ML020730039
| ML020730039 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 03/05/2002 |
| From: | Gallagher M AmerGen Energy Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 5928-01-20355 | |
| Download: ML020730039 (60) | |
Text
AmerGen AmerGen Energy Company, LLC Telephone: 717-944-7621 An Exelon/British Energy Company Three Mile Island Unit 1 Route 441 South, P.O. Box 480 Middletown, PA 17057 March 5, 2002 5928-01-20355 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001
SUBJECT:
THREE MILE ISLAND, UNIT 1 (TMI UNIT 1)
OPERATING LICENSE NO. DPR-50 NRC DOCKET NO. 50-289 TMI Unit 1 Relief Requests RR-02-19 and RR-02-20 Regarding Weld Examinations Applicable to the Second and Third Ten Year Inservice Inspection (ISI) Interval Pursuant to 10 CFR 50.55a(g)(5)(iii), the purpose of this letter is to request relief from certain code requirements regarding weld examinations performed during the second and third ten year Inservice Inspection (ISI) Intervals including examinations performed during the previous TIR14 refueling outage which ended in December 2001. Because of the configuration of certain welds, it was not possible to obtain the required examination coverage.
The third ten year IS interval for TMI Unit 1 began on April 20, 2001. Therefore, during the T1 R14 outage, third interval examinations were being performed in accordance with the ASME Code Section XI, 1995 Edition through 1996 Addenda along with deferred second interval examinations in accordance with the ASME Code Section XI 1986 Edition and augmented examinations of Reactor Vessel shell welds in accordance with the ASME Code Section XI 1989 Edition. Details of these requests are provided in the attached Relief Requests RR-02-19 and RR-02-20. These requests for relief are similar to the relief granted by the NRC for Comanche Peak in a Safety Evaluation dated January 9, 2002 and for Davis Besse in a Safety Evaluation dated June 4, 2001.
Respectfully, Gallagher Director - Licensing and Regulatory Affairs Mid-Atlantic Regional Operating Group - Relief Request No. RR-02-19 - Relief Request No. RR-02-20 cc:
H. J. Miller, USNRC, Regional Administrator, Region I T. G. Colburn, USNRC, Senior Project Manager, TMI Unit 1 J. D. Orr, USNRC, Senior Resident Inspector, TMI Unit 1 File No. 01086 4
ATTACHMENT 1 TMI Unit 1 ASME Code Section Xl Relief Request Associated with Second Ten Year ISI Interval Class I Weld Examinations Relief Request No. RR-02-19
5928-01-20355 Attachment I Page 1 of 53 Three Mile Island Unit I Second Ten Year ISI Interval Request for Relief No. RR-02-19 Examination Coverage of ASME Section XI Code Class I Welds Part A: Examination of the Reactor Vessel Lower Shell to Head Circumferential Weld I. System/Component for which Relief is Requested:
Reactor Vessel Lower Shell to Head Circumferential Weld No. RCT0001 RV001 5 I1. Code Requirement:
ASME Code Section XI, 1989 Edition, Subsection IWB, Examination Category B-A, Item B1. 11 10 CFR 50.55a(g)(6)(ii)(A)(2) requires licensees to implement the examination requirements of the 1989 Edition of ASME Code Section XI for Reactor Vessel shell welds. Subsection IWB, Table IWB-2500-1, Examination Category B-A, Item B13.11 requires essentially 100% of the shell welds to be examined. As defined in 10 CFR 50.55a(g)(6)(ii)(A)(2), essentially 100% means more than 90% of the examination volume of each weld where the reduction in coverage is due to interference by another component, or part geometry.
Ill. Basis for Relief:
The location of the Reactor Vessel welds is shown in Figures Ia and lb.
Figures 2a and 2b provide drawings of the Reactor Vessel Lower Shell to Head Circumferential Weld (Weld Number RCT0001 RV001 5) and a plan view.
It is not possible to obtain ultrasonic interrogation of greater than 90% of this volume due to interference caused by the core support lugs and flow stabilizer remnants. Access to approximately 71% of the examination volume is restricted.
The core support lugs are welded to Reactor Vessel shell just above the lower shell to head weld and extend approximately 2 inches below the centerline of the weld. The flow stabilizer remnants are located just below the lower shell to head weld. These lugs and remnants restrict the URSULA manipulator's ability to move to areas necessary to fully examine the required volume.
Due to the configuration of the Reactor Vessel, and the existing obstructions, it is impractical to meet the examination requirements of the 1989 Edition of ASME Code Section XI. Relief is requested in accordance with 10 CFR 50.55a(g)(5)(iii).
IV. Alternative Examination:
No alternate examinations are proposed in lieu of ultrasonic examination of the inaccessible portion of the subject weld.
5928-01-20355 Page 2 of 53 Three Mile Island Unit 1 Second Ten Year ISI Interval Request for Relief No. RR-02-19 Examination Coverage of ASME Section XI Code Class I Welds V. Justification for Granting Relief:
During preparations for the 1 R14 Outage, the equipment and scan plan were developed to achieve maximum inspection coverage.
The accessible area was examined with techniques that have been demonstrated and qualified in accordance with Supplements 4 and 6 of the 1995 Edition, 1996 Addenda of ASME Code Section XI, Appendix VIII, using the Performance Demonstration Initiative (PDI) protocol. These examinations were performed from both sides of the weld, scanning both parallel and perpendicular to the weld. The aggregate examination coverage of the weld and base metal areas was approximately 29% of the required examination volume; and all indications were within the ASME Code Section Xl acceptance criteria.
The Reactor Vessel welds were examined from the inside surface using the Framatome URSULA inspection manipulator in conjunction with the Framatome ACCUSONEX data acquisition and analysis system. URSULA is a computer controlled, remotely operated manipulator which uses a contact UT head to obtain ultrasonic data for the detection and sizing of indications. The contact head is fitted with an array of transducers in direct contact with the Reactor Vessel surface.
With the ACCUSONEX data acquisition system multiple channels of ultrasonic data are amplified, filtered, digitized and processed, and integrated with the transducer position to provide computer generated images of the examination volume. The URSULA and ACCUSONEX system has been successfully demonstrated and qualified in accordance with Supplements 4 and 6 of the 1995 Edition, 1996 Addenda of ASME Code Section XI, Appendix VIII, using the PDI protocol.
In addition to the required ultrasonic examination, the welds attaching the core support lugs received a VT-1 examination in accordance with Table IWB-2500-1, Examination Category B-N-2, Code Item B13.50, Interior Attachment Welds Within Beltline Region. The VT-1 examination identified the structural condition of the Core Support Lug welds as acceptable, which would indicate the area of the lower shell to bottom head weld had not been subjected to any excessive loads. Also a VT-3 examination of the clad interior surfaces (category 813.10) on and adjacent to this weld was performed; and the results were found to be acceptable in accordance with the ASME Code.
This weld was examined in the first interval during the ten year Reactor Vessel examination. The examination coverage during this second interval examination is approximately the same or greater than that examined during the first interval ten year Reactor Vessel examination. No reportable indications were noted during the first interval examinations.
The Core Support Lugs were also visually examined during the first interval ten year Reactor Vessel examination. No deficiencies were noted during that examination.
5928-01-20355 Page 3 of 53 Three Mile Island Unit 1 Second Ten Year ISI Interval Request for Relief No. RR-02-19 Examination Coverage of ASME Section XI Code Class I Welds VI. Implementation Schedule:
The subject weld examination, applicable to the third period of the second ten year ISI interval, was performed during the T1 R14 outage (October 9, 2001 through December 6, 2001).
5928-01-20355 Page 4 of 53 Three Mile Island Unit 1 Second Ten Year ISI Interval Request for Relief No. RR-02-19 Examination Coverage of ASME Section XI Code Class I Welds Figure Ia RPV Plan & Section Views TAR= ~M =0u i.z =
IRV-00t flI0I FL00 RV-001n W03 RV-003Oz 80
5928-01-20355 Page 5 of 53 Three Mile Island Unit 1 Second Ten Year ISI Interval Request for Relief No. RR-02-19 Examination Coverage of ASME Section XI Code Class I Welds Figure lb RPV Layout View CPS BEAM TARGET #3 S1g5" a 237" II TARGET
- 4 CPS BEAM TARGET 11 TARGET 02 0 33Y
@ 15" 0 57" 0 14T Z-97.00 Z
I~
a,00 Z-W p549 Z-3(
,""I e,3B
5928-01-20355 Page 6 of 53 Three Mile Island Unit I Second Ten Year ISI Interval Request for Relief No. RR-02-19 Examination Coverage of ASME Section XI Code Class I Welds Figure 2a Weld: RCTOOOIRV0015 CORE GUIDE LUG QUAN-12 45°L 70"L THIS VIEW DEPICTS ALPHA (AXIAL)
SCANS FIRING DOWNWARD (DIRECTION 11)
FLOW STABILIZER REMNANT QUAN: 12 PARTIAL SCANS DUE TO GUIDE LUGS AND FLOIW STABILIZER REMNANTS
5928-01-20355 Page 7 of 53 Three Mile Island Unit I Second Ten Year ISI Interval Request for Relief No. RR-02-19 Examination Coverage of ASME Section XI Code Class I Welds Figure 2b Welds: RCT0001 RV001 5/16 Plan View
5928-01-20355 Page 8 of 53 Three Mile Island Unit I Second Ten Year ISI Interval Request for Relief No. RR-02-19 Examination Coverage of ASME Section XI Code Class I Welds Part B: Examination of the Reactor Vessel Head Circumferential Weld I. System/Component for which Relief is Requested:
Reactor Vessel Lower Head Circumferential Weld No. RCT0001 RV0016 I1. Code Requirement:
ASME Code Section XI, 1986 Edition, Subsection IWB, Examination Category B-A, Item 81.21 The ASME Code Section Xl, 1986 Edition, Subsection IWB, Table IWB-2500-1, Examination Category B-A, Item 81.21 requires essentially 100% of the head weld as defined by Figure IWB-2500-3 to be examined. Code Case N-460, Alternative Examination Coverage for Class I and Class 2 Welds, states that 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%.
Ill. Basis for Relief:
The location of the Reactor Vessel welds is shown in Figures la and lb. Figure 3 provides a drawing of the Reactor Vessel Lower Head Circumferential Weld (RCTOOO1RV0016).
It is not possible to obtain ultrasonic interrogation of greater than 90% of this volume due to interference caused by the incore instrument nozzles, the core support lugs, and flow stabilizer remnants. Access to approximately 58% of the examination volume is restricted. The remaining 42% of the examination volume was examined with techniques which have been demonstrated and qualified in accordance with Supplements 4 and 6 of the 1995 Edition, 1996 Addenda of ASME Code Section XI, Appendix VIII, using the Performance Demonstration Initiative (PDI) protocol. These welds were examined from both sides of the weld, scanning both parallel and perpendicular to the weld. These ultrasonic examinations did not reveal any recordable or reportable flaws in accordance with the ASME Code Section XI, 1986 Edition.
This weld was examined in the first interval during the ten year Reactor Vessel examination. The examination coverage during the first interval examination is approximately the same or less than that performed during the second interval ten year Reactor Vessel examination. No indications exceeding the acceptance criteria of ASME Code Section XI were noted during the first interval examination.
Due to the configuration of the Reactor Vessel, it is impractical to meet the examination coverage requirements of the ASME Code Section XI, 1986 Edition as clarified by Code Case N-460. Relief is requested in accordance with 10 CFR 50.55a(g)(5)(iii).
5928-01-20355 Page 9 of 53 Three Mile Island Unit 1 Second Ten Year ISI Interval Request for Relief No. RR-02-19 Examination Coverage of ASME Section XI Code Class I Welds IV. Alternative Examination:
No alternate examinations are proposed in lieu of ultrasonic examination of the inaccessible portion of the subject weld.
V. Justification for Granting Relief:
During preparations for the I R14 Outage, the equipment and scan plan were developed to achieve maximum inspection coverage.
The accessible area was examined with techniques that have been demonstrated and qualified in accordance with Supplements 4 and 6 of ASME Code Section X1, Appendix VIII using PDI protocol. These examinations were performed from both sides of the weld, scanning both parallel and perpendicular to the weld. The aggregate examination coverage of the weld and base metal areas was approximately 42% of the required examination volume.
The Reactor Vessel welds were examined from the inside surface using the Framatome URSULA inspection manipulator in conjunction with the Framatome ACCUSONEX data acquisition and analysis system. URSULA is a computer controlled, remotely operated manipulator which uses a contact UT head to obtain ultrasonic data for the detection and sizing of indications. The contact head is fitted with an array of transducers in direct contact with the Reactor Vessel surface.
With the ACCUSONEX data acquisition system multiple channels of ultrasonic data are amplified, filtered, digitized and processed, and integrated with the transducer position to provide computer generated images of the examination volume. The URSULA and ACCUSONEX system has been successfully demonstrated and qualified in accordance with Supplements 4 and 6 of the 1995 Edition, 1996 Addenda of ASME Code Section XI, Appendix VIII, using the PDI protocol.
VI. Implementation Schedule:
The subject weld examination, applicable to the third period of the second ten year ISI interval, was performed during the T1R14 outage (October 9, 2001 through December 6, 2001).
5928-01-20355 Page 10 of 53 Three Mile Island Unit 1 Second Ten Year ISI Interval Request for Relief No. RR-02-19 Examination Coverage of ASME Section XI Code Class I Welds Figure 3 Weld: RCT0001 RV0016 1.00-NOZZLE BHT/2-AS CLAD CLADDING
5928-01-20355 Page 11 of 53 Three Mile Island Unit 1 Second Ten Year ISI Interval Request for Relief No. RR-02-19 Examination Coverage of ASME Section XI Code Class I Welds Part C: Examination of the Reactor Vessel Shell to Shell Longitudinal Welds I. System/Component for which Relief is Requested:
Reactor Vessel Shell to Shell Longitudinal Weld No. RCT0001 RV0020L and RCT0001 RV0021 L)
II. Code Requirement:
ASME Code Section XI, 1989 Edition, Subsection IWB, Examination Category B-A, Item 81.12.
10 CFR 50.55a(g)(6)(ii)(A)(2) requires licensees to implement the examination requirements of the 1989 Edition of ASME Code Section XI for Reactor Vessel shell welds. Subsection IWB, Table IWB-2500-1, Examination Category B-A, Item B13.12 requires essentially 100% of the shell welds to be examined. As defined in 10 CFR 50.55a(g)(6)(ii)(A)(2), essentially 100% means more than 90% of the examination volume of each weld where the reduction in coverage is due to interference by another component, or part geometry.
Ill. Basis for Relief:
The location of the Reactor Vessel welds is shown in Figures Ia and lb. Figure 4 provides a drawing of the Reactor Vessel shell longitudinal welds.
It is not possible to obtain ultrasonic interrogation of greater than 90% of this volume due to interference caused by the core support lugs. These lugs restrict the URSULA manipulator's ability to move to areas necessary to fully examine the required volume. Access to approximately 21 % of the examination volume of these welds is restricted. The remaining 79% of the examination volume of these welds was examined by techniques which have been demonstrated and qualified in accordance with Supplements 4 and 6 of the 1995 Edition, 1996 Addenda of ASME Code Section XI, Appendix VIII, using the Performance Demonstration Initiative (PDI) protocol. These examinations were performed from both sides of the weld, scanning both parallel and perpendicular to the welds. These ultrasonic examinations did not reveal any recordable or reportable flaws in accordance with the ASME Code Section XI, 1989 Edition.
Due to the configuration of the Reactor Vessel, and the existing obstructions, it is impractical to meet the examination requirements of the 1989 Edition of ASME Code Section XI. Relief is requested in accordance with 10 CFR 50.55a(g)(5)(iii).
IV. Alternative Examination:
No alternate examinations are proposed in lieu of ultrasonic examination of the inaccessible portion of the subject welds.
5928-01-20355 Page 12 of 53 Three Mile Island Unit I Second Ten Year ISI Interval Request for Relief No. RR-02-19 Examination Coverage of ASME Section XI Code Class I Welds V. Justification for Granting Relief:
During preparations for the 1 R14 Outage, the equipment and scan plan were developed to achieve maximum inspection coverage.
The accessible areas were examined with techniques that have been demonstrated and qualified in accordance with Supplements 4 and 6 of the 1995 Edition, 1996 Addenda of ASME Code Section XI, Appendix VIII, using the PDI protocol. These examinations were performed from both sides of the weld, scanning both parallel and perpendicular to the weld. The aggregate examination coverage of the weld and base metal areas was approximately 79% of the required examination volume for each of these welds.
The Reactor Vessel welds were examined from the inside surface using the Framatome URSULA inspection manipulator in conjunction with the Framatome ACCUSONEX data acquisition and analysis system. URSULA is a computer controlled, remotely operated manipulator which uses a contact UT head to obtain ultrasonic data for the detection and sizing of indications. The contact head is fitted with an array of transducers in direct contact with the Reactor Vessel surface.
With the ACCUSONEX data acquisition system multiple channels of ultrasonic data are amplified, filtered, digitized and processed, and integrated with the transducer position to provide computer generated images of the examination volume. The URSULA and ACCUSONEX system has been successfully demonstrated and qualified in accordance with Supplements 4 and 6 of the 1995 Edition, 1996 Addenda of ASME Code Section XI, Appendix VIII, using the PDI protocol.
In addition to the required ultrasonic examination, the welds attaching the core support lugs received a VT-1 examination in accordance with Table IWB-2500-1, Examination Category B-N-2, Code Item BI 3.50, Interior Attachments within Beltline Region. The VT-1 examination identified the structural condition of the Core Support Lug welds as acceptable, which would indicate the areas within the shell to shell longitudinal welds had not been subjected to excessive loads.
These welds were examined in the first interval during the ten year Reactor Vessel examination. The examination coverage during the first interval examination is approximately the same or less than that examined during the second interval ten year Reactor Vessel examination. No reportable indications were noted during the first interval examinations.
The Core Support Lugs were also visually examined during the first interval ten year Reactor Vessel examination. No deficiencies were noted during this examination.
5928-01-20355 Page 13 of 53 Three Mile Island Unit 1 Second Ten Year ISI Interval Request for Relief No. RR-02-19 Examination Coverage of ASME Section XI Code Class I Welds VI. Implementation Schedule:
The subject weld examinations, applicable to the third period of the second ten year ISI interval, were performed during the T1R14 outage (October 9, 2001 through December 6, 2001).
5928-01-20355 Page 14 of 53 Three Mile Island Unit 1 Second Ten Year ISI Interval Request for Relief No. RR-02-19 Examination Coverage of ASME Section XI Code Class I Welds Figure 4 Welds: RCT0001 RV0020L & RCT0001 RV0021 L
5928-01-20355 Page 15 of 53 Three Mile Island Unit 1 Second Ten Year ISI Interval Request for Relief No. RR-02-19 Examination Coverage of ASME Section XI Code Class I Welds Part D: Examination of the Inlet Nozzle to Reactor Vessel Shell Welds
- 1. System/Component for which Relief is Requested:
Inlet Nozzle to Reactor Vessel Shell Welds No. RCT0001 RV0001 N, RCTOOOI RV0003N, RCT0001 RV0004N, and RCT0001 RV0006N II. Code Requirement:
ASME Code Section XI, 1986 Edition, Subsection IWB, Examination Category B-D, Item B3.90 The ASME Code Section XI, 1986 Edition, Subsection IWB 2500-1, Examination Category B-D, Item B3.90 for Reactor Vessel nozzle to vessel welds requires essentially 100% of the weld length as defined by Figure IWB 2500-7(b) be examined. Code Case N-460, Alternative Examination Coverage for Class 1 and Class 2 Welds, states that 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%.
Ill. Basis for Relief:
The location of the Reactor Vessel welds is shown in Figures la and lb. Figures 5a and 5b provide drawings representative of the Inlet Nozzle to Reactor Vessel Shell Welds (Weld Numbers RCT0001 RV0001 N, RCT0001 RV0003N, RCT0001 RV0004N, and RCT0001 RV0006N).
It is not possible to obtain ultrasonic interrogation of greater than 90% of this volume, due to the configuration of the Inlet nozzle boss. The contour of the nozzle radius (See Figures 5a and 5b) restricts the URSULA manipulator's ability to scan the weld and adjacent base material from the vessel shell. Access to approximately 20% of the examination volume from the vessel shell is restricted.
Due to the configuration of the nozzle, it is impractical to meet the examination requirements of the ASME Code Section XI 1986 Edition. Relief is requested in accordance with 10 CFR 50.55a(g)(5)(iii).
IV. Alternative Examination:
No alternate examinations are proposed in lieu of the ultrasonic examination of the inaccessible portion of the subject welds.
5928-01-20355 Page 16 of 53 Three Mile Island Unit 1 Second Ten Year ISI Interval Request for Relief No. RR-02-19 Examination Coverage of ASME Section XI Code Class I Welds V. Justification for Granting Relief:
During preparations for the 1 R14 Outage, the equipment and scan plan were developed to achieve maximum inspection coverage.
The aggregate examination coverage of the weld and base metal areas was approximately 80% of the required examination volume for each of these welds.
As there is no limitation for the examination from the nozzle bore, 100% of the weld is examined by at least two angles.
The Reactor Vessel welds were examined from the inside surface using the Framatome URSULA inspection manipulator in conjunction with the Framatome ACCUSONEX data acquisition and analysis system. The inlet nozzle to shell welds were examined from the shell side to the extent possible. These examinations were performed from both sides of the weld, scanning both parallel and perpendicular to the weld. The aggregate examination coverage of the weld and base metal areas was approximately 80% of the required examination volume.
The requirements of the ASME Code Section XI 1986 Edition as clarified by Code Case N-460 was met for the examinations from the nozzle bore.
URSULA is a computer controlled, remotely operated manipulator which uses a contact UT head to obtain ultrasonic data for the detection and sizing of indications. The contact head is fitted with an array of transducers in direct contact with the Reactor Vessel surface. With the ACCUSONEX data acquisition system multiple channels of ultrasonic data are amplified, filtered, digitized and processed, and integrated with the transducer position to provide computer generated images of the examination volume.
These welds were examined in the first interval during the ten year Reactor Vessel examination. The examination coverage during the second ten year interval examination is approximately the same or greater than that performed during the first interval ten year Reactor Vessel examination. No indications exceeding the acceptance criteda of ASME Code Section Xl were noted during this examination.
VI. Implementation Schedule:
The subject weld examinations, applicable to the third period of the second ten year ISI interval, were performed during the T1R14 outage (October 9, 2001 through December 6, 2001).
5928-01-20355 Page 17 of 53 Three Mile Island Unit 1 Second Ten Year ISI Interval Request for Relief No. RR-02-19 Examination Coverage of ASME Section XI Code Class I Welds Figure 5a Welds: RCT0001RV0001N, 3N, 4N, & 6N HORIZONTAL SECTION VIEW VERTICAL SECTION VIEW NOZZLE COVERAGE NOZZLE WELD 15' = 16.14 SQ IN.
45" = 18.09 SQ IN.
ADJACENT BASE METAL 15"/45' = 199.66 SQ IN.
WELD 15" = 21.17 SQ IN.
45" = 21.17 SQ IN.
ADJACENT BASE METAL 15"/45* = 219.46 SQ IN.
INLET AXIAL FROM BORE
5928-01-20355 Page 18 of 53 Three Mile Island Unit I Second Ten Year ISI Interval Request for Relief No. RR-02-19 Examination Coverage of ASME Section XI Code Class I Welds Figure 5b Welds: RCTOOOIRV0001N, 3N, 4N, & 6N HORIZONTAL SECTION VIEW/
VERTICAL SECTION VIEW INLET NOZZLE WELD & ADJACENT BASE METAL (BALANCE OF VOLUME)
FROM VESSEL I.D.
WELD Shell/7 45" =
2.36 SQ IN.
60' = 18.09 SQ IN.
0' = 18.09 SQ IN.
Shell/8 45' = 18.09 SQ IN.
60" =
2.36 SQ IN.
0' = 18.09 SQ IN.
ADJACENT BASE METAL ShelI7/8 45-/60"/0'
-- 104.53 SQ IN.
WELD SheII/7 45" = 21.17 SQ IN.
60° = 21.17 SQ IN.
0' = 21.17 SQ IN.
Shell/8 45" = 21.17 SQ IN.
60" = 21.17 SQ IN.
0" = 21.17 SQ IN.
ADJACENT BASE METAL SheI17/8 45"/60"/0' = 174.8'9 SQ IN.
5928-01-20355 Page 19 of 53 Three Mile Island Unit 1 Second Ten Year ISI Interval Request for Relief No. RR-02-19 Examination Coverage of ASME Section XI Code Class I Welds Part E: Examination of the Core Flood Nozzle to Shell Welds I. System/Component for which Relief is Requested:
Core Flood Nozzle to Shell Welds No. RCT0001 RV0007N, and RCT0001 RV0008N I1. Code Requirement:
ASME Code Section XI, 1986 Edition, Subsection IWB, Examination Category B-D, Item B3.90.
The ASME Code Section XI, 1986 Edition, Subsection IWB 2500-1, Examination Category B-D, Item B3.90 for core flood nozzle to shell welds requires essentially 100% of the weld length as defined by Figure IWB 2500-7(b) be examined. Code Case N-460, Alternative Examination Coverage for Class 1 and Class 2 Welds, states that a reduction in examination coverage on any Class I or Class 2 weld may be accepted provided the reduction in coverage for that weld is less than 10%.
I1l. Basis for Relief:
The location of the Reactor Vessel welds is shown in Figures Ia and lb. Figures 6a, 6b, 6c, and 6d provide drawings representative of the Core Flood Nozzle to Shell Welds (Weld Numbers RCT0001RV0007N, and RCT0001 RV0008N).
It is not possible to obtain ultrasonic interrogation of greater than 90% of the weld volume. This is due to scan limitations caused by the flow restrictor located in the bore of the core flood nozzles, and the radius blend between the Reactor Vessel shell and the bore of the core flood nozzle. The flow restrictor is welded to the bore of the core flood nozzle and therefore is not removable. This restriction prohibits any examination of the weld from the bore of the nozzle. Access to approximately 18% of the examination volume from the vessel shell is restricted.
Due to the configuration of the nozzle, it is impractical to meet the examination requirements of the 1986 Edition of ASME Code Section XI. Relief is requested in accordance with 10 CFR 50.55a(g)(5)(iii).
IV. Alternative Examination:
No alternate examinations are proposed in lieu of ultrasonic examination of the inaccessible portion of the subject welds.
5928-01-20355 Page 20 of 53 Three Mile Island Unit 1 Second Ten Year ISI Interval Request for Relief No. RR-02-19 Examination Coverage of ASME Section XI Code Class I Welds V. Justification for Granting Relief:
During preparations for the 1 R14 Outage, the equipment and scan plan were developed to achieve maximum inspection coverage.
The core flood nozzle to shell welds were examined from the shell side to the extent possible. These examinations were performed from both sides of the weld, scanning both parallel and perpendicular to the weld. The aggregate examination coverage of the weld and base metal areas was approximately 82% of the required examination volume. The accessible 82% of the examination volume were examined from the shell side in accordance with the ASME Code Section XI, 1986 Edition.
The Reactor Vessel welds were examined from the inside surface using the Framatome URSULA inspection manipulator in conjunction with the Framatome ACCUSONEX data acquisition and analysis system. URSULA is a computer controlled, remotely operated manipulator which uses a contact UT head to obtain ultrasonic data for the detection and sizing of indications. The contact head is fitted with an array of transducers in direct contact with the Reactor Vessel surface.
With the ACCUSONEX data acquisition system multiple channels of ultrasonic data are amplified, filtered, digitized and processed, and integrated with the transducer position to provide computer generated images of the examination volume.
These welds were examined in the first interval during the ten year Reactor Vessel examination. The examination coverage during the first ten year interval examination is approximately the same or less than that performed during the second interval ten year Reactor Vessel examination. No indications exceeding the acceptance criteria of ASME Code Section XI were noted during this examination.
VI. Implementation Schedule:
The subject weld examinations, applicable to the third period of the second ten year ISI interval, were performed during the T1R14 outage (October 9, 2001 through December 6, 2001).
5928-01-20355 Page 21 of 53 Three Mile Island Unit I Second Ten Year ISI Interval Request for Relief No. RR-02-19 Examination Coverage of ASME Section XI Code Class I Welds Figure 6a Welds: RCT0001 RV0007NiNI & RCT0001 RV0008N/NI START OF CORE SUPPORT LEDGE TAPER 0 Z = 27" BEAM DIRECTION 1 = NWN SCANS
5928-01-20355 Page 22 of 53 Three Mile Island Unit I Second Ten Year ISI Interval Request for Relief No. RR-02-19 Examination Coverage of ASME Section XI Code Class I Welds Figure 6b Welds: RCT0001 RV0007N/NI & RCT0001 RV0008N/NI 45"/6oY WELD: 19.20 SQ IN.
ADJACENT BASE METAL: 158.00 SQ IN.
INNER 15% BMT. 23.67 SQ IN.
INNER RADIUS: 6.25 SO IN.
BEAM DIRECTION 1-ZONE 3 60° OF 90' (66.6% OF SCAN)
5928-01-20355 Page 23 of 53 Three Mile Island Unit 1 Second Ten Year ISI Interval Request for Relief No. RR-02-19 Examination Coverage of ASME Section XI Code Class I Welds Figure 6c Welds: RCT0001 RV0007N/NI & RCT0001 RV0008NINI
- 45.
WELD: 4.59 SQ IN.
60*
WELD: 4.66 SQ IN.
BEAM DIRECTION 2-ZONE 4
5928-01-20355 Page 24 of 53 Three Mile Island Unit 1 Second Ten Year ISI Interval Request for Relief No. RR-02-19 Examination Coverage of ASME Section XI Code Class I Welds Figure 6d Welds: RCT0001 RV0007N/NI & RCT0001 RV0008N/NI 45"/60'/70o WELD: 19.20 SQ IN.
ADJACENT BASE METAL:
SHELL/3: 142.41 SQ IN.
SHELL/4:
97.90 SQ IN.
INNER15% BMT: 22.41 SQ IN.
INNER RADIUS: 0.26 SQ IN.
BEAM DIRECTION 3 & 4-ZONE 5 W=8.75 ALL SCANS I P-ff 7
5928-01-20355 Attachment I Page 25 of 53 Three Mile Island Unit 1 Second Ten Year ISI Interval Request for Relief No. RR-02-19 Examination Coverage of ASME Section XI Code Class I Welds Part F: Examination of the Core Flood Nozzle Inner Radius Sections I. System/Component for which Relief is Requested:
Core Flood Nozzle Inner Radius Sections No. RCT0001RV0007NI and RCT0001 RV0008NI II. Code Requirement:
ASME Code Section XI, 1986 Edition, Subsection IWB, Examination Category B-D, Item B3.100.
The ASME Code Section Xl, 1986 Edition, Subsection IWB 2500-1, Examination Category B-D, Item B3.100 for core flood nozzle inside radius sections requires essentially 100% of the weld length as defined by Figure IWB 2500-7(b) be examined. Code Case N-460, Alternative Examination Coverage for Class 1 and Class 2 Welds, states that a reduction in examination coverage on any Class I or Class 2 weld may be accepted provided the reduction in coverage for that weld is less than 10%.
Ill. Basis for Relief:
The location of the Reactor Vessel welds is shown in Figures la and lb. Figures 6a and 6b provide drawing of the core flood nozzle inner radius sections (RCT0001 RV0007NI, and RCT0001RV0008NI).
It is not possible to obtain ultrasonic interrogation of greater than 90% of the inner radius section volume due to scan limitations caused by the flow restrictor located in the bore of the core flood nozzle. The flow restrictor is welded to the bore of the core flood nozzle and therefore is not removable. This restriction prohibits any examination of the inner radius from the bore of the nozzle. Access to approximately 48% of the examination volume from the vessel shell is restricted for each of these welds.
Due to the configuration of the nozzle, it is impractical to meet the examination requirements of the 1986 Edition of ASME Code Section Xl. Relief is requested in accordance with 10CFR 50.55a(g)(5)(iii).
IV. Alternative Examination:
No alternate examinations are proposed in lieu of ultrasonic examination of the inaccessible portion of the subject welds.
5928-01-20355 Page 26 of 53 Three Mile Island Unit 1 Second Ten Year ISI Interval Request for Relief No. RR-02-19 Examination Coverage of ASME Section XI Code Class I Welds V. Justification for Granting Relief:
During preparations for the 1 R14 Outage, the equipment and scan plan were developed to achieve maximum inspection coverage.
The core flood nozzle inner radius sections were examined from the shell side to the extent possible. These examinations were performed from both sides of the weld, scanning both parallel and perpendicular to the weld. The aggregate examination coverage of the weld and base metal areas was approximately 52% of the required examination volume of each weld.
The remaining 52% of the examination volume was examined from the shell side in accordance with the ASME Code Section XI, 1986 Edition. No indications exceeding the acceptance criteria of ASME Code Section XI were noted during this examination.
The Reactor Vessel welds were examined from the inside surface using the Framatome URSULA inspection manipulator in conjunction with the Framatome ACCUSONEX data acquisition and analysis system. URSULA is a computer controlled, remotely operated manipulator which uses a contact UT head to obtain ultrasonic data for the detection and sizing of indications. The contact head is fitted with an array of transducers in direct contact with the Reactor Vessel surface.
With the ACCUSONEX data acquisition system multiple channels of ultrasonic data are amplified, filtered, digitized and processed, and integrated with the transducer position to provide computer generated images of the examination volume.
These welds were examined in the first interval during the ten year Reactor Vessel examination. The examination coverage during the first ten year interval examination is approximately the same or less than that performed during the second interval ten year Reactor Vessel examination. No indications exceeding the acceptance criteria of ASME Code Section XI were noted during this examination.
VI. Implementation Schedule:
The subject weld examinations, applicable to the third period of the second ten year ISI interval, were performed during the T1 R14 outage (October 9, 2001 through December 6, 2001).
5928-01-20355 Page 27 of 53 Three Mile Island Unit I Second Ten Year ISI Interval Request for Relief No. RR-02-19 Examination Coverage of ASME Section XI Code Class I Welds Part G: Examination of the Core Flood Pipe to Safe End Welds I. System/Component for which Relief is Requested:
Core Flood Pipe to Safe End Welds No. CF0001 and CF0020 I1. Code Requirement:
ASME Code Section XI, 1986 Edition, Subsection IWB, Examination Category B-J, Item B9.11.
The ASME Code Section XI, 1986 Edition, Subsection IWB, Table IWB-2500-1, Examination Category B-J, Item B9.11 for core flood pipe to safe end to weld, requires essentially 100% of the weld length as defined by Figure IWB-2500-8 be examined. Code Case N-460, Alternative Examination Coverage for Class 1 and Class 2 Welds states that 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%.
Ill. Basis for Relief:
The location of the Reactor Vessel welds is shown in Figures la and lb. Figure 7 provides a drawing of the core flood pipe to safe end welds (CF0001, and CF0020).
It is not possible to obtain ultrasonic interrogation of greater than 90% of this volume, due to configuration of the safe end and existing weld melt through in the root of the weld. The contour of the safe end (See Figure 8) restricts intimate contact (lift-off) with the surface of the transducers face 100% of the time. Access to approximately 11% (Weld Number CF0001) and 29% (Weld Number CF0020) of the examination volume from the safe end is restricted.
Due to the configuration of the safe end and the existing weld melt through, it is impractical to meet the examination requirements of the 1986 Edition of ASME Code Section XI. Relief is requested in accordance with 10 CFR 50.55a(g)(5)(iii).
IV. Alternative Examination:
No alternate examinations are proposed in lieu of ultrasonic examination of the inaccessible portion of the subject welds.
5928-01-20355 Page 28 of 53 Three Mile Island Unit I Second Ten Year ISI Interval Request for Relief No. RR-02-19 Examination Coverage of ASME Section XI Code Class I Welds V. Justification for Granting Relief:
During preparations for the 1R14 Outage, the equipment and scan plan were developed to achieve maximum inspection coverage.
The core flood pipe to safe end welds were examined from both sides of the weld, scanning both parallel and perpendicular to the weld. Due to the configuration of the safe end and existing weld metal convexity in the root of the weld, the inspection from the safe end side was restricted. The aggregate examination coverage of the welds and base metal areas was approximately 89% (Weld Number CF0001) and 71% (Weld Number CF0020), of the required examination volume.
The remaining 89% (Weld Number CF0001) and 71% (Weld Number CF0020),
were examined from the safe end side and pipe sides in accordance with the ASME Code Section XI, 1986 Edition. No indications exceeding the acceptance criteria of ASME Code Section XI were noted during this examination.
The Reactor Vessel welds were examined from the inside surface using the Framatome URSULA inspection manipulator in conjunction with the Framatome ACCUSONEX data acquisition and analysis system. URSULA is a computer controlled, remotely operated manipulator which uses a contact UT head to obtain ultrasonic data for the detection and sizing of indications. The contact head is fitted with an array of transducers in direct contact with the Reactor Vessel surface.
With the ACCUSONEX data acquisition system multiple channels of ultrasonic data are amplified, filtered, digitized and processed, and integrated with the transducer position to provide computer generated images of the examination volume.
VI. Implementation Schedule:
The subject weld examinations, applicable to the third period of the second ten year ISI interval, were performed during the T1 R14 outage (October 9, 2001 through December 6, 2001).
5928-01-20355 Page 29 of 53 Three Mile Island Unit 1 Second Ten Year ISI Interval Request for Relief No. RR-02-19 Examination Coverage of ASME Section XI Code Class I Welds Figure 7 Welds: CFOOO1 & CF0020 ORwn
- a.
Iiýuh L,
U 0
0
0 o
IL z
00 wi
NOZZLE-TO-SAFE END CIRC SCANS
-1.0 CARRIAGE ARM INTERVAL 0.64 0.21 REFERENCE 0.00 99.86 ENCODER CPU 746.67 20000.00 START POSITION
-190.0 103.31 STOP POSTON 120 107.17 STEPPER SPU 12..50 12.50 I SPEED 20.00 0.80 INDEX DIR: ARM CONFIGURATION 2 NOZZLE-Tq-SAF AXIAL SCANS
- t.
1 FE END CARRIAGE ARM INTERVAL 1.90 O.OB REFERENCE 99.6 ENCODER CPU 746.67 20000.00 START POSITION
-190 103.86 STOP POSITION 190 115.14 STEPPER SPU 12.50 12.50 SPEED 20.00 0.80 o(D 05, U'.-.-
L" Co 0h 0c CA) th cn "1"
co UD 0
C) 90 0u 0
0 0
C?
0 m
x 0
0 0
- u r C 0
(D mC - m Cz' x~J o
0 0
iD m
CD
==.
- 5.
- 5.
m.
INDEX DIR: CARRIAGE CONFIGURATION I
5928-01-20355 Page 31 of 53 Three Mile Island Unit 1 Second Ten Year ISI Interval Request for Relief No. RR-02-19 Examination Coverage of ASME Section XI Code Class I Welds Part H: Examination of the Core Flood Nozzle to Safe End Welds I. System/Component for which Relief is Requested:
Core Flood Nozzle to Safe End Welds No. RCT0001 RV0009BM and RCTOOOI RV001 0BM I1. Code Requirement:
ASME Code Section XI, 1986 Edition, Subsection IWB, Examination Category B-F, Item B5.10.
The ASME Code Section XI, 1986 Edition, Subsection IWB, Table IWB-2500-1, Examination Category B-F, Item B5.10 for core flood nozzle to safe end welds requires essentially 100% of the weld length as defined by Figure IWB-2500-8 be examined. Code Case N-460, Alternative Examination Coverage for Class 1 and Class 2 Welds, states that 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%.
Ill. Basis for Relief:
The location of these Reactor Vessel welds is shown in Figures la and lb. Figure 8 provides a drawing depicting the configuration of the core flood nozzle to safe end welds (RCT0001 RV0009BM, and RCT0001 RVOO1 OBM).
It is not possible to obtain ultrasonic interrogation of greater than 90% of this volume, due to configuration of the safe end. The contour of the safe end (See Figure 8) restricts intimate contact (lift-off) with the surface of the transducer face.
Access to approximately 20% (Weld Number RCT0001RV0009BM) and 16%
(Weld Number RCT0001 RV001OBM) of the examination volume from the safe end is restricted.
Due to the configuration of the safe end, it is impractical to meet the examination requirements of the 1986 Edition of ASME Code Section XI. Relief is requested in accordance with 10 CFR 50.55a(g)(5)(iii).
IV. Alternative Examination:
No alternate examinations are proposed in lieu of ultrasonic examination of the inaccessible portion of the subject welds.
5928-01-20355 Page 32 of 53 Three Mile Island Unit 1 Second Ten Year ISI Interval Request for Relief No. RR-02-19 Examination Coverage of ASME Section XI Code Class I Welds V. Justification for Granting Relief:
During preparations for the 1R14 Outage, the equipment and scan plan were developed to achieve maximum inspection coverage.
The core flood nozzle to safe end welds were examined from both sides of the weld, scanning both parallel and perpendicular to the weld. Due to the configuration of the safe end, the inspection from the safe end side was restricted.
The aggregate examination coverage of the welds and base metal areas was approximately 80% (Weld Number RCT0001RV0009BM) and 84% (Weld Number RCT0001 RV001 OBM) of the required examination volume.
The accessible 80% (Weld Number RCT0001 RVO009BM) and 84% (Weld Number RCT0001RV0010BM) were examined from the safe end and nozzle sides in accordance with the ASME Code Section X1, 1986 Edition. No indications exceeding the acceptance criteria of ASME Code Section XI were noted during this examination.
The Reactor Vessel welds were examined from the inside surface using the Framatome URSULA inspection manipulator in conjunction with the Framatome ACCUSONEX data acquisition and analysis system. URSULA is a computer controlled, remotely operated manipulator which uses a contact UT head to obtain ultrasonic data for the detection and sizing of indications. The contact head is fitted with an array of transducers in direct contact with the Reactor Vessel surface.
With the ACCUSONEX data acquisition system multiple channels of ultrasonic data are amplified, filtered, digitized and processed, and integrated with the transducer position to provide computer generated images of the examination volume.
VI. Implementation Schedule:
The subject weld examinations, applicable to the third period of the second ten year ISI interval, were performed during the T1 R14 outage (October 9, 2001 through December 6, 2001).
5928-01-20355 Attachment I Page 33 of 53 Three Mile Island Unit 1 Second Ten Year ISI Interval Request for Relief No. RR-02-19 Examination Coverage of ASME Section XI Code Class I Welds Part I: Examination of the Reactor Vessel Head to Flange Weld I. System/Component for which Relief is Requested:
Reactor Vessel Head to Flange Weld No. RCTOOO/RHOO01 II. Code Requirement:
ASME Code Section XI, 1986 Edition, Subsection IWB, Examination Category B-A, Item B1.40.
The ASME Code Section XI, 1986 Edition, Subsection IWB, Table IWB-2500-1, Examination Category B-A, item B1.40 requires essentially 100% of the Reactor Vessel head-to-flange weld length as defined by Figure IWB-2500-5 be examined.
Code Case N-460, Alternative Examination Coverage for Class I and Class 2 Welds, states that 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%.
Ill. Basis for Relief:
Figure 9 provides a drawing of the Reactor Vessel Head to Flange Weld (Weld Number RCTOOO/RHOO01).
It is not possible to obtain ultrasonic interrogation of greater than 90% of this volume due to flange configuration, and interference from three lifting lugs. The lifting lugs are welded to the Reactor Vessel head just above the head-to-flange weld, and restrict the ultrasonic transducer's ability to move to areas necessary to fully examine the required volume. The configuration of the head-to-flange interface only permits the weld to be scanned from the head side. Access to approximately 15% of the examination volume is restricted. The remaining 85% of the examination volume was examined by techniques which have been demonstrated and qualified in accordance with the 1986 Edition of ASME Code Section XI.
Due to the configuration of the head-to-flange interface and the three lifting lugs, it is impractical to meet the examination requirements of the ASME Code Section XI, 1986 Edition. Relief is requested in accordance with 10 CFR 50.55a(g)(5)(iii).
IV. Alternative Examination:
No alternate examinations are proposed in lieu of ultrasonic examination of the inaccessible portion of the subject weld.
5928-01-20355 Page 34 of 53 Three Mile Island Unit 1 Second Ten Year ISI Interval Request for Relief No. RR-02-19 Examination Coverage of ASME Section XI Code Class I Welds V. Justification for Granting Relief:
During preparations for the 1 R14 Outage, the equipment and scan plan were developed to achieve maximum inspection coverage.
The accessible areas were examined with techniques that have been demonstrated and qualified in accordance with the ASME Code Section XI, 1986 Edition. The aggregate examination coverage of the weld and base metal areas was approximately 85% of the required examination volume and was found to be acceptable in accordance with the ASME Code.
In addition to the required ultrasonic examination, the weld was examined by the magnetic dry particle test method (MT) and found to be acceptable.
VI. Implementation Schedule:
The subject weld examination applies to the second ten year ISI interval. Portions of the examination were performed during the Outages 1OR (September 1993 October 1993), 12R (September 1997-October 1997), and 13R (September 1999
- October 1999).
5928-01-20355 Page 35 of 53 Three Mile Island Unit 1 Second Ten Year ISI Interval Request for Relief No. RR-02-19 Examination Coverage of ASME Section XI Code Class I Welds Figure 9 Weld: RCTOOO1RHOOO1 a A JI
5928-01-20355 Page 36 of 53 Three Mile Island Unit 1 Second Ten Year ISI Interval Request for Relief No. RR-02-19 Examination Coverage of ASME Section XI Code Class I Welds Part J: Examination of the Steam Generator Tubesheet to Head Weld I. System/Component for which Relief is Requested:
Steam Generator Tubesheet to Head Weld No. RCH0001 BSGOO1 2 I1. Code Requirement:
ASME Code Section XI, 1986 Edition, Subsection IWB, Examination Category B-B, Item B2.40.
The ASME Code Section XI, 1986 Edition, Subsection IWB, Table IWB-2500-1, Examination Category B-B, item B2.40 requires essentially 100% of the steam generator tubesheet-to-head weld length as defined by Figure IWB-2500-6 be examined. Code Case N-460, Alternative Examination Coverage for Class 1 and Class 2 Welds, states that 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%.
Ill. Basis for Relief:
Figure 10 provides a drawing that shows the Steam Generator Tubesheet to Head Weld (Weld Number RCHOOO1BSGO012).
It is not possible to obtain ultrasonic interrogation of greater than 90% of this volume, due to the steep entry angle from the tubesheet side into the weld, which causes transducer lift off. This lift off restricts the transducer's ability to move to areas necessary to fully examine the required volume. Access to approximately 26% of the examination volume is restricted.
Due to the configuration of the steep tubesheet entry angle to head, it is impractical to meet the examination requirements of the 1986 Edition of ASME Code Section XI. Relief is requested in accordance with 10 CFR 50.55a(g)(5)(iii).
IV. Alternative Examination:
No alternate examinations are proposed in lieu of ultrasonic examination of the inaccessible portion of the subject welds.
5928-01-20355 Page 37 of 53 Three Mile Island Unit I Second Ten Year ISI Interval Request for Relief No. RR-02-19 Examination Coverage of ASME Section XI Code Class I Welds V. Justification for Granting Relief:
The accessible areas were examined with techniques that have been demonstrated and qualified in accordance with the 1986 Edition of ASME Code Section X1. The aggregate examination coverage of the weld and base metal areas was approximately 74% of the required examination volume.
The accessible 74% of the examination volume was examined by techniques which have been demonstrated and qualified in accordance with the 1986 Edition of ASME Code Section XI and was found to be acceptable.
VI. Implementation Schedule:
The subject weld examination applies to the second ten year ISI interval and was performed during the 13R Outage (September 1999-October 1999).
5928-01-20355 Page 38 of 53 Three Mile Island Unit 1 Second Ten Year ISI Interval Request for Relief No. RR-02-19 Examination Coverage of ASME Section XI Code Class I Welds Figure 10 Weld: RCHOOOIBSGO012 LU 0
CO M
0 I
5928-01-20355 Page 39 of 53 Three Mile Island Unit 1 Second Ten Year ISI Interval Request for Relief No. RR-02-19 Examination Coverage of ASME Section XI Code Class I Welds Part K: Examination of the Steam Generator Nozzle to Vessel Welds and Inner Radius
- 1. System/Component for which Relief is Requested:
Steam Generator Nozzle to Vessel Welds No RCH0001BSGO008N and RCH0001 BSGO009N I1. Code Requirement:
ASME Code Section XI, 1986 Edition, Subsection IWB, Examination Category B-D, Items B3.130 and B3.140.
The ASME Code Section XI, 1986 Edition, Subsection IWB, Table IWB-2500-1, Examination Category B-D, item B3.130 requires essentially 100% of the steam generator nozzle-to-vessel welds as defined by Figure IWB-2500-7(a) be examined. Examination Category B-D, item B3.140 requires essentially 100% of the nozzle inner radius section, as defined by Figure IWB-2500-7(a), be examined.
Code Case N-460, Alternative Examination Coverage for Class 1 and Class 2 Welds, states that 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%.
Ill. Basis for Relief:
Figure 11 provides a drawing depicting the configuration of the Steam Generator Nozzle to Vessel Welds and associated inner radius (Weld Numbers RCH0001 BSGO008N and RCH0001 BSGO009N)
It is not possible to obtain ultrasonic interrogation of greater than 90% of weld volume due to nozzle to vessel interface radius is too small causing transducer lift off. Also, the configuration of the barrel type nozzle restricts the transducer's ability to move to areas necessary to fully examine the required volume. The configuration of the barrel type nozzle only permits the weld to be scanned from the vessel side. It is not possible to obtain ultrasonic interrogation of greater than 90% of nozzle inner radius volume due to the external nozzle to vessel interface radius being too small, and causing transducer lift off. Access to approximately 53% of the weld and 21% of the nozzle inner radius volumes were restricted from examination.
Due to the configuration the barrel type nozzle and the small nozzle to vessel radius causing transducer lift off, it is impractical to meet the examination requirements of the 1986 Edition of ASME Code Section Xl. Relief is requested in accordance with 10 CFR 50.55a(g)(5)(iii).
5928-01-20355 Attachment I Page 40 of 53 Three Mile Island Unit 1 Second Ten Year ISI Interval Request for Relief No. RR-02-19 Examination Coverage of ASME Section XI Code Class I Welds IV. Alternative Examination:
No alternate examinations are proposed in lieu of ultrasonic examination of the inaccessible portion of the subject welds.
V. Justification for Grantinq Relief:
The accessible areas were examined with techniques that have been demonstrated and qualified in accordance with the 1986 Edition of ASME Code Section XI. The aggregate examination coverage of the welds was approximately 47%, and the nozzle inner radius volumes were approximately 79% of the required examination volume and the results were found to be acceptable in accordance with the ASME Code.
In addition to the required ultrasonic examination, the welds were examined by magnetic particle test method (MT) and found to be acceptable.
VI. Implementation Schedule:
The subject weld examinations apply to the second ten year ISI interval and were performed during the 13R Outage (September 1999 - October 1999).
5928-01-20355 Page 41 of 53 Three Mile Island Unit I Second Ten Year ISI Interval Request for Relief No. RR-02-19 Examination Coverage of ASME Section XI Code Class I Welds Figure 11 Welds: RCH0001BSGO008N & RCHOOO1BSGO009N WO..&
Id N,
0 LLI 17
-N.
II 3/4 0.*
U, zz OD0) 01 03 C00
ý00 0 0 CO V) l I
w I
5928-01-20355 Attachment I Page 42 of 53 Three Mile Island Unit 1 Second Ten Year ISI Interval Request for Relief No. RR-02-19 Examination Coverage of ASME Section XI Code Class I Welds Part L:
Examination of the Pressurizer Nozzle to Safe End Weld I. System/Component for which Relief is Requested:
Pressurizer Nozzle to Safe End Weld No. RCT0002PROO21 BM II. Code Requirement:
ASME Code Section XI, 1986 Edition, Subsection IWB, Examination Category B-F, Item B5.40.
The ASME Code Section XI, 1986 Edition, Subsection IWB, Table IWB-2500-1, Examination Category B-F, B5.40 requires essentially 100% of the pressurizer nozzle-to-safe end butt weld as defined by Figure IWB-2500-8 be examined. Code Case N-460, Alternative Examination Coverage for Class 1 and Class 2 Welds, states that 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%.
I1l. Basis for Relief:
Figure 12 provides a drawing depicting the configuration of the Pressurizer Nozzle to Safe End Weld (Weld Number RCT0002PROO21 BM).
It is not possible to obtain ultrasonic interrogation of greater than 90% of this volume, due to the remaining portion of the nozzle restraint creating interference on approximately 180 degrees of the examination area. The remaining portion of the restraint is just above the weld area and restricts the transducer's ability to move to areas necessary to fully examine the required volume. Access to approximately 13% of the examination volume is restricted.
Due to the non-removable remaining portion of the nozzle restraint at the nozzle to safe end weld, it is impractical to meet the examination requirements of the 1986 Edition of ASME Code Section XI. Relief is requested in accordance with 10 CFR 50.55a(g)(5)(iii).
IV. Alternative Examination:
No alternate examinations are proposed in lieu of the ultrasonic examination of the inaccessible portion of the subject weld.
5928-01-20355 Page 43 of 53 Three Mile Island Unit 1 Second Ten Year ISI Interval Request for Relief No. RR-02-19 Examination Coverage of ASME Section XI Code Class I Welds V. Justification for Granting Relief:
The accessible areas were examined with techniques that have been demonstrated and qualified in accordance with the 1986 Edition of ASME Code Section XI. The aggregate examination coverage of the weld and base metal areas was approximately 87% of the required examination volume and the results were acceptable in accordance with the ASME Code.
VI. Implementation Schedule:
The subject weld examination applies to the second ten year ISI interval and were performed during the 13R Outage (September 1999 - October 1999).
5928-01-20355 Page 44 of 53 Three Mile Island Unit 1 Second Ten Year ISI Interval Request for Relief No. RR-02-19 Examination Coverage of ASME Section XI Code Class I Welds Figure 12 Weld: RCT0002PR0021BM PZ.R
.R.CTOOO2/PR0021BMANVELD It 3"
/
5928-01-20355 Page 45 of 53 Three Mile Island Unit 1 Second Ten Year ISI Interval Request for Relief No. RR-02-19 Examination Coverage of ASME Section XI Code Class I Welds Part M: Examination of the Reactor Coolant Pump Integral Attachment Welds I. System/Component for which Relief is Requested:
Reactor Coolant Pump Integral Attachment Welds No. RCP0001 BRC0279WA, RCP0001BRC0280WA, and RCP0001BRC0281WA I1. Code Requirement:
ASME Code Section XI, 1986 Edition, Subsection IWB, Examination Category B-K-I, Item 810.20.
The ASME Code Section Xl, 1986 Edition, Subsection IWB, Table IWB-2500-1, Examination Category B-K-I, item B10.20 requires essentially 100% of the integrally welded attachments as defined by Figure IWB-2500-15 be examined.
Code Case N-460, Alternative Examination Coverage for Class 1 and Class 2 Welds, states that 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%.
I1l. Basis for Relief:
Figures 13a, 13b, and 13c provide sketches of the Reactor Coolant Pump Integral Attachment Welds (Weld Numbers RCP0001 BRC0279WA, RCP00011BRC0280WA, and RCP0001BRC0281WA).
It is not possible to obtain surface examination coverage greater than 90% of the examination surface area, due to the pump motor stand obstructing a portion of the weld and the insulation structural steel framework creating interference in the examination area. Access to approximately 50% of the examination surface area for welds RCP0001 BRC0279WA, and RCP0001 BRC0280WA is restricted. For weld RCP0001BRC0281WA approximately 17% of the examination surface area is restricted.
Due to the obstruction of the pump motor stand, and interference caused by the insulation structural steel framework, it is impractical to meet the examination requirements of the 1986 Edition of ASME Code Section Xl. Relief is requested in accordance with 10 CFR 50.55a(g)(5)(iii).
IV. Alternative Examination:
No alternate examinations are proposed in lieu of the surface examination of the subject welds.
5928-01-20355 Page 46 of 53 Three Mile Island Unit 1 Second Ten Year ISI Interval Request for Relief No. RR-02-19 Examination Coverage of ASME Section XI Code Class I Welds V. Justification for Granting Relief:
The accessible areas were examined with techniques that have been demonstrated and qualified in accordance with the 1986 Edition of ASME Code Section X1. The aggregate examination coverage of the weld and base metal areas was approximately 50% for welds RCP0001 BRC0279WA, and RCP0001BRC0280WA, and approximately 83% for weld RCP0001 BRC0281WA, of the required examination volumes and the results were acceptable in accordance with the ASME Code.
VI. Implementation Schedule:
The subject weld examinations apply to the second ten year ISI interval. Weld numbers RCP0001BRC0279WA, RCP0001 BRC0280WA were examined during the 11R Outage (September 1995 - October 1995). Weld number RCP0001BRC0281WA was examined during the 13R Outage (September 1999 October 1999).
5928-01-20355 Page 47 of 53 Three Mile Island Unit 1 Second Ten Year ISI Interval Request for Relief No. RR-02-19 Examination Coverage of ASME Section XI Code Class I Welds Figure 13a Weld: RCP0001 BRC0279WA
"', J " -*...
j
=
.;.; (
(
I t.....-.
~~~~~~~~~~~~~.
-]*
L
-J........
......)....."--"T....*...
.4
~~~~~~~.
.)........
i S........
(:....... i..............:...*... i...-...(...!. :.,' -..'...
i - :
5928-01-20355 Page 48 of 53 Three Mile Island Unit 1 Second Ten Year ISI Interval Request for Relief No. RR-02-19 Examination Coverage of ASME Section XI Code Class I Welds Figure 13b Weld: RCP0001 BRC0280WA 7...
T -'
Z*
'" "' '" " 'L.....
- *...+.,+ i i
+
.L..... *
+
i
+.,...,,h.....
- ..,o.*
... ! +- !
- "*.... *"'-i
5928-01-20355 Page 49 of 53 Three Mile Island Unit 1 Second Ten Year ISI Interval Request for Relief No. RR-02-19 Examination Coverage of ASME Section XI Code Class I Welds Figure 13c Weld: RCP0001BRC0281WA r1 18r
.1
5928-01-20355 Page 50 of 53 Three Mile Island Unit 1 Second Ten Year ISI Interval Request for Relief No. RR-02-19 Examination Coverage of ASME Section XI Code Class I Welds Part N: Examination of the Pressurizer Integral Attachment Welds I. System/Component for which Relief is Requested:
Pressurizer Integral Attachment Welds No. RCT0002PR0022WA, RCT0002PR0023WA, RCT0002PR0024WA, RCT0002PROO25WA, RCT0002PR0026WA, RCT0002PR0O27WA, RCT0002PROO28WA, and RCT0002PR0029WA II. Code Requirement:
ASME Code Section XI, 1986 Edition, Subsection IWB, Examination Category B-K-I, Item B10.10.
The ASME Code Section XI, 1986 Edition, Subsection IWB, Table IWB-2500-1, Examination Category B-K-I, item B10.10 requires essentially 100% of the integrally welded attachments as defined by Figure IWB-2500-15 be examined.
Code Case N-460, Alternative Examination Coverage for Class 1 and Class 2 Welds, states that a reduction in examination coverage on any Class 1 and Class 2 weld may be accepted provided the reduction in coverage for that weld is less than 10%.
Ill. Basis for Relief:
Figure 14a provides a sketch showing the location of the Pressurizer Integral Attachment Welds (Weld Numbers RCT0002PR0022WA, RCT0002PROO23WA, RCT0002PROO24WA, RCT0002PR0025WA, RCT0002PROO26WA, RCT0002PROO27WA, RCT0002PR0028WA, and RCT0002PROO29WA). Figure 14b provides a sketch showing one of the attachment welds that allowed no weld examination coverage.
It is not possible to obtain surface examination coverage greater than 90% of the examination surface area, due to the obstruction caused by the existing structural support I-beam. The I-beam supports the lugs, which are attached by the subject welds to the Pressurizer. The I-beam obstructs the access to the portion of the attachment welds under the lug and the supporting surface of the I-beam. Another obstruction that interferes with the examination of the integral attachment welds, is the insulation shroud above the support lugs. Also, there are bolted connections on the I-beam next to the supporting lugs, which interfere with a portion of the vertical direction of the integral attachment weld. Access to approximately 29% of the examination surface area for welds RCT0002PR0022WA, and RCT0002PROO23WA is restricted. Access to approximately 45% of the examination surface area for welds RCT0002PROO24WA, and RCT0002PROO25WA is restricted. Access to 100% of the examination surface area for welds RCT0002PROO26WA, and RCT0002PROO27WA is restricted.
Access to approximately 45% of the examination surface area for weld
5928-01-20355 Page 51 of 53 Three Mile Island Unit 1 Second Ten Year ISI Interval Request for Relief No. RR-02-19 Examination Coverage of ASME Section XI Code Class I Welds RCT0002PROO28WA is restricted. Access to approximately 83% of the examination surface area for weld RCT0002PROO29WA is restricted.
Due to the obstruction created by the structural support I-beam and attachments, it is impractical to meet the examination requirements of the 1986 Edition of ASME Code Section XI. Relief is requested in accordance with 10 CFR 50.55a(g)(5)(iii).
IV. Alternative Examination:
No alternate examinations are proposed in lieu of a surface examination of the inaccessible portion of the subject welds.
V. Justification for Granting Relief:
The remaining percentage for the subject welds were examined by techniques which have been demonstrated and qualified in accordance with the 1986 Edition of ASME Code Section XI and found to be acceptable.
These welds were examined in the first interval. The examination coverage during this second interval examination is approximately the same or greater than that examined during the first interval.
VI. Implementation Schedule:
The subject weld examinations apply to the second ten year ISI interval. Weld numbers RCT0002PROO22WA and RCT0002PROO23WA were examined during the 1OR Outage (September 1993 - October 1993). Weld numbers RCT0002PR0024WA, RCT0002PR0025WA, RCT0002PR0026WA, RCT0002PR0027WA, RCT0002PR0028WA, and RCTO002PROO29WA were examined during the 12R Outage (September 1997-October 1997).
5928-01-20355 Page 52 of 53 Three Mile Island Unit 1 Second Ten Year ISI Interval Request for Relief No. RR-02-19 Examination Coverage of ASME Section XI Code Class I Welds Figure 14a Welds: RCT0002PROO22WA, RCT0002PROO23WA, RCT0002PROO24WA, RCT0002PROO25WA, RCT0002PROO26WA, RCT0002PROO27WA, RCT0002PROO28WA & RCT0002PROO29WA ELEVAnON vY
5928-01-20355 Page 53 of 53 Three Mile Island Unit 1 Second Ten Year ISI Interval Request for Relief No. RR-02-19 Examination Coverage of ASME Section XI Code Class I Welds Figure 14b Weld: RCT0002PROO27WA
'I° NAid
- r.
.s*7R
,6(E o tccssn9,5E
ATTACHMENT 2 TMI Unit 1 ASME Code Section XI Relief Request Associated with Third Ten Year ISI Interval Class I Weld Examinations Relief Request No. RR-02-20
5928-01-20355 Page 1 of 4 Three Mile Island Unit 1 Third Ten Year ISI Interval Request for Relief No. RR-02-20 Examination Coverage of ASME Section XI Code Class I Welds Examination of the Outlet Nozzle to Reactor Vessel Shell Welds I. System/Component for which Relief is Requested:
Outlet Nozzle to Reactor Vessel Shell Welds No. RCT0001 RV0002N and RCT0001 RV0005N I1. Code Requirement:
ASME Code Section XI, 1995 Edition with Addenda through 1996, Subsection IWB, Examination Category B-D, Item B3.90.
The ASME Code Section XI, 1995 Edition with Addenda through 1996, Subsection IWB 2500-1, Examination Category B-D, Item B3.90 for Reactor Vessel nozzle to shell welds require essentially 100% of the weld length as defined by Figure IWB 2500-7(a) be examined. Code Case N-460, Alternative Examination Coverage for Class 1 and Class 2 Welds, states that 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%.
I1l. Basis for Relief:
The location of the Reactor Vessel welds is shown in Figures la and lb. Figures 15a and 15b provide drawings depicting the configuration of the Outlet Nozzle to Reactor Vessel Shell Welds (Weld Numbers RCT0001 RV002N and RCT0001 RV0005N).
It is not possible to obtain ultrasonic interrogation of greater than 90% of this volume, due to the configuration of the outlet nozzle boss. The contour of the nozzle radius (See Figures 15a and 15b) restricts the URSULA manipulator's ability to scan the weld and adjacent base material from the vessel shell. Access to approximately 44% of the examination volume from the vessel shell is restricted.
Due to the configuration of the nozzle, it is impractical to meet the examination coverage requirements of the ASME Code Section XI, 1995 Edition. Relief is requested in accordance with 10 CFR 50.55a(g)(5)(iii).
IV. Alternative Examination:
No alternative examinations are proposed in lieu of ultrasonic examination of the inaccessible portion of the subject welds.
5928-01-20355 Page 2 of 4 Three Mile Island Unit 1 Third Ten Year ISI Interval Request for Relief No. RR-02-20 Examination Coverage of ASME Section XI Code Class I Welds V. Justification for Granting Relief:
During preparations for the 1 R14 Outage, the equipment and scan plan were developed to achieve maximum inspection coverage.
The outlet nozzle to shell welds were examined from the shell side to the extent possible. These examinations were performed from both sides of the weld, scanning both parallel and perpendicular to the weld. The aggregate examination coverage of the weld and base metal areas was approximately 56% of the required examination volume of each weld. The requirements of the ASME Code Section Xl, 1995 Edition was met for the examinations from the nozzle bore.
The Reactor Vessel welds are examined from the inside surface using the Framatome URSULA inspection manipulator in conjunction with the Framatome ACCUSONEX data acquisition and analysis system. URSULA is a computer controlled, remotely operated manipulator which uses a contact UT head to obtain ultrasonic data for the detection and sizing of indications. The contact head is fitted with an array of transducers in direct contact with the Reactor Vessel surface.
With the ACCUSONEX data acquisition system multiple channels of ultrasonic data are amplified, filtered, digitized and processed, and integrated with the transducer position to provide computer generated images of the examination volume.
The remaining 56% of the examination volume of each weld was examined from the shell side of each weld in accordance with the ASME Code Section XI, 1995 Edition with Addenda through 1996. As there is no limitation for the examination from the nozzle bore, 100% of each weld is examined by at least two angles.
These welds were examined in the first and second ten year interval Reactor Vessel examinations. The examination coverage during the third ten year interval examination was approximately the same or greater than that performed during the first and second ten year interval Reactor Vessel examination. No indications exceeding the acceptance criteria of ASME Code Section XI were noted during this examination.
VI. Implementation Schedule:
The subject weld examinations, applicable to the first period of the third ten year ISI interval, were performed during the T1 R14 outage (October 9, 2001 through December 6, 2001).
5928-01-20355 Page 3 of 4 Three Mile Island Unit 1 Third Ten Year ISI Interval Request for Relief No. RR-02-20 Examination Coverage of ASME Section XI Code Class I Welds Figure 15a Welds: RCT0001RV0002N & RCT0001RV0005N WELD 15*
18.09 SQ IN.
- 45.
18.09 SQ IN.
ADJACENT BAS 15"/45-S 215.27 SQ IN.
E METAL HORIZONTAL SECTION VIEW I VERTICAL SECTION VIEWI OUTLET NOZZLE AXIAL COVERAGE FROM NOZZLE BORE WELD 15' 22.95 SQ IN.
- 45.
22.95 SQ IN.
ADJACENT BASE METAL 1'5/45"s 234.17 SQ IN.
5928-01-2035 Page 4 of 4 5
Three Mile Island Unit 1 Third Ten Year ISI Interval Request for Relief No. RR-02-20 Examination Coverage of ASME Section XI Code Class I Welds Figure 15b Welds: RCT0001RV0002N & RCT0001RV0005N WELD SheII/7 45* =
0.00 SQ IN.
60" =
0.00 SQ IN.
0.00 SQ IN.
Shell/8 45" =
0.00 SQ IN.
60" =
0.00 SQ IN.
0*=
0.00 SQ IN.
ADJACENT BASE METAL Shell7/8 45-/60-/0" = 81.51 SQ IN.
HORIZONTAL SECTION VIEW I VERTICAL SECTION VIEW I WELD Shell/7 45' =
0.00 60* = 20.87 0 = 20.87 SheII/8 45' = 20.87 60" =
0.00 0* = 20.87 OUTLET NOZZLE
-WELD & ADJACENT BASE METAL (BALANCE OF VOLUME)
FROM VESSEL I.D.
SQ SQ SQ SQ SQ SQ IN.
IN.
IN.
IN.
IN.
IN.
ADJACENT BASE METAL Shell7/8 45"/60"/0' = 109.1.3 SQ IN.