-Scan achieved = 4.8 Sq. In.

450 P-Scan achieved = 33.6 Sq. In.

IRS P-Scan achieved = 8.5 Sq. In,

./ ~~70 'P5P Z S:aoi f-2Iannaf 45*P2 45;P1 K---- -- --- /

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Limerick Unit-1 Recirc Inlet - N2J 600 RL limited due to N8B nozzle 70W Exam Volume = 12.0 Sq. In.

45' Exam Volume = 39.2 Sq. In.

Inner 15%T Exam Volume (IRS & 60'T) 8.5 Sq. In.

700 T-Scan achieved = 6.1 Sq. In.

45' T-Scan achieved = 34.5 Sq. In.

60' T-Scan achieved = 7.2 Sq. In.

I *" ~13.35" -

start

-0 3 Scanner 70 T 45 T 60 1

/1 / /

"" ! J ' [. - .. .

Weld: N2K Summary Number: 600970 Unit: 1 Item Number: B3.90 Outage: 1R10 (Spring 2004)

Coverage: 80.4%

Base Metal and Weld Materials: Carbon Steel Examination Volume: Full penetration coverage per figure IWB-2500-7 "Nozzle in Shell or Head" UT Exam Type: Automated UT Examination 0°L, 450S, 60°RL, and 70°RL Performed per the requirements of ASME Code, Section Xl, Appendix VIII:

Yes, the examination was in accordance with ASME Section XI Appendix VIII as modified by the PDI program.

Limitation

Description:

The completed examination was limited to 80.4% Code required coverage due to the design of the reactor vessel nozzle. The following coverage calculation sheet and the drawings contain the limitations. No unacceptable indications were noted. A system pressure test was also completed with no unacceptable indications observed.

Summary NO.:

bUU~J/U I 5ummary No.: 6009 / u Limerick Unit-1 Weld N2K Spring 2004 CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE Percent Weld Length = 360. Required Exam Area Scanned of Area Weld Length Percent Exam Volume = 59.7 Area Sq. In. Auto Auto Auto Auto 70' T-Scan A 12 6,1 10.2% 360 5.1%

45ý T-Scan A 39.2 34.5 57,8% 360 28.9%

60" T-Scan A 8.5 8.5 14.2% 360 7.1%

70" P-Scan A 12 4.8 8.0% 360 4.0%

45" P-Scan A 39.2 33.6 56.3% 360 28.1%

IRS P-Scan A 8.5 8.5 14.2% 360 7,1%

70' T-Scan 45" "T-Scan 60W T-Scan "

70W P-Scan 45' P-Scan IRS P-Scan 70, T-Scan 45' T-Scan 600 T-Scan 70' P-Scan 45' P-Scan IRS P-Scan '_'_'

% Total Composite Coverage = 80.4%

Comments: A - Scanned 360 deg., Scanning limited due to nozzle configuration.

Note - Rounding methods may affect calculated values.

Limerick Unit-1 Recirc Inlet - N2 70' Exam Volume = 12.0 Sq. In.

, 45' Exam Volume = 39.2 Sq. In.

Inner 15%T Exam Volume (IRS & 6WT) 8.5 Sq. In.

70' T-Scan achieved = 6.1 Sq. In.

45'T-Scan achieved 34.5 Sq. In.

60' T-Scan achieved = 8.5 Sq. In.

// 0 .3Scanner sian7 t //

/1 , /:\I 1! I

," L-

Limerick Unit-1 Recirc Inlet - N2 70" Exam Volume = 12.0 Sq. In.

45' Exam Volume = 39.2 Sq. In, Inner 15%T Exam Volume (IRS & 60-T) = 8.5 Sq. In.

70' P-Scan achieved = 4.8 Sq. In.

45' P-Scan achieved = 33.6 Sq. in.

IRS P-Scan achieved = 8.5 Sq. In.

Scarlle r Slart JO.,0 70"P 455P2 45 P1 F--- / _

I

Weld: N3A Summary Number: 601000 Unit: 1 Item Number: B3.90 Outage: 1R09 (Spring 2002)

Coverage: 58.2%

Base Metal and Weld Materials: Carbon Steel Examination Volume: Full penetration coverage per figure IWB-2500-7 "Nozzle in Shell or Head" UT Exam Type: Automated UT Examination 0L, 45'S, 600S and 70ORL Performed per the requirements of ASME Code, Section Xl, Appendix VIII:

No, the examination was performed to requirements contained in ASME Section Xl,Section V, and Reg Guide 1.150. This was the approved technical guidance at the time of the examination.

Limitation

Description:

The completed examination was limited to 58.2% Code required coverage due to the design of the reactor vessel nozzle. The following coverage calculation sheet and the drawings contain the limitations. No unacceptable indications were noted. A system pressure test was also completed with no unacceptable indications observed.

Limerick Unit I N3A Spring 2002 CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE Area Scanned  % of Area Scanned Degrees Scanned  % Scanned 2 Manual Auto Manual 0 Area Inch Auto Manual Auto Manual Auto U0 WELD METAL N 75.6 34.03 0.0 45.0 0.0 360.0 0.0 45.0 0.0 45"T-SCAN N 756 57.36 0.0 75.9 00 360.0 0.0 75 9 00 60WT-SCAN Y 75.6 63.37 0.0 83.8 0.0 360.0 0.0 83.8 0.0 45' P-SCAN CW N 75.6 35.56 0.0 47.0 0.0 360.0 0.0 47.0 0.0 60W P-SCAN CW N 75.6 41.16 0.0 54.4 0.0 360.0 0.0 54.4 0.0 45' P-SCAN CCW N 75.6 35.56 0.0 47.0 0.0 360.0 0.0 47.0 0.0 60' P-SCAN CCW N 75.6 41.16 0.0 54.4 0.0 360.0 0.0 544 0.0 58.2 0.0 Total 0%, 450 and 600 Coverage = 58.2 70; T-SCAN N 70ý P-SCAN CW N 70" P-SCAN CCW N Total 70° Coverage = 39.9 COMMENTS:

,l'

Limerick 1 Main Steam (N3 Nozzle)

Code Required Exam Volume - 75.60 Sq. In.

L-Wave Weld Metal Exam volume - 34.03 Sq. In.

I d

N Limerick 1 Main Steam (N3 Nozzle)

Code Required Exam Volume - 75.60 Sq. In.

450 T-Scan Exam volume - 57.36 Sq. In.

60* T-Scan Exam volume - 63.37 Sq. In.

/

,i J 4

Limerick 1 Main Steam (N3 Nozzle)

Code Required Exam Volume - 75.60 Sq. In.

450 P-Scan Exam volume - 35.56 Sq. In.

60* P-Scan Exam volume - 41.16 Sq. In.

/

P

Limerick 1 Main Steam (N3 Nozzle)

Code Required Exam Volume - 27.47 Sq. In.

70° T-Scan Exam volume -13.19 Sq. In.

70° P-Scan Exam volume - 9.84 Sq. In.

70"P

Weld: N3B Summary Number: 601030 Unit: 1 Item Number: B3.90 Outage: 1 R09 (Spring 2002)

Coverage: 58.2%

Base Metal and Weld Materials: Carbon Steel Examination Volume: Full penetration coverage per figure IWB-2500-7 "Nozzle in Shell or Head" UT Exam Type: Automated UT Examination 0°L, 45°S, 60°S and 70°RL Performed per the requirements of ASME Code, Section Xl, Appendix VIII:

No, the examination was performed to requirements contained in ASME Section Xl,Section V, and Reg Guide 1.150. This was the approved technical guidance at the time of the examination.

Limitation

Description:

The completed examination was limited to 58.2% Code required coverage due to the design of the reactor vessel nozzle. The following coverage calculation sheet and the drawings contain the limitations. No unacceptable indications were noted. A system pressure test was also completed with no unacceptable indications observed.

Limerick Unit 1 N3B Spring 2002 CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE Area Scanned  % of Area Scanned Degrees Scanned  % Scanned 0, 2 Manual Auto Manual Area Inch Auto Manual Auto Manual Auto 0 WELD METAL 75.6 34.03 0.0 45.0 0.0 360.0 0.0 45.0 0.0 N

45° T SCAN N 75 6 57.36 0.0 75 9 0.0 360.0 0.0 75.9 00 60' T-SCAN 75.6 63.37 0.0 83.8 0.0 360.0 0.0 83.8 0.0 45ý P-SCAN OW N 75.6 35.56 0.0 47.0 0.0 360.0 0.0 47.0 0.0 60' P-SCAN CW N 75.6 41.16 0.0 54.4 0.0 360.0 0.0 54.4 0-0 N

45' P-SCAN CCW N 75.6 35.56 0.0 47.0 0.0 360.0 0.0 47.0 0.0 60' P-SCAN CCW 75.6 41.16 0.0 54.4 0.0 360.0 0.0 54.4 0.0 58.2 0.0 Total 0°, 45° and 60* Coverage = 58.2 27,47 13.19 0.0 48.0 0.0 360.0 0.0 48&0 0.0 70" T-SCAN N 2T47 9.84 0.0 35-8 0.0 360.0 0.0 I 35ý8 0.0 70- P-SCAN CW N 70' P-SCAN CCW N 27.47 9.84 0.0 35.8 0.0 360.0 0.0 35.8 0.0 39.900 Total 70° Coverage = 39.9 COMMENTS:

Automated UT scans were limited due to the nozzle OD blend radius.

Credit for the initial 114" of material in code coverane taken with the 70° I *l*t* I1 1 02/2910

Limerick 1 Main Steam (N3 Nozzle)

Code Required Exam Volume - 75.60 Sq. In.

\,/ 0' L-Wave Weld Metal Exam volume - 34.03 Sq. In.

I 0° L-wove

Limerick 1 Main Steam (N3 Nozzle)

Code Required Exam Volume - 75.60 Sq. In.

450 T-Scan Exam volume - 57.36 Sq. In.

60* T-Scan Exam volume - 63.37 Sq. In.

0 60* T

Limerick 1 Main Steam (N3 Nozzle)

Code Required Exam Volume - 75.60 Sq. In.

45' P-Scan Exam volume - 35.56 Sq. In.

60* P-Scan Exam volume - 41.16 Sq. In.

145- P P

Limerick 1 Main Steam (N3 Nozzle)

Code Required Exam Volume - 27.47 Sq. In.

70* T-Scan Exam volume -13.19 Sq. In.

70* P-Scan Exam volume - 9.84 Sq. In.

70**

70"P Fn~

Weld: N3C Summary Number: 601060 Unit: 1 Item Number: B3.90 Outage: 1R07 (Spring 1998)

Coverage: 58.4%

Base Metal and Weld Materials: Carbon Steel Examination Volume: Full penetration coverage per figure IWB-2500-7 "Nozzle in Shell or Head" UT Exam Type: Automated UT Examination 0°L, 450S, and 60 0 S Manual UT Examination was performed in area obstructed due to a drain line and I-beam. This was performed to increase code coverage.

Performed per the requirements of ASME Code,Section XI, Appendix VIII:

No, the examination was performed to requirements contained in ASME Section XI, Section V, and Reg Guide 1.150. This was the approved technical guidance at the time of the examination.

Limitation

Description:

The completed examination was limited to 58.4% Code required coverage due to the design of the reactor vessel nozzle and interference from a nearby drain line and I-beam. The following coverage calculation sheet and the drawings contain the limitations. No unacceptable indications were noted. A system pressure test was also completed with no unacceptable indications observed.

Limerick Unit 1 N3C Nozzle CROSS SECTIONAL AREA (per slice) 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 0 wm 74.76 32.88 32.88 43.98 43.98 304 56.0 37.1 6.8 45 T-scan 74.76 56.79 56.79 75.96 75.96 304 56.0 64.1 11.8 60 T-scan 74.76 62.39 62.39 83.45 83.45 304 56.0 70.5 13.0 45 P-scan CW 74.76 37.19 37Z19 49.75 49.75 304 56.0 42.0 7.7 60 P-scan CW 74.76 39.55 39.55 52.90 52.90 304 56.0 44.7 8.2 45 P-scan CCW 74.76 3Z.19 37.19 49.75 49.75 304 56.0 42.0 77 60 P-scan CCW 74.76 39.55 39.55 52.90 52.90 304 56.0 44.7 8.2 Co verages 49.3 9.1 Total coverage 58.4 No credit taken for initial 1/4" of materialin Code coverage calculationsdue to nearfield effects.

Fn~ri

ThermocoupWe Pad a 282" 303" Manual Scan Area Due To Drain Line N3D N30 42 Manuat Scan Area Due To I-Beam

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M-,j(~

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N N12D

Limerick 1 Main Steam N3C Or L-wave weld metal code examination coverage

/

(" L-wave M-4M

Limerick 1 Main Steam N3C 45" and 60 T-scon exrmnation coverage

Limerick 1 Main Steam N3C 45" and 60" P-scan code examination coverage 60r P 45* P n ~J r C) ~

K rn C)

Weld: N3D Summary Number: 601090 Unit: 1 Item Number: B3.90 Outage: 1R07 (Spring 1998)

Coverage: 58.4%

Base Metal and Weld Materials: Carbon Steel Examination Volume: Full penetration coverage per figure IWB-2500-7 "Nozzle in Shell or Head" UT Exam Type: Automated UT Examination 0°L, 450S, and 600S Performed per the requirements of ASME Code,Section XI, Appendix Vill:

No, the examination was performed to requirements contained in ASME Section Xl,Section V, and Reg Guide 1.150. This was the approved technical guidance at the time of the examination.

Limitation

Description:

The completed examination was limited to 58.4% Code required coverage due to the design of the reactor vessel nozzle. The following coverage calculation sheet and the drawings contain the limitations. No unacceptable indications were noted. A system pressure test was also completed with no unacceptable indications observed.

Limerick Unit 1 N3D Nozzle CROSS SECTIONAL AREA (perslice) 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 Owm 74.76 32.88 0 43.98 0.00 360 0.0 44.0 0.0 45 T-scan 74.76 56.79 0 75.96 0.00 360 0.0 76.0 0.0 60 T-scan 74.76 62-39 0 83.45 0.00 360 0.0 8325 0.0 45 P-scan CW 74.76 37.19 0 49.75 0.00 360 0.0 49.7 0.0 60 P-scan CW 74.76 39.55 0 52.90 0.00 360 0.0 52.9 0.0 45 P-scan CCW 74.76 37.19 0 49.75 0.00 360 0.0 49.7 0.0 60 P-scan CCW 74.76 39.55 0 52.90 0.00 360 O.0 52.9 0.0 Coverages 58.4 0.0 Total coverage 58.4 Automated scans were not restricted No credit taken for initial 1/4'of material in Code coverage calculations due to near field effects.

N N..

Limerick 1 Main Steam N3D 0r L-wove weld metal code examination coverage T L-wave rn, M

Limerick 1 Main Steam N3D 45" and 60 T-scan oxminotlon coveroge I

t 0I, C-)

Limerick 1 Main Steam N3D 45" and 60" P-scan code examination coverage

/

60 P

-~J ZO m ~ m 0'

K

Weld: N4A Summary Number: 601120 Unit: 1 Item Number: B3.90 Outage: 1R09 (Spring 2002)

Coverage: 68.8%

Base Metal and Weld Materials: Carbon Steel Examination Volume: Full penetration coverage per figure IWB-2500-7 "Nozzle in Shell or Head" UT Exam Type: Automated UT Examination 0°L, 450S, 60 0 S and 70°RL Performed per the requirements of ASME Code,Section XI, Appendix VIII:

No, the examination was performed to requirements contained in ASME Section XI, Section V, and Reg Guide 1.150. This was the approved technical guidance at the time of the examination.

Limitation

Description:

The completed examination was limited to 68.8% Code required coverage due to the design of the reactor vessel nozzle. The following coverage calculation sheet and the drawings contain the limitations. No unacceptable indications were noted. A system pressure test was also completed with no unacceptable indications observed.

Limerick Unit 1 N4A Spring 2002 CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE Area Scanned  % of Area Scanned Degrees Scanned  % Scanned 0 2 Area Inch Auto Manual Auto Manual Auto Manual Auto Manual 0' WELD METAL N 56.88 27.91 0.0 49.1 0.0 360.0 0.0 49.1 0.0 45' T-SCAN N 56.88 46.24 0.0 81 3 0.0 360.0 0.0 81 3 0.0 60' T-SCAN N 56.88 50.04 0.0 88.0 0.0 360.0 0.0 88.0 0.0 N 56.88 0.0 0,0 0.0 0.0 0.0 0.0 0.0 45' P-SCAN CW N 56.88 34.41 0.0 60.5 0.0 360.0 0.0 60.5 0.0 60' P-SCAN CW N 56.88 40.51 0.0 71.2 0.0 360.0 0.0 71.2 0.0 45' P-SCAN CCW N 56.88 34.41 0.0 60.5 0.0 360.0 0.0 60.5 0.0 60' P-SCAN CCW N 56.88 40.51 0.0 71.2 0.0 360.0 0.0 71.2 0.0 68.8 0.0 Total 00, 45° and 600 Coverage 68.8 70' -- SCAN N 22.41 10.99 0.0 49.0 0.0 360.0 0.0 49.0 0.0 70( P-SCAN CW N 22.41 7.64 0.0 34.1 0.0 360.0 0.0 34.1 0.0 70 P-SCAN CCW N 22.41 7.64 0.0 34.1 0.0 360.0 0.0 34 1 0.0 39 1 0.0 Total 700 Coverage = 39.1 COMMENTS:

I Automated UT scans were limited due to the nozzle OD blend radius.702 taken with the Credit for the initial 1/4" of material in code coverage 1 2290

Limerick 1 Feedwater Code Required Exam Volume - 56.88 Sq. In.

00 L-wave Exam Volume - 27.91 Sq. In.

450 T-Scan Exam Volume - 46.24 Sq. In.

600 T-Scan Exam Volume - 50.04 Sq. In.

45" T 60" T

- 60 T 45 T ' L-wave

-.1

Limerick 1 Feedwater Code Required Exam Volume - 56.88 Sq. In.

450 P-Scan Exam Volume - 34.41 Sq. In.

60° P-Scan Exam Volume - 40.51 Sq. In.

/

-1

Limerick 1 Feedwater Code Required Exam Volume - 22.41 Sq. In.

70" T-Scan Exam Volume - 10.99 Sq. In.

70" P-Scan Exam Volume - 7.64 Sq. In.

70"P ql r~jJ

Weld: N4B Summary Number: 601150 Unit: 1 Item Number: B3.90 Outage: 1R08 (Spring 2000)

Coverage: 64.6%

Base Metal and Weld Materials: Carbon Steel Examination Volume: Full penetration coverage per figure IWB-2500-7 "Nozzle in Shell or Head" UT Exam Type: Automated UT Examination 0°L, 450 S, 60 0 S, and 70°RL Performed per the requirements of ASME Code, Section Xl, Appendix VIII:

No, the examination was performed to requirements contained in ASME Section XI, Section V, and Reg Guide 1.150. This was the approved technical guidance at the time of the examination.

Limitation

Description:

The completed examination was limited to 64.6% Code required coverage due to the design of the reactor vessel nozzle. The following coverage calculation sheet and the drawings contain the limitations. No unacceptable indications were noted. A system pressure test was also completed with no unacceptable indications observed.

Limerick Unit i N4B CROSS SECTIONAL AREA (per slice) 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 0, wm 59.70 27.1 0.0 45.4 0.0 360.0 00 45.4 0.0 45' T-scan 59.70 45.7 0.0 76.5 0.0 360.0 0-0 76.5 00 60' T-scan 59.70 49.8 00O 834 0.0 360.0 00 83.4 0.0 45° P-scan CW 59.70 32.8 0.0 54.9 0.0 360.0 0.0 54.9 0.0 60' P-scan CVV 59,70 39.2 0.0 65.7 0.0 360,0 0.0 65.7 0.0 45' P-scan CCW 59.70 32,8 0.0 54.9 0.0 360.0 0.0 54.9 0.0 60* P-scan CCW 59.70 39.2 0.0 65.7 0.0 360.0 0.0 657 0.0 63.8 0.0 Automated scans were not restricted.

No credit taken for initial 1/4" of material in Code coverage calculations due to near field effects. Composite Coverage 63.8 CROSS SECTIONAL AREA (per slice) 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 70' T-scan 58.84 1.2 0.0 2.0 0.0 360.0 0.0 2.0 0.0 70' P-scan CW 58.84 1.1 0.0 1.9 0.0 360.0 0.0 1.9 0.0 70' P-scan CW 5884 11 0.0 1,9 0.0 360.0 0 0 1.9 0ý0 0.8 0.0 Examination coverage 70' RL calculations.

Composite Coverage = 0.8 rz Total Composite Coverage = 64.6 C-100

Limerick 1 N4 Feedwafer 0 L-wave weld metal, 45* and 60" T-scan exam coverage 60'T C;

Limerick 1 N4 Feedwater 45" and 60" P-scan exam coverage

/

S'7C 60 P C

Limerick 1 N4 Feedwater 70" T-scan and P-scan exam coverage I

6v ,707 /

-r 0

Weld: N4C Summary Number: 601180 Unit: 1 Item Number: B3.90 Outage: 1R08 (Spring 2000)

Coverage: 64.6%

Base Metal and Weld Materials: Carbon Steel Examination Volume: Full penetration coverage per figure IWB-2500-7 "Nozzle in Shell or Head" UT Exam Type: Automated UT Examination 0°L, 450S, 60 0 S, and 70°RL Performed per the requirements of ASME Code, Section Xl, Appendix VIII:

No, the examination was performed to requirements contained in ASME Section X1,Section V, and Reg Guide 1.150. This was the approved technical guidance at the time of the examination.

Limitation

Description:

The completed examination was limited to 64.6% Code required coverage due to the design of the reactor vessel nozzle. The following coverage calculation sheet and the drawings contain the limitations. No unacceptable indications were noted. A system pressure test was also completed with no unacceptable indications observed.

Limerick Unit 1 N4C CROSS SECTIONAL AREA (per slice) TOTAL CODE COVERAGE code rross 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 0 wm 5970 27. I 0.0 45.4 0.0 360.0 0,0 454 0,0 45' T-scan 59.70 457 0.0 76.5 0.0 360.0 0.0 76.5 0.0 60' T-scan 5970 49.8 0.0 83.4 0.0 360.0 0,0 63.4 0.0 45' P-scan CW 59.70 32.8 0.0 54.9 0.0 360.0 0.0 54.9 0.0 60° P-scan CVV 59.70 39.2 0.0 65.7 0.0 360.0 0.0 65.7 0.0 45' P-scan CCW 59.70 32.8 0.0 54.9 0.0 360.0 0.0 54.9 0.0 60' P-scan CCW 59 70 3j 2 0.0 65.7 0.0 360.0 0.0 55.7 0.0 63.8 0.0 Automated scans w"ie not iestrcteo.

No credit taken for rntial 1/4" of matertal in Code coverage calculations due to near field effects. Composite Coverage = 63.8 CROSS SECTIONAL AREA (per slice) TOTAL CODE COVERAGE code closs 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 70' T-scan 58.84 1.2 0.0 2.0 0.0 360.0 0.0 2.0 0.0 70" P-scan CW 58,84 1.1 0.0 1.9 0.0 360.0 0.0 1.9 0.0 70° P-scan CVJ 58.,4 1.1 0.0 1.9 0.0 360.0 0.0 1.9 0.0 0.6 0.0 Examination coerage 70° RL calculations Composite Coverage = 0.8 Total Composite Coverage = 64.6 7-) 75 r-i-

CDP

Limerick 1 N4 Feedwaler 0* L-wave weld metal, 45" and 60" T-scan exam coverage

~nxJ r--

K 60"T K

Limerick 1 N4 Feedwater 45° and 60" P-scan exam coverage

/

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60'P CD

Limerick 1 N4 Feedwater 70" T-scan and P-scan exam coverage m-70"P C,

Weld: N4D Summary Number: 601210 Unit: 1 Item Number: B3.90 Outage: 1R08 (Spring 2000)

Coverage: 55.9%

Base Metal and Weld Materials: Carbon Steel Examination Volume: Full penetration coverage per figure IWB-2500-7 "Nozzle in Shell or Head" UT Exam Type: Automated UT Examination 0°L, 450S, 600S, and 70°RL Performed per the requirements of ASME Code, Section Xl, Appendix VIII:

No, the examination was performed to requirements contained in ASME Section X1,Section V, and Reg Guide 1.150. This was the approved technical guidance at the time of the examination.

Limitation

Description:

The completed examination was limited to 55.9% Code required coverage due to the design of the reactor vessel nozzle and the location of the N11 B nozzle. The following coverage calculation sheet and the drawings contain the limitations. No unacceptable indications were noted. A system pressure test was also completed with no unacceptable indications observed.

Limerick Unit 1 N4D CROSS SECTIONAL AREA (per slice) 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 00 wm 59,70 27.1 00 45.4 0.0 311.2 0.0 39.2 0.0 450 T-scan 0.0 59.70 45.7 0.0 76.5 0.0 311.2 0.0 66.2 600 T-scan 59.70 49,8 0.0 83.4 0.0 311.2 0.0 72.1 0.0 45* P-scan CVV 59.70 32.8 0.0 54.9 0.0 311.2 0.0 47.5 0.0 60* P-scan CW 59.70 39.2 0.0 65.7 0.0 311.2 00 56-8 0,0 45' P-scan CCW 59.70 32.8 0.0 54.9 0.0 311.2 O.0 47.5 0.0 60' P-scan CCW 59.70 39 2 0.0 65.7 0.0 311.2 0.0 56 8 0.0 55.1 0.0 Automated scans were restricted, due to the proximity of N11 B nozzle.

No credit taken for initial 114" of material in Code coverage calculations due to near field effects. Composite Coverage = 55.1 CROSS SECTIONAL AREA (per slice) 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 70' T-scan 58.84 1.2 0.0 2.0 0.0 311.2 0.0 1.7 0.0 700 P-scan CW 58.84 1.1 0.0 1.9 0.0 311.2 0.0 1.6 0.0 70' P-scan CW 55.84 1.1 0.0 1.9 0.0 311.2 0.0 16 0.0 0.7 0.0 Examination coverage 70' RL calculations.

Composite Coverage = 0.7 Total Composite Coverage = 55.9 0r

Limerick 1 N4 Feedwater 0' L-wave weld metal, 45" and 60" T-scan exam coverage rii~Qm 6Q'T 0

Limerick 1 N4 Feedwater 45° and 60" P-scan exam coverage

/

0

Limerick 1 N4 Feedwater 70' T-scan and P-scan exam coverage I

70"P 1

K. i

296.0* oz.

344.8" az.

AREA SCAN

-n O N4D 45", 60° T-SCANS AND 0O L-WAVE AUTOMATED EXAMS RESTRICTED DUE TO N11B

296.0° az.

344.8" oz.

AREA SCAN CO: mj N4D 45"/60" PARALLEL SCAN (P1)

AUTOMATED EXAMS RESTRICTED DUE TO N11B

296.0*oz 344.8*oz AREA

7zJ N4D 45'/60" PARALLEL SCAN (P2)

C-,

(~J ~

AUTOMATED EXAMS RESTRICTED DUE TO Ni1B

296.0* oz.

344.8" cz.

AREA SCAN N4D 700 T-SCAN AND P-SCANS 0'

• .tr1 AUTOMATED EXAMS RESTRICTED DUE TO N11B

Weld: N4E Summary Number: 601240 Unit: 1 Item Number: B3.90 Outage: 1R10 (Spring 2004)

Coverage: 79.1%

Base Metal and Weld Materials: Carbon Steel Examination Volume: Full penetration coverage per figure IWB-2500-7 "Nozzle in Shell or Head" UT Exam Type: Automated UT Examination 0°L, 45 0 S, 60°RL, and 70°RL Performed per the requirements of ASME Code, Section Xl, Appendix VIII:

Yes, the examination was in accordance with ASME Section X1 Appendix VIII as modified by the PDI program.

Limitation

Description:

The completed examination was limited to 79.1% Code required coverage due to the design of the reactor vessel nozzle. The following coverage calculation sheet and the drawings contain the limitations. No unacceptable indications were noted. A system pressure test was also completed with no unacceptable indications observed.

C' ~~ NI..n .1 Cl'Af U I C1 8u[-mmay NoL.ý I

Limerick Unit-1 Weld N4E Spring 2004 CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE Percent Weld Length = 360. Required Exam Area Scanned of Area Weld Length Percent Exam Volume = 59.7 Area Sq. In. Auto Auto Auto Auto 70' T-Scan A 12 6.1 10.2% 360 5.1%

45' T-Scan A 39.2 34.5 57.8% 360 28.9%

60' T-Scan A 8.5 8.5 14.2% 360 7.1%

70' P-Scan A 12 4.9 8.2% 360 4.1%

45" P-Scan A 39.2 31.9 53.4% 360 26.7%

IRS P-Scan A 8.5 8.5 14.2% ' 360 7.1%

70' T-Scan I"'

45' T-Scan 60' T-Scan 70ý P-Scan 45' P-Scan IRS P-Scan 70" T-Scan 45' T-Scan 60" T-Scan 70' P-Scan 45' P-Scan IRS P-Scan

% Total Composite Coverage = 79.1%

Comments: A - Scanned 360 deg., Scanning limited due to nozzle configuration.

Note - Roundina rmethods rn-ov 'iilect calculated values.

D Limerick Unit-1 N

Feedwater - N4 70' Exam Volume ý 12.0 Sq. In.

45' Exam Volume ý 39.2 Sq. In.

Inner 15%T Exam Volume (IRS & 60'T) = 8.5 Sq. In-K 70' T-Scan achieved = 6.1 Sq. In.

45' T-Scan achieved = 34.5 Sq. In.

60' T-Scan achieved = 8.5 Sq. In.

U /

70CT 451' 60 T I

I, 1"

3 D

Limerick Unit-1 Feedwater - N4 70" Exam Volume = 12.0 Sq. In.

45' Exam Volume = 39.2 Sq. In.

Inner 15%T Exam Volume (IRS & 60"T) 8 5 Sq. In.

70* P-Scan achieved = 4.9 Sq. In.

45' P-Scan achieved = 31.9 Sq. In.

IRS P-Scan achieved 8.5 Sq. In.

70'P

-u 45

-- P2 3 F- ---

,,/ // /

Weld: N4F Summary Number: 601270 Unit: 1 Item Number: B3.90 Outage: 1R10 (Spring 2004)

Coverage: 77.1%

Base Metal and Weld Materials: Carbon Steel Examination Volume: Full penetration coverage per figure IWB-2500-7 "Nozzle in Shell or Head" UT Exam Type: Automated UT Examination 0°L, 450 S, 60°RL, and 70°RL Performed per the requirements of ASME Code,Section XI, Appendix VIII:

Yes, the examination was in accordance with ASME Section XI Appendix VIII as modified by the PDI program.

Limitation

Description:

The completed examination was limited to 77.1% Code required coverage due to the design of the reactor vessel nozzle. The following coverage calculation sheet and the drawings contain the limitations. No unacceptable indications were noted. A system pressure test was also completed with no unacceptable indications observed.

Summary No.: bU61/U Limerick Unit-1 Weld N4F Spring 2004 CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE Percent Weld Length = 360, Required Exam Area Scanned of Area Weld Length Percent Exam Volume = 59.7 Area Sq. In. Auto Auto Auto Auto 70' T-Scan A 12 5.8 9.7% 360 4.9%

45' T-Scan A 39.2 33.5 56.1% 360 28.1%

600 T-Scan A 8.5 8.5 14.2% 360 7.1%

701, P-Scan A 12 4.5 7.5% 360 3.8%

45' P-Scan A 39.2 31.3 52.4% 360 26.2%

IRS P-Scan A 8.5 8.5 14 2% 360 7.1%

70' T-Scan 45" T-Scan 60' T-Scan 70' P-Scan 45' P-Scan IRS P-Scan 70' T-Scan 45' T-Scan 60" -T-Scan 700 P-Scan 45"_P-Scan IRS P-Scan

% Total Composite Coverage = 77.1%

Comments: A - Scanned 360 deg., Scanning limited due to nozzle configuration.

Note - Rounding methodsc may a.tlect calculated values.

Limerick Unit-1 Feedwater - N4 70" Exam Volume = 12.0 Sq. In.

45° Exam Volume = 39.2 Sq. In.

Inner 15%T Exam Volume (tRS & T) 8,5 Sq. In.

70- T-Scan achieved = 5.8 Sq. In.

45\ I-Scan achieved 33.5 Sq. In.

605 T-Scan achieved = 8.5 Sq. In.

CD T 4D T "O 8. S

....... _ _--~-- T-H T

D Limerick Unit-1 Feedwater - N4 70 Exam Volume = 12.0 Sq. In.

45' Exam Volume = 39.2 Sq. In.

Inner 15%T Exam Volume (IRS & 60'T) - 8.5 Sq, In 70' P-Scan achieved = 4.5 Sq. In.

45 P-Scan achieved = 31.3 Sq. In.

IRS P-Scan achieved = 8.5 Sq- In.

• 0 70 p.4 P?

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-h

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Weld: N5A Summary Number: 601300 Unit: 1 Item Number: B3.90 Outage: 1R07 (Spring 1998)

Coverage: 61.9%

Base Metal and Weld Materials: Carbon Steel Examination Volume: Full penetration coverage per figure IWB-2500-7 "Nozzle in Shell or Head" UT Exam Type: Automated UT Examination 00 L, 450S, and 60 0 S Performed per the requirements of ASME Code, Section Xl, Appendix Vill:

No, the examination was performed to requirements contained in ASME Section X1,Section V, and Reg Guide 1.150. This was the approved technical guidance at the time of the examination.

Limitation

Description:

The completed examination was limited to 61.9% Code required coverage due to the design of the reactor vessel nozzle. The following coverage calculation sheet and the drawings contain the limitations. No unacceptable indications were noted. A system pressure test was also completed with no unacceptable indications observed.

Limerick Unit I N5A Nozzle CROSS SECTIONAL AREA (perslice) 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 o wm 59.43 2733 0 45.99 0.00 360 0.0 46.0 0.0 45 T-scan 59.43 45.87 0 77.18 0.00 360 0.0 77.2 0.0 60 T-scan 59.43 49.82 0 83.83 0.00 360 0.0 83.8 0.0 45 P-scan CW 59.43 32.84 0 55.26 0.00 360 0.0 55.3 0.0 60 P-scan CW 59.43 34.36 0 5Z82 0.00 360 0.0 5Z8 0.0 45 P-scan CCW 59.43 32.84 0 55.26 0.00 360 0.0 55.3 0.0 60 P-scan CCW 59.43 34.36 0 57.82 0.00 360 0.0 57.8 0.0 Coverages 61.9 0.0 Total coverage 61.9 Automated scans were not restricted No credit taken for initial 1/4"of materialin Code coverage calculationsdue to near field effects.

!1

-C)* r.'

Limerick 1 Core Spray N5A 0' L-wave weld metal code examination area IN, OWM C) m -~

C)

C)

Limerick 1 Core Spray N5A 45" and 60' T-scan examination coverage Pn -j M

Limerick 1 Core Spray N5A 45"and 60" P-scan examination area 6'

1/

rn ~ rn K

Weld: N5B Summary Number: 601330 Unit: 1 Item Number: B3.90 Outage: 1R07 (Spring 1998)

Coverage: 61.9%

Base Metal and Weld Materials: Carbon Steel Examination Volume: Full penetration coverage per figure IWB-2500-7 "Nozzle in Shell or Head" UT Exam Type: Automated UT Examination 0°L, 450S, and 60)S Performed per the requirements of ASME Code, Section Xl, Appendix VIII:

No, the examination was performed to requirements contained in ASME Section Xl,Section V, and Reg Guide 1.150. This was the approved technical guidance at the time of the examination.

Limitation

Description:

The completed examination was limited to 61.9% Code required coverage due to the design of the reactor vessel nozzle. The following coverage calculation sheet and the drawings contain the limitations. No unacceptable indications were noted. A system pressure test was also completed with no unacceptable indications observed.

Limerick Unit I N5B Nozzle CROSS SECTIONAL AREA (perslice) 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 O wm 5943 27.33 0 45.99 0.OO 360 0.0 46.0 0.0 45 T-scan 59.43 45.87 0 77.18 0.00 360 0.0 71.2 0.0 60 T-scan 59.43 49.82 0 83.83 0.00 360 0.0 83.8 0.0 45 P-scan CW 59.43 32.84 0 55.26 0.00 360 0.0 55.3 0.0 60 P-scan CW 59.43 34.36 0 57.82 0.00 360 0.0 51.8 0.0 45 P-scan CCW 59.43 32.84 0 55.26 0.00 360 0.0 55.3 0.0 60 P-scan CCW 59.43 34.36 0 51.82 0.00 360 0.0 578 0.0 Coverages 61.9 0.0 Total coverage 61.9 Automated scans were not restricted No credit taken for initial 1/4" of materialin Code coverage calculations due to near field effects.

-oj

Limerick 1 Core Spray N5B 0* L-wave weld metal code examination area

/

OWM m

C-,

(~3~

Limerick 1 Core Spray N5B 45" and 60 T-scan examination coverage Fn~~'

Limerick 1 Core Spray N5B 45"and 60' P-scan examination area C)

Weld: N6A Summary Number: 601360 Unit: 1 Item Number: B3.90 Outage: 1R10 (Spring 2004)

Coverage: 58.0%

Base Metal and Weld Materials: Carbon Steel Examination Volume: Full penetration coverage per figure IWB-2500-7 "Nozzle in Shell or Head" UT Exam Type: Manual UT Examination 60 0 L and 600S Performed per the requirements of ASME Code, Section Xl, Appendix VIII:

Yes, the examination was in accordance with ASME Section XI Appendix VIII as modified by the PD1 program.

Limitation

Description:

The completed examination was limited to 58.0% Code required coverage due to the design of the reactor vessel nozzle. The following drawing contains the limitations. No unacceptable indications were noted. A system pressure test was also completed with no unacceptable indications observed.

Limerick Unit-1 Closure Head N6 Nozzle Bottom Side 600 Exam Volume = 30.5 Sq. In.

60° T-Scan achieved = 26.0 Sq. In.

60' P-Scan achieved 21.5 Sq In.

64'P 10 Nozzle Top Side 60' Exam Volume = 22.0 Sq. In.

600 T-Scan achieved = 17.4 Sq. In.

60' P-Scan achieved = 11.6 Sq. In.

Weld: N6B Summary Number: 601380 Unit: 1 Item Number: B3.90 Outage: IR 10 (Spring 2004)

Coverage: 58.0%

Base Metal and Weld Materials: Carbon Steel Examination Volume: Full penetration coverage per figure IWB-2500-7 "Nozzle in Shell or Head" UT Exam Type: Manual UT Examination 60 0 L and 60 0 S Performed per the requirements of ASME Code,Section XI, Appendix VIII:

Yes, the examination was in accordance with ASME Section X1 Appendix VIII as modified by the PDI program.

Limitation

Description:

The completed examination was limited to 58.0% Code required coverage due to the design of the reactor vessel nozzle. The following drawing contains the limitations. No unacceptable indications were noted. A system pressure test was also completed with no unacceptable indications observed.

Limerick Unit-i Closure Head N6 Nozzle Bottom Side 60' Exam Volume = 30.5 Sq. In.

600 T-Scan achieved = 26.0 Sq. In.

60' P-Scan achieved z 21.5 Sq. in.

I

// \

" 53" $S.o-Nozzle Top Side 60' Exam Volume = 22.0 Sq. In.

60' T-Scan achieved 17.4 Sq, In.

60' P-Scan achieved = 11.6 Sq. In.

Weld: N7 Summary Number: 601400 Unit: 1 Item Number: B3.90 Outage: 1R10 (Spring 2004)

Coverage: 79.4%

Base Metal and Weld Materials: Carbon Steel Examination Volume: Full penetration coverage per figure IWB-2500-7 "Nozzle in Shell or Head" UT Exam Type: Manual UT Examination 60 0 L and 600S Performed per the requirements of ASME Code,Section XI, Appendix VIII:

Yes, the examination was in accordance with ASME Section XI Appendix VIII as modified by the PDi program.

Limitation

Description:

The completed examination was limited to 79.4% Code required coverage due to the design of the reactor vessel nozzle. The following drawing contains the limitations. No unacceptable indications were noted. A system pressure test was also completed with no unacceptable indications observed.

Limerick Unit-1 Closure Head N7 600 Exam Volume =

19.4 Sq. In.

60' T-Scan achieved = 16.8 Sq.

60" P-Scan achieved In.

14.7 Sq. In.

II S tý,

60T L614tý%.k- IT

Weld: N8A Summary Number: 601420 Unit: 1 Item Number: B3.90 Outage: 1R07 (Spring 1998)

Coverage: 60. 1%

Base Metal and Weld Materials: Carbon Steel Examination Volume: Full penetration coverage per figure IWB-2500-7 "Nozzle in Shell or Head" UT Exam Type: Manual UT Examination 00 L, 450S, and 60°S Performed per the requirements of ASME Code, Section Xl, Appendix Vill:

No, the examination was performed to requirements contained in ASME Section Xl,Section V, and Reg Guide 1.150. This was the approved technical guidance at the time of the examination.

Limitation

Description:

The completed examination was limited to 60.1% Code required coverage due to the design of the reactor vessel nozzle. The following coverage calculation sheet and the drawings contain the limitations. No unacceptable indications were noted. A system pressure test was also completed with no unacceptable indications observed.

Limerick Unit I N8A Nozzle CROSS SECTIONAL AREA (perslice) 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 O wm 59.8 0.0 2ZO 0.00 45.15 0 360 0,0 45.2 45 T-scan 59.8 0.0 45.5 0.00 76.09 0 380 0,0 76.1 60 T-scan 59.8 0.0 49.6 0.00 82.94 0 360 0.0 82.9 45 P-scan CW 59.8 0.0 29.4 0.00 49.16 0 360 0.0 49.2 60 P-scan CW 59.8 0.0 35.3 0.00 59.03 0 360 0.0 59.0 45 P-scan CCW 59.8 0.0 29.4 0.00 49.16 0 360 0.0 49.2 60 P-scan CCW 59.8 0.0 35.3 0.00 59.03 0 360 0.0 59.0 Coverages 0.0 60.1 Total coverage 60.1 Manual scans were not restricted No credit taken for initial 1/4" of materialin Code coverage calculations due to near field effects.

rwi -"

\

Limerick 1 Jet Pump NBA D* 0* L-wave code cross-sectionatl examination coverage 0* L-wave C>

Limerick 1 JET PUMP NBA

~Z45" and 60" T-scan code cross-sectional examination coverage l

c-n am

Limerick 1 JET PUMP N8A W 45" and 60" P-scan code cross-sectionaL examination coverage rn H

Weld: N8B Summary Number: 601440 Unit: 1 Item Number: B3.90 Outage: 1R07 (Spring 1998)

Coverage: 60.1%

Base Metal and Weld Materials: Carbon Steel Examination Volume: Full penetration coverage per figure IWB-2500-7 "Nozzle in Shell or Head" UT Exam Type: Manual UT Examination 0°L, 450S, and 600S Performed per the requirements of ASME Code,Section XI, Appendix VIII:

No, the examination was performed to requirements contained in ASME Section Xl,Section V, and Reg Guide 1.150. This was the approved technical guidance at the time of the examination.

Limitation

Description:

The completed examination was limited to 60.1% Code required coverage due to the design of the reactor vessel nozzle. The following coverage calculation sheet and the drawings contain the limitations. No unacceptable indications were noted. A system pressure test was also completed with no unacceptable indications observed.

Limerick Unit 1 N8B Nozzle CROSS SECTIONAL AREA (per slice) 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 0 wm 59.8 0.0 27.0 0.00 45.15 0 360 0.0 45.2 45 T-scan 59.8 00 45.5 0.00 76.09 0 360 0.0 76.1 60 T-scan 59.8 0.0 49.6 0.00 82.94 0 360 0.0 82.9 45 P-scan CW 59.8 0.0 29.4 0.00 49.16 0 360 0.0 49.2 60 P-scan CW 59.8 0.0 35.3 0.00 59.03 0 360 0.0 59.0 45 P-scan CCW 59.8 0.0 29.4 0.00 49.16 0 360 0.0 49.2 60 P-scan CCW 59.8 0.0 35.3 0.00 59.03 0 360 0.0 59.0 Coverages 0.0 60.1 Total coverage 60.1 Manual scans were not restricted No credit taken for initial 1/4"of material in Code coverage calculationsdue to near field effects.

ry MA Kr

Limerick 1 Jet Pumnp N8B D0o L-wave Ccde cross-sectionaL exam~ination coveraige 0* L-wave

,L-wave C0r M1

Limerick 1 JET PUMP N8B.

D 45* and 60" T-scan code cross-sectional examination coverage Or)

Z),

__s:j

Limerick I JET PUMP N8B W 45" and 60" P-scan code cross-sectional examination coverage i

m ~ ri, C)

-A

-I

Weld: N9 Summary Number: 601460 Unit: 1 Item Number: B3.90 Outage: 1R07 (Spring 1998)

Coverage: 60.1%

Base Metal and Weld Materials: Carbon Steel Examination Volume: Full penetration coverage per figure IWB-2500-7 "Nozzle in Shell or Head" UT Exam Type: Manual UT Examination 00 L, 45 0 S, and 600S Performed per the requirements of ASME Code, Section Xl, Appendix VIII:

No, the examination was performed to requirements contained in ASME Section Xl,Section V, and Reg Guide 1.150. This was the approved technical guidance at the time of the examination.

Limitation

Description:

The completed examination was limited to 60.1% Code required coverage due to the design of the reactor vessel nozzle. The following coverage calculation sheet and the drawings contain the limitations. No unacceptable indications were noted. A system pressure test was also completed with no unacceptable indications observed.

Limerick Unit I N9 Nozzle CROSS SECTIONAL AREA (perslice) 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 o wm 59.8 0.0 21.0 0.00 45.15 0 360 0.0 4512 45 T-scan 59.8 0.0 45.5 0.00 76.09 0 360 0.0 76.1 60 T-scan 59.8 0.0 49.6 0.00 82.94 0 360 0.0 82.9 45 P-scan CW 59.8 0.0 29.4 0.00 49.16 0 360 0.0 49.2 60 P-scan CW 59.8 0.0 35.3 0.00 59.03 0 360 0.0 59.0 45 P-scan CCW 59.8 0.0 29.4 0.00 49.16 0 360 0.0 49.2 60 P-scan CCW 59.8 0.0 35.3 0.00 59.03 0 360 0.0 59.0 Coverages 0.0 60.1 Total coverage 60.1 Manualscans were not restricted No credit taken for initial 1/4" of materialin Code coverage calculations due to near field effects.

KCI m -.

CD

Limerick 1 CRD N9 LI 0 L-wave code cr'oss-sectionoa examination cvrg 0* L-wave m

Limerick 1 CRD N9 D- 45* and 60* T-scan code cross-sectional examrinaition coverage C')

0HM

Limerick 1 CPD El 45' and 60' P-scan code cross-sectional exam~ination coverage mjr7 C)

Weld: N17A Summary Number: 601490 Unit: 1 Item Number: B3.90 Outage: 1R07 (Spring 1998)

Coverage: 61.9%

Base Metal and Weld Materials: Carbon Steel Examination Volume: Full penetration coverage per figure IWB-2500-7 "Nozzle in Shell or Head" UT Exam Type: Automated UT Examination 0°L, 450S, and 60 0 S Performed per the requirements of ASME Code, Section Xl, Appendix VIII:

No, the examination was performed to requirements contained in ASME Section Xl,Section V, and Reg Guide 1.150. This was the approved technical guidance at the time of the examination.

Limitation

Description:

The completed examination was limited to 61.9% Code required coverage due to the design of the reactor vessel nozzle. The following coverage calculation sheet and the drawings contain the limitations. No unacceptable indications were noted. A system pressure test was also completed with no unacceptable indications observed.

Limerick Unit I N17A Nozzle CROSS SECTIONAL AREA (per slice) 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 0 wm 59.43 27.9 0 46.95 0.00 360 0.0 46.9 0.0 45 T-scan 59.43 45.8 0 7.07 0.00 360 0.0 77. 1 0.0 60 T-scan 59.43 49.8 0 83.80 0.00 360 0.0 83.8 0.0 45 P-scan CW 59.43 32.7 0 55.02 0.00 360 0.0 55.0 0.0 60 P-scan CW 59.43 34.3 0 57.71 0.00 360 0.0 57.7 0.0 45 P-scan CCW 59.43 32.7 0 55.02 0.00 360 0.0 55.0 0.0 60 P-scan CCW 59.43 34.3 0 57.71 0o00 360 0.0 51.7 0.0 Coverages 61.9 0.0 Total coverage 61.9 Automated scans were not restricted No credit taken for initial 1/4"of materialin Code coverage calculations due to near field effects.

W-5

Limerick 1 N17A LPCI 0* L-wave weld metal exam coverage

(" L-wove Cj Ip

Limerick 1 N17A LPCI 45 and 60 T-scons examination coverage I

m j~

i5 K

Limerick 1 N17A LPCI 60" and 45" P-scan exam coverage I

Qjr M0 j

Weld: N17B Summary Number: 601520 Unit: 1 Item Number: B3.90 Outage: 1R07 (Spring 1998)

Coverage: 61.9%

Base Metal and Weld Materials: Carbon Steel Examination Volume: Full penetration coverage per figure IWB-2500-7 "Nozzle in Shell or Head" UT Exam Type: Automated UT Examination 0°L, 450S, and 60 0 S Performed per the requirements of ASME Code, Section Xl, Appendix VIII:

No, the examination was performed to requirements contained in ASME Section Xl,Section V, and Reg Guide 1.150. This was the approved technical guidance at the time of the examination.

Limitation

Description:

The completed examination was limited to 61.9% Code required coverage due to the design of the reactor vessel nozzle. The following coverage calculation sheet and the drawings contain the limitations. No unacceptable indications were noted. A system pressure test was also completed with no unacceptable indications observed.

Limerick Unit I N17B Nozzle CROSS SECTIONAL AREA fper slice) TOTAL CODE COVERAGE code cross area limited area  % of code area  % of code area degrees degrees percent percent sectional scanned scanned scanned limited area scanned limited scanned limited area automated automated automated scanned automated scan area automated scan area O wm 59.43 27.9 0,00 46.95 0.00 360 0.0 46.9 0.0 45 T-scan 59.43 45.8 0.00 7Z07 0.00 360 0.0 77.I 0.O 60 T-scan 59.43 49.8 0.00 83.80 0.00 360 0.0 83.8 0.0 45 P-scan CW 59.43 32.7 0.00 55.02 0.00 360 0.0 55.0 0.0 60 P-scan CW 59.43 34.3 0.00 57.71 0.00 360 0.0 57.7 0.0 45 P-scan CCW 59.43 32.7 0.00 55.02 0.00 360 0.O 55.0 0.0 60 P-scan CCW 59.43 34.3 0.00 57.71 0.00 360 0.0 5Z7 0.0 Coverages 61.9 0.0 Total coverage 67.9 Automated scans were not restricted No credit taken for initial 1/4 of materialin Code coverage calculationsdue to near field effects.

C y

Limerick 1 N17B LPCI 0* L-wave weld metal exam coverage I

0* L-wave 0

Q-)

C0

Limerick 1 N17B LPCI 45 and 60r T-scons examination coverage

'1

Limerick 1 N17B LPCI 60" and 45" P-scan exam coverage I

60" P-scan

'1

Weld: N17D Summary Number: 601580 Unit: 1 Item Number: B3.90 Outage: 1R07 (Spring 1998)

Coverage: 61.9%

Base Metal and Weld Materials: Carbon Steel Examination Volume: Full penetration coverage per figure IWB-2500-7 "Nozzle in Shell or Head" UT Exam Type: Automated UT Examination 0°L, 450S, and 60 0 S Performed per the requirements of ASME Code, Section Xl, Appendix Vill:

No, the examination was performed to requirements contained in ASME Section X1,Section V, and Reg Guide 1.150. This was the approved technical guidance at the time of the examination.

Limitation

Description:

The completed examination was limited to 60.1% Code required coverage due to the design of the reactor vessel nozzle. The following coverage calculation sheet and the drawings contain the limitations. No unacceptable indications were noted. A system pressure test was also completed with no unacceptable indications observed.

Limerick Unit I LW. IAP 2 0 '98 Ni7D Nozzle CROSS SECTIONAL AREA (perslice) TOTAL CODE COVERAGE code cross area limited area  % of code area  % of code area degrees degrees percent percent sectional scanned scanned scanned limited area scanned limited scanned limited area automated automated automated scanned automated scan area automated scan area OWm 59.43 27.9 0.00 46.95 0.00 360 0.0 46.9 0.0 45 T-scan 59.43 45.8 0.00 7Z07 0.00 360 0.0 77.1 0.0 60 T-scan 59.43 49.8 0.00 83.80 0.00 360 0.0 83.8 0.0 45 P-scan CW 59.43 32.7 0.00 55.02 0.00 360 0.0 55.0 0.0 60 P-scan CW 59.43 34.3 0.00 5.71 0.00 360 0.0 5Z7 0.0 45 P-scan CCW 59.43 32.7 0.00 55.02 0.00 360 0.0 55.0 0.0 60 P-scan CCW 59.43 34.3 0.00 5Z.71 0.00 360 0.0 57.7 0.0 Coverages 61.9 0.0 Total coverage 61.9 Automated scans were not restricted No credit taken for initial 1/4" of material in Code coverage calculationsdue to near field effects.

C) H rCn C:)

APR 2 0 '98 Limc rick 1 N17D LPCI 0 L-wave we Id metal exam coverage O"*L-wove 0" L-wave CI

,. - GO 2 0 '98 Lin- ierick 1 N17 D LPCI 45" and 60* T- scans examination coverage 60' T I 45' T rn, ..j r,'

C)O 00

VV~\~D :-c Enz.?7 GO APR 2 0 '98 fZIE SuiPGRT GROUJP~ L /

Limerick 1 N17D LPCI 60" and 45' P-scan exam coverage

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Weld: BF Summary Number: 600300 (right side) and 600290 (left side)

Unit: 1 Item Number: B1.12 Outage: 1 R09 (Spring 2002)

Coverage: 85.9%

Base Metal and Weld Materials: Carbon Steel Examination Volume: Full penetration coverage per figure IWB-2500-2 "Vessel Shell Longitudinal Weld Joints" UT Exam Type: Automated UT Examination 0°L, 450 S, 60 0 L, and 70°RL Performed per the requirements of ASME Code,Section XI, Appendix Vill:

Yes, the examination was in accordance with ASME Section Xl Appendix VIII as modified by the PDI program.

Limitation

Description:

The completed examination was limited to 85.9% Code required coverage due to the N17B nozzle being located in the center of the vertical weld. The following coverage calculation sheet and the drawings contain the limitations. No unacceptable indications were noted. A system pressure test was also completed with no unacceptable indications observed.

Limerick Unit-1 Weld BF Spring 2002 CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE 1Z WedLngth t Area Scanned %of Area Scanned Weld Length Scanned  % Scanned

, Area Incht - Auto Manual Auto Manual Auto Manual Auto Manual Unrestricted Scans RIGHT SIDE 70* T-SCAN N 8.05 8.05 0.00 100.0 00 92.50 00 13.7 0.0 RIGHT SIDE 45" T-SCAN N 36.78 36.78 0.00 100.0 0.0 92.50 00 62.5 0.0 RIGHT SIDE 60 T-SCAN N 805 8.05 0.00 100.0 00 92.50 0.0 13.7 0.0 70' P-SCAN UP N 8.05 8.05 0.00 100.0 0.0 92.50 00 137 0.0 45 P-SCAN UP N 36.78 36.78 000 100.0 00 92.50 00 625 00 60' P-SCAN UP N 8.05 805 000 100.0 0.0 92.50 00 137 0.0 Unrestricted Scans LEFT SIDE 70° T-SCAN N 805 8.05 000 1000 00 8450 00 12.5 00 LEFT SIDE 45 T-SCAN N 36,78 36.78 0.00 100.0 00 84.50 00 57.1 0.0 LEFT SIDE 60* T-SCAN N 805 8.05 0.00 100.0 0.0 84.50 00 12,5 0.0 70" P-SCAN DOWN N 805 8.05 0.00 100.0 G0 84.50 00 125 0.0 45" P-SCAN DOWN N 36.78 36.78 0.00 100.0 0.0 84.50 00 57 t 0.0 60* P-SCAN DOWN N 8.05 805 000 100.0 00 8450 0.0 12.5 0.0

___ _ _ _ _ _ _ _ I _ __ __ ___

Cov.ragest 85,9 0.0 Total Ccn-ncStC Couernge = 85.9 eb Ilenjth reduced due lo NI-B nozzle being ,u c nfer of verticil wNod BF, ital reduced area 34 C0" Cc,,C;i;rIs ',ý?ý:2C02 hI^

Limerick 1 Shell Course 2 Weld BF Right Side Coverage Required 45° T-Scan Exam Volume - 36.78 Sq. In.

Required 600 T-Scan Exam Volume - 8.05 Sq. In.

Required 70° T-Scan Exam Volume - 8.05 Sq. In.

60'T 5T

Limerick 1 Shell Course 2 Weld BF Right Side Coverage Required 45" P-Scan Exam Volume - 36.78 Sq. In.

Required 600 P-Scan Exam Volume - 8.05 Sq. In.

Required 70" P-Scan Exam Volume - 8.05 Sq. In.

F, 70*

°°"5T / , ,*.

60* 601

Limerick 1 Shell Course 1 Weld BB Left Side Coverage Required 45* T-Scan Exam Volume - 36.78 Sq. In.

Required 60* T-Scan Exam Volume - 8.05 Sq. In.

Required 70° T-Scan Exam Volume - 8.05 Sq. In.

Z I 14 '

~,...D rn 7ý 5

Limerick 1 Shell Course 1 Weld BB Left Side Coverage Required 45* P-Scan Exam Volume - 36.78 Sq. In.

Required 60* P-Scan Exam Volume - 8.05 Sq. In.

Required 70* P-Scan Exam Volume - 8.05 Sq. In.

F-'

Unit 1 Vessel Nozzle and Weld Locations VESSEL F-LANOE STUD439 CLOSUjRE SILO -76 STUDIt (TYPICAL. 28 STUDS) STUD 38 FHOLE HEADFLANGE LEHOLE HOLE LOCATION LO

ýCATION LOCATION LOCATION 100 2 0 20 270 0 330 0 00 2 fie 0 0 '0 10 0 5 0 wo0 Z jO 7~ 70~ ~3 jLILJJ'IJ 2 taw 6 05 18 VESSEL ELEV..

II 716.25" 1 5'-8,25' c

N3C 0 AFN3A 31)SITE ELEV.

SHELL NO.~ 0 VESELEL'4 SEP=23.5" 511-11.51 SITE ELEV.

0 CLM 3161-2.5*

~ Q VESSEL ELEV.

917- 44'-9. 5' H26 ~ QH N~jlil NZ ~ C8 tC HD 'ZE 110 SITE ELE'V.

0 00~ 0 MIA 0 (T3C 0Th r (28.51 SHVELL NO.1 NA k ~VESSEL ELEV.

0 0 0

11: - ' -: . :: 1::

0 :m0 so 3 60 0. SITE ELEV.

210 248 0m 12 150 28 -*

i1610E VIEW NOTE-t;EE XI-RPV1- K0.2 FOR AZMTHJh ANDELEVATION TAB5LES. ELEV. W"(f-'F26'"

REACTOR PRESSURE VESSEL IsI DRAWING - REACTOR BUILDING RPV SCAN LIMITATION DRAWING REPPOENTS ANAREAWKRL* SCANNING~

-- ,w IN~TERFERENCES EXIST. wF jqILSEUE[J FOR 1ST'-IMIC[f'1Cf

~IbNSP. INTERVAL. [1 MWo'f1j -. 80ý1" I XI-8A-6 N

10 I PHILADELPHIA ELECTRIC COMPANY LGS UNITS I & 21 NOT FOR CNSTRUCTION [ PAGE I OF I z ~

Weld: BM Summary Number: 600400 (right side) and 600390 (left side)

Unit: 1 Item Number: B1.12 Outage: 1R09 (Spring 2002)

Coverage: 83.1%

Base Metal and Weld Materials: Carbon Steel Examination Volume: Full penetration coverage per figure IWB-2500-2 "Vessel Shell Longitudinal Weld Joints" UT Exam Type: Automated UT Examination 0°L, 45 0 S, 60 0 L, and 70°RL Performed per the requirements of ASME Code, Section Xl, Appendix VIII:

Yes, the examination was in accordance with ASME Section XI Appendix VIII as modified by the PDI program.

Limitation

Description:

The completed examination was limited to 83.1% Code required coverage due to insulation interference. The following coverage calculation sheet and the drawings contain the limitations.

No unacceptable indications were noted. A system pressure test was also completed with no unacceptable indications observed.

Limerick Unit-1 Weld BM Spring 2002 CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE Weld Length

• Area Scanned  % of Area Scanned Weld Length Scanned  % Scanned 85,75 2 0 Area nch Auto - Manual Auto I Manual Auto T Manual Auto I Manual Unrestricted Scans RIGHT SIDE 70" T-SCAN Y 8.05 805 0.00 100.0 00 6800 00 12.1 00 RIGHT SIDE 45' T-SCAN Y 36.78 3678 000 100.0 0.0 68.00 00 55.2 00 RIGHT SIDE 60 T-SCAN Y 805 8.05 0.00 100.0 00 68.00 00 12.1 0.0 70 P-SCAN UP Y 805 8.05 0.00 100.0 0.0 68.00 0.0 12.1 00 45" P-SCAN UP Y 36.78 36.78 0.00 100.0 00 68.00 00 55.2 0.0 60" P-SCAN UP Y 8.05 805 0.00 100.0 00 68.00 00 121 1 00 Unrestricted Scans LEFT SIDE 70'T-SCAN Y 8.05 8.05 0.00 1000 00 7450 0.0 132 0.0 LEFT SIDE 45* T-SCAN Y 36.78 36.78 0.00 100.0 0.0 74.50 00 60.4 00 LEFT SIDE 60"T-SCAN Y 8.05 805 0,00 100.0 00 74.50 00 132 0.0 70 P-SCAN DOWN Y 8.05, 8,05 0,00 100.0 0.0 74.50 0.0 132 0.0 45' P-SCAN DOWN Y 36.78 36.78 0.00 1000 00 74,50 00 60.4 0.0 60 P-SCAN DOWN Y 805 8.05 0.00 100.0 0.0 7450 0 0 13.2 00 Ci, erages 63.1 0'Z Total Ccmosite Coveraqe 83 1 Comments

'Automwted Scanning restricted on both sides of PM due to insulation interference vC2ic no Rog

Limerick 1 Shell Course 4 Weld BM Right Side Coverage Required 450 T-Scan Exam Volume - 36.78 Sq. In.

Required 60* T-Scan Exam Volume - 8.05 Sq. In.

Required 700 T-Scan Exam Volume - 8.05 Sq. In.

-60 1 607 2_3.

"5*T 45*Tr-

Limerick 1 Shell Course 4 Weld BM Right Side Coverage Required 45* P-Scan Exam Volume - 36.78 Sq. In.

Required 60* P-Scan Exam Volume - 8.05 Sq. In.

Required 70* P-Scan Exam Volume - 8.05 Sq. In.

45"P I 45P 60"P .....

Limerick 1 Shell Course 4 Weld BM Left Side Coverage Required 45* P-Scan Exam Volume - 36.78 Sq. In.

Required 600 P-Scan Exam Volume - 8.05 Sq. In.

Required 70" P-Scan Exam Volume - 8.05 Sq. In.

7 OT 45"T 45'P S 60 P 60"P ---- 4 I'I

Limerick 1 Shell Course 4 Weld BM Left Side Coverage Required 45* T-Scan Exam Volume - 36.78 Sq. In.

Required 60* T-Scan Exam Volume - 8.05 Sq. In.

Required 700 T-Scan Exam Volume - 8.05 Sq. In.

70'T 45T 60' r2 60*

45' 15'

I

• BM Righ-t Side Automated exam~ area not restricted IBM

- Y= 555.5' Automated exam area restricted due to 3 Insutation Interference

`1-1\ AD Y= 537,75'

BM Left Side Y= 6235' Automated exam area not restricted BM NIPC Y= 549.00' HI A*,tomatecd exam area restricted due to C-)

lzIndatkoin interference Y= 537,75' q

Weld: AG Summary Number: 600570 Unit: 1 Item Number: B1.40 Outage: 1R10 (50%) (Spring 2004) and 1R08 (50%) (Spring 2000)

Coverage: 85.1%

Base Metal and Weld Materials: Carbon Steel Examination Volume: Full penetration and surface per figure IWB-2500-5 "Head to Flange Weld Joint" UT Exam Type: 1 R08 Manual UT Examination 0°L, 450S, 60 0 S, and 70ORL 1R10 Manual UT Examination 600 L Magnetic Particle Examination (MT)

Performed per the requirements of ASME Code, Section Xl, Appendix VIII:

The portion of the examination completed during 1 R08 was not in accordance with ASME Section XI Appendix VIII. This was the approved technical guidance at the time of the examination. The portion of the examination completed during 1R10 was completed in accordance with ASME Section XI Appendix VIII.

Limitation

Description:

The completed examination was limited to 85.1% Code required coverage due to the design of the reactor vessel head. The following drawing contains the limitations. No unacceptable indications were noted. A system pressure test was also completed with no unacceptable indications observed.

Limerick Unit-1 Closure Head Flange Weld 60* Exam Volume = 37.0 Sq. In.

600 T-Scan achieved = 36.2 Sq. In.

60' P-Scan achieved = 29.2 Sq. In.

30 601JP I - -~

Flange

Attachment 4 Relief Request 34 - LGS, Unit 2 Second Ten-Year Inservice Inspection Interval Component NDE Exam Limitations

Weld: N1B Summary Number: 704200 Unit: 2 Item Number: B3.90 Outage: 2R07 (Spring 2003)

Coverage: 71%

Base Metal and Weld Materials: Carbon Steel Examination Volume: Full penetration coverage per figure IWB-2500-7 "Nozzle in Shell or Head" UT Exam Type: Automated UT Examination 0°L, 45°S, 60°RL, and 70°RL Performed per the requirements of ASME Code, Section Xl, Appendix VIII:

Yes, the examination was in accordance with ASME Section XI Appendix VIII as modified by PDI program.

Limitation

Description:

The completed examination was limited to 71% Code required coverage due to the design of the reactor vessel nozzle. The following coverage calculation sheet and the drawings contain the limitations. No unacceptable indications were noted. A system pressure test was also completed with no unacceptable indications observed.

Summary No.: 704200 Limerick Unit 2, L2RO7 Weld Li2-N 1B Spring 2003 CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE Percent Weld Length = 360° Required Exam Area Scanned of Area Weld Length Percent Exam Volume = 58.7 Area Sq. In. Auto Auto Auto Auto 70° T,-Scan A 11.1 5.6 9,5% 360' 4.8%

45*'T-Scan A 39.2 33.6 57.2% 360 28.6%

600 T-Scan A 8.4 8.4 14.3% 3600 7.2%

70' P-Scan A 11.1 4.5 7.7% 360 3.8%,

45" P-Scan A 39.2 26,7 45,5%.. 360' 22.7%

IRS P-Scan A 8.4 5.1 8.7% '" 360" 4.3%

70' T-Scan ... . ......... ..

45° T-Scan ' '

60ý'T-Scan 70W P-Scan 45' P-Scan IRS P-Scan 70' T-Scan 45' T-Scan .....

60ý T-Scan 70' P-Scan ......

IRS P-Scan H ,i j, , ,

I otal Composite Coverage = 71%

Comments: A - Examined 360', Scanning limited due to nozzle configuration.

Nljote - Rounding rell d may aftect calculated values.

3 (D

N.)

CD Limerick Unit-2 Recirc Outlet - N1 70 Exam Volume = 11,1 Sq. In.

45 Exam VoiumL = 39.2 Sq. In.

Inner 15%T Exam Volume JIRS &60"T) 48.

Sq. I*i.

70: T-Scan achieved = 5.6 Sq, In.

45' T-Scan achieved - 33.6 Sq. In.

60' T-Scan achieved - 8.4 Sq. In.

-o C701-CDII 45- 60.T

-3 C:

Co Limerick Unit-2 Recirc Outlet - Ni 70: Exam Volume -11. 1 Sq. in.

45 Exam Volume - 39.2 Sq. In, Inner 15%T Exam Volume (IRS & 60-n - .4 Sq.In.

70* P-Scan achieved 4.5 Sq- In.

RecrcOule--N 45' P-Scan achieved =26.7 Sq. In.

IRS P-Scan achieved 5.1 Sq. in.

70'P 45P1 I45*P HmVlm 70 =1. q n

Weld: N2B Summary Number: 704800 Unit: 2 Item Number: B3.90 Outage: 2R07 (Spring 2003)

Coverage: 77%

Base Metal and Weld Materials: Carbon Steel Examination Volume: Full penetration coverage per figure IWB-2500-7 "Nozzle in Shell or Head" UT Exam Type: Automated UT Examination 0°L, 45°S, 60°RL, and 70°RL Performed per the requirements of ASME Code, Section Xi, Appendix VIII:

Yes, the examination was in accordance with ASME Section Xl Appendix VIII as modified by PDI program.

Limitation

Description:

The completed examination was limited to 77% Code required coverage due to the design of the reactor vessel nozzle. The following coverage calculation sheet and the drawings contain the limitations. No unacceptable indications were noted. A system pressure test was also completed with no unacceptable indications observed.

Summary No.: 704800

.3 Limerick Unit 2

(')

Li2 / N2B Spring 2003 Weld Length =

Exam Volume =

360" 59.7 1

CODE CROSS-SECTIONAL AREA Required Exam Area Sq. In.

Area Scanned Auto Percent of Area Auto TOTAL CODE COVERAGE Weld Length Auto Percent Auto 70 T-Scan A 12 538 9.7% 3600 4.9%

45 T-Scan A.... 39.2 33.5 561% 3600 28.1%

60; T.-Scan A 8.5 8.5 14.2% 360' 7,1%

70CY P-Scan A____ 12 '_4_.5_'_ _ 7.5% 360' 3.8%

4 P Scan__

an A 39.2 31.3 52.4% 360' 26.2%

IRS P-Scan A 8.5 8.5 14.2% 360' 7.1.%

70- T-Scan ... ......

45' T-Scan 6W° --Scan,_

70*' P-Scan 450 P-Scan 7RS P-Scan

' 70: T"Scan " _ _ _ ________ _______

45- TScan .,__

60, ]}-Scan'

70' P-Scan .... ... .

45s P,-Scan IRS P-Scan 4~___ Stn Iotal Composite Coverage = 7(7

-0 Comments: A - Examined 360'. Scanning limited due to nozzle configuration.

(,)

Note - Rounding m~ids mna-y afiect calculated values.

CD Limerick Unit-2 CD Recirc Inlet - N2 45' Exam Voflume 39 2 Sq. hi.

nnefl i5%T Exam Volume (IR~S & 6U1T)= 8, Sq. In.

45~ TScan achieved 33.6 Sq. In.

6W~ T-Scan achieved 6 5 Sq. In, 7at,1 45'1 0

--C)

C)

C) w)

Limerick Unit-2 Recirc Inlet - N2

?70 Exara Volume = 12-0 Sq. In.

45° Exam Volume - 39.2 Sq. In.

Inner 15%T Exam Volume (IRS & 60Tij = 8.5 Sq. in-70' P-Scan achieved = 4.5 Sq. li.

45' P-Scan achieved = 31,3 Sq. In.

IRS P-Scan achieved = 8.5 Sq. In, 701P 45"P2 45'pI 0

Weld: N2C Summary Number: 705100 Unit: 2 Item Number: B3.90 Outage: 2R07 (Spring 2003)

Coverage: 77%

Base Metal and Weld Materials: Carbon Steel Examination Volume: Full penetration coverage per figure IWB-2500-7 "Nozzle in Shell or Head" UT Exam Type: Automated UT Examination 0°L, 450S, 60°RL, and 70°RL Performed per the requirements of ASME Code, Section Xl, Appendix VIII:

.Yes, the examination was in accordance with ASME Section Xl Appendix VIII as modified by PDI program.

Limitation

Description:

The completed examination was limited to 77% Code required coverage due to the design of the reactor vessel nozzle and interference with the N8A nozzle. The following coverage calculation sheet and the drawings contain the limitations. No unacceptable indications were noted. A system pressure test was also completed with no unacceptable indications observed.

Summary No.: 705100 Limerick Unit 2 L2RO7 Li2 / N2C 0

Spring 2003 CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE Percent Weld Length = 360' Required Exam Area Scanned of Area Weld Length Percent Exam Volume = 59-7 Area Sq. In. Auto Auto Auto Auto 70' T-Scan A 12 5.8 9.7% 360' 4.9%

45' T-Scan A 39.2 33.5 56.1% 3600 2a.1%

60" T-Scan A 8.5 8.5 14.2% 2990 5.9%

70' P-Scan A 12 4,5 7.5% 360" 3.8%

45" P-Scan A 39.2 31.3 52.4% 3600 26,2%

IRS P-Scan _, A. 8.5 8,5 14.2% 360" 7.1%

{-o 70' T-Scan 45' T-Scan -...

60" T-Scan B 8.5 6.6 11.1% 61" 0.9%

70' P-Scan ... .....

45' P-Scan IRS P-Scan .. .. _,... ' _, _,_, _, __ " ___________..... .... _..

70' T-Scan 45' T-Scan ..........

60" T-Scan ....

70' P-Scan ' _'_......

45' P-Scan ... . ....

IRS P-Scan otal C.omposite Coverage =

Io 77%

Co-'mment--, -A - Scanning limited due to nozzle configuration.'

B - 60' RL scan limited due to N8A nozzle Note - Rounding melhods may affect calculated values.

r-.

3 CD%

C)

C)

Limerick Unit-2

-u C]

Recirc Inlet - N2 CD 70' Exam Volumei 12,0 q.qa.

45' Exam Volumne 39.2 Sq, In.

Inner 15%T Exam Voiuin. (IRS & 60 1) a5 Sq In.

70. T-Scan achievvd - 5 a Sq. In.

45: T-S an

.. achi -ed

= 33.5 Sq, In.

60°T-$can achieved = 8,5 Sq in I

CD

/ l I-

C)

C~)

Limerick Unit-2 Recirc Inlet - N2 70~£'ain Voliug,,- 12.0 Sq. icy 45 : EzXafflIVOCh~fc 29 2 Sq In.

Innef 15%T Exadn) Volumce (IkS & 60 T) 8.11Sq.In.

790P-Scan a~cheved 4.5 Sqý Iny 45 : P-Scao achlieved =31.3 Sq. In.

IRS P-Scan achieved B.5 Sq In, i

CD

r-CD, Limerick Unit-2 Recirc Inlet - N2 70' Exam Volume = 12.0 Sq. in.

45' Exam Volume = 39.2 Sq. In.

inner 15%T Exam Volume (IRS & 60'T) = 8.5 Sq. in.

70 T-Sdcan achieved = 5.8 Sq. In.

45" T-Scan achieved z 33.5 Sq. In.

60 T-SCan achieved - 6.6 Sq. In.

60*7Scanitaed aa ta N6Aem.w 1 - 12.7, - 1 CD l

Unit 2 Vessel Nozzle and Weld Locations VESSEL FLANGE STUD 439 CLOSURE STUD *76 STUD 4i (TYPICAL 76 STUDS) STUD %38 ISO 0

210 0

HOEHEAD LOCATION 240

\AME 278 FLANGE 3W 8

HOLE LOCAT ION 3380 ~ 0 0

HOLE LOCA7ION 3~0 so 0

100 HOLE LOCATION 150 0 jI 0 VESSEL ELEV.

JINJJ!S" I 59'i-B.295, I III I 71R.Z*"

AF H3ASITE ELEV.

0 I 0 0 3 325'-1.25 SHELL NO,.5 0 0 0 0 VESSEL ELEV, AE 82E35 5N1-11.5" SITE ELEV.

0 SHL O40 0 N12 SHL N12D N12A N5I"X VESSEL ELEV.

S/SITE ELV.

0 0 KIA 0 03I11-5' N40 0ESE ME ELEMVN4 SELN.3NBNAN VESSEL ELEV.

NI6C SITE ELEV.

S7 0 299'-7.5" SHELL NO.1 02~~~\ VESSEL ELEV.

(SELN.10 AA ~ 8O I

188 0 I 218 0

2400 270 3 330 0 0 00 GO0 0 90 I 0~Ui 0 ~

SITE ELEV.

°L0 276'-q5" INSIDE VIEW NOTE.

SEE XI-RPV-2 PG. 2 FOR AZIMUTH AND ELEVATION TABLES. ELEV. 0" (REF)=286'3" /

REACTOR PRESSURE VESSEL ISI DRAWING - REACTOR BUILDING RPV SCAN LIMITATION DRAWING flEPRESENTS AN AREA WHERE SCANNING ILIT I INTERFERENCES EXIST.

ISSUED FR (Arl3 D IO#TI UI-BA- M

' INSS.INTERI ' (L.  ?(- ?r- z8031 1 r PHILADELPHIA ELECTRIC COMPANY LGS UNITS'I & 2 1 NOT FOR CONSTRUCTION IPAGE I OF I

\~ 1 fr K

Weld: N2E Summary Number: 705700 Unit: 2 Item Number: B3.90 Outage: 2R07 (Spring 2003)

Coverage: 77%

Base Metal and Weld Materials: Carbon Steel Examination Volume: Full penetration coverage per figure IWB-2500-7 "Nozzle in Shell or Head" UT Exam Type: Automated UT Examination 0°L, 451S, 601RL, and 70°RL Performed per the requirements of ASME Code, Section Xl, Appendix VIII:

Yes, the examination was in accordance with ASME Section XI Appendix VIII as modified by PDI program.

Limitation

Description:

The completed examination was limited to 77% Code required coverage due to the design of the reactor vessel nozzle. The following coverage calculation sheet and the drawings contain the limitations. No unacceptable indications were noted. A system pressure test was also completed with no unacceptable indications observed.

Summary No.: T4"2tU Limerick Unit 2, L2RO7 -7o5 700 F- Weld Li2-N2_ C Spring 2003 CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE Percent Weld Length = 3600 Required Exam Area Scanned of Area Weld Length Percent Exam Volume = 59.7 Area Sq. In. Auto Auto Auto Auto 70' T-Scan" A 12 5.8 9.7% 3600 49%

45ýý T-Scan A 39.2 33.5 56.1% 360° 28.1%

60"' T-Scan A 8.5 8.5 14.2% 360" 7.1%

.70 P-Scan A 12 4,5 7.5% 360' 3.8%

45' P-Scan A 39.2 31.3 52.4% 360" 26.2%

IRS P-Scan A 8.5 8.5 14.2% 3600 7.1%

70" T-Scan .. .... ........

45 ]T-Scan ...... . ....

r-u 60' T-Scan ......

1) 70 ' P -S c a n _ _.. ... . .... ... ..... ..

J 45' P-Scan IRS P-Scan 70' T -Scan .. ..... '_. .... .......

450 T-Scan "_-

60' T-Scan 70' P-Scan . ........ .

45' P-Scan IRS P-Scan iU0a '

10c posae Coverage = (7/

Comments: A - Examined 360". Scanning limited due to nozzle configuration.

Note - Rounding inetroods may affect calculated values.

.3

-zj Limerick Unit-2 Recirc Inlet - N2 701 Exam Volume = 12.0 Sq. In.

45' Exam Volume = 39.2 Sq. In.

Inner 15%T Exam Volume (IRS & 601T) = 8.5 Sqr In.

70' T-Scan achieved - 5.8 Sq. In 45" T-Scan achieved = 33.5 Sq. tIn 60 T.Scan achieved = 8.5 Sq. In.

45'T M /1 . .

I I

C C

C Limerick Unit-2 Recirc Inlet - N2 70' Exam Votume = 12.0 Sq. In, 45, Exam Vol.me = 39.2 Sq. in.

Inner 15%T Exam Volume (IRS & 60'T) = 8.5 Sq In.

70: P-Scan achieveO = 4.5 Sq. In.

45° P-Scan achieved = 31.3 Sq. In.

IRS P-Scan achieved = 8.5 Sq. In.

70,P45'PZ I 45,P1

Weld: N2F Summary Number: 706000 Unit: 2 Item Number: B3.90 Outage: 2R07 (Spring 2003)

Coverage: 77%

Base Metal and Weld Materials: Carbon Steel Examination Volume: Full penetration coverage per figure IWB-2500-7 "Nozzle in Shell or Head" UT Exam Type: Automated UT Examination 0°L, 450 S, 60°RL, and 70°RL Performed per the requirements of ASME Code, Section Xl, Appendix Vill:

Yes, the examination was in accordance with ASME Section Xl Appendix VIII as modified by PD0 program.

Limitation

Description:

The completed examination was limited to 77% Code required coverage due to the design of the reactor vessel nozzle. The following coverage calculation sheet and the drawings contain the limitations. No unacceptable indications were noted. A system pressure test was also completed with no unacceptable indications observed.

znul["mmacy 1,40': 1uuuJUU CD Limerick Unit 2 L2RO7 Li2/ N2F Spring 2003 CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE

-0 Percent Weld Length = 360' Required Exam Area Scanned of Area Weld Length Percent Exam Volume = 597 Area Sq. In. Auto Auto Auto Auto 70' T-Scan A 12 5.8 9.7% 3600 49%

45" T-Scan A 39.2 33.5 56.1% 3600 28.1%

606 T-Scan A 8.5 8.5 14.2% 360' 7.1%

70" P-Scan A 12 4.5 7.5% 360' 3.8%

45'" P-Scan A 39.2 31.3 52.4% 3600 26.2%

IRS P-Scan A 8.5 8.5 14.2% 360" 7.1%

7W° T-Scan t 45' T..Scan iO 60o T-Scan 70° P-Scan

"-4 45' P-Scan _

IRS P-Scan '_"___,'_i 70W I-Scan .......... .... ... .

45" T-Scan 60( T-Scan 70" P-Scan 4 5' P -S ca n . .. . . .... ...........

IRS P-Scan .............

% Total Composite Coverage = 77%

Comments: A - Examined 3600. Scanning limited due to nozzle configuration.

a Note - Rounding methIods may affect calculated values.

C-CD Limerick Unit-2 Recirc Inlet - N2 70: Exam Volume = 12.0 Sq In.

45 Exam Volume = 39.2 SqI in.

lnner 15%1 Exam Votume (IRS & 60'T) = 8.5 Sq, In.

70' T-Scan achieved 5.8 Sq, In.

45* T-Scan achieved =33.5 Sq. In.

60' 7-Scan achieved =8,5 Sq- In, 70*T 45"T i I

X-C')

N)

CD Limerick Unit-2 Recirc Inlet - N2 C()

70: Exam Volume = 12.0 Sq. in.

45' Exam Volume )39.2 Sq. In.

inner 15%T Exam Volua -IRS & - 5.5

-*T) Sq in.

70' P-Scan achireved -4.5 Sq, In.

406 P-Scani achieved 31.3 Sq. In.

IRS P-Scan achieved 8.5 Sq. In.

70'p

/

t 45 P$

Weld: N2G Summary Number: 706300 Unit: 2 Item Number: B3.90 Outage: 2R07 (Spring 2003)

Coverage: 77%

Base Metal and Weld Materials: Carbon Steel Examination Volume: Full penetration coverage per figure IWB-2500-7 "Nozzle in Shell or Head" UT Exam Type: Automated UT Examination 0°L, 451S, 60°RL, and 70°RL Performed per the requirements of ASME Code, Section Xl, Appendix VIII:

Yes, the examination was in accordance with ASME Section XI Appendix VIII as modified by PDI program.

Limitation

Description:

The completed examination was limited to 77% Code required coverage due to the design of the reactor vessel nozzle. The following coverage calculation sheet and the drawings contain the limitations. No unacceptable indications were noted. A system pressure test was also completed with no unacceptable indications observed.

Summary No.: 705700 Limerick Unit 2, L2RO7 Weld Li2-N2G Spring 2003 C:

CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE Percent Weld Length = 360' Required Exam Area Scanned of Area Weld Length Percent Exam Volume = 59.7 Area Sq. In. Auto Auto Auto Auto 700' T-Scan A 12 5.8 9.7% 3600 4_9%

45' T-Scan A 39.2 33.5 56.1% 360' 28"1%

600 T-Scan A 8.5 8.5 14.2% 360W 7.1%

70' P-Scan A 12 4.5 7.5% 360' 3.8%

45' P--Scan A 39.2 31.3 52.4% 360° 26.2%

ItRS P-Scan A 8.5 8.5 14.2% . 360" 7.1%

700 T-Scan .....

450 T-Scan _ _ __.....

60O'T-Scan ""_,_.. ... .. .......

70, P-Scan 45' P-Scan .. .....

IRS P-Scan 70' T-Scan 45' T-Scan _ .... _.. . ... . .

60' T-Scan 70' P-Scan '_

45" P-Scan IRS P-Scan .. ... . .. .

% Total Composite Coverage = 77%

Comments: A - Examined 3600. Scanning limited due to nozzle configuration.

All a4 Note - Roundingj me~tIods may affect catcuiated values.

A, Limerick Unit-2 Recirc Inlet - N2 70: Exam Volume = 12.0 Sq. In.

45 Exam Volume = 39.2 Sq In.

Inner 15%T Exam Voiume (IRS & 60'T) = 8.5 Sq. in.

701 T-Scan achieved = 5,8 Sq. in-45" T-Scan achieved = 33.5 Sq, In, 6W T-Scan achieved = 8.5 Sq. In.

Limerick Unit-2 Recirc Inlet - N2 70 Exam Volume = 12.0 Sq. In.

45: Exam Volume = 39.2 Sq. In.

Inner 15%T Exam Volume (IRS & 60*T) z 8,5 Sq. In.

70: P-Scan autseved - 4,5 Sq. In.

45' P-Scan achieved = 31,3 Sq. In, IRS P-Scan achieved = 8.5 Sq. In.

/ 101"P 4s"F2.

'0

Weld: N3A Summary Number: 707500 Unit: 2 Item Number: B3.90 Outage: 2R07 (Spring 2003)

Coverage: 77%

Base Metal and Weld Materials: Carbon Steel Examination Volume: Full penetration coverage per figure IWB-2500-7 "Nozzle in Shell or Head" UT Exam Type: Automated UT Examination 0°L, 45 0 S, 60°RL, and 70°RL Performed per the requirements of ASME Code, Section X1, Appendix VIII:

Yes, the examination was in accordance with ASME Section X1 Appendix VIII as modified by PDI program.

Limitation

Description:

The completed examination was limited to 77% Code required coverage due to the design of the reactor vessel nozzle. The following coverage calculation sheet and the drawings contain the limitations. No unacceptable indications were noted. A system pressure test was also completed with no unacceptable indications observed.

7fl~7~(\A IUI*UU zumrnary r'o.: IV1l juuý E Limerick Unit 2 L2RO7 fl N3A-N/S Spring 2003 0)

CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE N)

Percent Weld Length = 360' Required Exam Area Scanned of Area Weld Length Percent Exam Volume = 75 Area Sq. In. Auto Auto Auto Auto 70' T-Scan A 13.9 6.2 8.3% 3600 4.1%

450 T-Scan A 50.5 42.8 57.1% 3600 28.5%

60' T-Scan A 10.6 10.6 14.1% 360' 7.1%

70* P-Scan A 13.9 5.5 7.3% 36'. 3.7%

45' P-Scan A 50.5 40.5 54.0% 3600 27.0%

IRS P-Scan A 10.6 10.6 14A1% 3600 7.1%

70' T-Scan 45' T-Scan . _ _. . ...... .. . ... . ........

600' T-Scan ...............

700 P-Scan ..... . . ...... . _

45' P-Scan ....... ......... .............

IRS P-Scan 700 T-Scan

- 45.) T-Scan _ __ _ _ __ _ __ _, . __ .,__

60' T-Scan _

70' P-Scan 45" P-Scan "'__

IRS P-Scan

% Total Composite Coverage = 77%

0 Comments: A - Examined 360'. Scanning limited due to nozzle configuration.

AlJ NoIte - Rounding methods mIay make calculated values appear in error,

0 Limerick Unit-2 Steam Outlet - N3 CD 70* Exam Volume = 13.9 Sq. In.

45° Exam Volume = 50.5 Sq. i.

Inner 15%T Exam Volume (IRS & 60'T) = 10,6 Sq. In, 70: T-Scan achteved = 6.20 Sq. In.

45 -- Scan achievecd 42.8 Sq. In.

60. T-Scan achieved = 10.6 Sq. In.

0 70'T 45'T6 "T

(D CLimerick Unit-e Steam Outlet - N3 o445" 70: Exam Votume =13.9 Sq. In.

Exam Volume = 50.5 Sq. In.

inner I 5%T Exam Volume (IRS &6( 1= 0.6 Sq. In.

70' P-Scan achieved w 5.5 Sq. in.

45' P-Scan achJ-ieved = 40-5 Sq. In.

IRS P-Scan achieved z 10,6 Sq. In.

-o7oP 45-PIRS (D

a] I I II

Weld: N3B Summary Number: 707800 Unit: 2 Item Number: B3.90 Outage: 2R07 (Spring 2003)

Coverage: 77%

Base Metal and Weld Materials: Carbon Steel Examination Volume: Full penetration coverage per figure IWB-2500-7 "Nozzle in Shell or Head" UT Exam Type: Automated UT Examination 0°L, 451S, 60°RL, and 70°RL Performed per the requirements of ASME Code, Section Xl, Appendix VIII:

Yes, the examination was in accordance with ASME Section X1 Appendix VIII as modified by PDI program.

Limitation

Description:

The completed examination was limited to 77% Code required coverage due to the design of the reactor vessel nozzle. The following coverage calculation sheet and the drawings contain the limitations. No unacceptable indications were noted. A system pressure test was also completed with no unacceptable indications observed.

Summary No.: 707800 Limerick Unit 2 L2RO7 N3B-N/S U.

Spring 2003 r.)

CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE 0 Percent Weld Length = 3600 Required Exam Area Scanned of Area Weld Length Percent Exam Volume = 75 Area Sq. In. Auto Auto Auto Auto 70' T-Scan A 13.9 6,2 8.3% 360' 4.1%

45' T-Scan A 50.5 42.8 57.1% 360 28.5%

60W T-Scan A 10.6 10,6 14.1% 360' 7.1%

70' P-Scan A 13.9 5.5 7.3% 360' 3.7%

45' P-Scan A 50.5 40.5 54.0%. . 360' 27.0%

IRS P-Scan A 10.6 10.6 14.1% 360' 7.1%

70' T-Scan 45' F-Scan 60" T-Scan "

70' P-Scan 45ýP -S can " '_.... .. ...

IRS P-Scan 70W T-Scan ..........

45',I-Scan _,_ ...

60' T-Scan .....

700 P-Scan ....

450 P-Scan IRS P-Scan

-/ba oial uomposie Coverage = 77%

Comments: A - Examined 360'. Scanning limited due to nozzle configuration.

_0 W1 Note - Rounding rne:tods mnay make calculated values appear in error.

I-C)

xi C)

Limerick Unit-2 4o Steam Outlet - N3 0 70" Exam Volume ý 13.9 Sq. In.

45" Exam Volume = 50.5 Sq. In.

Inner 15%T Exam Volume (IRS & 60*T) = 10.6 Sq. In.

70' T-Scan achieved = 6.20 Sq. In.

45* T-Scan achieved = 42.8 Sq. In.

60' T-Scan achieved = 10.6 Sq. In.

/

-D 70*T 45'T 60'T (0 I I-

-I CD 0 ----------------

V

r--

CD I)

CD Limerick Unit-e r-Steam Outlet - N3 0 70* Exam Volume = 13.9 Sq. In.

14 45" Exam Volume = 50.5 Sq. In.

0'T) = 10.6 Sq. In.

Inner 15%T Exam Volume (IRS & 61 70' P-Scan achieved z 5-5 Sq. In.

45° P-Scan achieved = 40.5 Sq. In.

IRS p-Scan achieved = 10-6 Sq. in.

"0701p 45*P I IRS Ail C)

Weld: N4C Summary Number: 705100 Unit: 2 Item Number: B3.90 Outage: 2R07 (Spring 2003)

Coverage: 77%

Base Metal and Weld Materials: Carbon Steel Examination Volume: Full penetration coverage per figure IWB-2500-7 "Nozzle in Shell or Head" UT Exam Type: Automated UT Examination 0°L, 45°S, 60°RL, and 70°RL Performed per the requirements of ASME Code, Section Xl, Appendix VIII:

Yes, the examination was in accordance with ASME Section Xl Appendix VIII as modified by PDI program.

Limitation

Description:

The completed examination was limited to 77% Code required coverage due to the design of the reactor vessel nozzle and the location of the N9 nozzle. The following coverage calculation sheet and the drawings contain the limitations. No unacceptable indications were noted. A system pressure test was also completed with no unacceptable indications observed.

Summary No,:  ?-O, (D Limerick Unit 2 705lo.o Weld Li 2-N4fC Spring 2003 N)

N) CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE C) Percent Weld Length 360' Required Exam Area Scanned of Area Weld Length Percent Exam Volume 59.7 Area Sq. In. Auto Auto Auto Auto 70' T-Sc'an A 12 5.8 9.7% 3180 4_3%

45" T-Scan A 39,2 33.5 56,1% 3180 24.8%

601'T-Scan A 8.5 8.5 14.2% 3180 6.3%

700 P-Scan A 12 4.5 7.5% 3180 3.3%

45 P-Scan A 39.2 31.3 52.4% 3180 23.2%

IRS P-Scan A 8.5 8.5 14.2% 3180 6.3%

70' T-Scan B 12 5.8 9.7% 420 0.6%

45' T-Scan B 39.2 33.5 56.1% 420 3.3%

600 T-Scan B 8.5 7.1 11.9% 420 0.7%

70u P-Scan B 12 4.5 7.5% 42" 0.4%

45' P-Scan B 39.2 31.3 52.4% 420 3.1%

IRS P-Scan 85

&B 8,5 14,2% 1 420 0.8%

7 0 ' T -S ca n ..... .... . .. .... . . .. ....... .

45' T-Scan 60 T-Scan .......... .....

70' P-Scan 45' P-Scan' IRS P-Scan

% Total Composite Coverage = 77%

-U Comments: A - Examined 360'. Scanning limited due to nozzle configuration and N9 nozzle, (C~k (0

B - Examination area was limited due to N9 nozzle.

Lt-C Note - Rounding rriethods may make calculated values appear in error.

3 Limerick Unit-2 Feedwater - N4 N

N 70 Exam Volume = 12.0 Sq, In.

45' Exam Volume = 39.2 Sq. In.

Inner 15%T Exam Volume (IRS & 60°T) = 8.5 Sq. In.

70' T-Scan achieved = 5.8 Sq. In.

45' T-Scan achieved = 33.5 Sq. In.

Ur) 60' T-Scan achieved = 8.5 Sq. In.

fC)

/

6D0T I

i 9.

I- x

-~ I

0 Limerick Unit-2 Feedwater - N4

0 700 Exam Volume = 12,0 Sq. In.

450 Exam Volume = 39.2 Sq. In.

Inner 15%T Exam Volume (IRS & 60'T) = 8.5 Sq. In.

70' P-Scan achieved = 4.5 Sq. In.

450 P-Scan achieved = 31.3 Sq. In.

IRS P-Scan achieved = 8.5 Sq. In.

/

701P 45'P2 45'P1 "D

Co F----

CD I0

C)

~0 N)

Q Lir nerick Unit-2 LA)

Fe ;edwater - N4 N) 0 70' E xam Volume = 12.0 Sq. In.

450 E xam Volume = 39.2 Sq. In.

Inner 15%T Exam Volume (IRS & 60'T) = 8.5 Sq. In.

700 T--Scan achieved = 5.8 Sq, In.

450 T -Scan achieved = 33.5 Sq. In.

60' T -Scan achieved = 7.1 Sq. In.

/

ýT Ca (DQ

'N. -

2 0£--

K

Unit 2 Vessel Nozzle and Weld Locations VESSEL FLANGE STUD 439 CLOSURE STUD *76 STUD 91 (TYPICAL 76 STUDS) STIUD38 HOLE HEADFLANGE HOLE HOLE HOLE LOCATION LOCATION LOCATION LOATION 0 0 0 182 I" 1I :::

210a 240 i1  : ', : 2700I: 1: : 3300

300 I: I:0  : I:103/

A

• 1 : : : '. :9010:

680 I

VESSEL ELEV.

II ~5*'-B,25" 7L.25 NOC w (3 NmA NIA NN I~NT325'-1I.25- SITE ELEV.

SHELL NO.S 0I 0 & VESSEL ELEV.

0 l

0. ll AE 023.5" N12 0 0 31VL-2.5' 011 SHELL NO.4 N120 Na N12C IISITE ELEV.

<$ VESSEL..ELEV.

0 O 0 MI0 0 ,i-SITE ELEV.

NQ0 N4E 0 K4F N 0 NO1 WC As2 sN12C r-i.,

N SITE ELEV.

SHELL NO. 2 VSE LV N2F N26G 2 2 M'(A N2A 2 (4C 20 82E SITE ELEV.

0 0 Q 288'-2.5"

~ HELL NO.)I AA4 4 CO I26.6~

VESSEL ELEV.

101-6.5-0u

° 2 ' 2400 270 .. 3..! -. !33! ' "- 1... ',  ! 1.'  !!J'!," ' , I., '!!! I.0 I SITE ELEV.

90 0 120 1500 180 O 276'-9,5" NOTE: INSIDE VIEW SEE XI-RPV-2 PG. 2 FOR AZIMUTH ANDELEVATION TABLES. ELEV. 0" (FEF)=2S67' REACTOR PRESSURE VESSEL "I[S] DRAWING - REACTOR BUILDING RPV SCAN LIHTAIIJN DRAWING REPRESENTS AN AREA WHERE SCANNING "ILIST 1)

INTERFERENCES EXIST.

JISSUED FOR ISTI&YD I' jjSvj Djd~tr

'9INSP. INTERVAL. w- ~ P~~ 8031 XI-BA-8 101 PHILADELPHIA ELECTRIC COMPANY LGS UNITS 1 & 21 NOT FOR CONSTRUCTION I PAGE I OF I

Weld: N4D Summary Number: 709600 Unit: 2 Item Number: B3.90 Outage: 2R07 (Spring 2003)

Coverage: 66%

Base Metal and Weld Materials: Carbon Steel Examination Volume: Full penetration coverage per figure IWB-2500-7 "Nozzle in Shell or Head" UT Exam Type: Automated UT Examination OIL, 451S, 60°RL, and 70°RL Performed per the requirements of ASME Code, Section Xl, Appendix VIII:

Yes, the examination was in accordance with ASME Section X1 Appendix VIII as modified by PDl program.

Limitation

Description:

The completed examination was limited to 66% Code required coverage due to the design of the reactor vessel nozzle and the location of the N11 B nozzle. The following coverage calculation sheet and the drawings contain the limitations. No unacceptable indications were noted. A system pressure test was also completed with no unacceptable indications observed.

Summary No.: 709600 Limerick Unit 2 (D

Weld Li 2-N4D Spring 2003 7'

CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE M2 Percent Weld Length = 360' Required Exam Area Scanned of Area Weld Length Percent Exam Volume = 597 Area Sq. In. Auto Auto Auto Auto 70' T-Scan A 12 5.8 9.7% 3060 4.1%

455 T-Scan A 39.2 33.5 56.1% 306Q 23.9%

60' T-Scan A 8.5 8.5 14.2% 3060 6.1%

70" P-Scan A 12 4.5 7.5% 3060 3.2%

45' P-Scan A 39.2 31.3 52.4% 3060 22,3%

IRS P-Scan EA 8.5 8.5 14.2% 3060 6.1%

70*"T-Scan ........... ....

45' T-Scan 60' T-Scan 70' P-Scan "

45' P-Scan IRS P-Scan .......

70' T-Scan ....

450 T-Scan ......

600 T-Scan 70' P-Scan . ...

45' P-Scan .....

IRS P-Scan _"'

0 I otal Composite Coverage = 66%

Comments: A - Examined 3600. Scanning limited due to nozzle configuration and N11B nozzle.

-0 cc Ca Note - Rounding meth-ods may make calculated values appear in error.

CD Limerick Unit-2 Feedwate, - N4 70' Exam Volume = 12.0 Sq. In.

in.

45' Exam Volume = 39.2 Sq.

inner 15%T Exam Volume (IRS & 60WT) = 8.5 Sq. In.

CD 70' T-Scan achieved = 5.8 Sq. In.

/ 45° T-Scan achieved = 33.5 Sq. In.

600 T-Scan achieved = 8.5 Sq. In.

0 60X11

+1

(D Cz Limerick Unit-2 C:) Feedwater - N4 70° Exam Volume = 12.0 Sq. In.

45°Exam Volume = 39.2 Sq. In, Inner 15%T Exam Volume (IRS & 60'T) = 8,5 Sq. In.

70°P-Scan achieved = 4.5 Sq. In.

450 P-Scan achieved = 31.3 Sq. In.

IRS P-Scan achieved = 8.5 Sq. In.

/ 70'P 45'P2 I 45'P1 CD

/

Unit 2 Vessel Nozzle and Weld Locations VESSEL FLANGE STUD439 CLOSURE STUD 776 STUO*1 (TYPICAL 76 STUDS) STUD 38 HOLE H-E FLANGE HOLE HOLE HOLE LOCATION LOCATION LOCATION LOCATION 60 0 0 0 5 0 0

]8o 210 2401' 2780o 0 330 *  ; AMER I12 5 oI; 8S VESSEL ELEV.

I I I 7iF.*51 i 59'-8,25" N3C N30 AF N3A N3B SITE ELEV.

325'-I-P5" SHELL NO.5 0 0 0 0 - VESSEL ELEV.

AE 623.5" 51'-LI"5=

Si

% 0 0 . 0 NO0 SITE ELEV.

31-2" S-ELL NO.4 [ N120

• . N12A NI2C VES.SEL ELEV.

ELEV.

SMT ELEV1 I~M INE *FC NQ S 103VESSEL ELEV.

7-S4L't tAC 40.5" 33'-4.5*

1 0 M N178SITE ELEV.

10 0 R7 0 299'-7.5" N1( N NIA N1E N22C NSE I L SýELL NO,2 VESSEL ELEV.

00 0 0 q .L 0 0 2W'-2.5 2G3.5. IB (SHELL.NO.l 0B*, 0Z5 hA 0 VESSEL ELEV.

i

' ' 1  :  : i  : I 1 : :

m

- - : ,: : I -  :- : I IE LV 18, 200 200 0 20 30 0 33800 0 0 1500 900 120 NOTE- INSIDE VIEW SEE XI-RPV-2 M. 2 FOR AZIMUTH ANDELEVATION TABLES. ELEV. 16"(EF--26"'3" REACTOR PRESSURE VESSEL 'Is] DRAWING - REACTOR BUILDING RPV SCAN LIMITAIION DRAWING REPRESENTS AN AftrA WHERE SCANNING IIMIT I INTERFERENCES EXI.T. "IIF 0ll FOR 1ST I=

iNSP. INTERVAL.

ISSUED 1 1 la *l 03 XI-,A-8 - Im DELPHIA ELECTRIC COMPAY LGS UNITS I & 2 1 NOT FOR CONSTRUCTION I PAGE 1 OF I PIL...

MAL0M rA

/ ~

~34tA '~~-e

Weld: N4D-IR Summary Number: 709700 Unit: 2 Item Number: B3.100 Outage: 2R07 (Spring 2003)

Coverage: 88%

Base Metal and Weld Materials: Carbon Steel Examination Volume: Full penetration coverage per figure IWB-2500-7 "Nozzle in Shell or Head" UT Exam Type: Automated UT Examination 68°S, 66.71S, 28°S, and 20°S Performed per the requirements of ASME Code, Section Xl, Appendix Vill:

Yes, the examination was in accordance with ASME Section XI Appendix VIII as modified by PDI program.

Limitation

Description:

The completed examination was limited to 88% Code required coverage due to the location of the N1 I B nozzle and the thermocouple. The following coverage calculation sheet and the drawings contain the limitations. No unacceptable indications were noted. A system pressure test was also completed with no unacceptable indications observed.

Summary NO.:

Limerick Unit-2 7(~7c~O Weld 2-NfR-4D -J ..

Spring 2003 CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE Percent Exam Length 360. Required Exam Area Scanned of Area Exam Length Percent Exam Volume= 3.9 Area Sq. In. Auto Auto Auto Auto Zone 1/ 2A 7A 3.9 3.9 100.0% 315 88%

Zone I/2A  ! I

% Total Composite Coverage 88%

iCODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE Percent .

Exam Length = 360. Required Exam Area Scanned of Area Exam Length Percent Exam Volume = 3.1 Area Sq. in. Auto Auto Auto Auto Zone 2B/3 A 3.1 3.1 100.0% 315 . 88%

Zone 2B/3 I..

% Total Composite Coverage = 88%

Comments; A - Examined 360'. Scanning not limited.

Zones 1 and 2A are ASME Section Xi examinations.

(D Zones 2B and 3 are BWROG alternate requirements to NUREG-0619 feedwater nozzle examinations.

(0 Single sided coverage was obtained in the area restricted by Ni 1 nozzle.

• • Single sided coverage was obtained in the area restricted by a thermocouple.

0 Note - Rounding methods may make calculated values appear in error.

Unit 2 Vessel Nozzle and Weld Locations VESSEL FLANGE CLOSURE HEADFLANE 10 2700 I:: u:

VESSEL ELEV.

59'-5.25" SITE ELEV.

325'-11,25 VESSEL ELEV, 51'-I1.5" SITE EL.EV.

3ES&-2.5' VESSEL ELEV.

VESSEL ELEV.

33°-4E5L SITE ELEV.

2W*9-7.5" VESSEL ELEV.

?l'-U.5,"

NOTE: INSIDE VIEW SEE XI-RPV-2 Of. 2 FOR AZIMUTH ANDELEVATION TABLES. ELEV. 0" IREF)266'37' REACTOR PRESSURE VESSEL iiEPRESENTS AN AKEA WI"IEE SCANNING INTERFERENCES EXIST.

4o

-'Y JIY S SUEDINTERVAL.

IINSP. FOR 1ST'm~ I" ?C p PHILADELPHIA ELECTRIC COMPANY LGS UNITS I & 2 IOO.,.%tc*;

C.'* *v. i-J,

f'v Ais *,4

• f V VO I I+k4' Location of the thermocouple on the N4D nozzle

Weld: N5A Summary Number: 710500 Unit: 2 Item Number: B3.90 Outage: 2R08 (Spring 2005)

Coverage: 71.75%

Base Metal and Weld Materials: Carbon Steel Examination Volume: Full penetration coverage per figure IWB-2500-7 "Nozzle in Shell or Head" UT Exam Type: Manual UT Examination 45 0S and 60°RL Performed per the requirements of ASME Code,Section XI, Appendix VIIi:

Yes, the examination was in accordance with ASME Section Xl Appendix VIII as modified by PDI program.

Limitation

Description:

The completed examination was limited to 71.75% Code required coverage due to the design of the reactor vessel nozzle. The following drawings contain the limitations. No unacceptable indications were noted. A system pressure test was also completed with no unacceptable indications observed.

CD)

Limerick Unit-2 Core Spray- N5 600 NS Exam Volume = 11.2 Sq. In.

60° FV Exam Volume = 39.2 Sq. In.

Inner 15%T Exam Volume (IRS & 60'T) = 8.5 Sq. In.

600 NS T-Scan achieved = 6.2 Sq. In.

60' FV T-Scan achieved 38.3 Sq. In, Inner 15%T-Scan achieved (IRS & 607T) = 8.5 Sq. In.

/ 600 NS T 60' FV T I

1-C:

0 (P,

Limerick Unit-2 Core Spray - N5 60' NS Exam Volume = 11.2 Sq. In.

60' FS Exam Volume = 39.2 Sq. In.

Inner 15%T Exam Volume (IRS & 60'T) = 8.5 Sq. In, 600 P-Scan achieved = 5.6 Sq. In.

60' P-Scan achieved = 32.9 Sq. In.

45' IRS P-Scan achieved = 8.5 Sq. In.

6O00NS P 45' FV P I'P I I I

Weld: N6A Summary Number: 715400 Unit: 2 Item Number: 83.90 Outage: 2R08 (Spring 2005)

Coverage: 71.75%

Base Metal and Weld Materials: Carbon Steel Examination Volume: Full penetration coverage per figure IWB-2500-7 "Nozzle in Shell or Head" UT Exam Type: Manual UT Examination 60 0 S and 60°RL Performed per the requirements of ASME Code, Section Xl, Appendix VIII:

Yes, the examination was in accordance with ASME Section Xl Appendix VIII as modified by PDI program.

Limitation

Description:

The completed examination was limited to 71.75% Code required coverage due to the design of the reactor vessel nozzle. The following drawing contains the limitations. No unacceptable indications were noted. A system pressure test was also completed with no unacceptable indications observed.

Limerick Unit-2 c

Closure Head N6 Cl Cl Nozzle Bottom Side 60° Exam Volume = 30.5 Sq. In.

600 T-Scan achieved = 26,0 Sq. In.

60' P-Scan achieved = 21.5 Sq. In.

CCI? "T

-o Co Nozzle Top Side 60' Exam Volume = 22.0 Sq. In.

60' T-Scan achieved = 17.4 Sq. In.

60' P-Scan achieved = 11.6 Sq. In.

0

'I'

Weld: N6B Summary Number: 715600 Unit: 2 Item Number: 63.90 Outage: 2R08 (Spring 2005)

Coverage: 71.9%

Base Metal and Weld Materials: Carbon Steel Examination Volume: Full penetration coverage per figure IWB-2500-7 "Nozzle in Shell or Head" UT Exam Type: Manual UT Examination 601S and 60°RL Performed per the requirements of ASME Code, Section Xl, Appendix VIII:

Yes, the examination was in accordance with ASME Section XI Appendix VIII as modified by PDI program.

Limitation

Description:

The completed examination was limited to 71.9% Code required coverage due to the design of the reactor vessel nozzle. The following drawing contains the limitations. No unacceptable indications were noted. A system pressure test was also completed with no unacceptable indications observed.

Limerick Unit-2 c-fl Closure Head N6 Nozzle Bottom Side 60' Exam Volume = 30.5 Sq, In.

60' T-Scan achieved = 26,0 Sq. In.

600 P-Scan achieved = 21.5 Sq. in.

INi I

Nozzle Top Side 60' Exam Volume 22.0 Sq. In.

60' T-Scan achieved = 17A4 Sq. in.

60' P-Scan achieved = 11,6 Sq. In.

tC

Weld: N7 Summary Number: 715800 Unit: 2 Item Number: B3.90 Outage: 2R08 (Spring 2005)

Coverage: 81.25%

Base Metal and Weld Materials: Carbon Steel Examination Volume: Full penetration coverage per figure IWB-2500-7 "Nozzle in Shell or Head" UT Exam Type: Manual UT Examination 600S and 60°RL Performed per the requirements of ASME Code,Section XI, Appendix VilI:

Yes, the examination was in accordance with ASME Section Xl Appendix VIII as modified by PDI program.

Limitation

Description:

The completed examination was limited to 81.25% Code required coverage due to the design of the reactor vessel nozzle. The following drawing contains the limitations. No unacceptable indications were noted. A system pressure test was also completed with no unacceptable indications observed,

Limerick Unit-2 Closure Head N7 60' Exam Volume = 19.4 Sq. In.

60' T-Scan achieved = 16.8 Sq. In, 600 P-Scan achieved = 14.7 Sq. In.

T\

-u-cI_ __

S.

C*

Weld: N9 Summary Number: 711500 Unit: 2 Item Number: B3.90 Outage: 2R08 (Spring 2008)

Coverage: 77.1%

Base Metal and Weld Materials: Carbon Steel Examination Volume: Full penetration coverage per figure IWB-2500-7 "Nozzle in Shell or Head" UT Exam Type: Manual UT Examination 450S and 60°RL Performed per the requirements of ASME Code, Section Xl, Appendix VIII:

Yes, the examination was in accordance with ASME Section XA Appendix VIII as modified by PDI program.

Limitation

Description:

The completed examination was limited to 77.1% Code required coverage due to the design of the reactor vessel nozzle. The following drawings contain the limitations, No unacceptable indications were noted. A system pressure test was also completed with no unacceptable indications observed.

C 3)

(D Limerick 2 0

N9 - CONTROL ROD DRIVE 600 NS Exam Volume = 12.3 Sq. In.

600 FV Exam Volume = 39.1 Sg, In.

Inner 15%T Exam Volume (IRS &607T) = 8.4 Sq. In.

60' NS T-Scan achieved = 5.6 Sq. In.

60' FV T-Scan achieved = 37.6 Sq. In.

Inner 15%T-Scan achieved (IRS & 60°T) = 8.4 Sq. In.

/

/ 60' NS T-scan 60° FV T-scan I

V I

C Limerick 2 in N9 - CONTROL ROD DRIVE 600 NS Exam Volume = 12.3 Sq. In.

600 FV Exam Volume = 39.1 Sg. In.

Inner 15%T Exam Volume (IRS & 60*T) = 8,4 Sq. In.

QJ 0ý 60° NS P-Scan achieved = 5.0 Sq. In.

60' FV P-Scan achieved = 31.4 Sq. In.

Inner 15% P-Scan achieved (IRS & 60*T) = 8.4 Sq. In.

/

/ 600 NS P 60° FV P

/

I

~~~~1' /

I I

(D

~0

Weld: N17A Summary Number: 711700 Unit: 2 Item Number: B3.90 Outage: 2R08 (Spring 2005)

Coverage: 81.2%

Base Metal and Weld Materials: Carbon Steel Examination Volume: Full penetration coverage per figure IWB-2500-7 "Nozzle in Shell or Head" UT Exam Type: Manual UT Examination 45°S and 60°RL Performed per the requirements of ASME Code, Section Xl, Appendix VIII:

Yes, the examination was in accordance with ASME Section XI Appendix VIII as modified by PDI program.

Limitation

Description:

The completed examination was limited to 81.2% Code required coverage due to the design of the reactor vessel nozzle. The following drawings contain the limitations. No unacceptable indications were noted. A system pressure test was also completed with no unacceptable indications observed.

77 3

Limerick Unit-2 LPCI - N17 60' NS Exam Volume = 11.2 Sq. In.

600 FV Exam Volume = 39.2 Sq. In.

Inner 15%T Exam Volume (IRS & 600 T) = 8,5 Sq. In.

60' NS T-Scan achieved 6.2 Sq. In.

60' FV T-Scan achieved = 38.3 Sq. In.

0 Inner 15%T-Scan achieved (IRS & 60°T) = 8.5 Sq. In.

600 NS T 60' FV T I I

3 N) 0 Limerick Unit-2 LPCI - N17 C'

600 NS Exam Volume = 11.2 Sq. In.

60' FS Exam Volume = 39,2 Sq. In.

Inner 15%T Exam Volume (IRS & 60'T) = 8.5 Sq. In.

60' P-Scan achieved = 5.6 Sq. In.

600 P-Scan achieved = 32.9 Sq. In.

450 IRS P-Scan achieved = 8.5 Sq. In.

45' FV P F--- ,/

-o C

I

Weld: N17C Summary Number: 712300 Unit: 2 Item Number: B3.90 Outage: 2R07 (Spring 2003)

Coverage: 77%

Base Metal and Weld Materials: Carbon Steel Examination Volume: Full penetration coverage per figure IWB-2500-7 "Nozzle in Shell or Head" UT Exam Type: Automated UT Examination 0°L, 45°S, 60°RL, and 70°RL Performed per the requirements of ASME Code,Section XI, Appendix VIII:

Yes, the examination was in accordance with ASME Section X1 Appendix VIII as modified by PDI program.

Limitation

Description:

The completed examination was limited to 77% Code required coverage due to the design of the reactor vessel nozzle. The following coverage calculation sheet and the drawings contain the limitations. No unacceptable indications were noted. A system pressure test was also completed with no unacceptable indications observed.

E-C OU111I*I m, ý 711),AnO

]if IU Limerick Unit 2 L2RO7 Li2 / N17C Spring 2003 CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE 0 Percent Weld Length = 360' Required Exam Area Scanned of Area Weld Length Percent Exam Volume = 59,7 Area Sq. In. Auto Auto Auto Auto 70* T-Scan A 12 5.8 9.7% 3600 4.9%

450 T-Scan A 39,2 33.5 56.1% 360' 28.1%

60' T-Scan A 8.5 8.5 14.2% 3600 7.1%

700 P-Scan A 12 4.5 7.5% 360' 3.8%

-45" P-Scan A 39.2 31.3 52-4% 360' 26,2%

IRS P-Scan A 8.5 8.5 14.2% 360 1 7.1%

70' T-Scan ...

450 T-Scan _ ,,

60' T-Scan 70' P-Scan . ...

45' P-Scan IRS_ P-Scan___

700 T-Scan 45" T-Scan 60' T-Scan ... ...

70' P-Scan 450 P-Scan IRSP-Scan _______ _ _ _ _ _ _ ______ ______

% Total Composite Coverage = 77%

'0 Comments: A - Examined 3600. Scanning limited due to nozzle configuration.

'I-,

Note - Rounding melnods 'nay affect calculated values.

3 I.

ick Unit-2

• X, Llmer LPCI -N17 TC° Exam Vokume = 12o0 Sq. In.

CD 45' Exam Vol ume = 39°0 Sq. In.

Inner 15%T E*(YamVolume (IRS & 60*T) = 86 Sq. In.

70' T-Scan ac,hieved = 5.8 Sq. In.

45 T-Scan ac hieved = 33.5 Sq. In.

60 T-Scan ac hieved = 8.5 Sq. In.

0 70'OT 45'T 61 I-- ------------

"-3

3 Limerick Unit-2 0

LPCI - N17 70' 450 Exam Exam Volume Volume == 12.0 Sq. in.

39.0 Sq, In.

Inner 15%T Exam Volume (IRS & 60*T) = 8.6 Sq. In.

CA) 70' P-Scan 45" P-Scan achieved achieved =

= 4.5 31.3Sq.

Sq.In.In.

IRS P-Scan achieved = 8.5 Sq. In.

70'T I45*P2 0

Weld: AG Summary Number: 714500 Unit: 2 Item Number: B13.40 Outage: 2R08 (33.3%) (Spring 2005) and 2R07 (33.3%) (Spring 2003)

Coverage: 88.4%

Base Metal and Weld Materials: Carbon Steel Examination Volume: Full penetration coverage per figure IWB-2500-5 "Head to Flange Weld Joint" UT Exam Type: 2R07 manual UT Examination 60°RL 2R08 Manual UT Examination 60°RL Magnetic Particle Examination (MT)

Performed per the requirements of ASME Code,Section XI, Appendix Vill:

Yes, the examination was in accordance with ASME Section XI Appendix VIII as modified by PDI program.

Limitation

Description:

The completed examination was limited to 88.4% Code required coverage due to the design of the reactor vessel nozzle. The following drawing contains the limitations. No unacceptable indications were noted. A Magnetic Particle Examination (Surface) and a system pressure test were also completed with no unacceptable indications observed.

CD 0x "I I Limerick Unit-2 Closure Head Flange Weld 00 p600 600 Exam Volume = 37.0 Sq. In.

600 T-Scan achieved = 36.2 Sq. In.

P-Scan achieved = 29.2 Sq. In.

Top Heau, Flange S

CD (0

0

Attachment 5 Relief Request 35 - LGS, Unit 1 Second Ten-Year Inservice Inspection Interval Component NDE Exam Limitations

Weld: CSB 015 Summary Number: 100990 Unit: 1 Item Number: R1.20 Outage: 1 R10 (Spring 2004)

Coverage: 50%

Base Metal and Weld Materials: Stainless Steel Examination Volume: The examination volume is defined in EPRI TR-112657 "Revised Risk-Informed Inservice Inspection Evaluation Procedure" Rev B-A. For a failure mechanism of R1.20 (element is not subject to a damage mechanism) the required volume is N-578-1 "Risk-Informed Requirements for Class 1, 2, or 3 Piping, Method B Section XI, Division 1". Per the code case the examination volume is contained in Figure IWB-2500-8(c) "Similar and Dissimilar Metal Welds in Components and Piping" with an expanded volume of 1/2 inch beyond each side of the base metal thickness transition or counterbore.

UT Exam Type: Manual examination 450S, 45°RL and 60°RL Performed per the requirements of ASME Code, Section Xl, Appendix VIII:

Yes, the examination was performed to requirements contained in ASME Section X1 Appendix VIII per the PDI program.

Limitation

Description:

The exam completed was limited to 50% Code required coverage because the upstream axial UT scan was not performed due to the weld configuration. The valve material is cast stainless steel whose acoustic properties are not conducive for ultrasonic examination of the full weld.

No unacceptable indications were noted. The following drawings characterize the limitations.

No technology has been approved to obtain additional coverage on cast stainless steel components with this configuration.

GE NUCLEAR ENERGY Wall Thickness LUineriqf Unit: 1 Summary' No.:

Profile Sheet Project- Ma31

... . . . I .. .. .. . . I I 1[ _=1 I Site:

COMrnpoiant QfNumb~ef: CSB 015 1.5" F4 5" F5 17,7_1 11-7 27b,

• 1-17 7-- lq M FLUSH 0.74 CI-w Widtoh:

VALV FL UED HEA 74- 'I...")

UPST Component: DNST Component:

U.7t)' U-W6 Weil Lean*ih:

FLOW Vrit VC Scale = 1 : 1

• ',"< .-. ';'7.. . .. ? .

L~7Reviewed

• Level; Date: um eiReviewed By: Da-te:

Date: ANtI Reviewed By:

Page ." of "

...... ... . ... ...... i. .

Unit:

GE NUJCLEAR EMERGY .'n~ui Un i C verage Saw U.o Report No.

PltSheet IProject: i FLUED HEAp Component 10 Numbear rs 1 Configlurtiton:

.1y I

~MT /4 minitas: Examniner: Levei: Dateý GE Revievd* 'y: Level: Date: 41Reviewed By. Date ANII Reviewe By: Date:

Page oft .

Weld: DCA-101-1 SW2402 Summary Number: 113401 Unit: 1 Item Number: R1.20 Outage: 1R09 (Spring 2002)

Coverage: 50%

Base Metal and Weld Materials: Stainless Steel Examination Volume: The examination volume is defined in EPRI TR-1 12657 "Revised Risk-Informed Inservice Inspection Evaluation Procedure" Rev B-A. For a failure mechanism of R1.20 (element is not subject to a damage mechanism) the required volume is N-578-1 "Risk-Informed Requirements for Class 1, 2, or 3 Piping, Method B Section Xi, Division 1". Per the code case the examination volume is contained in Figure IWB-2500-8(c) "Similar and Dissimilar Metal Welds in Components and Piping" with an expanded volume of 1/2 inch beyond each side of the base metal thickness transition or counterbore.

UT Exam Type: Manual examination 0°L, 45°S and 70°S Performed per the requirements of ASME Code, Section Xl, Appendix Vill:

Yes, the examination was performed to requirements contained in ASME Section Xl Appendix VIII per the PDI program.

Limitation

Description:

The exam completed was limited to 50% Code required coverage because the downstream axial UT scan was not performed due to the weld configuration. The valve material is cast stainless steel whose acoustic properties are not conducive for ultrasonic examination of the full weld. No unacceptable indications were noted. The following drawings characterize the limitations. No technology has been approved to obtain additional coverage on cast stainless steel components with this configuration.

Indication / Coverage System:

GE NUCLEAR ENERGY RWCU Plot Sheet Component ID Number DCA-101-1 SW2402 I Site:

Project:

Limerick IR09 Unit: I Report No.:

113401 Corifiguration PIPE VALVE q_ foe SQ /~, Cý-V&-A 96-cc f/ý fPLXT.

44A Tocid Ginder ;ar.

Ifltials Examiner: Level: Date: GE Reviewed Level: Date: Utility B at ANII Reviewed By D Page ( of,

GE NUCLEAR ENERGY Wall Thickness Profile Sheet ISite- Limerick IR09 Unit: 1 Repoft No.:

113401 Sysiem: RWCU Component ID Number DCA-101-1 SW2402 Lp_"'it {)

k:* qQ" 18V= 270' 0.40 0.41 0,40 0.41 Crown Height: FLUSH 0.40 0.40 o.40 0.41 0,54 0,54 j 0.53 0.52 Crown Width: 0. 8" 0.56 0.56 0,56 Nominal Diameter 6.0" 1 -, I 0.I 6 NIA MIA NIA Weld Length: 21.0" INIA I FLOWV 0) 90"b j Todd Grnder II 02122/102 zz /LaK 3~K Level Date: GE Reviewed 13 Level: Date Utility Reviewed. By ANII Reviewed By: Date, Initials: Exaninei:

Page b ofr

Weld: DCA-101-1 SW2403 Summary Number: 113411 Unit: 1 Item Number: R1.20 Outage: 1 R09 (Spring 2002)

Coverage: 50%

Base Metal and Weld Materials: Stainless Steel Examination Volume: The examination volume is defined in EPRI TR-112657 "Revised Risk-Informed Inservice Inspection Evaluation Procedure" Rev B-A. For a failure mechanism of R1.20 (element is not subject to a damage mechanism) the required volume is N-578-1 "Risk-Informed Requirements for Class 1, 2, or 3 Piping, Method B Section XI, Division 1". Per the code case the examination volume is contained in Figure IWB-2500-8(c) "Similar and Dissimilar Metal Welds in Components and Piping" with an expanded volume of Y2 inch beyond each side of the base metal thickness transition or counterbore.

UT Exam Type: Manual examination 0°L, 45°S and 700S Performed per the requirements of ASME Code, Section Xl, Appendix Vill:

Yes, the examination was performed to requirements contained in ASME Section XI Appendix VIII per the PDI program.

Limitation

Description:

The exam completed was limited to 50% Code required coverage because the upstream axial UT scan was not performed due to the weld configuration. The valve material is cast stainless steel whose acoustic properties are not conducive for ultrasonic examination of the full weld.

No unacceptable indications were noted. The following drawings characterize the limitations.

No technology has been approved to obtain additional coverage on cast stainless steel components with this configuration.

Wall Thickness Unit: 1 Report No.:

\~GE NUCLEAR ENERGY Profile Sheet I Site:

Project Limerick 1R09 113411 System. RWCU Component 1D Number t, DCA-101-1 $W2403 0 90, 18G" 270' 2 44 N/A N/A N/A N/A Crown Height: FLUSH El 0.56 0.56 0.55 0.56 Crown Width: 0..7" 0.55 0.54 0.54 0.55 VALVE PIPE UPST Component: DNST Component:

0.40 0.39 0.40 0.41 Nominal Diameter 6.0" 4

0.40 0.40 Weld Length: 21.0 5 1 0.41 10.41 FLOW qO°

' 1v* Todd Ginder 11 02/22/02: V ...

.t

.. t Initials: Examiner- Level. Date: GE Reviewed 8y. Level: Date: I ......

y R.viewed By: Date* 7ANII Reviewed By: Date:

Page " of o

W/GiNUCLEAR ENERGY Indication I Coverage Site: Umerick Unit: Report No.

iPlot Sheet l Project:

i Ii 1RO9

.. .. . .. 113411 System RWCU Component ID Number DgA-101-1 SW2403 Configuration: VALVE PIPE 0

00 oVt "

Todd Ginder Hl 02/22/02 Initials: Examinet, Level: Date: GE Reviewed dy: Level: -NiiyR!eviewed By: at IANII Reviewed BY:

oaf Page 4ý

Weld: DCA-101-1 SW2406 Summary Number: 113431 Unit: 1 Item Number: R1.20 Outage: 1R09 (Spring 2002)

Coverage: 50%

Base Metal and Weld Materials: Stainless Steel Examination Volume: The examination volume is defined in EPRI TR-1 12657 "Revised Risk-Informed Inservice Inspection Evaluation Procedure" Rev B-A. For a failure mechanism of R1.20 (element is not subject to a damage mechanism) the required volume is N-578-1 "Risk-Informed Requirements for Class 1, 2, or 3 Piping, Method B Section XI, Division 1". Per the code case the examination volume is contained in Figure IWB-2500-8(c) "Similar and Dissimilar Metal Welds in Components and Piping" with an expanded volume of Y2 inch beyond each side of the base metal thickness transition or counterbore.

UT Exam Type: Manual examination 0°L, 450S and 700S Performed per the requirements of ASME Code, Section Xl, Appendix VIII:

Yes, the examination was performed to requirements contained in ASME Section Xl Appendix VIII per the PDI program.

Limitation

Description:

The exam completed was limited to 50% Code required coverage because the downstream axial UT scan was not performed due to the weld configuration. The valve material is cast stainless steel whose acoustic properties are not conducive for ultrasonic examination of the full weld. No unacceptable indications were noted. The following drawings characterize the limitations. No technology has been approved to obtain additional coverage on cast stainless steel components with this configuration.

Wall Thickness Limerick Unit: I Report 1.

GE NUCLEAR ENERG Y Profile Sheet I 1Re9 113431 System: RWCU kQMP onent IDNumber OCA-101-1 SW2406 Position 0 90, 180X 270' 0.40 0.40 0.40 0.40 Crown Height: FLUSH 0.40 0,40 0.40 o.40 2

Crown Width: 0.7" 0.52 0.52 0.53 0.54 PIPE VALVE 3

UPST Component: ONST Component:

0.58 0.56 0.58 0.56 Nominal Diameter NIA N/A NIA WIA Weld Length: 2110" 5

0O 9O D I

270* .J -"

Todd GirEder 110212?102 .Z kI Q ~ ~ e lnitials: Examiner: Level: Date: GE Reviewed  : Level Date: Utility Reviewed By: Da e: . ANII Reviewed By: Dat I Page of 6

Indication I Coverage Limerick Unit: 1 I Report N GE NUCLEAR ENERGY Plot Sheet t: 1R09 113431 System: RWCu Component ID Number DCA-101.1 SW2408 Configuration: PIPE VALVE go  % (~~J E~Ac.v ~ 7- ~ , 0 Q2 4F~

Todd Gind.er Initials: Examiner:

It 02122102 7 _ (I -

GERvewe:

Level.vel Dae: Utility Reviewed By: ANII Reviewed By:~ D Page (of~

Weld: DCA-104-2 SW501 Summary Number: 116050 Unit: 1 Item Number: R1.11 Outage: 1R11 (Spring 2006)

Coverage: 50%

Base Metal and Weld Materials: Stainless Steel Examination Volume: The examination volume is defined in EPRI TR-112657 "Revised Risk-Informed Inservice Inspection Evaluation Procedure" Rev B-A. For a failure mechanism of R1.11 (Thermal Fatigue) the required volume is EPRI TR-1 12657 Figure 4-2 "Examination Volume for Thermal Cracking in Piping Welds NPS 4 or Larger."

UT Exam Type: Manual examination 45 0 S, 0°L and 60°RL Performed per the requirements of ASME Code, Section Xl, Appendix VIII:

Yes, the examination was performed to requirements contained in ASME Section XI Appendix VIII per the PDI program.

Limitation

Description:

The exam completed was limited to 50% Code required coverage because the upstream axial UT scan was not performed due to the weld configuration. The valve material is cast stainless steel whose acoustic properties are not conducive for ultrasonic examination of the full weld.

No unacceptable indications were noted. The following drawings characterize the limitations.

No technology has been approved to obtain additional coverage on cast stainless steel components with this configuration.

Wall Thickness Site : Unit: i Riepoli No.~:

aGE NUCLEAR ENERGY i i Profile Sheet Project; Li 1R11 I1bg~50 System: R"-t Component iD Number:

1.5" w

DCA-104-4 FW501 I

N IA NA VA /A Crown Height: FLUSH WA NIA NIA NIA Crown Width:

IVA '689 WA M/A VAL PIPE UPST Component: ONST Component:

Nominal Diameter: 12.,O' WA b36 N/A NI/A Weld Length: 405'L N/A NIA (WA Reading 4&5 taken from ID and O protfies.

Readings 4&5 were not taken on Pipe, no readings due to non paralell surfaces.

\/ I

\ /

John She Orawn byý Level: Date: GE Reviewed By- Leve[ Date, vie Date: ANti Review: /

Page

• of 7

Weld: DCA-104-4 SW1702C1 Summary Number: 116070 Unit: 1 Item Number: R1.11 Outage: 1R11 (Spring 2006)

Coverage: 50%

Base Metal and Weld Materials: Stainless Steel Examination Volume: The examination volume is defined in EPRI TR-1 12657 "Revised Risk-Informed Inservice Inspection Evaluation Procedure" Rev B-A. For a failure mechanism of R1. 11 (Thermal Fatigue) the required volume is EPRI TR-1 12657 Figure 4-2 "Examination Volume for Thermal Cracking in Piping Welds NPS 4 or Larger."

UT Exam Type: Manual examination 450 S, 600S and 60°RL Performed per the requirements of ASME Code,Section XI, Appendix VIII:

Yes, the examination was performed to requirements contained in ASME Section Xl Appendix VIII per the PDI program.

Limitation

Description:

The exam completed was limited to 50% Code required coverage because the upstream axial UT scan was not performed due to the weld configuration. The valve material is cast stainless steel whose acoustic properties are not conducive for ultrasonic examination of the full weld.

No unacceptable indications were noted. The following drawings characterize the limitations.

No technology has been approved to obtain additional coverage on cast stainless steel components with this configuration.

Ultrasonic Examination Indication Report I Data Report Number: 116070 GE NUCLEAR ENERGY; GCal I Data Sheet Numrer: 0-099 Ste: Limerick Procedure: GE-POI-UT-213 / 106-07.05-40

WOIOID- DCA-?0-I-2FWIIG2 CJ Drawing: DCA-104.4, Rev. 4 Size: 1L Thickness: 0 Exam Start: 1554 LO LoCalton: Tai Dead Center WO Location: Center Line Weld Width: I2' Weld l-heigtit: Exam End: 1637 ind Angle A nc~~ ecl Metal Path Axi iupsti Noý Us~ed DIAC j L' 4 .VDisanc MPI xP MP: 2 Circ Dn ~t I 0- so 12.C0W V916 ax W I...A._..*.NST ROOTGEOMETRY (60* Shear) 2 1 60 125i 12'OGW~ . ......

........ ....... DNST ROOT GEOMETRY_ (50RL) i

Sketch Flow Valve Pipe Valve Pipe Gf Root Geometry, seen intermittently 360' L~~V 3 ~/'57 , eZWSW- 7

,07 4wa - YZ

ýý?z

Wall Thickness G~ENUCLEAR EN~ERGY Profile Sheet J Site:

Project: Limerk LJiII I Unit: / Reponr No.:

116070 Sy5tem: RHR omponent tD Number: DCA-104-2 FW1702 CI w

I-I5 WA N/A NIA VA Crown Height: FJ.USI-2 NA N/A N/A /A Crown Width: 1.2" 3 NA /VA N/A NA VALVE PIPE UPST Component: DNST Component:

Nominal Diameter: 12.0" 4 WNA /A

, WA Weld Length: 40.0/ FLO7

[ -681 1 jN/

NIA WAL FLO L-'

V ikLVE IP + QD CQv&JrioclA TAkEN A-T 0* (,rbc)

Simon C1rothers It 3/14:/010 - 2VP3~

Drawn by: t.evel Date: GE Reviewed 5y Level: Date: j MiliReview: Date ANLI Review: Date

- Page Z ot I

Weld: GBB-105-2 FW5 Summary Number: 254750 Unit: 1 Item Number: R1.20 Outage: 1R1 1 (Spring 2006)

Coverage: 69.5%

Base Metal and Weld Materials: Carbon Steel Examination Volume: The examination volume is defined in EPRI TR-1 12657 "Revised Risk-Informed Inservice Inspection Evaluation Procedure" Rev B-A. For a failure mechanism of R1.20 (element is not subject to a damage mechanism) the required volume is N-578-1 "Risk-Informed Requirements for Class 1, 2, or 3 Piping, Method B Section XI, Division 1". Per the code case the examination volume is contained in Figure IWB-2500-8(c) "Similar and Dissimilar Metal Welds in Components and Piping" with an expanded volume of Y2 inch beyond each side of the base metal thickness transition or counterbore.

UT Exam Type: Manual examination 0°L, 45°S, 60 0 S and 700S Performed per the requirements of ASME Code, Section Xl, Appendix Vill.

Yes, the examination was performed to requirements contained in ASME Section XI Appendix VIII per the PDI program.

Limitation

Description:

The exam completed was limited to 69.5% code required coverage because the downstream axial UT scan was limited due to the weld configuration. No unacceptable indications were noted. The following drawings characterize the limitations.

254750 Ultrasonic Examination Indication Report Data~ Report NumOer:

GE NUCLEAR ENERGY1 Cal / Data Steet Nuf"er: 22 Ia 0-028 Site: Lirnerick Procedure: GfEPDJI-UT-11/4/06-06 Drawing: G88-15-2 Size: 1j Thickness: .375_ Exam Start: 0959 La Loaction: Too DeaO Center Wo Location: Weld Centerfine Weld Width: 0 Weld Height: 0.05" Exam End: 1048 IUsed I DAC r ii W Distance MY hA , 1ý

,,Metal Path MP I MP Max MPO2 Ax/ I Upst/ I Circ Dnst f, ..... . I L2

=:_

70* i w i o

0,5" 0.75Ax iUpstRotGeometry A 2 I 5.0* CCW 0 80.I0

=  :- ...... Ax A IU p1.Ro *ry Geom,,

• Sketch Flow Pipe Valve 3 Root Geometry, seen intermittently 3600 SiMon Croih~rs 113/1001200 GE Reviewed8y'" Level: Date: Utility Review. Date: Dat6 :

Examiner i,,oi:~ Date- Page 6 ol 100

. S.t Wall Thickness Unit: I Repon Nc.:

GE NUCLEAR ENERGY Profile Sheet Project: 254750 Li JI Systern: RH.R Component IO Numue: GBB-105-2 FW5 TII Grown Height: 0.05' Ctown Width: 0.70' PIne Valve UPST Component: ONST Comnpotieni:

Nominal Diameter: 16.0'_

Wetd Lenyth: 50.25' PLOW~

P PE VAL~ VC:

Simon Crothers it 3/iCW20OC)  ;-/2 _

Drawn by: Level: Date: GE Reviewedt* Levet Date f Utility Review: Date Date:

Page 7 of 10

Indication Coverage it Li'meick Unit: I Repow Number.

aGE NUCLEAR ENERGY Plot Sheet Li IRI I 254750 System: Component iD Number: BB-105-2 FWS Configuration: Pi,1e Valve Flow Exam Area:

, (0.5" us+ crown + 0.5" ds) x (TI 3) = 1.7" xO.13"= 0.22 in" Axial Exam:

,, (0.95 x 0.13) + (0.4 x 0.13)12 =0.15 in2 0,15 i 0.22 68%

Circ Exam:

o Exam width = (0.5" us + crown + 0,5") ds = 1.7"

• Examined (0.5" us + crown) = 1.2"

• 1.21.7 = 71%

Coverage Calc:

• (68% + 71%)/2 = 69.5%

• Achieve6d 66,95% coverage.

Simon Crathere /1 3/1002__6 .. .

Drawn by. Lavor Date: GE Reviewed/y: Level: Date Utility Reviewed By: Date: I.e Sy:

Pagc 01 ID

Weld: RH 004 (DCA-105-3-2 FW2)

Summary.Number: 115070 Unit: 1 Item Number: B9.11 Outage: 1R08 (Spring 2000)

Coverage: 50%

Base Metal and Weld Materials: Stainless Steel Examination Volume: IWB-2500-8 "Similar and Dissimilar Metal Welds in Components and Piping" UT Exam Type: Manual examination 45°S and 60°RL Performed per the requirements of ASME Code, Section Xl, Appendix Vitt:

Yes, the examination was performed to requirements contained in ASME Section XI Appendix VIII per the P01 program.

Limitation

Description:

The exam completed was limited to 50% Code required coverage because the downstream axial UT scan was not performed due to the weld configuration, The valve material is cast stainless steel whose acoustic properties are not conducive for ultrasonic examination of the full weld. No unacceptable indications were noted. A liquid penetrant exam and system pressure test were also completed with no unacceptable indications observed. The following drawings characterize the limitations. No technology has been approved to obtain additional coverage on cast stainless steel components with this configuration.

I WALL THICKNESS SITE: UNIT:*...-

SUMMARY

NO.:

GE Nuclear Energy PROFILE SHEET PROJECT 11315 .lA9a..

SYSTEM: R . - COMPONENT ID NO.: CA-i0 -2 ..........

POSITION o' 8° 180" 270' PROCEDURE NO. >JJTUMý4Q2ŽV1_R foi-*- 4

.... ..... ........................... ...- - - - - - -I__ *j* , . . .. .. . . .4 S:

1 .. 1,0

... ..... ............. N..............

.... IA N A.. L ... N....

IA .. C R OW N H EE...

C.... IG H T :- ?Q .N

• EM . ............... .....................

2 1.0 NIA NIA N/A CROWN WIDTH: .2.Q-LNC.ES..

S--- VALVET 3 .96 NA N/A iN/A ICOMPONENT COMPONENT NOM DIAMETER_200ANCiE .

4 104 NiA NA NiA

. . WELD LENGTH: 4JN ..

5 NiA! N/A NiA N/A FLOW THICKNESS: AND.ONTO.R TAKEN FRO. 1980 DATA

INDICATION PLOT SHEET UNIT: Jf108_

SUMMARY

NO.:

GE NuclearEnergy PROJECT:.-JIi5. ... ... . ..............

........... 114.98 {3. ...

.... COMPONENT ID NO.:.. .D.CA-.1Q,5_3 _ 2 ... .

...... ..... FLOW

....... ....... . VA LV E . ... . ..... .

SYSTEM :..Hi.. - PROCEDURE NO.: ...UJ.-LIM-IOQ2-V,-R1- .. . CONFIGURATION-ilIPRE.

,i r 7 .-

INDICATION#1 = ID GEOMETRY tROOT)-

-:LEVEL DA4~ >2 Anf

'/ ERE AT PECO NDEREV DATE HIS.B.& 1.CO.ANII Ry!WOg

Weld: RH 007 (DCA-105-3-1 FW4)

Summary Number: 115070 Unit: 1 Item Number: B9.11 Outage: 1R07 (Spring 1998)

Coverage: 50%

Base Metal and Weld Materials: Stainless Steel Examination Volume: IWB-2500-8 "Similar and Dissimilar Metal Welds in Components and Piping" UT Exam Type: Manual examination 450S and 60°RL Performed per the requirements of ASME Code,Section XI, Appendix VIII:

No, the examination was performed to requirements contained in ASME Section XI and V. This was the approved technical guidance at the time of the examination.

Limitation

Description:

The exam completed was limited to 50% Code required coverage because the downstream axial UT scan was not performed due to the weld configuration. The valve material is cast stainless steel whose acoustic properties are not conducive for ultrasonic examination of the full weld. No unacceptable indications were noted. A liquid penetrant exam and system pressure test were also completed with no unacceptable indications observed. The following drawings characterize the limitations. No technology has been approved to obtain additional coverage on cast stainless steel components with this configuration.

WALL THICKNESS SITE :. LIMERICK UNIT: 1.RQ7

SUMMARY

NO.:

GE Nuclear Energy PROFILE SHEET PRC 115070 IJECT:- 1G1OQ SYSTEM. RHR COMPONENT ID .DCA,-JU1l3- F-4.

POSITION 0. . 50 180' 270-1< t5 i i<

4 .

CROWN HEIGHT: 10" :2,

.90 N/A N/A N/A 2 95 N/A NWA N/A CROWN WIDTHi ...2,&80' VALVE

.95 N/A  : NIA N/A NOM DIAMETER:.20.0" 4  : N/A N/A 1.00 N/A

~AICi ri I CkLCTL,. CA PIt' U L*-.l* ... ....

• n . ...... .. g ,u . FLO W 5 N/A N/A N/A N/A VVL.L................

• - :- . - . _- ~ _ .. -. ' _ L _ . . L _* . . _ . _ . . -. -, -_ -,

_ _ L -__-"

- ' _L-_-- _-.. __- _- . L

• _'

.-*. ...... . . .-... .. . - * . .. . -i, - , . . . - - -; - - - - - , - , *, * , - , -- - -* - , *- , - - -i - , * , * * *-P . - --, . ,

LEVEL DATE - RI" ED- " LEVEL DATE GE REVIEW .

__ LEVEL DATE PECO NDE REVIEW DATE LEVEL DATE PECO NDE REVIEW DATE I.- - .GE REVIEW 84

SITE: LIMERICK, UNIT: 1RO7

SUMMARY

NO.:

GE Nuclear Energy SKETCH SHEET PROJECT: 1G10Q . .. 11,507G

-1 -________

SLow . VALVE SYSTEM. Ri-jR COMPON DCAkI.QS-3-_ FWA ... CONFIGURATION:- PPE.

- - - - - - - - - - - - --- '-- - -L-.

.. . . - - .- -- -. .- - - -- 7.-.- - -

DAT3 GEVREVTBY DATE PAGE: 5 OF:

GE REVIEW BY LEVEL DATE PECO NDE REVIEW BY DATE SoBa. & CO. ANII REVIEW DATE

Weld: RH 008 (DCA-105-1-3 FW5)

Summary Number: 115090 Unit: 1 Item Number: B9,11 Outage: 1R07 (Spring 1998)

Coverage: 50%

Base Metal and Weld Materials: Stainless Steel Examination Volume: IWB-2500-8 "Similar and Dissimilar Metal Welds in Components and Piping" UT Exam Type: Manual examination 45°S and 60°RL Performed per the requirements of ASME Code, Section Xl, Appendix Vill:

No, the examination was performed to requirements contained in ASME Section XI and V. This was the approved technical guidance at the time of the examination.

Limitation

Description:

The exam completed was limited to 50% Code required coverage because the upstream axial UT scan was not performed due to the weld configuration. The valve material is cast stainless steel whose acoustic properties are not conducive for ultrasonic examination of the full weld.

No unacceptable indications were noted. A liquid penetrant exam and system pressure test were also completed with no unacceptable indications observed. The following drawings characterize the limitations. No technology has been approved to obtain additional coverage on cast stainless steel components with this configuration.

E EWALL THICKNESS SITE: ...- IMERIQK -. UNIT:_.1 R-O?.

SUMMARY

NO.:

SGE NuclearEnergy PROFILE SHEET PROJECT: iO,..0Q.. 115D90_

SYSTEM: RJR ... COMPONENT ID _DCI-D54 aFW.

,< 1.5 .< 1.s- )'i POSITION 0. 980' 18o. 27o.

CROWN HEIGHT: FLUSH .. *2 NIA N/A N/A N/A

.. ..... . . ........... ......... O W W I TH .... .. ...

2  :: *91" NIA N/A N/A CROWNWIDTII 1.2.",... .

VALVE, piPE 3 -87" N/A NIA N/A

-- NOM DIAMETER:. 2,Q'.

.85', N/A N/A N/A WELD LENGTH: 63-0" . ...

FLOW 7' NIA N/A NIA 7

I I

-~ -RQ -R~ - -:--AT---

DRAWN BY LEVEL DATE 6R VEWED8Y LEVEL DATE IPAGE: 4 OF: 6 5- AT .

GE REVIEW BY LEVEL DATE PECO NDE REVIEW DATE H.S.B.I. & CO. ANII RMVIEW l/AT% IV

UNIT:-8. 1I7

SUMMARY

NO,:

HST E TSITE:-LIMERICK SK -

GE Nuclear Energy SKTC SIE PROJECT:- 1,GAIOQ . i5090 SYSTEM-, RHR . COMPONENT iD DGA4QEý1=3 FW5 COFGRTO:~LL- . FLOW PIPE

-OFIURTIN YALAVFt

- ------ --- - -- ----- -- 7 K7 -

a - - -* -----.

-- ------------------------ ---- -- -- -- L -- -- -- -- -- -- - -- -

- - - - - -l - - - - - - - - - - -

A. ------------ ~---------- - i 2v j t T =-S $ N

• --. - ,.- -..--.i-------------~I

~ ~ ~

-- - -- - -- --z- - -- - -- - -- - - -

LEVEL DATE ( EREIW DATE PAE:5OF7 GE REVIEW BY 4 LEVEL DATE PECO NDE REVIEW BY DATE H I& ATMNtALU I~t UONIRs

Weld: RH 015 Summary Number: 115240 Unit: 1 Item Number: R1.20 Outage: 1R10 (Spring 2004)

Coverage: 50%

Base Metal and Weld Materials: Stainless Steel Examination Volume: The examination volume is defined in EPRI TR-112657 "Revised Risk-Informed Inservice Inspection Evaluation Procedure" Rev B-A. For a failure mechanism of R1.20 (element is not subject to a damage mechanism) the required volume is N-578-1 "Risk-Informed Requirements for Class 1, 2, or 3 Piping, Method B Section XI, Division 1". Per the code case the examination volume is contained in Figure IWB-2500-8(c) "Similar and Dissimilar Metal Welds in Components and Piping" with an expanded volume of /2 inch beyond each side of the base metal thickness transition or counterbore.

UT Exam Type: Manual examination 450S, 450 RL, and 60°RL Performed per the requirements of ASME Code, Section Xl, Appendix VIII:

Yes, the examination was performed to requirements contained in ASME Section Xl Appendix VIII per the PDI program.

Limitation

Description:

The exam completed was limited to 50% Code required coverage because the downstream axial UT scan was not performed due to the weld configuration. The valve material is cast stainless steel whose acoustic properties are not conducive for ultrasonic examination of the full weld. No unacceptable indications were noted. The following drawings characterize the limitations. No technology has been approved to obtain additional coverage on cast stainless steel components with this configuration.

Wall Thickness I Site: Limerick Unit: I Summary No.:

GE NUCLEAR ENERGY Profile Sheet Project: 329118 115240

~>j 717K 77-

"I ý.,N Compoirlent IDtumber: RH tfl I

~.C3 t) J~)

Crown H~,:ihz: pL u.s Oz~2 o a~

oý4~2 Crowni Wiint:

,FLUED HEAD . VALVE a~ CL~q DNST Component:

-j UPST Component:

Narminal Diarnater: 20 0" o~2 1j~ I '2 I 2e ] Weid Leaitn:

FLOW E/

Scale = 1: 1

/ f" i~-d~js: xanhine, , eReviewed,.

.. GE Level: Date: Utility Reviewed By: Date: ANII Reviewed By: (Date Pae a olg

a GE NUCLEAR ENERGY Indication / Coverage i site: Limeric Unit: I Report No Plot Sheet Project: 32318 115240 Component ID Number. RH 015 Configuration: FLUED HEAD VAL VE

\iALv6

'-I

/

&, 14is -I / /

Lev"t: Date: GE Reviewed w< Levelý Date; Utility Reviewed By: Dale: ANII Reviewed By:. Date:

Page 7 3f

Weld: RHA 002 (DCA-318-3-1 FW4)

Summary Number: 115750 Unit: 1 Item Number: B9. 11 Outage: 1R07 (Spring 1998)

Coverage: 50%

Base Metal and Weld Materials: Stainless Steel Examination Volume: IWB-2500-8 "Similar and Dissimilar Metal Welds in Components and Piping" UT Exam Type: Manual examination 45°S and 60°RL Performed per the requirements of ASME Code,Section XI, Appendix VIII:

No, the examination was performed to requirements contained in ASME Section XI and V. This was the approved technical guidance at the time of the examination.

Limitation

Description:

The exam completed was limited to 50% Code required coverage because the upstream axial UT scan was not performed due to the weld configuration. The valve material is cast stainless steel whose acoustic properties are not conducive for ultrasonic examination of the full weld.

No unacceptable indications were noted. A liquid penetrant exam and system pressure test were also completed with no unacceptable indications observed. The following drawings characterize the limitations. No technology has been approved to obtain additional coverage on cast stainless steel components with this configuration.

WALL THICKNESS SITE:-, LUMERICK.... . UNIT: 1 RO7

SUMMARY

NO.:

GE Nuclear Energy PROFILE SHEET PRO!ECT: AGIOQ l575Q SYSTEM: RHR COMPONENT ID DCA-31BA-.E"AN4.

P O SM ON 0" ia"

• aO* 2 0 . 3 < . - i CROWN HEIGHT _FLUSH A 4.  :

NIA NiA NIA NiA

• 1.

2 CROWN WIDTH: 1.25" .

. 7. .* N. ......

A.LE N. ..

....A..

.. . , ELBOW 3 64 NJA NIA N/A

. . . . - . NOM

. DIAMETER: .12.0"

,62 N/A N/A N/A WELD LENGTH:* 3-.0" ... FLOW

.64 NiA N/A N/A

.. . . . . . . . .. ,o .; - -

-, - -'¢ -- ", -- -- - ---; -'* "---- *- -; . .*-- - " £ - = , =- - "- - - - :-- -

...  :-- - ... -.: - -t...; -:- --:-- -- :-- - -- , -- -- -- -- -------- - -- -- --- -"--b-.----:-

~v4~- - - -J5A

-~~

DRAWN9?' LEVEL DATE GAREI WEUBY) LEVEL DATE GLLC I-& " ,PAGE! 4 of, 6 GE REVIEW BY LEVEL DATE PECO NDE REVIEW DATE H4S.11 & CO. ANDIR- 5 ATE

GENucearIEnergy SKETCH SHEET SITE: LIMERICK. - UNIT: IRQ7

SUMMARY

NO.:

PROJECT: GlO- . .. -.. 115Z5 ..

SYSTEM: RHR COMPONENT ID .... CA&-__3n1 E-_4 CONFIGURATION:.-VALVE .. W ELBOW

-- ---V--L---

.--.. - - - . . . =JA....U~

-T ....

GEREVIAEWbY LEVEL DATE Y DATE GE REVIEW BY LEVEL DATE PECO NDE REVIEW BY DATE

Weld: RHA 003 (DCA-318-3-2 FW5)

Summary Number: 115780 Unit: 1 Item Number: B9.11 Outage: 1R07 (Spring 1998)

Coverage: 50%

Base Metal and Weld Materials: Stainless Steel Examination Volume: IWB-2500-8 "Similar and Dissimilar Metal Welds in Components and Piping" UT Exam Type: Manual examination 450S and 60°RL Performed per the requirements of ASME Code, Section Xl, Appendix Vill:

No, the examination was performed to requirements contained in ASME Section XI and V. This was the approved technical guidance at the time of the examination.

Limitation

Description:

The exam completed was limited to 50% Code required coverage because the downstream axial UT scan was not performed due to the weld configuration. The valve material is cast stainless steel whose acoustic properties are not conducive for ultrasonic examination of the full weld. No unacceptable indications were noted. A liquid penetrant exam and system pressure test were also completed with no unacceptable indications observed. The following drawings characterize the limitations. No technology has been approved to obtain additional coverage on cast stainless steel components with this configuration.

WALL THICKNESS SITE: _LMERICK*.... UNIT: 1 R07

SUMMARY

NO.:

\e GE Nuclear Energy PROFILE SHEET PROJECT:. 1Gl0Q 115780 SYSTEM: RIHR COMPONENT ID DC&ý318r.3.2 FW5

."- 1.~' ).

POSITION 0- 90c 180' 270° CROWN HEIGHT: -FLUSH.

1 .70 NA NI N/A:

2  !.65 N/A N/A N/A CROWN WIDTH: 1.20" PIPE 3 .66 N/A N/A 1 NIA NOM DIAMETER: 12.0" 4 68 N/A NIA I NIA N/A : NIA N/*A N/AWELD LENGTH: 40,0" FLOW

---

I- . .- ..-- ...-----

- FL~v4-N .

ýw------

m LEVEL DATE GE REVIEW BY LEVEL DATE PE(

4~, GE Nuclear Energy SKETCH SHEET SSKETCH SHEET SITE:.. LIMERICK .. . UNIT: 1R07.

SUMMARY

NO.:

GE Nuclear Energy S MC N1J- PROJECT:. 1G1.OQ 115780 SYSTEM. RI-IR COMPONENT ID DC,&31.8-32 F-W5 CONFIGURATION:. PIPE FLOW VALVE

- - ----- - - - - I

---

VALq

-Pý?E -.CL-

---

- ----------------- ------- ------ 7 I 1 7 I T

-C - - --- - - - - - - p

- --j..

- - - - - -- Li's -- - - - -

-r-..

r-,%j e ---

---

1--L-- -------- ------

p AW,'4if GE REVEW k3Y/

LEVEL LEVEL DATE DATE

,:%1,T)77J' IPAG 5 OF: F6 J

Weld: RHB 002 (DCA-318-2-1 FW4)

Summary Number: 116760 Unit: 1 Item Number: B9.11 Outage: 1R08 (Spring 2000)

Coverage: 50%

Base Metal and Weld Materials: Stainless Steel Examination Volume: IWB-2500-8 "Similar and Dissimilar Metal Welds in Components and Piping" UT Exam Type: Manual examination 450S and 60°RL Performed per the requirements of ASME Code, Section Xl, Appendix VIII:

Yes, the examination was performed to requirements contained in ASME Section X1 Appendix VIII per the PDI program.

Limitation

Description:

The exam completed was limited to 50% Code required coverage because the upstream axial UT scan was not performed due to the weld configuration. The valve material is cast stainless steel whose acoustic properties are not conducive for ultrasonic examination of the full weld.

No unacceptable indications were noted. A liquid penetrant exam and system pressure test were also completed with no unacceptable indications observed. The following drawings characterize the limitations. No technology has been approved to obtain additional coverage on cast stainless steel components with this configuration.

WALL THICKNESS SITE: i in;i .. . . . _-.'.-.... . . UNIT: _

SUMMARY

NO.:

GE NuclearEnergy PROFILE SHEET 11t 7.60.

PROJECT: _1 1315 SYSTEM: RHR ........ COMPONENT ID NO:DCAa1&2-I FW4 . .

1-,5 >'**

POSITION 1800, 170 PROCEDURE NO.: UT-:LIMiA.Q2Y.__Ri, i.

I NIA '. N/A NiA NiA *

........T: ...... *.... ..... ..*CROWN HEIGHT:.FLULSH ............... .......

2 70 N/A N/A N/A CROWN WIDTH:. A20 N.C, ...

COMPONENT COMPONENT 3 70 N/A N/A NA

..--... -- NOM DIAMETER:_2.0 _I F . .-

4 .67 N/A N/A N/A WELD LENGTH.3L7Q._*.NhL. _-

I - I p.

5 .72 N/A N/A NIA FLOW FLOW P~LOW VALv" FL 130 W-THICKNESS

. ... .. . .. ..... . . . _.AND

_* ~ CONTO)JR

~ * * . .. TAKEIN

. .. . t -FROM

• L ..PREVIOUS

.! - - * ..DATA:

. . L . .; . .. ; .. .

777- -~

Weld: RHB 003 (DCA-318-2-1 FW5)

Summary Number: 116790 Unit: 1 Item Number: B9.1 1 Outage: 1R08 (Spring 2000)

Coverage: 50%

Base Metal and Weld Materials: Stainless Steel Examination Volume: IWB-2500-8 "Similar and Dissimilar Metal Welds in Components and Piping" UT Exam Type: Manual examination 45°S and 60°RL Performed per the requirements of ASME Code, Section Xl, Appendix VIII:

Yes, the examination was performed to requirements contained in ASME Section XI Appendix VIII per the PDI program.

Limitation

Description:

The exam completed was limited to 50% Code required coverage because the downstream axial UT scan was not performed due to the weld configuration. The valve material is cast stainless steel whose acoustic properties are not conducive for ultrasonic examination of the full weld. No unacceptable indications were noted. A liquid penetrant exam and system pressure test were also completed with no unacceptable indications observed. The following drawings characterize the limitations. No technology has been approved to obtain additional coverage on cast stainless steel components with this configuration.

1..

SUMMARY

NO.:

WALL THICKNESS SITE: .Limiri*k, .. ..................... UNIT:

GE Nuclear Energy PROFILE SHEET PROJECT: U_. ......

J167_9D_

SYSTEM: ......... iCOMPONENT ID NO..CA-1 ....... i

<--+ ,+, -) I,< .... .5" -. .>

POSITION 0 10 80° 1"" PROCEDURE NO.. UT-L1M102V0 R1 *i4

.4 1 .68 ..... .... N/A. ..... NIA

... . ..................... N;A _ C R OW N HEIG HT :._E L i ,

2 .66 NjA NjA NfA CROWN WIDTH :2.1.20_NHE..

VXLVE.

3 .72 N/A N/A t N/A COMdPON4ENT COMPONENT NOM DIAMETER:_._I-E.....

4 .72 N/A N/Al NIA WELD LENGTH:--7,.7G.D NCtiEa.- .---.-. ......

S N/A NiA N/A NA FLOW 2-i... ,..+.:.; . .-+- . : . ... ;. . -*- - .. . .. . . - - . .. . .. . . . .. . . ..

ý ... _j

~ ~

.. .F+ ' ".T. - ' ... . ...C

.r *-L , + *Z+ - - .

L .

~1 LEVEL  !,

OF:-

LEVEL DATE r- DATE I H.S.GI1 &LCO. ANII REVI B

Weld: RRB 004 (RS-1-B2 SWA)

Summary Number: 110150 Unit: 1 Item Number: 89.11 Outage: 1 R08 (Spring 2000)

Coverage: 50%

Base Metal and Weld Materials: Stainless Steel Examination Volume: IWB-2500-8 "Similar and Dissimilar Metal Welds in Components and Piping' UT Exam Type: Manual examination 450 S and 60°RL Performed per the requirements of ASME Code, Section Xl, Appendix Vill:

Yes, the examination was performed to requirements contained in ASME Section XI Appendix VIII per the PD1 program.

Limitation

Description:

The exam completed was limited to 50% Code required coverage because the upstream axial UT scan was not performed due to the weld configuration. No unacceptable indications were noted. A liquid penetrant exam and system pressure test were also completed with no unacceptable indications observed. The following drawings characterize the limitations.

WALL THICKNESS UNIT: 1......

SUMMARY

NO.:

GE Nuclear Energy PROFILE SHEET SYSTEM: RR-.. COMPONENT ID NO.: _RS1I-SA2* .

<- 15~ > i< )>:

POSITION 0 Q 270 PROCEDURE NO.: U-r4AA402VL -REV. 1 pl "*i-t1 2 S N/A NiA NIA N!A CROWN HEIGHT.*.*LU.i,5 ......

2 N,Ak NiA NiA NiA CROWN WIDTH:.__.U 9NES COMPONENT COMPONENT 3 134 NIA NiA NIA NOM DIAMETER, .2. ..

4 1.08 NrA NIA NiA WELD LENGTH: 57al ,NCkES.. .. ...........

s 1.?4 NfA NiA t NiA FLOW

""..-'. . .. '.~ ~~i..

~~~~..

.' . .L ' . . - * * *. . . . L - - - . . . . - . , L _ . .  :

- - - ---- - -~

TNI~<NSSNDZ~UR TKNIROM 198 DATA

-w IPAGE ' OF:

INDICATION PLOT SHEET I SITE:-Limeri*k .. UNIT:- IRQ0.

SUMMARY

NO.:

GE Nuclear Energy - PROJECT:.1315 .. ".... A1015_.

- COM PONENT ID NO.:..RS.irB , .......... .....

SYSTEM:.. RR PROCEDURE NO.: ...UT-LJM*fl2VO,-NFIGURATIONL--EE , P IPE I

• F, -. ,t iNI2ICATION #1 ID GEOM1ETRY (ROOT)

- -. -r 1 - -~ -.

LEVEL DATT/

ýY Pei PE vi HS-11 - - ---VEW I....

I - 1,46.0 OF:

E LEVEL C*kTE j CO NAER V16Wý B.1 & 1.

460. ANII

Weld: RRB 013 (RD-1-B1 FWWB6)

Summary Number: 110370 Unit: 1 Item Number: B9.11 Outage: 1R07 (Spring 1998)

Coverage: 50%

Base Metal and Weld Materials: Stainless Steel Examination Volume: IWB-2500-8 "Similar and Dissimilar Metal Welds in Components and Piping" UT Exam Type: Manual examination 45 0S and 60°RL Performed per the requirements of ASME Code, Section Xl, Appendix VIII:

No, the examination was performed to requirements contained in ASME Section Xl and V. This was the approved technical guidance at the time of the examination.

Limitation

Description:

The exam completed was limited to 50% Code required coverage because the upstream axial UT scan was not performed due to the weld configuration. The pump material is cast stainless steel whose acoustic properties are not conducive for ultrasonic examination of the full weld.

No unacceptable indications were noted. A liquid penetrant exam and system pressure test were also completed with no unacceptable indications observed. The following drawings characterize the limitations. No technology has been approved to obtain additional coverage on cast stainless steel components with this configuration.

WALL THICKNESS SITE:. L-MIERICK. UNIT:.-._1_._.

SUMMARY

NO.:

GE Nuclear Energy PROFILE SHEET PROJECT: --IW.0Q_ .11.0370 .

SYSTEM: BR COMPONENT ID RD:1BINB.

< 1.5- - > 1.5~

POSTION 0 180- 270' CROWN HEIGHT: ELUSH I 2: 4j 1 NIA NJA N/A N/A 2 N/A N/A N/A N/A CROWN WIDTH: 1.5".....

EUME 3 1 5" N/A NIA NIA

"-- -- ..... '"-,-"- --- NOM DIAMETER:.. 28,W. .........

4 1.4" N/A. N/A, N/A

. WELD LENGTH: 88.0"' FLOW 5 S5" NIA N/A N/A

-.!....... ,--....*Y7 ... :,... -.-7 -..- .......

,*-.--7

. -*.~~~~~~~~~~~~~

... ... ... .... ;'- ... ... . ..-. - [- -

---

- -- --- -- T ``- *- - - ` T -` 7' '` - .` - - -

~--~K - -~~v

-~--

"DRA BY LEVEL DATE GE REVIEVNED BY LEVEL DATE PAGE: 4 OF: 7 GE REViE*E BY LEVEL DATE PECO NDE REVIEW DATE , - HS..~~IE ATE wi p u I

SITE:--.MERIC&...... UNIT: -1RO7

SUMMARY

NO.:

GE Nuclear Energy

_ _ _ _ _ _PR SKETCH SHEET t ST:.U- O JECT :- .. ......

f.1O.* .. .... ..... ...... ... ... U1 Q i_1 _ ,

SYSTEM RR . COMPONENT ID ... BI.W Bt . CONFIGURATION:- UMP .... P! . .. .....

- . .- .--. -.- . - . - -. "- . L. - . . -- .- - - - --- - .- . - -- "- - -- - -----

--- - - - - -- - --- - i - - - - - ------- ---------- -- -- - - -. ------

..... ~~~~ -i -~ii:;iii

--- -7i 7 -------- -- 7 --...

6 yEW B DAT *r-Hi GE~tl BLEL By LEVEL DATE TEEREEWYDAE/ PECO NOE R~EVIEW BY DATE H 1..&C.AI EIWATE oREVW G PORM-IJT3 5 RFV

SITE: -LIMERICK -.-.... UNIT:.. 1R07

SUMMARY

NO.:

GE Nuclear Energy SKETCH SHEET PROJECT: AGI0, ... .. 1 1037.0 ,

SYSTEM. RR COMPONENT ID .R.I_1.-B1 FVWVB6..

I CONFIGURATION:- PUMP..

FLOW FLOW

• r 71711

... . . . ...... ... * .. . r-t-.-....-.-..-.-....'.* . .* .* `. *......... .... _--..... _--*

~~~~--

• ..-i-i....-'i.... -'r i!......!

.....i--i- ...-.....

!-:.,.... . / --i-i .. ..i- -.-------/ .... -.----. ...---- - - ......

'll::~ ~~~~~~ ~~ * ! --- -

L!)

-!!-,.4

--i -- i

-. i:!

• . .i . . .....) .* ..=.. ... ........... ;.1. ..A

.. ..; =-k

....-- 6 0 ... .. -4~

-~ - -- -- i. . . . . ,. . . . ..:. . ..

P RL4 DR"~N BY LEVEL DATE GE REVIEW BY DATE Gt RE\)tzw By LEVEL DATE PECO NDE REVIEW BY DATE

Weld: RRB 016 (RD-1-B1 FWWB7)

Summary Number: 110390 Unit: 1 Item Number: B9.11 Outage: 1R07 (Spring 1998)

Coverage: 50%

Base Metal and Weld Materials: Stainless Steel Examination Volume: IWB-2500-8 "Similar and Dissimilar Metal Welds in Components and Piping" UT Exam Type: Manual examination 450S and 60°RL Performed per the requirements of ASME Code, Section Xl, Appendix VIII:

No, the examination was performed to requirements contained in ASME Section XI and V. This was the approved technical guidance at the time of the examination.

Limitation

Description:

The exam completed was limited to 50% Code required coverage because the downstream axial UT scan was not performed due to the weld configuration. The valve material is cast stainless steel whose acoustic properties are not conducive for ultrasonic examination of the full weld. No unacceptable indications were noted. A liquid penetrant exam and system pressure test were also completed with no unacceptable indications observed. The following drawings characterize the limitations. No technology has been approved to obtain additional coverage on cast stainless steel components with this configuration.

I WALL THICKNESS SITE:--LiMER1CK--- - UNIT:., RQ

SUMMARY

NO.:

GE Nuclear Energy PROFILE SHEET PROJECTil.G100 .Q i10390 SYSTEM: RR COMPONENT ID RD_1*B1 F-W",7 2'- i< *.s >'

1.~ >

POSM ON .1 0 " 270 "

CROWN HEIGHT. .FLUSH. ... i2 ,4i 5 1 1.47 N/A NIA N/A t25 N/A !N/A N/A CROWN WIDTH: 1.75'., .

1.5 NANAPIPE - . b 1.30 N/A N/A N/A i

. .. - NOM DIAMETER: 28'.'

1.50 NIA NIA NiA FLOW

...... i.......... WELD LENGTH: 8 _. . . .. . ..... . . ... FLOW 1 55 NIA N/A N/A

-V ...i -i-i- -- ---- ------

DR,4N BY LEVEL DATE GE REVIEWED BY LEVEL DATE GE REVIEW. BY LEVEL DATE PFCO N[IF RFVlFW flhTI DATE PECO NOE REVIEW

(A SITE:. LIMERICK . - UNIT:.. !i-OZ

SUMMARY

NO.:

GE Nuclear Energy SKETCH SHEET PROJECT: G1 Q .................... 10390 PIBE..- o.w VALVE SYSTEM. RR COMPONENT ID _. -I:aBI. F 57- CONFIGURATION:.-

r/ov ----------

E ~--T~

-A- --- T ---

.'L'r 0 WN BY LEVEL DATE GE REVIEW BY DATE 4"o-, -z= vlla /p.?

GE REV)rW BY LEVEL DATE PECO NDE REVIEW BY DATE I

SITE: _. IMERICK_ ... ... UNIT:..11R07

SUMMARY

NO.:

GE NuclearEnergy SKETCH SHEET PROJECT:... G . . . . . . 110390.

FLOWY SYSTEM. RR .......- COMPONENT ID .... E*B*7* CONFIGURATION: PPE ..... _ALVE

~- - - -- -- - - - - - -

- P-o

~ ~~~ ~ 6 / ----I-r~

-ot DRAWA BY LEVEL DATE GE REVIEW BY DATE BY LEVEL DATE PECO NDE REVIEW BY DATE

Weld: RW 020 (DCB-102-1-1 FW1)

Summary Number: 244640 Unit: 1 Item Number: 05.11 Outage: 1R08 (Spring 2000)

Coverage: 50%

Base Metal and Weld Materials: Stainless Steel Examination Volume: IWC-2500-7 "Welds In Piping" UT Exam Type: Manual examination 450S and 70°S Performed per the requirements of ASME Code, Section Xi, Appendix VIII:

Yes, the examination was performed to requirements contained in ASME Section X1 Appendix VlIl per the PDI program.

Limitation

Description:

The exam completed was limited to 50% Code required coverage because the upstream axial UT scan was not performed due to the weld configuration. The valve material is cast stainless steel whose acoustic properties are not conducive for ultrasonic examination of the full weld.

No unacceptable indications were noted. A liquid penetrant exam and system pressure test were also completed with no unacceptable indications observed. The following drawings characterize the limitations. No technology has been approved to obtain additional coverage on cast stainless steel components with this configuration.

S ITE : -- i e f.J ..... . ........ ....... ......

k ------ UNIT:. .

SUMMARY

NO.:

WALL THICKNESS GE Nuclear Energy PROFILE SHEET 244640 PROJECT:__ 11315 ........ ......

SYSTEM:_ RW* U COMPONENT ID NO.: ._D.CB-_.,02-.:L-.FW_1.

3< 1.5s >

POSiTION 0 *95' 150' 27o* PROCEDURE NO.: -,-

12 .4.

1 N.A NIjA NJA NiA CROWN HEIGHT: -FLUSH,......... - ..........

2 ,45 N'A N/A N)A

! .. .. . .- CROW N WIDTH [-S.60-!NCH-EJ S... ...... ........ ......... ..

RiP pE COMPONENT COMPONENT 3 .50 ....

• .....N/A

..... ....... NIA

....... - NiA NOM DIAMETER: ._6..JQNGhE.S 4 .45. N;A NiA NiA WELD LENGTH:_21t..INCHES 5 .46 NIA N/A NiA FLOW

~)

V /

DRAVý% BY LEVEL DATE PAGE OF:

IEVEL y2

'&~ )z

/AT1E ~DT A X n 60 SI& oAt RE hW BY

Attachment 6 Relief Request 35 - LGS, Unit 2 Second Ten-Year Inservice Inspection Interval Component NDE Exam Limitations

Weld: DBB-203-1 FW2 Summary Number: 120000 Unit: 2 Item Number: R1.11 and R1.18 Outage: 2R08 (Spring 2005)

Coverage: 81.5%

Base Metal and Weld Materials: Carbon Steel Examination Volume: The examination volume is defined in EPRI TR-112657 "Revised Risk-Informed Inservice Inspection Evaluation Procedure" Rev B-A. For a failure mechanism of RI. 11 (Thermal Fatigue) the required volume is EPRI TR-1 12657 Figure 4-2 "Examination Volume for Thermal Cracking in Piping Welds NPS 4 or Larger."

LIT Exam Type: Manual examination 45 0 S, 60 0 S and 700S Performed per the requirements of ASME Code, Section Xl, Appendix Vill:

Yes, the examination was performed to requirements contained in ASME Section XI Appendix VIII per the PDI program.

Limitation

Description:

The exam completed was limited to 81.5% Code required coverage due to the weld configuration. No unacceptable indications were noted. The following drawings characterize the limitations.

,Ultrasonic Examination Indication Report I Data Report Number: 120000 4 GE NUCLEAR ENERGY Site: Limerick Procedure: GE-PDI-UT-1 / R3 / N/A Cal / Data Sheet Number: D-076 Weld ID: DBB-203-1 FW2 Drawing: XI-DBB-203-1 Size: 24" Thickness: 1.812" Exam Start: 15:42 Lo Location: TDC Wo Location: Weld Centerline Weld Width: 1.40" Weld Height: Flush Exam End: 16:25 Ind Angle %of Indication Length W Distance Metal Path Ax / Upst/

No. Used IDAC Li LMax I ,2 W I W Max W2 MP  !'MP 'x MP2 Crc Dnst Comments:

1 6.o° L2_2 4 o"_W NIA . J ' NlA.2,e8 ___l Upet !*Obnnerdirnmtttnt.y 3600 at varying anlritude_. Root Geometry Sketch VA4 y*

• 7,oý15

/ 0 Chad Olson 11 Level: Da e: tillReview: Date: I ANII Review: Date:

Examiner Level: Date: Page 5 of 7

Wall Thickness Site: Limerick Unit: 2 Report No.:

GE NUCLEAR ENERGY Profile SheetI Project: 36022 120000 System: FW k15" Component ID Number: DBB-203-1 FW2 Position 0U. 90, 180, 270' 1 N/A N/A N/A N/A Crown Height: Flush 2 1.68" N/A N/A NA Crown Width: 1.40" Valve Tee 3 1.85" NA N/A NA UPST Component: DNST Component:

Nominal Diameter: 24.0" 4 1.73" N/A INA N/A 5 NIA jN/A NAII NAV Weld Length: 76.0" FLON Contours taken from previous data.

A LV" Limited Examination Due to OD Configuration Ax Scan:

Total Examination Area = 1.235 Square Inches Actual Examination Area = 0.78 Square Inches Ax Scan Coverage = 63%

Circ Scan = 100% A/0 Cov7d &t- 2ý Code Coverage Achieved = 81.5%

C.q_ Chad Olson /1 31/72005 Initials: Examiner: Level: Date: Level: Date: Date:

Page 6 of 7

Weld: DBB-204-1-1A SW7 Summary Number: 124400 Unit: 2 Item Number: R1.11 and R1.18 Outage: 2R07 (Spring 2003)

Coverage: 89%

Base Metal and Weld Materials: Carbon Steel Examination Volume: The examination volume is defined in EPRI TR-112657 "Revised Risk-Informed Inservice Inspection Evaluation Procedure" Rev B-A. For a failure mechanism of R1.11 (Thermal Fatigue) the required volume is EPRI TR-1 12657 Figure 4-2 "Examination Volume for Thermal Cracking in Piping Welds NPS 4 or Larger."

UT Exam Type: Manual examination 450S Performed per the requirements of ASME Code, Section Xl, Appendix VIII:

Yes, the examination was performed to requirements contained in ASME Section XI Appendix VIII per the PDI program.

Limitation

Description:

The exam completed was limited to 89% Code required coverage due to the sweepolet in the pipe. No unacceptable indications were observed. The following drawings characterize the limitations.

Indication I Coverag e ..

Site Limerick Unit: 2 Report No.:

GE NUCLEAR ENERGY Plot Sheet L12R.O 124400 L Project System: FW Component IDNumber: SaB-20*4-1-A SW7 Configuration: Pipe Sweepolet a

45 J II P) PE L5 V-JCLPOL..LT Chrles Littlefield II 03190 lniKls: Examiner: Level: Dale: GE Reviewed By' Level Date: Utility Reviewed By: Date: ANII Reviewed By: D te:

Page .3 of /

Weld: DCA-201-1 FW10 Summary Number: 662700 Unit: 2 Item Number: B9.11 Outage: 2R06 (Spring 2001)

Coverage: 50%

Base Metal and Weld Materials: Stainless Steel Examination Volume: IWB-2500-8 "Similar and Dissimilar Metal Welds in Components and Piping" UT Exam Type: Manual examination 0°L, 450S and 700S Performed per the requirements of ASME Code,Section XI, Appendix VIII:

Yes, the examination was performed to requirements contained in ASME Section Xl Appendix VIII per the PDI program.

Limitation

Description:

The exam completed was limited to 50% Code required coverage because the downstream axial UT scan was not performed due to the weld configuration. The valve material is cast stainless steel whose acoustic properties are not conducive for ultrasonic examination of the full weld. No unacceptable indications were noted. A liquid penetrant exam and system pressure test were also completed with no unacceptable indications observed. The following drawings characterize the limitations. No technology has been approved to obtain additional coverage on cast stainless steel components with this configuration.

Wall Thickness Profile Sheet Rwcu Crown Height: fIit"

- - Crown Width: inch

.48 PS/A P/A N/A I UPST Co

- .46 NA - " -A Nominal Diameter: 6 Inch* mponent: DNST Componient:

4

.42 WA WA Weld Length: 21 Inches IPI. FRo, VA"Ve ir~i~s xichard J Lshevn e Date0 G Ui R in~i:Examiner: Level: Date: GE Reviewed ~fLevel: Date: Utility Reviewed By: B:

e Date:

Page ~of r

Weld: DCA-201-1 SW1402 Summary Number: 661810 Unit: 2 Item Number: B9.11 Outage: 2R06 (Spring 2001)

Coverage: 50%

Base Metal and Weld Materials: Stainless Steel Examination Volume: IWB-2500-8 "Similar and Dissimilar Metal Welds in Components and Piping" UT Exam Type: Manual examination 0°L, 450S and 70 0 S Performed per the requirements of ASME Code,Section XI, Appendix VIII:

Yes, the examination was performed to requirements contained in ASME Section XI Appendix VIII per the PDI program.

Limitation

Description:

The exam completed was limited to 50% Code required coverage because the downstream axial UT scan was not performed due to the weld configuration. The valve material is cast stainless steel whose acoustic properties are not conducive for ultrasonic examination of the full weld. No unacceptable indications were noted. A liquid penetrant exam and system pressure test were also completed with no unacceptable indications observed. The following drawings characterize the limitations. No technology has been approved to obtain additional coverage on cast stainless steel components with this configuration.

661810 Ultrasonic Examination Indication Report Cata D Report Number:

WI*/ GE NUCLEAR ENERGY Call/ Data Sheet Number: D-049 Site: Limerdck Procedure. PDI-UT-2 / B / N/A i WeldID: OCA-201-1 SW1402 Drawing: XI-DCA-201-1 Size: 6 Thickness: 0 .432 Exam Start: 1220 Lo Location: 0* Wo Location: Weld Centerline Weld Width: 1.0 Weld Height: Flush Exam End: 1225 Ind I Angle I% of Indication Length W Distance Metal Path Ax/ Upst/

No.1 Used DACI L1 I L Max L2 W1 W Max W2 MP 1 ' MP M P2 Circ Dnst Comments:

1i 70 .125 "  ! 16.25 - 1.1 * . '2 ._' * ._A.xal .Upst D geometry root 360 intermittently at varying ampliudes

'Sketch N

N rDfJhPhca ICGtRLcaT6f 2 y, John Shea If 313012001 GReiwdLevel: Date:

Utility Reviewed By: Date: Date:

f; rn 7 EmZr)iner Level: Date.

Wall Thickness - Site: LVmedck Unit: 2 Report No.:

GE NUCLEAR ENERGY Profile Sheet Project: 19765 661810 System: RWCU Component ID Number: DCA-20f-1 SW1402 1.5" 1.5" Position 0. 90" 180* 270° Ii 2i

.42 .43 .42 .42 Crown Height: Flush

.42 .42 .42 .42 2

Crown Width: 1.0 Inches

.45 .44 .44 .44 PValve 3

UPST Component: DNST Component:

Nominal Diameter: 6 inch 4

Weld Length: 21 Inches 5

FLOW__--

S. . . John

. Shea

.. . .. H 03/30/..1

. 1............ _e _

inalas: Examiner: Level: Date: GE Reviewed BV Level: Date: Utility Reviewed By: Date: ANII Reviewed ByDate:

L~~~~~~~~~

. .- .. ~.

...- . . . . ~ . .- - ~-~age 7 of Z

Weld: DCA-201-1 SW1403 Summary Number: 662110 Unit: 2 Item Number: B9.11 Outage: 2R06 (Spring 2001)

Coverage: 50%

Base Metal and Weld Materials: Stainless Steel Examination Volume: IWB-2500-8 "Similar and Dissimilar Metal Welds in Components and Piping" UT Exam Type: Manual examination 0°L, 450S, and 70 0 S Performed per the requirements of ASME Code, Section Xl, Appendix Vill:

Yes, the examination was performed to requirements contained in ASME Section XI Appendix VIII per the PDI program.

Limitation

Description:

The exam completed was limited to 50% Code required coverage because the upstream axial UT scan was not performed due to the weld configuration. The valve material is cast stainless steel whose acoustic properties are not conducive for ultrasonic examination of the full weld.

No unacceptable indications were noted. A liquid penetrant exam and system pressure test were also completed with no unacceptable indications observed. The following drawings characterize the limitations. No technology has been approved to obtain additional coverage on cast stainless steel components with this configuration.

S N Wall Thickness Site: L Unit: . Report No.:

GE NUCLEAR ENERGY Profile Sheet Projectd 1ili 662110 I

System: RWCU Component ID Number: DCA-201-1 SWI403 1.5"1 M31 j

• Crown Height:

Crown Width: 1.0 Inch UPST Component: DNST Component:

Noninal Diameter: 6.0 inch" Weld Length: 21.0 Inches FLEk no TOJ~A)eISs ~Rk~iflLaJc. 77'~ Th!Ar~ iW~1 "477~,L)

John Shea U T140'KF-S 6() 7 IPJA1*I)

-E*A:r /-)*=: 7"oo In1aats: Examiner: Level: Date: GE Reviewe y: Level: Date: Utity Reviewed By Date MIl Reviewed By Page 4 of z

Ultrasonic Examination Indication Report Data Report Number. 662110 GE NUCLEAR ENERGY Cal / Data Sheet Number: 0-of' Site: Limerick Procedure: PDI-UT-2/1B N/A Weld ID: OCA-201-1 SW1403 Drawing: XI-OCA.201-1 Size: fI Thickness: Al2 Exam Start 0 oca n: &!d&UM Wo Locauon: Weld Centerline Weld Width: j. Weld Height: Flush Exam End:

Ind Angle I% of I Indication Length I W Distance I Metal Path I Ax / I Ups IJ No Used DAC Li L Max L2 Wi W Max I W 2 IMP I IMP Max I MP 2 1 Circ Dnst Comments:

. 9 1 .40 10 70 l t . Ll. .. 1JI !Lirotemty~360 in~rmutoliytvsyl:

Sketch aD ioo-1 cds,vx* TRe*

il 3/t1'2001~

John Sha .J4=7 V///c i4 Z John She 3/30/20 GE Reviewed B Level, Date: Utility Reviewed By: Date: ANI Examiner Level. Dale:

Weld: DCA-201-2 SW702 Summary Number: 671810 Unit: 2 Item Number: B9.11 Outage: 2R06 (Spring 2001)

Coverage: 50%

Base Metal and Weld Materials: Stainless Steel Examination Volume: IWB-2500-8 "Similar and Dissimilar Metal Welds in Components and Piping" UT Exam Type: Manual examination 0°L, 45 0S and 70°S Performed per the requirements of ASME Code, Section Xl, Appendix VIII:

Yes, the examination was performed to requirements contained in ASME Section X1 Appendix VIII per the PDI program.

Limitation

Description:

The exam completed was limited to 50% Code required coverage because the downstream axial UT scan was not performed due to the weld configuration. The valve material is cast stainless steel whose acoustic properties are not conducive for ultrasonic examination of the full weld. No unacceptable indications were noted. A liquid penetrant exam and system pressure test were also completed with no unacceptable indications observed. The following drawings characterize the limitations. No technology has been approved to obtain additional coverage on cast stainless steel components with this configuration.

Wall Thickness I ste: Li Unit: I Report No.:

GE NUCLEAR ENERGY Profile Sheet Project: 197 7871 1

System:

Position 0.

.42 90°

.42 RWCU 180°

-43 270°

.42 Component t0 Number: DCA-201-2 SW702 H

r-1.5" M3 15 Crown Height: Flush

.42 ,42 43 .42 2

Crown Width: i1.0Ice

.44 44 .45 .44 El ValVe 3

UPST Component: DNST Component:

Nominal Diameter: 0.0 nches 4

Weld Length:

5 FLO__.

0 D 10 Z-7? -I---

4- NJ o -rw Z: I S~~'

V~i-i~

- tý InI.

• 1

. iIII11 r-J

^

L

-rh/^n J. 'IL rl"A'Irl I

0

'LiI

ý I £I IV hr als John shea I iials: Examiner: Level: Date: GE Reviewed,, y: Level: Date: Utility IReviewed By:~ Date: ANtI Reviewed By: D te.

Page 01 of

Weld: DCA-204-2 FW 101 Summary Number: 325510 Unit: 2 Item Number: B9.11 Outage: 2R06 (Spring 2001)

Coverage: 50%

Base Metal and Weld Materials: Stainless Steel Examination Volume: IWB-2500-8 "Similar and Dissimilar Metal Welds in Components and Piping" UT Exam Type: Manual examination 0°L, 450S and 60ORL Performed per the requirements of ASME Code, Section Xl, Appendix VIII:

Yes, the examination was performed to requirements contained in ASME Section XI Appendix VIII per the PDI program.

Limitation

Description:

The exam completed was limited to 50% Code required coverage because the downstream axial UT scan was not performed due to the weld configuration. The valve material is cast stainless steel whose acoustic properties are not conducive for ultrasonic examination of the full weld. No unacceptable indications were noted. A liquid penetrant exam and system pressure test were also completed with no unacceptable indications observed. The following drawings characterize the limitations. No technology has been approved to obtain additional coverage on cast stainless steel components with this configuration.

Data Report Number. 325i510 ii Ultrasonic Examination Indication Report I GE NUCLEAR ENERGY Calt I Data Sheet Number D-044 Site. Limerick Procedure: PDI-UT-2 Weld I: DCA-204-2FWI102 Drawing. XI-DCA-204-2 Size: 12 Thickness. .6M Exam Start: 1105 Lo Locaton: 0. Wo Location: Weld Centerline Weld Width: 1.2 Weld Height: Flush Exam End: 1120 Ind An 1 ~le A Io~f indiatcaion Length ...I W Distance Metal Pathl IAx/'""lUpst/ I No. LUsed DAC L1 L Max L2j WI W Max W2 MP'I MP Max MP 2 Circ I Dnst Comments:

6,60 112 13.75 , - - 1.1 -_ .,

• 1.35 , 0 Axial IUpst LD metry root obseved 360"intermittently at varying amplitudes.

Sketch Shea II 312312001 GE Reviewed Level: Date: LItility Reviewed By: Date: ANII Reviewed By:

Ex-mner Level: Date: Page 6 oa 7

Wall Thickness Unit: I Report N.

GE NUCLEAR ENERGY Profile Sheet System:

1 1.5 "1 Crown Height: "ui Crown Width. 1.0 Inches Viae UPST Component: DNST Component:

Nominal Diameter: 12 Inches Weld Length: 40.75 Inche no~

-~~ ~

-rtEAtCC, I - To h Fg tUA John She Examiner: Level: Date: GE Reviewved/dy: Level: Date: Utility Reviewed By: Date: ANII Revii By: age IDat(k Page Sof Z

Ultrasonic Examination Indication Report Data Report Number 329915 GE NUCLEAR ENEIRGY Cal l Data Sheet Number: D-062 it.,* I iir-ripk Procedure: PDI-UT-2

'Weld ID: DCA-204-4 FW701 Orawing: XI-OCA-204-4 Size: Ii Thickness: Exam Start; .112 LO Location: 0' Wo Location: Weld Centerdiins Weld Width: 1.1 Weld Height: Flush Exam End: 1136 Ind Angle 0/

of indication Le tngth W Distance Metal Path A Ix i Upst

40. Used DAC L, L Max *L2 ¶ W, WMax I W2 MP 1 MPMax MP2 Cic Dnst Comments:

1 60 " 9 . . . I . 1.. __ _ "_ 1,45 . ' . ..A n t .. Ageometr Q ro, obserd intermttently

, 360 at

_ vayng armnpti*dues.

Sketch

.. P i*.Ce.T r* _ ,L _.K_y ... .... .... . .. .

) John Shea 11 3/23/2001 GE Reviewed Level: Date: Utility Reviewed 8BDte aminer Level:. Date: Page 6 ot 7

Wall Thickness Unit: I Report No.

GE NUCLEAR ENERGY Profile Sheet Ing91I F11 1 1.5'1 Crown HeigM Ew Crown Width:

12 inheg UPST Component: ONST Component:

.Nominal Diameter:

.86 Weld Length: 40.75 inches FLW____

~-' ~-

Weld: DCA-205-1 FW9 Summary Number: 332200 Unit: 2 Item Number: R1.20 Outage: 2R07 (Spring 2003)

Coverage: 75%

Base Metal and Weld Materials: Stainless Steel Examination Volume: The examination volume is defined in EPRI TR-112657 "Revised Risk-Informed Inservice Inspection Evaluation Procedure" Rev B-A. For a failure mechanism of R1.20 (element is not subject to a damage mechanism) the required volume is N-578-1 "Risk-Informed Requirements for Class 1, 2, or 3 Piping, Method B Section XI, Division 1". Per the code case the examination volume is contained in Figure IWB-2500-8(c) "Similar and Dissimilar Metal Welds in Components and Piping" with an expanded volume of 2 inch beyond each side of the base metal thickness transition or counterbore.

UT Exam Type: Manual examination 450 RL and 60°RL Performed per the requirements of ASME Code,Section XI, Appendix VIII:

Yes, the examination was performed to requirements contained in ASME Section Xl Appendix VIII per the PDI program.

Limitation

Description:

The exam completed was limited to 75% Code required coverage because the downstream axial UT scan was limited due to the weld configuration. The valve material is cast stainless steel whose acoustic properties are not conducive for ultrasonic examination of the full weld.

No unacceptable indications were noted. The following drawings characterize the limitations.

F Site: LImarilc Unit: - Report No.:

GE NUCLEAR ENERGY Wall Thickness Profile Sheet I Project: 332200 system:

Component ID Number: DCA.206-1fW9 - -I fL 1." 25 Crown Height: Elush Crown Width: L.76 FlaIued Havalve UPST Component: DNST Component:

Nominal Diameter: 2RE Weld Length: WE F ui 0~LY& LO u)

VAv R ELI b

s: Examiner: Level: Date, ANII Reviewed By:

Page 6 of 7

GE NUCLEAR ENERGY .I Indication I Coverage Plot Sheet Site:

Project:

Limerick LW2R07 Unit: 2 Report tNuv 33220 System: RHR Component ID Number: DCA-205-1 FW Configuration: Flued Head Valve 45k.

flI~A = , Ay5-JA L C'O4:7z&.:F= 7-f 0 t~o 0 rfe36 7rz I) Charles Litltefield Ii 3/10/03 -'I,--

Level; Date: GE Reviewed B/' Level Date: Utility Reviewed By: Atill Reviewed By:

Da4 Da oe7 Page

Indication /C overage 2 I

Site: LOmerick Unit: Report No.

GE NUCLEAR ENERGY Plot Sheet Project: LQ2R07 332200 System: RHFI Component ID Number: DCA-205-1 FWD Configuration: Fl'ed Head* Vavee CLeVFG

~sŽ~ ~

-A' Examiner: Level; ODki.

f CharLes Littlefield IU 3/10/03 GE Reviewed*y. Level: Date: ( t~itty Rviewed ýBy: ANHI Reviewed By:

Page 8 ut

Weld: DCB-202-1 FW1002 and DCB-202-1 FW1003 Summary Number: 671820 AND 671825 Unit: 2 Item Number: C5.51 Outage: 2R06 (Spring 2001)

Coverage: 50%

Base Metal and Weld Materials: Stainless Steel Examination Volume: IWC-2500-7 'Welds in Piping" UT Exam Type: Manual examination 0°L, 450S and 700S Performed per the requirements of ASME Code, Section Xl, Appendix VIII:

Yes, the examination was performed to requirements contained in ASME Section X1 Appendix VIII per the PDI program.

Limitation

Description:

The exam completed was limited to 50% Code required coverage for both welds because the welds are located so close together that there is no area between the welds that can be examined. No unacceptable indications were noted. A liquid penetrant exam and system pressure test were also completed with no unacceptable indications observed. The following drawings characterize the limitations.

Wall Thickness Site: kierick Unit: 2 Report No,:

GE NUCLEAR ENERGY Profile Sheet Project:

System: RWCU Component ID Number: DC&202-? FW1002 Crown Height: Flush Crown Width: .75 inche pine UPST Component: DNST Component.-

Nominal Diameter: 0 /ncho Weld Length: 20.75 inches 7zPlP6 ___ ___ ___

6A)-4-11 O3czaoý--( j~LO LAJ-61-L loc"S-aca-l Fwlc*.3

___ q S &Richard Jashen idý/ilsiExaminer: Level: Date: GE RevieweBy: Level: Date: Ultity Reviewed By: Date: ANII Reviewed By:

__ jPage 6 of 6

Weld: DCB-202-1 SW1001 Summary Number: 671815 Unit: 2 Item Number: C5.11 Outage: 2R06 (Spring 2001)

Coverage: 50%

Base Metal and Weld Materials: Stainless Steel Examination Volume: IWC-2500-7 'Welds in Piping" UT Exam Type: Manual examination 0°L, 450S and 700S Performed per the requirements of ASME Code, Section Xl, Appendix Vill:

Yes, the examination was performed to requirements contained in ASME Section Xl Appendix VIII per the PDI program.

Limitation

Description:

The exam completed was limited to 50% Code required coverage because the upstream axial UT scan was not performed due to the weld configuration. The valve material is cast stainless steel whose acoustic properties are not conducive for ultrasonic examination of the full weld.

No unacceptable indications were noted. A liquid penetrant exam and system pressure test were also completed with no unacceptable indications observed. The following drawings characterize the limitations. No technology has been approved to obtain additional coverage on cast stainless steel components with this configuration.

Ultrasoni c Examination Indication Report Data Report Number 671815 GE NUCLEAR ENERGY III I II I Cal / Data Sheet Number: D.035 Site. Limerick Procedure: PDI-UT-2, Rev. B..

Weld ID: DCB-202-1 SWlO01 Drawing: XI-DCB-202-1 Size:

• Thickness: 0.432 Exam Start: 1130 Lo Location: 0* Wo Location: Weld Centerline Weld Width: 1.0" Weld Height: Flush Exam End: 1140 Ind Angle 1%ofI Indication Length W Distance Metal Path Ax/ Upst/l No. Used DAC r. Li I-May L2 W1 W Max W2 MP I MP Max MP2. Circ I Dnst ..!Comments:

S _ _1.2_ . . AxDal Dns _i geomet.360_ intermittently at varying amplitudes.

Sketch TI) RoCT G-LIwAC-rR,.y . ....

11 3/30/2001 GE Reviewed By". Level: Date: Utility Reviewed By / Date- 7~

V- John Shea Examiner Level: Date:

Wall Thickness Site: Umerck Unit: Report No.:

GE NUCLEAR ENERGY Profile Sheet Project: 19765 671818 System: RWCU Component ID Number: dcb-202-1 swIOO1 Posilion 0. 90. 180* 270" _1 F3_, 1 M' 1

Crown Height: Emuih 2

Crown Width: 1.0 inch

.44 .44 .44 .45 3

UPST Component: DNST Component:

.42 .42 Nominal Diameter: 6.0 inch

.42 .42 4

.43 .42 .42 .42 Weld Length: Inches 5 FLOW*

90 John Shea # 03/30/011 * - 2 9/N/vj tal Examiner: Level: Date: GE Reviewed Level: Date: Utility Reviewed By: Date:

Weld: DLA-210-1 FW1 Summary Number: 025900 Unit: 2 Item Number: R1.20 Outage: 2R07 (Spring 2003)

Coverage: 71%

Base Metal and Weld Materials: Carbon Steel Examination Volume: The examination volume is defined in EPRI TR-1 12657 "Revised Risk-Informed Inservice Inspection Evaluation Procedure" Rev B-A. For a failure mechanism of R1.20 (element is not subject to a damage mechanism) the required volume is N-578-1 "Risk-Informed Requirements for Class 1, 2, or 3 Piping, Method B Section XI, Division 1". Per the code case the examination volume is contained in Figure IWB-2500-8(c) "Similar and Dissimilar Metal Welds in Components and Piping" with an expanded volume of 1/2 inch beyond each side of the base metal thickness transition or counterbore.

UT Exam Type: Manual examination 45 0 RL, 45 0 S, 60°RL, and 700S Performed per the requirements of ASME Code, Section Xl, Appendix Vill:

Yes, the examination was performed to requirements contained in ASME Section Xl Appendix VIII per the PDI program.

Limitation

Description:

The exam completed was limited to 71% Code required coverage due to the weld configuration.

No unacceptable indications were observed. The following drawings characterize the limitations.

Ultrasonic Examination Indication Report .. J Data Report Number: 25900 GE NUCLEAR ENERGY Cal / Data Sheet Number D-133 / 135 I Site: Lmerick Procedure: GE-PDI-UT-2/ R3 / N/A Weld ID: DLA-210-1 FW1 Drawing: X/- OLA-210-1 Size: i2 Thickness: 0.688" Exam Start: 1300 Lo Location: TDC Wu Location: Weld Centerline Weld Width: 1.75" Weld Height: Flush Exam End: 15_0 Ina nAle 96 of IndiCatiOn L-Ength I W Distance Metal Path A!I I Upstl No. Used DAC Li I L Max L2 W1 W Max W 2 MPI MP Max I MP2 Circ Dnst Comments:

2. 45- 100%! 2' 1-35' A* OST !..urface geometry seen 3.0. at varying amplitudes.

3 80' 45 100%~

1i00%,

0" 0'

t 1.6"

_1 1i.1,62A.1j -

Ax AX, DNST Inside surface geometry seen 360- at varying amplitudes.

UPST ILnside surtace geometry seen 360' at varying amplitudes.

Sketch I' LV--1 1jA.;)

Todd Ginder 11 311 Z/2003 GE Reviewed Date: I ANII Reviewed By: Pag ot7~

Examiner LevuI: Date.

Weld: GBB-220-1 FW2 Summary Number: 484500 Unit: 2 Item Number: C5.11 Outage: 2R06 (Spring 2001)

Coverage: 50%

Base Metal and Weld Materials: Stainless Steel Examination Volume: IWC-2500-7 "Welds in Piping" UT Exam Type: Manual examination 450S and 60°RL Performed per the requirements of ASME Code, Section Xl, Appendix Vill:

Yes, the examination was performed to requirements contained in ASME Section XI Appendix VIII per the PDI program.

Limitation

Description:

The exam completed was limited to 50% Code required coverage because the downstream axial UT scan was not performed due to the weld configuration. The valve material is cast stainless steel whose acoustic properties are not conducive for ultrasonic examination of the full weld. No unacceptable indications were noted. A liquid penetrant exam and system pressure test were also completed with no unacceptable indications observed. The following drawings characterize the limitations. No technology has been approved to obtain additional coverage on cast stainless steel components with this configuration.

Wall Thickness Site: UMLeA Unit: 2 Report No.:

GENUCLEARENERGY Profile Sheet Project: 786 48450

~.1-System: RIHq Component ID Number: GBB-220-1 FW2 Position 0. 90. 180, 270' F-31 1

.770 N/A I/A N/A Crown Height:

2w

.730 N/A N/A N/A 2

Crown Width: 1.20 Incheys

.82 NA W/A NAV ~IR~ Valve 3

UPST Component: DNST Component:

N/A N/A N/A N/A Nominal Diameter: 12anches 4

NAV NV/A NAV W/A Weld Length: 40.0 Inches 5 L ~FLOW*'

--rtL Paul Valden Initials: Examiner: Level: Date GE Reviewed Level: Date:

Weld: GBB-220-2 FW2 Summary Number: 486500 Unit: 2 Item Number: C5.11 Outage: 2R06 (Spring 2001)

Coverage: 50%

Base Metal and Weld Materials: Stainless Steel Examination Volume: IWC-2500-7 "Welds in Piping" UT Exam Type: Manual examination 450S and 60°RL Performed per the requirements of ASME Code, Section Xl, Appendix VIII:

Yes, the examination was performed to requirements contained in ASME Section XI Appendix VIII per the PDI program.

Limitation

Description:

The exam completed was limited to 50% Code required coverage because the downstream axial UT scan was not performed due to the weld configuration. The valve material is cast stainless steel whose acoustic properties are not conducive for ultrasonic examination of the full weld. No unacceptable indications were noted. A liquid penetrant exam and system pressure test were also completed with no unacceptable indications observed. The following drawings characterize the limitations. No technology has been approved to obtain additional coverage on cast stainless steel components with this configuration.

GENUCLEARENERGY S E: NURLAR jY Wall Thickness Profile Sheet I Ste:

Project: 9766 LimeftUnit: Report No.:

Sy ste.. . RHR....

L.AJAnqetfIC um r:hIFI. ,O fr r~r 1.5" R3 PostiLon 0.

.76 90" N/A 180" N/A 270" N/A M-Crown Height: Fush

.76 N/A N/A N/A 2

.82 N/A N/A N/A Crown Width: 1-0iJnches 3

UPST Component: IDST Component:

Nominal Diameter:

WA MA WA W/A 4

NAV W/A W/A W/A Weld Length:

5 FLOWN rL

-nC *ra w 1Ori, Dwras t1Z-4k4 ZVO 7-0

~/ Paul Vaiden Initials: Examiner:

Weld: HBB-218-1 FW7 Summary Number: 495100 Unit: 2 Item Number: C5.11 Outage: 2R06 (Spring 2001)

Coverage: 50%

Base Metal and Weld Materials: Stainless Steel Examination Volume: IWC-2500-7 "Welds in Piping" UT Exam Type: Manual examination 45 0 S and 60°RL Performed per the requirements of ASME Code, Section Xl, Appendix ViUI:

Yes, the examination was performed to requirements contained in ASME Section XI Appendix VIII per the PDI program.

Limitation

Description:

The exam completed was limited to 50% Code required coverage because the upstream axial UT scan was not performed due to the weld configuration. The valve material is cast stainless steel whose acoustic properties are not conducive for ultrasonic examination of the full weld.

No unacceptable indications were noted. A liquid penetrant exam and system pressure test were also completed with no unacceptable indications observed. The following drawings characterize the limitations. No technology has been approved to obtain additional coverage on cast stainless steel components with this configuration.

Wall Thickness

'~J~GE NUCLEAR ENERGY System: R, RR

.Profile Sheet I

-I Site:

Project:

LIMeric 1.-111.5" Unit: 2 Report No.:

=7 Component 10 Number: HB&-218-1 FW7 Position 0. 9so 180" 270" 49l51 Dl __r _

1 Crown Height: Flush

.87 .82 .82 .84 2

Crown Width:. 1inche

.91 .91 .90 .89 3

UPST Component: i. NST Component:

.82 .79 Nominal Diameter: 20 inch"

.82 .80 4

.90 .90 .90 .91 Weld Length: 63 Inches 5 FLOW=.-

q_8 o"

90a 14^

Troy Steinbiauer Y 04/07M0 __________ ___

1i; ais Examiner: Level: Date: GE Reviewed B!' Level: Date: Utility Reviewed By: Date: ANII Reviewe

- - - - - ..----------.----------.----- _ _J. _ _ _ - __ Page 5 of,

Weld: DCA-204-4 FW701 Summary Number: 329915 Unit: 2 Item Number: B9.11 Outage: 2R06 (Spring 2001)

Coverage: 50%

Base Metal and Weld Materials: Stainless Steel Examination Volume: IWB-2500-8 "Similar and Dissimilar Metal Welds in Components and Piping" UT Exam Type: Manual examination 0°L, 45°S and 60°RL Performed per the requirements of ASME Code, Section Xl, Appendix VIII:

Yes, the examination was performed to requirements contained in ASME Section XI Appendix VIII per the PDI program.

Limitation

Description:

The exam completed was limited to 50% Code required coverage because the upstream axial UT scan was not performed due to the weld configuration. The valve material is cast stainless steel whose acoustic properties are not conducive for ultrasonic examination of the full weld.

No unacceptable indications were noted. A liquid penetrant exam and system pressure test were also completed with no unacceptable indications observed. The following drawings characterize the limitations. No technology has been approved to obtain additional coverage on cast stainless steel components with this configuration.

Indication I Coverage Site: Limerick Unit: 2 Report No.:

GE NUCLEAR ENERGY Plot Sheet Project: 0i2RO7 25900 System: Cs Component ID Number: DLA-210-1 FWI Configuration: Valve Flued Head Ai?'cq 'Cf~cF-;c"xtLy 1 .X' , 7Sa / J 7

78' -/ x JOG

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