LR-N08-0266, Submittal of Relief Request Associated with the Second Inservice Inspection (ISI) Interval
| ML083590292 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 12/11/2008 |
| From: | Keenan J Public Service Enterprise Group |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| LR-N08-0266 | |
| Download: ML083590292 (33) | |
Text
PSEG Nuclear LLC P.O. Box 236,, Hancocks Bridge, NJ 08038-0236 0 PSEG NuclearL.L. C.
10 CFR 50.55a LR-N08-0266 December 11, 2008 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Hope Creek Generating Station Facility Operating License No. NPF-57 NRC Docket No. 50-354
Subject:
Submittal of Relief Request Associated with the Second Inservice Inspection (ISI) Interval In accordance with 10 CFR 50 55a, "Codes and standards," paragraph (g)(5)(iii), PSEG Nuclear LLC (PSEG) hereby requests NRC approval of the attached request for the second 10-year inservice inspection (ISI) interval for the Hope Creek Generating Station which ended on December 12, 2007. The request addresses examination limitations for exams performed in accordance the requirements of the American Society of Mechanical Engineering (ASME) Boiler and Pressure Vessel Code, Section Xl for Class 1 and 2 components.
PSEG requests approval of this request by December 12, 2009.
There are no commitments in this letter or attachment.
If you have any questions or require additional information, please contact Mr. Paul Duke at 856-339-1466.
Sincerely, Manager - Licensing PSEG Nuclear LLC
Attachment:
10 CFR 50.55a Request HC-12-RR-A25 A
LR-N08-0266 December 11, 2008 Page 2 cc: S. Collins, Regional Administrator - NRC Region I R. Ennis, Project Manager - USNRC NRC Senior Resident Inspector - Hope Creek P. Mulligan, Manager IV, NJBNE
10 CFR 50.55a Request Number: HC-12-RR-A25 Relief Request In Accordance With 10 CFR 50.55a(g)(5)(iii)
Inservice Inspection Impracticality NOTE:
Hope Creek Second Ten-Year Interval Inservice Inspection (ISI) examinations were conducted between December 13, 1997 (start) and December 12, 2007 (end).
NRC Approved (Yes or No): Date
- 1. ASME Code Component(s) Affected Code Class: 1,2
Reference:
IWB-2200, IWB-2500, IWC-2500, Code Case N-578-1 paragraph -2500 Code Case N-460 Examination Categories: B-A, B-D, B-G-1, B-J, C-G, R-A Item Numbers: See Table 1
Description:
Volumetric and surface examination coverage Component ID: See Table 1
2. Applicable Code Edition and Addenda
The code of record for the start of the Hope Creek Generating Station (HCGS) Second Ten-Year ISI Program interval isSection XI of the ASME Code, 1989 Edition, without Addenda. Beginning with the Third Period of the interval, PSEG elected to perform a mid-interval update to the 1998 Edition through 2000 Addenda. (Reference 2)
Also commencing with the Third Period of the interval, PSEG invoked a Risk-Informed Inservice Inspection (RISI) program based on EPRI Topical Report TR-1 12657, Rev. B-A methodology, which was supplemented by Code Case N-578-1. (Reference 3) The first outage of the Third Period was RF12.
3. Applicable Code Requirement
ASME Section XI, 1989 Edition, and 1998 Edition 2000 Addenda, requires examinations on components and welds as specified in Table IWB-2500-1 and IWC-2500-1. Code 10 CFR 50.55a Request Number: HC-12-RR-A25 Case N-578-1 requires examinations on risk-informed piping as specified in Table 1 of the Code Case.
PSEG invoked ASME Section Xl Code Case N-460, "Alternative Examination Coverage for Class 1 and Class 2 welds,Section XI Division 1." Code Case N-460 states in part,
"... when the entire examination volume or area cannot be examined due to interference by another component or part geometry, a reduction in examination coverage on any Class 1 or Class 2 weld may be accepted provided the reduction in coverage for that weld is less than 10%." ASME Code Case N-460 is approved for use by the NRC in Regulatory Guide (RG) 1.147, Revision 15, "Inservice Inspection Code Case Acceptability, ASME Section Xl, Division 1."
The exam categories for this relief request are B-A, B-D, B-G-1, B-J, C-G, and R-A.
The applicable code requirements for the relevant item numbers are as follows.
A. Exam Category B-A Pressure Retaining Welds in Reactor Vessels Code Requirement: Item B1.12 requires essentially 100% volumetric examination, as defined by Figure IWB-2500-2, of all longitudinal reactor pressure vessel (RPV) shell welds. Item B1.40 requires essentially 100% of the head-to-flange weld as defined by Figure IWB-2500-5.
B. Exam Category B-D Full Penetration Welds of Nozzles in Vessels Code Requirement: Item B3.90 requires essentially 100% volumetric examination, as defined by Figures IWB-2500-7 a through d, of the reactor vessel nozzle-to-vessel welds.
C. Exam Category B-G-1 Pressure Retaining Bolting Greater Than 2 Inches in Diameter Code Requirement: Item B6.40 requires essentially 100% volumetric examination, as defined by Figure IWB-2500-12, of reactor vessel threads in flange.
D. Exam Category B-J Pressure Retaining Piping Welds Code Requirement: Items B9.11 and B9.31 require essentially 100% volumetric and surface examinations, as defined by Figures IWB-2500-8, -9, -10, or -11, as applicable, for piping circumferential and branch connection welds.
E. Exam Category C-G Pressure Retaining Welds in Pumps and Valves Code Requirement: Item C6.10 requires either inside or outside surface examination, as defined by Figure IWC-2500-8 for pump casing welds, including 10 CFR 50.55a Request Number: HC-12-RR-A25 100% welds in all components in each piping run examined under Examination Category C-F.
F. Exam Category R-A Risk Informed Piping Examinations Code Requirement: Item R1 .20 requires essentially 100% volumetric exams as defined by Figure IWB-2500-8(c). Additionally, the exam volume is expanded to include the area 1/2 inch beyond each side of the base material thickness transition or counterbore.
- 4. Basis for Relief:
Pursuant to 10CFR50.55a(g)(5)(iii), relief is requested from ASME Xl examination requirements for the performance of certain piping and vessel welds due to exam limitations. Table 1 herein identifies those inservice inspection nondestructive examinations contained within the Hope Creek ISI Program Long Term Plan for the Second Ten-Year Interval whose NDE exams were found to be inaccessible, physically limited or partially obstructed and therefore not capable of fully meeting code coverage requirements for examination extent. Attachment 1 provides additional descriptive details (sketches, illustrations, and/or drawings) for these components.
Subject components contained herein have received inservice inspection NDE examinations to the "extent practical" within the limitations of design, geometry and materials of construction of the components as allowed by Code. These components have also undergone necessary volumetric examination by radiography and/or surface examinations during fabrication, in accordance with approved construction/fabrication code requirements providing adequate assurance for the structural integrity of the components prior to plant operation. In addition, ASME Class 1 and Class 2 components, identified in Table 1, have been subjected to a visual leakage examination either after a completion of each refueling outage (Class 1 components) or during each inspection period (Class 2 component). This provides additional assurance that the structural integrity of the subject components was maintained.
PSEG has implemented Appendix VIII, "Performance Demonstration for Ultrasonic Examination Systems," of the ASME Code, Section Xl, 1995 Edition with the 1996 Addenda in accordance with the November 22, 1999 revision of 10CFR50.55a.
This provided new nondestructive examination requirements for reactor pressure vessel and Class 1 and 2 piping system welds. This resulted in revised coverage calculation methodologies that further reduced the credited examination coverage of those applicable components.
A. Exam Category B-A Pressure Retaining Welds in Reactor Vessels Table 1 identifies the specific component information, description of the limitation, and a Figure for the configuration.
10 CFR 50.55a Request Number: HC-12-RR-A25 Relief was previously granted in Hope Creek relief request RR-B1, Part A (TAC NO. MA2026) SER dated February 3, 2000 for the reactor vessel longitudinal weld seams examination coverage of at least 78%. This coverage was based on performing the examination from outside the reactor vessel as was the case for the first interval. The examination for the second interval was performed from inside the reactor vessel and less coverage was attained.
Impracticality Of Compliance: Code required coverage is impractical for the identified subject components due to the head flange configuration preventing ultrasonic examination from the flange side of the head flange weld, and proximity of core spray internal piping and feedwater spargers to the reactor vessel longitudinal weld seams limiting access to the weld seams.
Burden Caused By Compliance: The reactor vessel longitudinal weld seams were examined from inside the reactor vessel. Additional coverage could have been obtained if the inspection was performed from outside the reactor vessel but this would cause additional radiation dose to obtain access to the weld and to examine the weld.
To obtain full coverage of the flange, the Reactor Pressure Vessel (RPV) would require design modifications. This would impose a significant burden to PSEG.
Proposed Alternative And Basis For Use: No alternative provisions are practical for the subject welds. Examinations were performed to the maximum extent practical with no reportable indications.
Subject components have been subjected to a visual leakage examination after completion of each refueling outage. The head flange was also fully examined by MT with no reportable indications. These exams provide additional assurance that the structural integrity of the subject components was maintained.
B. Exam Category B-D Full Penetration Welds of Nozzles in Vessels - Inspection Program B Table 1 identifies the specific component information, description of the limitation, and a Figure for the configuration.
Impracticality Of Compliance: Code required coverage is impractical for the subject components due to nozzle configuration and therefore portions of the Code required examination volume can not be completely examined with ultrasonic techniques. The curvature of the blend radius of nozzle forgings prevents ultrasonic scanning of the weld from the nozzle side.
Burden Caused By Compliance: Altering the reactor vessel or nozzle configuration would require design modifications that would impose a significant burden to PSEG.
10 CFR 50.55a Request Number: HC-12-RR-A25 Proposed Alternative And Basis For Use: No alternative provisions are practical for the subject welds. Examinations were performed to the maximum extent practical with no reportable indications.
Subject components have been subjected to a visual leakage examination after completion of each refueling outage. This provides additional assurance that the structural integrity of the subject components was maintained.
C. Exam Category B-G-1 Pressure Retaining Bolting Greater Than 2 Inches in Diameter Table 1 identifies the specific component information, description of the limitation, and a Figure for the configuration.
Impracticality Of Compliance: Code required coverage is impractical for the identified subject component due to head flange configuration. The ultrasonic examination of the threads in the flange is performed on the exposed carbon steel reactor vessel flange around the stud holes. The flange has stainless steel cladding from the inside surface of the vessel to approximately 3/8 inch from the stud hole. The ultrasonic transducer does not have access to this small area of the exposed carbon steel flange between the stud hole and the cladding.
Burden Caused By Compliance: Altering the head flange design or bolting configuration would require design modification that would impose a significant burden on PSEG.
Proposed Alternative And Basis For Use: No alternative provisions are practical for the subject component. Examinations were performed to the maximum extent practical with no reportable indications.
Subject component has been subjected to a visual leakage examination after completion of each refueling outage. This provides additional assurance that the structural integrity of the subject component was maintained.
D. Exam Category B-J Pressure Retaining Piping Welds Table 1 identifies the specific component information, description of the limitation, and a Figure for the configuration.
Impracticality Of Compliance: Code required coverage is impractical for the identified subject components due to reducing tee configuration, branch piping configuration, valve and flange configuration, weld crown contours, weld-o-let configuration, sock-o-let configuration, and a pipe support. These issues limit or prevent full examination of the subject weld.
10 CFR 50.55a Request Number: HC-12-RR-A25 Burden Caused By Compliance: Altering these components would require design modifications that would impose a burden on PSEG from a cost and radiation dose perspective.
Proposed Alternative And Basis For Use: No alternative provisions are practical for the subject welds. Examinations were performed to the maximum extent practical with no reportable indications.
Subject components have been subjected to a visual leakage examination after completion of each refueling outage. Also all components, except for one that was limited by a pipe support, were also fully examined by PT with no reportable indications. This provides additional assurance that the structural integrity of the subject components was maintained.
E. Exam Category C-G Pressure Retaining Welds in Pumps and Valves Table 1 identifies the specific component information, description of the limitation, and a Figure for the configuration.
Relief was previously granted in Hope Creek relief request RR-C1, Part C (TAC NO. MA2026) SER dated February 3, 2000.
Impracticality Of Compliance: A major portion of the Core Spray Pump Casing Weld, CP 206-CSP-W2 is embedded in the concrete pump pedestal. Relief Request RR-C1, Part C, for the second inspection interval requested relief for 73% coverage for this weld. This coverage was based on the first interval data sheets reporting 73% coverage. Subsequent review of the first interval data sheets showed that the exam was 73% limited due to inaccessibility because of the pump pedestal. The second interval examination of this weld achieved 23.4% coverage due to the concrete pump pedestal obstruction.
Burden Caused By Compliance: Altering this component would require a design modification that would impose a burden on PSEG from a cost and radiation dose perspective.
Proposed Alternative And Basis For Use: No alternative provisions are practical for the subject weld. Examinations were performed to the maximum extent practical with no reportable indications.
The subject component has been subjected to a visual leakage examination during each period of the interval. This provides additional assurance that the structural integrity of the subject component was maintained.
10 CFR 50.55a Request Number: HC-12-RR-A25 F. Exam Category R-A Risk Informed Piping Examinations Table 1 identifies the specific component information, description of the limitation, and a Figure for the configuration.
Impracticality Of Compliance: Code required coverage is impractical for the identified subject components due to weld-o-let configuration, pipe to flange configuration, valve taper configuration, and a weld crown condition. These issues limit the examination of the subject weld.
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 PSEG.
Proposed Alternative And Basis For Use: No alternative provisions are practical for the subject welds. Examinations were performed to the maximum extent practical with no reportable indications.
Subject components have been subjected to a visual leakage examination after completion of each refueling outage. This provides additional assurance that the structural integrity of the subject components was maintained.
- 5. Duration of Proposed Alternative The End of Interval Relief is requested for the Second Ten-Year Inspection Interval for Hope Creek Generating Station, which ended on December 12, 2007.
- 6. Precedents:
As part of the submission of the Hope Creek second 10-year interval ISI program plan and associated relief requests, limitations relief requests RR-B1 and RR-C1 were submitted. In the Safety Evaluation of that submission, relief was granted for relief requests RR-B1, parts A, B, C, D, and F, and RR-C1, parts A, B, and C, for the Hope Creek second 10-year interval (Reference 1).
- 7.
References:
- 1) Safety Evaluation Of Relief Requests For Second 10-Year Interval For Inservice Inspection Program - Hope Creek Generating Station (TAC No. MA2026),
February 3, 2000
- 2) Letter, LR-N04-0420, from Christina L. Perino (PSEG Nuclear LLC) to USNRC, Update ASME XI Code of Record, dated October 29, 2004
- 3) Hope Creek Generating Station - Implementation Of a Risk-Informed Inservice Inspection Program (TAC No. MC2221), December 8, 2004 7-
Table 1 Hope Creek Generating Station RR#: HC-12-RR-A25 2nd ISI Interval Exam Limitations Limited Code Required Sum# Component ID Description ASME ASME ASME NDE Coverage Exam Figure Examination Limitation Description Cat Item # Class Exam Achieved Outage Volume 100055 RPV1-W12-1 LONGITUDINAL SEAM AT 110 DEG B-A B1.12 1 UT 71.40% RF14 1 >90% Examined from the inside surface. Examination limited dueto proximity of core spray internal piping & feedwater spargers.
Examined from the inside surface. Examination limited due to
-W12-2 LONGITUDINAL SEAM AT 230 DEG B-A B1.12 1 UT 70.00% RF14 2 RR-B1 proximity of core spray internal piping & feedwater spargers.
Required volume from approved relief request RR-B1 Examined from the inside surface. Examination limited due to 100065 RPV1-W12-3 LONGITUDINAL SEAM AT 350 DEG B-A B1.12 1 UT 71.50% RF14 RR-81 proximity of core spray internal piping &feedwalerspargers.
Required volume from approved relief request RR-B1 RF09 100145 RPVI-W20 ARF09 UT exams limited due to head flange configuration. No UT scan HEAD TO FLANGE B-A 131.40 1 UT 70.23% RF11 4 >90% fo lnesd.Fl oeaewsatie uigM xm RF13 from flange side. Full coverage was ated during MT exam.
100200 RPV1-N2B NOZZLE TO SHELL WELD 12" B-D B3.90 I UT 77.45% RF09 5 >90% UT limited due to nozzle configuration. Examined from the shell side RECIRC INLET AT 60 DEG only due to blend radii limiting nozzle side scan.
100205 RPV1-N2C NOZZLE TO SHELL WELD 12" B-D B3.90 1 UT 77.45% RF09 5 >90% UT limited due to nozzle configuration. Examined from the shell side RECIRC INLET AT 90 DEG only due to blend radii limiting nozzle side scan.
100235 RPV1-N2J NOZZLE TO SHELL WELD 12" B-D 83.90 1 UT 77.45% RF09 5 >90% UT limited due to nozzle configuration. Examined from the shell side RECIRC INLET AT 300 DEG only due to blend radii limiting nozzle side scan.
100240 RPV1-N2K NOZZLE TO SHELL WELD 12" B-D B3.90 1 UT 77.45% RF09 5 >90% UT limited due to nozzle configuration. Examined from the shell side RECIRC INLET AT 330 DEG only due to blend radii limiting nozzle side scan.
100265 RPV1-N4A NOZZLE TO SHELL WELD B-D B3.90 1 UT 75.00% RF12 5 >90% UT limited due to nozzle configuration. Examined from the shell side only due to blend radii limiting nozzle side scan.
100270 RPV1-N4B NOZZLE TO SHELL WELD B-D 83,90 1 UT 75.00% RF12 5 >90% UT limited due to nozzle configuration. Examined from the shell side only due to blend radii limiting nozzle side scan.
100275 RPV1-N4C NOZZLE TO SHELL WELD B-D B3.90 1 UT 71.00% RF12 5 >90% UT limited due to nozzle configuration. Examined from the shell side only due to blend radii limiting nozzle side scan.
100280 RPV1-N4D NOZZLE TO SHELL WELD B-D B3.90 1 UT 75.00% RF12 5 >90% UT limited due to nozzle configuration. Examined from the shell side I_ _ Ionly due to blend radii limiting nozzle side scan.
100285 RPV1-N4E NOZZLE TO SHELL WELD B-D B3.90 1 UT 75.00% RF12 5 >90% UT limited due to nozzle configuration. Examined from the shell side only due to blend radii limiting nozzle side scan.
100290 RPV1-N4F NOZZLE TO SHELL WELD B-D 83.90 1 UT 71.00% RF12 5 >90% UT limited due to nozzle configuration. Examined from the shell side only due to blend radii limiting nozzle side scan.
100295 RPV1-N5A NOZZLE TO SHELL WELD 10"CORE B-D 83.90 1 UT 77.45% RF09 5 >90% UT limited due to nozzle configuration. Examined from the shell side SPRAY INLET AT 120 DEG ___ only due to blend radii limiting nozzle side scan.
100300 RPV1-N5B NOZZLE TO SHELL WELD 10"CORE B-D B3.90 1 UT 77.45% RF09 5 >90% UT limited due to nozzle configuration. Examined from the shell side SPRAY INLET AT 240 DEG only due to blend radii limiting nozzle side scan.
100320 RPV1-N8A NOZZLE TO SHELL JET B-D B3.90 1 UT 75.00% RF12 5 >90% UT limited due to nozzle configuration. Examined from the shell side INSTRUMENTATION only due to blend radii limiting nozzle side scan.
100325 RPVl-N8B NOZZLE TO SHELL 4" JET B-D 83.90 1 UT 75.00% RF12 5 >90% UT limited due to nozzle configuration. Examined from the shell side INSTRUMENTATION only due to blend radii limiting nozzle side scan.
100330 RPV1-N9A NOZZLE TO SHELL WELD 4" CRD 8-D B3.go 1 UT 77.45% RF09 5 >90% UT limited due to nozzle configuration. Examined from the shell side HYDRAULIC RETURN _ _ _ only due to blend radii limiting nozzle side scan.
,100400 RPV1-N17A NOZZLE TO SHELL AT 45 DEG B-D B3.90 1 UT 75.00% RF12 5 >90% UT limited due to nozzle configuration. Examined from the shell side only due to blend radii limiting nozzle side scan.
100401 RPV1-N17B NOZZLE TO SHELL AT 135 DEG B-D B3.90 1 UT 75.00% RF12 5 >90% UT limited due to nozzle configuration. Examined from the shell side only due to blend radii limiting nozzle side scan.
100403 RPV1-N17D NOZZLE TO SHELL AT 315 DEG B-D B3.90 1 UT 75.00% RF12 5 >90% UT limited due to nozzle configuration. Examined from the shell side only due to blend radii limiting nozzle side scan.
100404 RPV1-N6A NOZZLE TO NOZZLE HEAD HEAD SPRAY BD 83.90 1 UT 7500% RF12 5 >90% UT limited due to nozzle configuration. Examined from the shell side only due to blend radii limiting nozzle side scan.
100405 RPV1-N6B NOZZLE TO HEAD SPARE HEAD B-D 83.90 1 UT 75.00% RF12 5 >90% UT limited due to nozzle configuration. Examined from the shell side NOZZLE only due to blend radii limiting nozzle side scan.
Table 1 Hope Creek Generating Station RR#: HC-12-RR-A25 2nd ISI Interval Exam Limitations ASME ASME ASME Limited Code Required Sum# Component ID Description NDE Coverage Figure Examination Cat Item # Class Exam Achieved Outage Volume Limitation Description 100406 RPVI°N7 NOZZLE TO HEAD VENT NOZZLE B-D B3.90 1 UT 75.00% RF12 5 >90% UT limited due to nozzle configuration. Examined from the shell side only due to blend radii limiting nozzle side scan.
100880 RPV1-THDF THREADS IN FLANGE B-G-1 B6.40 1 UT 75.00% RF14 6 >90% UT limited due to flange configuration.
105890 1-BB-28VCA-UT limited due to reducing tee configuration. Single sided access.
1B2VAPIPE TO REDUCING TEE B-J 89.1 1 1 013-6-R2 10LTPT T 50.00% RF10 7 >90% U100% PT covrage cvre 108105 1-BC-6DBA- VALVE TO FLANGE B-J 89.t1 1 UT 33.33% RF10 8 >90% UT limited due to configuration of valve and flange. 100% PT 003-21 coverage:
109170 1-BC-12CCA- PIPE TO REDUCING TEE B-J B9.11 1 UT 80.20% RF09 9 >90% UT limited due to tee configuration and weld contour. 100% PT 116-5 coverage.
110200 1-BG-4CCA- WELDOLET TO PIPE B-J B9.11 1 UT 50.00% RF10 10 >90% UT limited due to weld-o-let configuration. No exam upstream.
012-1 Single sided access. 100% PT coverage.
110230 1-BG-4CCA-011-1 WELDOLET TO PIPE BJ 89.11 1 UT 50.00% RF10 11 >90% UT limited Single sideddue to weld-o-let configuration. No exam upstream.
access. 100% PT coverage.
110432 1-FC-4DBA-003- PIPE TO FLOW ELEMENT B-J 89.11 1 UT 67.90% RF09 12 >90% UT limited due to sock-o-let configuration and weld contour. 100%
7A PT coverage.
110433 1-FC-4DBA-003-7B FLOW ELEMENT TO PIPE B-J B9.11 1 UT 76.20% RF09 12 >90% UT limited due to weld crown configuration. 100% PT coverage.
110475 1 6 MT 51.846% RF10 13 >90% MT exam and UT limited due to pipe support.
1 6F-DA03 LO OPP - gi UT 26.05%
106080 1-BB-22VCA- 12-IN BRANCH CONNECTION B-J B9.31 1 UT 75.00% RF10 14 >90% UT limited due branch piping configuration resulting in single sided 013-3BC1 access. 100% PT coverage.
106125 1-BB-22VCA- 12-IN BRANCH CONNECTION B-J 89.31 1 UT 75.00% RF10 15 >90% UT limited due branch piping configuration resulting in single sided 013-38C2 12_IN access. 100% PT coverage.
106910 1-BB-22VCA- 12-IN BRANCH CONNECTION B-J B9.31 1 UT 75.00% RF10 16 >90% UT limited due branch piping configuration resulting in single sided 014-1BC1 access. 100% PT coverage.
106955 1-BB-22VCA- 12-N BRANCH CONNECTION B-J 89.31 1 UT 75.00% RF1O 17 >90% UT limited due branch piping configuration resulting in single sided 014-11C2 access. 100% PT coverage.
107025 1-BB-22VCA 12-IN BRANCH CONNECTION B-J 8931 1 UT UT limited due branch piping configuration resulting in single sided 014-3BC2 75.00% RFI0 18 >90% access. 100% PT coverage.
250130 CP 206-CSP- CORE SPRAY PUMP - PUMP CASING C-G C6.10 2 PT 23.40% RF09 19 >73.0% PT limited due to a concrete pump pedestal obstruction. Required W2 WELD RR-Cl volume from approved relief request RR-C1 1-BB-4VCA-011- IUTlimited due to weld-o-let configuration. Pre-service exam 105585 1VC1 BRANCH CONNECTION TO PIPE R-A R1.20 1 UT 50.00% 3/30/05 20 >90% followed a repair during a forced outage. Supplemented by construction RT.
1-BB-4VCA-012- IUTlimited due to weld-o-let configuration. Pre-service exam 105790 1-V 1 BRANCH CONNECTION TO PIPE R-A R1.20 1 UT 50.00% 4/3/05 21 >90% followed a repair during a forced outage. Supplemented by 1 I II Iconstruction RT.
109810 1-BG-6DBA- PIPE TO VALVE R-A R1.20 1 UT 58.07% RF12 22 >90% UT limited due to valve taper configuartion and weld crown.
00 1-29 1_______________ 1____ _________________________ 1__________
Request Number HC-12-RR-A25 Figure 1 IHI SOUTHWEST TECHNOLOGIES 4ft RPV EXAMINATION - OCTOBER 2007 HOPE CREEK GENERATING STATION - RFI 4 Examination Location & Coverage Map for Weld No. RPV1-W12-1 Examined Area Feedwater Sparger Area not examined due to access Core Spray Internal Piping Transverse Exams Examined Area
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Request Number HC-12-RR-A25 Figure 2 IM SOUTHWEST TECHNOLOGIES RPV EXAMINATION - OCTOBER 2007 HOPE CREEK GENERATING STATION - RF14 Examination Location & Coverage Map for Weld No. RPV1-W12-2 Examined Area Feedwater Spargi Core Spray Internal Piping
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Request Number HC-12-RR-A25 Figure 3 TU SOUTHWEST TECHNOLOGIES RPV EXAMINATION - OCTOBER 2007 HOPE CREEK GENERATING STATION - RF14 Examination Location & Coverage Map for Weld No. RPVi-W12-3 Examined Area Feedwater Sparger Area not examined due to access Core Spray Internal Piping Transverse Exams Examined Area Feedwater SpargE Area not examined due to access Core Spray -
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Request Number HC-12-RR-A25 Figure 4 Limitation Due to Reactor Vessel Closure Head to Flange Configuration
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Request Number HC-12-RR-A25 Figure 16 Limitation Due to Branch Piping Configuration I -
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Request Number HC-12-RR-A25 Figure 20 Limitation Due to Weld-O-Let Configuration
< PSEG ULTRASONIC EXAMINATION SCAN LIMITATION REPORT
,stomer: PSEG/ HC1 System: BB Recirculation Loop B Summary No.: 105585 Component ID: 1-BB-4VCA-011-1-R1 Applicable Report No: UT-04-317, UT-04-318, UT-04-319 Reference Point: 0' No examination performed upstream due to the configuration of the branch connection.
- 1) Interfering Condition Branch Connection Distance From Centerline 0.0 To US Side Upstream Exam % Downstream Exam %
Distance From Ref. Point .0" CW To 14.50' CW Axial 0% 100%
- 2) Interfering Condition NA Circ CW 0% 100%
Circ CCW 0% 100%
Distance From Centerline NA To NA Distance From Ref. Point NA To NA (Calculations and/or Comments above)
- 3) Interfering Condition NA Total Exam Coverage: 50%
Distance From Centerline NA To NA Distance From Ref. Point NA To NA (For All Measurements Indicate: US, DS, CW, CCW)
Sketch Of Limitation(s):
Weld-o-let Weld 1"'.'
(INCLUDED THE EXTENAI.0% COWLETtED OFEXAM AND REASON FOR UMITED REPORT, AND SKETCH SHOWING AREA OFLIMITATION.)
Examiner: A A Con - el: III Date: 03-30-05 Examiner W J Persiger Level: 11 Date: 03-30-05
.iewer Bob Kellerhall
- l ,, ' .- Date:
Customer; John OIN ',I Date:
Page 5 of 5
Request Number HC-12-RR-A25 Figure 21 Limitation Due to Weld-O-Let Configuration ULTRASONIC EXAMINATION SCAN LIMITATION REPORT
,stomer: PSEG /HC1 System: BB Recirculation Loop A FSummary No.: 105790 Component ID: 1-BB-4VCA-012-1-R1 -A-I-licblWReport NO: UT-04-314, UT-04-315, UT-04-316 --
Reference Point: b0 No examination performed upstream due to the configuration of the branch connection.
- 1) Interfering Condition Branch Connection Distance From Centerline 0.0" To US Side Upstream Exam % Downstream Exam %
Distance From Ref. Point 0.0' Cw To 14.50' CW Axial 0% 100%
- 2) interfering Condition NA Circ CW 0% 100%
NA To NA Circ Cr CCW C 0%
%10 100%
Distance From Centerline Distance From Ref. Point NA To NA (Calculations and/or Comments above)
- 3) Interfering Condition NA Total Exam Coverage: 50%
Distance From Centerline NA To NA Distance From Ref. Point NA To NA (For All Measurements Indicate: US, DS, CW, CCW)
Sketch Of Limitationts):
Request Number HC-12-RR-A25 Figure 22 Limitation due to Valve Taper and Weld Crown PSEG Ahtclear LLC Weld Thickness & Contour (UT-04-248 Page 3 of 3)
'D-109810 ;AI 1-BG-6DBA-001-29 PIPE TO VALVE 0 0 AM Elselerni ESalern2 [DHlope Creek p 9Q 180- E 270" Photograph CD
.CC +,Cr-W *#6 7/.5'3o Ex,*,- V-14Cntour 7f'S."
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Dimensions
- Description Dim ____.__I__Comments _____
TI El Pipe [Ej3bow- Elalve ElTee Upstream .471" T2 Toe of weld upstream ..487 _____________________
T3 Weld Thickness .558 ______________________
- T4 Toe of weld: downstream NIA_ _____________________
T5 ElPipe El Elbow ElVelve El Tee Downstream NIA Limitations (if yes attach photo) 4Yes No _____________________
Is Weld Identification Marked Yes No ____________________
Is Lo Marked EYes ElNo ___________________
Can weld be visually defined El Yes OlNo ______________________
Examined By: persinger, IWalter Date: 11/17104 NDE.5pecialist Review: 77 7,7-07 Date: