L-2006-050, Closeout of the Third Ten-Year Inservice Inspection (ISI) Interval Relief Requests 1A, 14A & 15A
| ML060520631 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 02/20/2006 |
| From: | Jones T Florida Power & Light Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| L-2006-050 | |
| Download: ML060520631 (72) | |
Text
k n0 FEB 202006 FPL L-2006-050 10 CFR 50.55a U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 RE: Florida Power and Light Company Turkey Point Units 3 and 4 Docket Nos. 50-250 and 50-251 Closeout of the Third Ten-Year Inservice Inspection (ISI) Interval Relief Requests 1A. 14A and 15A Pursuant to 10 CFR50.55a (g)(6), Florida Power and Light Company (FPL) requests approval of revised Relief Request 1A, 14A, and 15A as part of the closeout of the ten-year inservice inspection (ISI) interval for Turkey Point Units 3 and 4. FPL has determined pursuant to 10 CFR50.55a (g)(5) (iii), that the examinations addressed in Relief Requests 1A, 14A, and 15A were performed to the extent possible and provide an acceptable level of quality and safely.
The objective of Relief Request 1A (Atlachment 1) is to resubmit the previously approved Relief Request No. 1. NRC letter dated March 31, 1995 (TAC No. M87725 and M87726) approved the initial submittal of Relief Request 1. The previous submittal of the relief request was based upon the techniques utilized and the limitations encountered during the examination volume coverage for the examinations performed during the second ten-year ISI interval examinations. This revision submits the examination volume coverage obtained during the third ten-year ISI interval inspection. Relief requests can only be granted for the interval in which they were submitted to the NRC because of the 10CFR50.55a requirement for licensees to update their ISI program every 120 months.
Examinations of reactor pressure vessel welds are performed to the maximum extent possible. Due to the configuration of the reactor vessel, it is impractical to meet the examination coverage requirements of the ASME Code, Section Xl, 1989 Edition, No Addenda, as clarified by 10CFR50.55ai'g)(6)(ii)(A)(2) and Code Case N-460. When examined, the welds listed within Relief Request No. 1A did not receive the required Code volume coverage due to their configuration and/or the presence of permanent attachments. These scanning limitations prohibit essentially 100% ultrasonic examination coverage of the required examination volume. Relief is requested in accordance with 10CFR50.55a(g)(5)(iii). These areas were identified during the third ten-year ISI interval.
Attachment 1 provides the details of the examination limitations by individual weld identification and description. The accompanying figures graphically depict the extent of the limitations during the third ten-year ISI examinations.
The objective of Relief Requests 14A (Attachment 2) and 15A (Attachment 3) is to resubmit the previously approved Relief Requests 14 and 15 for Class 1 and 2 vessel inside radius, vessel welds and piping welds that did not receive the code required t41 an FPL Group company
volume. NRC letter dated December 4,1996 (TAC No. M94326 and M94327) approved the initial submittal of Relief Requests No. 14 and 15. The previous submittal of the relief requests was based upon the techniques utilized and the limitations encountered during the examinations performed during the first period of the third ten-year ISI interval. This revision submits the Class 1 and 2 inner radius, vessel welds and piping welds with examination volume coverage obtained that were below the minimum acceptable during the third ten-year ISI interval inspection. Relief requests can only be granted for the interval in which they were submitted to the NRC because of the 10CFR50.55a requirement for licensees to update their ISI program every 120 months.
Examinations of Class 1 and 2 inner radius, vessel welds and piping welds are performed to the maximum extent possible. Due to configuration, it is impractical to meet the examination coverage requirements of the ASME Code, Section Xl 1989 Edition, No Addenda, as clarified by Code Case N-460. When examined, the welds listed within Relief Requests 14A and 15A did not receive the code required volume coverage due to their configuration and/or the presence of permanent attachments.
These scanning limitations prohibit essentially 100% ultrasonic examination coverage of the required examination volume. Relief is requested in accordance with 10CFR50.55a(g)(5)(iii). These areas were identified during the third ten-year ISI interval.
Should you have any questions on this submittal, please contact Walter Parker at (305) 246-6632.
Veiy truly yout Terry 0. Jones Vice President Turkey Point Nuclear Plant SM Attachments cc: Regional Administrator, USNRC, Region II Senior Resident Inspector, USNRC, Turkey Point Nuclear Plant
I Turkey Point Nuclear Plant Relief Request 1A L-2006-050 Attachment 1 Page 1 Relief Request In Accordance with 10 CFR50.55a(g)(5)(iii)
Inservice Inspection Impracticality
- 1. ASME Code Component(s) Affected Class 1 pressure retaining welds in the reactor pressure vessel (RPV).
2. Applicable Code Edition and Addenda
The American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Rules for Inservice Inspection of Nuclear Power Plant Components, Section Xl, 1989 Edition, No Addenda.
3. Applicable Code Requirement
Exa Item No. Exmnto-Rqieet B-A B1.21 Essentially 100% volumetric examination of all circumferential head welds.
B-A 31.30 Essentially 100% volumetric examination of the shell to flange weld.
B-G-1 B6.40 Essentially 100% volumetric examination of the 1 inch annular surface of flange surrounding each stud hole.
As defined by 10CFR50.55a(g)(6)(ii)(A)(2) and ASME Code Case N-460, essentially 100% means more than 90% of the examination volume of each weld where reduction in coverage is due to interference by another component or part geometry.
- 4. im~racticality of Compliance Due to the configuration of the Reaclor Vessel, it is impractical to meet the examination coverage requirements of the ASME Code, Section Xl, 1989 Edition, No Addenda, as clarified by Code Case N-460. Relief is requested in accordance with 10 CFR 50.55a(g)(5)(iii). These areas were found during the 3rd 10-year inservice inspection interval.
W'hen examined, the welds or surfaces listed within this request did not receive the required code volume coverage due to their configuration and/or the presence of permanent attachments. These scanning limitations prohibit essentially 100% ultrasonic examination coverage of the required examination volume.
Turkey Point Nuclear Plant Relief Request 1A L-2006-050 Page 2 Described below, coupled with figures, are details of the examination limitations by weld or examination description. The accompanying figures graphically depict the extent of the limitations.
RPV Lower Head Ring-to-Bottom Head Weld (3-WR-9 and 4-WR-9)
Examination Category B-A, Item B13.21 The examination of the Figure IWB-2500-3 A-B-C-D volume is limited due to the proximity of the instrumentation tubes. Access to approximately 17% of the examination volume is restricted. The remaining 83% of the examination volume was examined with techniques which have been qualified by demonstration in accordance with Supplements 4 & 6 of the 1995 Edition, 1996 Addenda of the ASME Code Section Xl, Appendix VIII, using the Performance Demonstration Initiative Protocol. This weld was examined from both sides of the weld, scanning both parallel and perpendicular to the weld. The ultrasonic examination identified no recordable indications.
The mechanized scanning of the lower head ring-to-lower head welds 3-WR-9 and 4-WR-9 are limited due to interference from the instrumentation tubes.
Figure 1 provides an illustration of the weld volume limitation due to the instrumentation tubes.
RPV Upper Shell-to-Flange Weld (3-WR-18 and 4-WR-18)
Examination Category B-A, Item B13.30 The examination of the Figure IWB-2500-4 A-B-C-D volume is limited due to the Keyways and Irradiation Slots. Access to approximately 29% of the examination volume is restricted. The remaining 71% of the examination volume was examined with ASME Code acceptable techniques. Additionally, the mechanized techniques employed for examination from the RPV inside surface have also been qualified by demonstration in accordance with Supplements 4 & 6 of the 1995 Edition, 1996 Addenda of the ASME Code Section Xl, Appendix VIII, using the Performance Demonstration Initiative Protocol. This weld was examined from both sides of the weld, scanning both parallel and perpendicular. The ultrasonic examination did not reveal any recordable or reportable flaws in accordance with the ASME Code Section Xl, 1989 Edition, No Addenda.
The upper shell-to-flange weld 3-WR-18 and 4-WR-18 is examined from the shell side and from the flange seal surface. The examination performed from the flange seal surface was not limited by configuration. Figure 2 shows the inside surface scan limitations and the location of the areas of incomplete coverage to the mechanized scanning due to the presence of the keyways and Irradiation slots.
Turkey Point Nuclear Plant Relief Request 1A L-2006-C50 Page 3 RPV Threads in Flange (3-Lig-1 thru 58 and 4-Lig-1 thru 58)
Examination Category B-G-1, Item B6.40 The examination of the Figure IWB-2500-12 A-B-C-D-E-F-G-H volume is limited when scanning the carbon steel base material surrounding the stud holes due to the sealing surfaces configuration. Access to approximately 15.33% of the examination volume is restricted. The remaining 84.67% of the examination volume was examined with ASME Code acceptable techniques. The ultrasonic examination did not reveal any recordable or reportable flaws in accordance with the ASME Code Section Xl, 1989 Edition, No Addenda.
The manual scanning of the l inch annulus surface around the RPV flange stud hole 3-Lig 1 thru 58 and 4-Lig 1 thru 58 is performed from the RPV flange surface. Figure 3 provides an illustration of the RPV flange surface limitation due to interference from the sealing surface configuration.
- 5. Burden Caused by Compliance It is not possible to obtain ultrasonic. interrogation of greater than 90% of the required examination volume due to interference caused by configuration and/or permanent attachments. Examinations are performed to the maximum extent possible. The Ultrasonic (UT) techniques for each weld or surface were reviewed to determine if additional coverage could be achieved. For the welds or surfaces listed above, it was not possible to remove the obstruction without significant work, increased radiation exposure, and/or damage to the plant.
- 6. Proposed Alternative and Basis for Use Proposed Alternative 1), Periodic system pressure tests in accordance with ASME Section Xl Category B-P, Table IWB-2500-1.
- 2) Conduct ultrasonic examinations to the maximum extent possible.
Basis FPL performed inservice examinations of selected welds and surfaces in accordance with the requirements of 10CFR50.55a, plant technical specifications, and the 1989 Edition, No Addenda, of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section XlI. When a component has conditions, which limit the examination volume, Florida Power and Light is required to submit the information to the enforcement and regulatory authorities having jurisdiction at the plant site. This Relief Request has been written to address areas where those types of conditions exist and the required amount of coverage was reduced below the minimum acceptable.
Turkey Point Nuclear Plant Relief Request 1A L-2006-050 Page 4 FPL performed mechanized ultrasonic examinations of the reactor vessel during the Unit 3 October 2004 and Unit 4 April 2005 refueling outages.
10 CFR 50.55a(g)(4) recognizes that throughout the service life of a nuclear power facility, components which are classified as ASME Code Class 1, Class 2, and Class 3 must meet the requirements set forth in the ASME Code to the extent practical within the limitations of design, geometry and materials of construction of the components.
By letter dated July 22, 2004, and supplemented August 19, 2004, FPL submitted relief request #35 to the U.S. Nuclear Regulatory Commission (NRC). The purpose of the relief request was to obtain permission to implement an alternative from certain provisions of the ASME Code, Section Xl, 1989 Edition, No Addenda, contained in the third ten-year interval Inservice inspection program. FPL proposed supplementing the ASME Section XI, 1989 Edition, No Addenda, Appendix I examination from the flange surface with the examination from the reactor vessel inside surface using procedures, equipment, and personnel qualified by demonstration to perform remote mechanized examination of the reactor vessel flange-to-shell weld from the inside surface in accordance with ASME Code 1995 Edition, 1996 Addenda, Section Xl, Appendix VII, Supplements 4 and 6, in lieu of Section V, Article 4 requirements. The NRC authorized the proposed alternative by letter dated October 20, 2004 (TAC NO. MC3891). The accessible areas of the shell weld were examined with personnel, equipment and procedures that were qualified by demonstration in accordance with Supplements 4 and 6 of the 1995 Edition, 1996 Addenda of the ASME Code, Section Xl, Appendix Vil, using the Performance Demonstration Initiative (PDI) protocol. These examinations were performed from both sides of the welds, scanning both parallel and perpendicular to the weld to the maximum extent possible. The examinations performed utilizing demonstrated and qualified techniques provided an equivalent or better examination than the requirements of the 1989 Edition, No Addenda, of ASME Section Xl.
FPL performed ultrasonic examinations of the remaining reactor vessel welds in accordance with the requirements of 10 CFR 50.55a, plant technical specifications, and the 1989 Edition, No Addenda, of ASIME Section Xl to the maximum extent possible.
Additionally, the mechanized techniques employed for examination from the RPV inside surface have also been demonstrated in accordance with Supplements 4 and 6 of the 1995 Edition, 1996 Addenda of the ASME Code Section Xl, Appendix Vil, using the Performance Demonstration Initiative Protocol.
NRC letter dated March 31, 1995 (TAC NO. M87725 and M87726) approved the initial submittal of Relief Request No. 1. The previous submittal of the relief request was based upon the techniques utilized and the limitations encountered during the examination during the second ten-year inservice inspection interval and detailed the anticipated examination volume coverage for the examinations performed during the third ten-year inservice inspection interval examinations. This revision submits the examination volume coverage obtained during the third ten-year inservice inspection interval inspection.
Turkey Point Nuclear Plant Relief Request 1A L-2006-C050 Page 5 In addition to the required ultrasonic examination, the interior of the reactor vessel, including welded attachments, received a visual examination in accordance with Table IWB-2500-1, Examination Categories B-N-1, B-N-2 and B-N-3. The visual examinations revealed no relevant indications.
The subject welds were examined in the second interval during the ten-year reactor vessel examination. These examinations did not reveal any recordable or reportable flaws during the previous examination.
The extent of examination volume achieved ultrasonically, the alternate scans performed, and the system pressure tests provide assurance of an acceptable level of quality and safety.
- 7. Duration of Proposed Alternative Third Inservice Inspection Interval Unit 3 - February 22, 1994 thru February 21, 2004 Unit4-April 15, 1994thruApril 14, 2004
- 8. References 10CFR50.55a ASME Section Xl, "Rules For Inservice Inspection of Nuclear Power Plant Components,"
1'989 Edition, No Addenda ASME Section V, "Rules For Inservice Inspection of Nuclear Power Plant Components,"
1'989 Edition, No Addenda ASME Section Xl, Division 1, Code Case N-460, "Alternative Examination Coverage for Class 1 and Class 2 Welds, Section Xl, Division 1" ASME Section Xl, "Rules For Inservice Inspection of Nuclear Power Plant Components,"
1995 Edition, 1996 Addenda
Turkey Point Nuclear Plant Relief Request 1A L-2006-050 Page 6
) Calf Sttaibring
.0- VetdW A...._1 tu be RPV Lower Head Ring-to-Bottom Head Weld (3-WR-9 and 4-WR-9)
Figure 1
Turkey Point Nuclear Plant Relief Request 1A L-20t)6-050 Page 7 DIR
- r CD.CTJENS 3 &
Parallel Scan Limitation ** . .....
... . .... .......... Missed Volume
. .....2 L-a..
- E1' -.' :' ' :E.# - : ': I Perpendicular Scan Limitation
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Miutmtd VAl ImP - iEiE -- E: ---.-- 4-i-,,
Turkey Point Nuclear Plant Relief Request 1A L-2006-050 Page 8 NNOr 44ARIA SBB Surface Edge
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Interest '-- ,rt RPV Flange Ligament Volume Limitation Illustration Figure 3
Turkey Point Nuclear Plant Relief Request 14A L-2006-050 Page 1 Relief Request In Accordance wil:h 10 CFR50.55a(g)(5)(iii)
--Inservice Inspection Impracticality--
- 1. ASME. Code Component(s) Affected Class 1 inner radius in vessels Class 1 and 2 pressure retaining welds in vessel and piping
- 2. Applicable Code Edition and Addenda The American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Rules for Inservice Inspection of Nuclear Power Plant Components, Section Xl, 1989 Edition, No Addenda.
- 3. Applicable Code Requirement Essentially 100% volumetric examination of the nozzle B-D B3.140 inner radius.
B-F B5.70 Essentially 100% volumetric and surface examination of Circumferential welds for >4" nominal pipe size.
B-J B9.11 Essentially 100% volumetric and surface examination of Circumferential welds for >4" nominal pipe size.
B-J B9.31 Essentially 100% volumetric and surface examination of branch pipe connections NPS 4 or larger.
C-A C1.10 Essentially 100% volumetric examination of the weld C1.20 length.
C-F-1 C5. 11 Essentially 100% volumetric and surface examination of Circumferential welds for >4" nominal pipe size.
C-F-1 C5.21 Essentially 100% volumetric and surface examination of Circumferential welds for > 1/5" nominal pipe size.
C-F-2 C5.51 Essentially 100% volumetric and surface examination of Circumferential welds for >4" nominal pipe size.
As defined by ASME Code Case N-460, essentially 100% means more than 90% of the examination volume of each weld where reduction in coverage is due to interference by another component or part geometry.
Turkey Point Nuclear Plant Relief Request 14A L-2006-050 Page 2
- 4. Lmpricticalfty of Compliance Due to the configuration of the welds included within this relief request, it is impractical to meet the examination coverage requirements of the ASME Code, Section Xl, 1989 Edition, No Addenda, as clarified by Code Case N-460. Relief is requested in accordance with 10 CFR 50.55a(g)(5)(iii). These areas were found during the third ten-year inservice inspection interval.
When a component has conditions, which limit the examination volume, Florida Power and Light is required to submit the information to the enforcement and regulatory authorities having jurisdiction at the plant site. This Relief Request has been written to address areas where those types of conditions exist and the required amount of coverage was reduced below the minimum acceptable.
When examined, the welds listed within this request did not receive the required code volume coverage due to their configuration and/or the presence of permanent attachments. These scanning limitations prohibit essentially 100% ultrasonic examination coverage of the required examination volume.
The Table 1 summarizes the percent of coverage achieved and references specific figures that show the extent of coverage. Arrows and lines on the figures illustrate the UT transducer beam direction and extent of the area examined.
Relief is requested from the ASME Boiler and Pressure Vessel Code required volume as identified in Figure IWB-2500-7,8,10 and IWC-2500 -1 and 7, as applicable.
- 5. Burden Caused By Compliance Examinations are performed to the maximum extent possible. The ultrasonic (UT) techniques for each weld were reviewed to determine if additional coverage could be achieved. If practical, physical obstructions were removed. For the welds listed within Table 1, it was not possible to remove the obstruction without significant work, increased radiation exposure, and/or damage to the plant. Additional weld preparation by welding or metal removal is a modification of the examination area requiring significant engineering and construction personnel support. Increased radiation exposure and cost would be incurred in order to perform these modifications.
Radiography is impractical due to the amount of work being performed in the areas on a 24-hour basis. This would result in numerous work-related stoppages and increased exposure due to the shutdown of and startup of other work in the areas. The water must be drained from systems where radiography is performed, which increases the radiation dose rates over a much broader area than the weld being examined. There would be significant burden associated with the performance of weld or area modifications or radiography in order to increase the examination coverage.
Turkey Point Nuclear Plant Relief Request 14A L-2006-050 Page 3
- 6. Proposed Altemative and Basis for Uise Proposed Altemative
- 1) Surface examination per category B-F, B-J, C-F-1 and C-F-2.
- 2) Conduct ultrasonic examinations to the maximum extent possible.
- 3) Periodic system pressure tests in accordance with ASME Section XI Category B-P, Table IWB-2500-1 and Category C-H, Table IWC-2500-1.
Basis FPL performed inservice examinations cf selected welds in accordance with the requirements of 10CF R50.55a, plant technical specifications, and the 1989 Edition, no addenda, of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section Xl. When a component has conditions, which limit the examination volume, Florida Power and Light is required to submit the information to the enforcement and regulatory authorities having jurisdiction at the plant site. This Relief Request has been written to address areas where those types of conditions exist and the required amount of coverage was reduced below the minimum acceptable.
It is not possible to obtain ultrasonic interrogation of greater than 90% of the required examination volume due to interference caused by configuration and/or permanent attachments.
Configuration, permanent attachments and/or structural interferences prohibit 100% ultrasonic examination of Code required volume. Additional ultrasonic techniques are employed where practical to achieve the code-required volume. The Table 1 summarizes the percent of coverage achieved and references specific figures that show the extent of coverage. Arrows and lines on the figures illustrate the UT transducer beam direction and extent of the area examined.
For examinations performed prior to the expedited implementation of Appendix Vill, Supplements 2 and 3 (May 22, 2000), the ultrasonic testing (UT) techniques for each weld were reviewed to determine if additional coverage could have been achieved. FPL's procedures require the examiner to consider whether additional coverage is necessary and practical. Those alternate techniques were investigated at the time of discovery. The alternate techniques considered were extending the calibration distance and/or using additional beam angles or modes. This has often provided the additional coverage needed to avoid relief. Using additional UT techniques on the weld examination areas in this relief request would have provided little or no additional coverage.
The coverage obtained was the maximum practical.
For examinations performed after the 10 CFR 50.55a required expedited implementation of Appendix VII, supplements 2 and 3 (May 22, 2000), the ultrasonic testing (UT) was performed utilizing personnel qualified and procedures demonstrated in accordance with the Performance Demonstration Initiative (PDI) program. In the cases where austenitic materials were examined (Code Category B-J and C-F-1), the credited volumetric examination of the weld required volume (WRV) is limited when access can only be obtained from one side. It should be noted that the volumetric examination was performed through 100% of the Code WRV; however, the PDI Appendix Vil procedure used is not qualified for the detection of flaws on the far side of the single sided access examinations of ausl:enitic piping welds. The techniques employed for the single sided examinations provided for a best effort examination. The coverage obtained was the maximum practical.
Turkey Point Nuclear Plant Relief Request 14A L-2006-050 Page 4 The required surface examinations were performed and were not limited. In all cases, 100 percent of the code required surface area was examined. These surface examinations did not reveal any recordable or reportable flaws in accordance with the ASME Code Section Xl, 1989 Edition, No Addenda.
For Category B-F, the Class 1 dissimilar metal piping welds have carbon steel nozzles buttered with stainless steel and field welded to forged stainless steel or cast stainless steel components with stainless steel weld material. All dissimilar metal weld examinations were performed prior to the expedited implementation of Appendix Vil, Supplements 10 (November 22, 2002). The ultrasonic testing (UT) techniques for each weld were reviewed to determine if additional coverage could have been achieved. FPL's procedures require the examiner to consider whether additional coverage is necessary and practical. Those alternate techniques were investigated at the time of discovery. The alternate techniques considered were extending the calibration distance and/or using additional beam angles or modes. This has often provided the additional coverage needed to avoid relief. Using additional UT techniques on the weld examination areas in this relief request would have provided little or no additional coverage. The coverage obtained was the maximum practical.
FPL performed the examinations to the extent possible. Operations personnel and system engineers perform walk downs of every system on a periodic basis looking for leakage or other abnormal conditions. Surface and volumetric examinations performed, along with the required system pressure tests, provide reasonable assurance of an acceptable level of quality and safety.
10 CFR 50.55a(g)(4) recognizes that throughout the service life of a nuclear power facility, components, which are classified as ASME Code Class 1, Class 2, and Class 3, must meet the requirements set forth in the ASME Code to the extent practical within the limitations of design, geometry and materials of construction of the components.
The extent of examination volume achieved ultrasonically and the alternate scans performed (reference Table 1) coupled with the system pressure tests provide assurance of an acceptable level of quality and safety.
- 7. Duration of Proposed Altemative Third Inservice Inspection Interval February 22, 1994 to February 21, 2004
- 8. References 10 CFR 50.55a ASME Section Xl, Rules For In-service Inspection of Nuclear Power Plant Components, 1989 Edition, No Addenda.
ASME Section Xl, Division 1, Code Case N-460, Alternative Examination coverage for Class 1 and Class 2 Welds, Section Xl, Division 1.
ASME Section Xl, Rules For In-service Inspection of Nuclear Power Plant Components, 1995 Edition, 1996 Addenda
Turkey Point Nuclear Plant Relief Request 14A L-2006-050 Page 5 Exam Category B-D Inlet Nozzle to Item No. B3.140 Inservice examination limited by welded pads, Inner Radius 3-SGA-I-IRS 2003 1 supports, insulation pins, and Inner Radius Fig. IWB-2500-7(D) 70% Coveraae Achieved configuration.
Outlet Nozzle Exam Category B-D Inservice examination limited by welded pads, To Inner 3-SGA-O-IRS 2003 Item No. B3.140 2 supports, insulation pins, and Inner Radius Radius Fig. IWB-2500-7(D) configuration.
___________70l/ Converage Inlet Nozzle Exam Category B-D Inservice examination limited by welded pads, To Inner 3-SGB-1-IRS 1994 Item No. B3.140 1 supports, insulation pins, and Inner Radius Radius Fig. IWB-2500-7(D) configuration.
70% Coverage Achieved _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
Exam Category B-D Item No. B3.140 Outlet Nozzle Fig. IWB-2500-7(D) Inservice examination limited by welded pads, To Inner 3-SGB-O-IRS 1994 70% Coverage Achieved In 2 supports, insulation pins, and Inner Radius Radius Two Circumferential configuration.
Directions Examined 1994 Inlet Nozzle Exam Category B-D Inservice examination limited by welded pads, To Inner 3-SGC-1-IRS 1998 I B-2 140-D FitegN. i supports, insulation pins, and Inner Radius Radius IWB-2500-7(D) 7Fig configuration.
Outlet Nozzle Exam Category B-D Inservice examination limited by welded pads, To Inner 3-SGC-O-IRS 1998 Fig. IWB-2500-7(D) 2 supports, insulation pins, and Inner Radius Radius 70% Coverage Achieved configuration.
Turkey Point Nuclear Plant Relief Request 14A L-2006-050 Page 6 Exam Category B-D Spray Nozzle Spray Nozzle- Item No. B3.140 Inservice examination limited by configuration Inner Radius 1995 3 and raised letters welded in the examination SP-03-1-IR Fig. IWB-2500-7(D) zone ExaCaegryB-70% Achieved Exam Category B-D Surge Nozzle 3-SRGN-01-lR 1994 Item No. B3.140 4 Inservice examination limited by Pressurizer Inner Radius Fig. IWB-2500-7(D) Heater Penetrations.
55% Achieved Exam Category B-F Elbow To SG 29"-RCS-1305-4 Fig. NWB 2500-8 Inservice examination limited by configuration, Now T1994 Fig. IWbow500de 5 examination is limited from the Elbow due to weld 2% From NoEle Side crown and Nozzle side due to taper.
Examined Exam Category B-F Item No.B5.70 Inservice examination limited by configuration, Nozzle 29"-RCS-1308-4 1998 47% From Elbow Side 6 examination is limited from the Elbow due to weld 0% From Nozzle Side crown and Nozzle side due to taper.
Examined Exam Category B-F SG Nozle To Fig. IWB-2500-8 Inservice examination limited by configuration, Elbo 31"-RCS-1302-5 1994 Fig. IWb-2500de 7 examination is limited from the Elbow due to weld 0% From Noble Side crown and Nozzle side due to taper.
Examined
Turkey Point Nuclear Plant Relief Request 14A L-2006-050 Page 7 Item No. B5.70 SG Nozzle To Fig. IWB-2500-8 Inservice examination limited by configuration, 31"-RCS-1303-5 1998 8 examination is limited from the Elbow due to weld Elbow 62% From Elbow Side 0% From Nozzle Side crown and Nozzle side due to taper.
Examined w 4"-RC-1304-18 I I Exam Category B-J Item No- l91 l Inservice examination limited by configuration, Lw ee-120) Fig. IWB2500-8 examination is limited trom Elbow and Tee side 82% CRV Achieved due to radius.
4"-RC-1304-20 Exam Tee To Tee 4"-120 1995 Item Category No. B9.11B-J 9 Inservice examination examination limited is limited from by sides both configuration, of the Tee (4"-120) 195Fig. IWB-2500-8siedetrau.
82% CRVsiedetrau.
Exam Category B-J Branch 4"-RC-1305-1 Item No. B9.11 Inservice examination limited by configuration, Connection (4"5120 1998 Fig. IWB-2500-8 10 examination is limited from Elbow due to weld To Elbow -1) 87% From Branch Conn. Side crown and Branch Connection side.
81 % From Elbow Side Exam Category B-J
.. Item No. B9.11 Inservice examination limited by configuration, ValveT8-RHR-13013 1998 Fig. IWB-2500-8 11 examination is complete from Elbow side and (8-1) 100% From Elbow Side limited from Valve side due to taper.
39% From Valve Side
Turkey Point Nuclear Plant Relief Request 14A L-2006-050 Page 8 8"-RHR-1304-8 Item No. B9.11 Inservice examination limited by configuration, Pipe To Tee 1998 Fig. IWB-2500-8 12 examination is limited from Pipe side due to weld (8"-120) 67% From Pipe Side crown and Tee side due to radius.
55% From Tee Side Exam Category B-J Item No. B9.11 PieTie 8"-RHR-1305-2A I ; 'U IlAIAA n I~ nInarie svanatio limited hy eennfinurw,,tion, Pipe To Pipe (8"-120) 1998 70% From Upstream Pipe 13 examination is limited from upstream and Side downstream Pipe side due to weld crown.
70% From Downstream Pipe Side Exam Category B-J Item No. B9.11 Inservice examination limited by configuration, Pipe To Tee 8"-RHR-1305-3 1998 Fig. IWB-2500-8 14 examination is limited from Pipe side due to weld (8"-120) 67% From Pipe Side crown and Tee side due to radius.
99% From Tee Side Exam Category B-J Item No. B9.11 Inservice examination limited by configuration, Elbow to 10"-SI-1302-1 1994 Fig. IWB-2500-8 examination is complete from Elbow side and Connection (10"-140) 100% From Elbow Side 15 limited from Branch Connection side due to 85% From Branch taper.
Connection Side Exam Category B-J Elbow To 10"-S -1302-4 1994 ItemIWB-2500-8 Fig. No. B9.11 16 Inservice examination examination limited is limited from by configuration, Elbow side due to Valve (10"140) 85% From Elbow Side weld crown and Valve side due to taper.
_25% From Valve Side
Turkey Point Nuclear Plant Relief Request 14A L-2006-050 Page 9 Exam Category B-J Elbow To 10"-Sl-1303-11I Item No. B9.11 Inservice examination limited by configuration, Valve (10"-140) 1998 Fig. IWB-2500-8 17 examination is complete from Elbow side and 100% From Elbow Side limited from Valve side due to taper.
4% From Valve Side Exam Category B-J Inservice examination limited by configuration, PipecTo 10"..SI-1303-15 I Item No. B9.1 1 18Iexamination is complete from Pipe side and Connection (1U -14U) Pipe limited from Branch Connection side due to lFr 100% From Pipe Side tpr 66% From Branch Conn. Side aper.
Exam Category B-J ItemIWB-2500-8 No. B9.11 Inservice examination limited Branch 12"-RCS-1301-1 1994 Fig. 19 examination is complete from by configuration, Pipe side and To Pnne (12"-140) 100% From Pipe Side limited from Branch Connection side due to pe 67% From Branch taper.
Connection Side Exam Category B-J Item No. B9.11 Inservice examination limited by configuration, Pipe To Valve 14"RHR-13016 1998 Fig. IWB-2500-8 20 examination is limited from Pipe side due to weld (14"-140) 86% From Pipe Side crown and Valve side due to taper.
8% From Valve Side Exam Category B-J Item No. B9.31 Inservice examination limited by configuration, 10" ranc Fi. IW-250-10examination is complete from Branch Connection Connection 27.5"-RCS-1306-4 1995 100% From Branch Conn. 21 side and limited from Main Loop Piping side due 0% From Main Loop Piping Side
Turkey Point Nuclear Plant Relief Request 14A L-2006-050 Page 10 Exam Category B-J Item No. B9.11 Inservice examination limited by configuration, Pump To Pipe I 27.5"-RCS-1306-11 1994 Fig. IWB-2500-8 22 examination is complete from Pipe side and 0% From Pump Side limited from Pump side due to taper.
100% From Pipe Side Exam Category B-J Item No. 69.31I. . .
Pin 1XAIP.91flA.n1n Inservice examination limited by configuration, i0t Branch 190nn. 21 examination is complete from Branch Connection Connection 27.5-RCS-1307-2 1995 100% From Branch side and limited from Main Loop Piping side due Side to taper.
0% From Main Loop Pipetoapr Side Exam Category B-J item No. B9.31 Inservice examination limited by configuration, 10" Branch Fig IWB-2500-10 examination is complete from Branch Connection Connection 27.5"-RCS-1309-3 1995 100% From Branch Conn. 21 side and limited from Main Loop Piping side due Side 0% From Main Loop Piping to taper.
______ ~Side_ _ _
Exam Category B-J Item No. B9.11 Inservice examination limited by configuration, Pump To Pipe 27.5"-RCS-1309-11 1998 Fig. IWB-2500-8 23 examination is limited from Pump side due to 0% From Pump Side taper and Pipe side due to weld crown.
87% From Pipe Side I_ I_
Turkey Point Nuclear Plant Relief Request 14A L-2006-050 Page 11 Exam Category B-J Item No. B9.31 Fig. IWB-2500-10 Inservice examination limited by configuration, 12" Branch examination is complete from Branch Connection 29"-RCS-1305-BC3 1995 100% From Branch Conn. 24 Connection side and limited from Main Loop Piping side due Side 0% From Main Loop Piping to taper.
Side Item No. B9.31 Fig.IWBm-No00-1 Inservice examination limited by configuration, 14" Branch Fi.IB20-0examination is complete from Branch Connection Connection 29"-RCS-1308-BC-1 1995 100% From Branch Conn. 25 side and limited from Main Loop Piping side due Sidetotpr 0% From Main Loop Piping to taper.
Side Exam Category B-J Elbow To 31"-RCS-1302-10 Item No. B9.11 Inservice examination limited by configuration, 1994 Fig. IWB-2500-8 26 examination is limited from Elbow due to weld ump66% From Elbow Side crown and Pump side due to taper.
0% From Pump Side Exam Category B-J Elbow To Item No. B9.11 Inservice examination limited by configuration, Pump 31"-RCS-1303-10 1998 Fig. IWB-2500-8 26 examination is limited from Elbow due to weld 56% From Elbow Side crown and Pump side due to taper.
0% From Pump Side
Turkey Point Nuclear Plant Relief Request 14A L-2006-050 Page 12 Exam Category B-J Item No. B9.11 Inservice examination limited by configuration, Pipe To Elbow 31"-RCS-1303-7 1998 Fig. IWB-2500-8 27 examination is limited from Pipe and Elbow side 79% From Pipe Side due to weld crown.
52% From Elbow Side Head To Shell IItem 3-RHE-AI 1997 IExam Category C-A Fin No. C1.20 iWC-2500-1 95% From Head Side 28 nservice examination limited by configuration, examination is limited side due to support from the integral Head andwelded attachment, attachments and nozzle reinforcement plate.
Shell 57% From Shell Side Exam Category C-A Inservice examination limited by configuration, Shell To 3RH 1997 Item No. C1.10 29 examination is limited from the Shell and Flange Flange -E-A2 Fig. WC-25001 29 side due to support integral attachment, welded 71% From Shell Side attachmentsandnozzlereinforcementplate.
100% From Flange Side Exam Category C-F-1 Inservice examination limited by configuration, Flange To 3"-Sl-2301-1 Item No. C5.21 examination performed with Appendix VIII Elow 3 -80) - 2001 Fig. IWC-2500-7(a) 30 demonstrated procedure, examination complete Eb (3-8) 100% From Elbow Side from Elbow side only and no exam performed 0% From Flange Side from the Flange side due to taper.
Exam Category C-F-1 Inservice examination limited by configuration,
,-SI-2301-4 Item No. C5.21 examination performed with Appendix VIII Pipe To Valve 3--80) 2001 Fig. IWC-2500-7(a) 31 demonstrated procedure, examination complete (3"-80) 100% From Pipe Side from Pipe side and no exam performed from the 0% From Valve Side Valve side due to taper.
Turkey Point Nuclear Plant Relief Request 14A L-2006-050 Page 13 I L^61I I y7~,UI - I Reducer To 8"-SI-2303-1 Item No. C5.11 Inservice examination limited by configuration, Pipe (8"-120) 1998 Fig. IWC-2500-7(a) 32 examination is limited from the Pipe side due to 62% From Pipe Side weld crown and Reducer side due to taper.
50% From Reducer Side Exam Category C-F-1 10"-Sl 2304 3 Item No. C5.11 Inservice examination limited by configuration, Valve To Pipe 1998 Fia. lWC-2500-7(a) 33 examination is limited from the Pine side due to (U -14U) 91% From Pipe Side weld crown and Valve side due to taper.
8% From Valve Side Exam Category C-F-1 Vl Item No. C5.11 Inservice examination limited by configuration, ve To 14-RHR-2301-1 1995 Fig. IWC-2500-7(a) 34 examination is limited from the Valve side due to Elbow (14"-40) 84% From Valve Side taper and Elbow side due to weld crown.
94% From Elbow Side Exam Category C-F-2 Inservice examination limited by configuration, 6"-BDC-2303-6 Item No. C5.51 examination performed with Appendix VIII Valve to Pipe 2003 Fig. IWC-2500-7(a) 35 demonstrated procedure, examination complete (6"-160) 0% From Valve Side from Pipe side and no exam performed from the
_ 100% From Pipe Side Valve side due to taper.
Turkey Point Nuclear Plant Relief Request 14A L-200)6-050 Page 14 I .:.:.. .......ET .::: - SGA-I-INRS TPCAI:
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Turkey Point Nuclear Plant Relief Request 14A L-2006-050 Page 18 4'..1.... ........ . ..... .. ... ...
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-I Turkey Point Nuclear Plant Relief Request 14A L-2006-050 Attachment 2 Page 19
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Turkey Point Nuclear Plant Relief Request 14A L-20C6-050 Page 20 6r-RHR-1 305-2A (TYPICAL)
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Turkey Point Nuclear Plant Relief Request 14A L-200)6-050 Page 21 1O"-SI-13024 (TYPICAL)
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Turkey Point Nuclear Plant Relief Request 14A L-2006-050 Attachment 2 Page 24 2g~C$13O~8-1(TY'PCAL)
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-U Turkey Point Nuclear Plant Relief Request 14A L-2006-050 Attachment 2 Page 25 3-RHE-A1 I t lteed.~ e wj4, nor'.
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Turkey Point Nuclear Plant Relief Request 14A L-2006-050 Page 26
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Turkey Point Nuclear Plant Relief Request 14A L-20}06-050 Page 27
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Turkey Point Nuclear Plant Relief Request 15A L-2006-050 Page 1 Relief Request In Accordance with 10 CFR5O.55a(g)(5)(iii)
--Inservice Inspection Impracticality--
- 1. ASME Code Component(s) Affected Class 1 inner radius in vessels Class 1 and 2 pressure retaining welds in vessel and piping
- 2. Applicable Code Edition and Addenda The American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Rules for Inservice Inspection of Nuclear Power Plant Components, Section Xl, 1989 Edition, No Addenda.
- 3. Applicable Code Requirement Essentially 100% volumetric examination of the nozzle B-D B3.140 inner radius.
B-F B5.70 Essentially 100% volumetric and surface examination of Circumferential welds for >4" nominal pipe size.
B-J B9. 1 Essentially 100% volumetric and surface examination of C~ircumferential welds for >4" nominal pipe size.
B-J B9.31 Essentially 100% volumetric and surface examination of branch pipe connections NPS 4 or larger.
C-A C1.10 Essentially 100% volumetric examination of the weld C1.20 length.
C-B C2.21 Essentially 100% volumetric and surface examination of the nozzle to vessel welds.
C-F-IC5. 11 Essentially 100% volumetric and surface examination of Circumferential welds for >4" nominal pipe size.
Essentially 100% volumetric and surface examination of C-F-i C5.21 Circumferential welds for > 1/5" nominal pipe size.
As defined by ASME Code Case N-460, essentially 100% means more than 90% of the examination volume of each weld where reduction in coverage is due to interference by another component or part geometry.
mm Turkey Point Nuclear Plant Relief Request 15A L-2006-050 Attachment 3 Page 2
- 4. Impracticality of Compliance Due to the configuration of the welds included within this relief request, it is impractical to meet the examination coverage requirements of -the ASME Code, Section Xl, 1989 Edition, No Addenda, as clarified by Code Case N-460. Relief is requested in accordance with 10 CFR 50.55a(g)(5)(iii). These areas were found during the third ten-year inservice inspection interval.
When a component has conditions, which limit the examination volume, Florida Power and Light is required to submit the information to the enforcement and regulatory authorities having jurisdiction at the plant site. This Relief Request has been written to address areas where those types of conditions exist and the required amount of coverage was reduced below the minimum acceptable.
When examined, the welds listed within this request did not receive the required code volume coverage due to their configuration and/or the presence of permanent attachments. These scanning limitations prohibit essentially 100% ultrasonic examination coverage of the required examination volume.
The Table 1 summarizes the percent of coverage achieved and references specific figures that show the extent of coverage. Arrows and lines on the figures illustrate the UT transducer beam direction and extent of the area examined.
Relief is requested from the ASME Boiler and Pressure Vessel Code required volume as identified in Figure IWB-2500-7,8, and 10 and IWC-2500-1, 4 and 7, as applicable.
- 5. Burden Caused By Compliance Examinations are performed to the maximum extent possible. The ultrasonic (UT) techniques for each weld were reviewed to determine if additional coverage could be achieved. If practical, physical obstructions were removed. For the welds listed within Table 1, it was not possible to remove the obstruction without significant work, increased radiation exposure, and/or damage to the plant. Additional weld preparation by welding or metal removal is a modification of the examination area requiring significant engineering and construction personnel support. Increased radiation exposure and cost would be incurred in order to perform these modifications.
Radiography is impractical due to the amount of work being performed in the areas on a 24-hour basis. This would result in numerous work-related stoppages and increased exposure due to the shutdown of and startup of other work in the areas. The water must be drained from systems where radiography is performed, increases the radiation dose rates over a much broader area than the weld being examined. There would be significant burden associated with the performance of weld or area modifications or radiography in order to increase the examination coverage.
- I Turkey Point Nuclear Plant Relief Request 15A L-2006-050 Page 3
- 6. Proposed Altemative and Basis for Use Proposed Altemative
- 1) Surface examination per category B-F, B-J, C-B, and C-F-1
- 2) Conduct ultrasonic examinations to the maximum extent possible.
- 3) Periodic system pressure tests in accordance with ASME Section Xl Category B-P, Table IWB-2500-1 and Category C-H, Table IWC-2500-1.
Basis FPL performed inservice examinations cf selected welds in accordance with the requirements of 10CF R50.55a, plant technical specifications, and the 1989 Edition, no addenda, of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section Xl. When a component has conditions, which limit the examination volume, Florida Power and Light is required to submit the information to the enforcement and regulatory authorities having jurisdiction at the plant site. This Relief Request has been written to address areas where those types of conditions exist and the required amount of coverage was reduced below the minimum acceptable.
It is not possible to obtain ultrasonic interrogation of greater than 90% of the required examination volume due to interference caused by configuration and/or permanent attachments.
Configuration, permanent attachments and/or structural interferences prohibit 100% ultrasonic examination of Code required volume. Additional ultrasonic techniques are employed where practical to achieve the code-required volume. The Table 1 summarizes the percent of coverage achieved and references specific figures that show the extent of coverage. Arrows and lines on the figures illustrate the UT transducer beam direction and extent of the area examined.
For examinations performed prior to the expedited implementation of Appendix Vill, Supplements 2 and 3 (May 22, 2000), the ultrasonic testing (UT) techniques for each weld were reviewed to determine if additional coverage could have been achieved. FPL's procedures require the examiner to consider whether additional coverage is necessary and practical. Those alternate techniques were investigated at the time of discovery. The alternate techniques considered were extending the calibration distance and/or using additional beam angles or modes. This has often provided the additional coverage needed to avoid relief. Using additional UT techniques on the weld examination areas in this relief request would have provided little or no additional coverage.
The coverage obtained was the maximum practical.
For examinations performed after the 10 CFR 50.55a required expedited implementation of Appendix VII, supplements 2 and 3 (May 22, 2000), the ultrasonic testing (UT) was performed utilizing personnel qualified and procedures demonstrated in accordance with the Performance Demonstration Initiative (PDI) program. In the cases where austenitic materials were examined (Code Category B-J and C-F-1, the credited volumetric examination of the weld required volume (WRV) is limited when access can only be obtained from one side. It should be noted that the volumetric examination was performed through 100% of the Code WRV, however, the PDI Appendix VilI procedure used is not qualified for the detection of flaws on the far side of the
Turkey Point Nuclear Plant Relief Request 15A L-2006-050 Page 4 single sided access examinations of austenitic piping welds. The techniques employed for the single sided examinations provided for a best effort examination. The coverage obtained was the maximum practical.
The required surface examinations were performed and were not limited. In all cases, 100 percent of the code required surface area was examined. These surface examinations did not reveal any recordable or reportable flaws in accordance with the ASEM Code Section Xl, 1989 Edition, No Addenda.
For Category B-F, the Class 1 dissimilar metal piping welds have carbon steel nozzles buttered with stainless steel and field welded to forged stainless steel or cast stainless steel components with stainless steel weld material. All dissimilar metal weld examinations were performed prior to the expedited implementation of Appendix Vil, Supplements 10 (November 22, 2002). The ultrasonic testing (UT) techniques for each weld were reviewed to determine if additional coverage could have been achieved. FPL's procedures require the examiner to consider whether additional coverage is necessary and practical. Those alternate techniques were investigated at the time of discovery. The alternate techniques considered were extending the calibration distance and/or using additional beam angles or modes. This has often provided the additional coverage needed to avoid relief. Using additional UT techniques on the weld examination areas in this relief request would have provided little or no additional coverage. The coverage obtained was the maximum practical.
FPL performed the examinations to the extent possible. Operations personnel and system engineers perform walk downs of every system on a periodic basis looking for leakage or other abnormal conditions. Surface and volumetric examinations performed, along with the required system pressure tests; provide reasonable assurance of an acceptable level of quality and safety.
10 CFR 50.55a(g)(4) recognizes that throughout the service life of a nuclear power facility, components, which are classified as ASMAE Code Class 1, Class 2, and Class 3, must meet the requirements set forth in the ASME Code to the extent practical within the limitations of design, geometry and materials of construction of the components.
The extent of examination volume achieved ultrasonically and the alternate scans performed (see Table 1) coupled with the system pressure tests provide assurance of an acceptable level of quality and safety.
- 7. Duration of Proposed Altemative Third Inservice Inspection Interval April 15,1994 to April 14, 2004
- 8. Refereances 10 CFR 50.55a ASME Section Xl, Rules For In-service Inspection of Nuclear Power Plant Components, 1989 Edition, No Addenda.
I Turkey Point Nuclear Plant Relief Request 15A L-2006-050 Page 5 ASME Section Xl, Division 1, Code Case N-460, Alternative Examination coverage for Class 1 and Class 2 Welds, Section Xl, Division I.
ASME Section Xl, Rules For In-service Inspection of Nuclear Power Plant Components, 1995 Edition, 1996 Addenda
Turkey Point Nuclear Plant Relief Request 15A L-2006-050 Page 6 Exam Category B-D Inservice examination limited by welded pads, Inlet Nozzle Item No. B3.140 4-SGA-1-IRS 1994 1 supports, insulation pins, and Inner Radius Inner Radius Fig. IWB -2500-7(D) 75% Coveraae configuration.
Outlet Nozzle I Exam Category B-D1 Item No. B3.140 Inservice examination limited by welded pads, Oner Ri 4-SGA-u-IRS 1994 Iteg No.-250 2 suDDorts. insulation Dins. and Inner Radius inner Raaius . .. Fg. ivvb -;e*uu-1(U) 2 .
75% Coverage configuration.
Exam Category B-D Inservice examination limited by welded pads, Inlet Nozzle 4-SGB-1-IRS 1997 Item No. B3.140 1 supports, insulation pins, and Inner Radius Inner Radius 4-SGB--IRS 1997 Fig. IWB -2500-7(D) 1 configuration.
75% Coverage Exam Category B-D Inservice examination limited by welded pads, Outlet Nozzle 4-SGB-0-IRS 1997 Item No. B3.140 2 supports, insulation pins, and Inner Radius Inner Radius Fig. IWB -2500-7(D) 75% Coverage configuration.
Exam Category B-D Inservice examination limited by welded pads, Inlet Nozzle Item No. 83.140ni eation Inner Radius 4-SGC-1-IRS 2002 Fig. IWB -2500-7(D) 1 supports, insulation pins, and Inner Radius 75% Coverage Achieved configuration.
Exam Category B-D Inservice examination limited by welded pads, Outlet Nozzle 4-SGC-0-I.RS 2002 Item No. B3.140 2 supports, insulation pins, and Inner Radius Inner Radius Fig. IWB -2500-7(D) cniuain
________75% Coverage Achieved cnIguaton
Turkey Point Nuclear Plant Relief Request 15A L-2006-050 Page 7 exam Category 5-L Inservice examination limited by configuration Spray Nozzle Item No. B3.140 Inner Radius SP-04-1-IR 2000 3 and raised letters welded in the examination Fig. IWB-2500-7(D) 70% Achieved zone Exam Category B-D Surge Nozzle 4SRGN01IR 1996 Item No. B3.140 4 Inservice examination limited by Pressurizer Inner Radius Fig. IWB-2500-7(D) Heater Penetrations.
55% Achieved Exam Category B-F Safe-End To 12"-RC-1401-9 Item No. B5.70 Inservice examination limited by configuration, Sae-nozzle (12--1401 1996 Fig. IWB-2500-8 5 examination is complete from Safe-end side and 100% From Safe-End Side limited from Nozzle side due to taper.
74% From Nozzle Side Exam Category B-F Item No. B5.70 Inservice examination limited by configuration, Nozzwo 29"-RCS-1404-4 1994 Fig. IWB-2500-8 6 examination is limited from the Elbow side due to 74% From Elbow Side weld crown and Nozzle side due to taper.
0% From Nozzle Side Exam Category B-F Elbow To SG 29"-RCS-1405-4 1997 Item No. B5.70 Inservice examination limited by configuration, Fig. IWB-2500-8 7 examination is limited from the Elbow side due to 53% From Elbow Side weld crown and Nozzle side due to taper.
10% From Nozzle Side
Turkey Point Nuclear Plant Relief Request 15A L-2006-050 Page 8 Exam Category Es-F SG Nozzle To Item No. B5.70 Inservice examination limited by configuration, 31"-RCS-1401-5 1994 Fig. IWB-2500-8 8 examination is limited from the Elbow side due to Elbow 0% From Nozzle Side weld crown and Nozzle side due to taper.
62% From Elbow Side Exam Category B-F RG Nn771P Tn Item No. B5.70 I Inservice examination limited by configuration, 31"-KU;b-14UZ-b 1Y( Fig. IWB-2500-8 9 examination is limited from the Elbow side due to ow 8% From Nozzle Side weld crown and Nozzle side due to taper.
42% From Elbow Side Exam Category B-J Valve To 8"-RHR-1401-6 Item No. B9.11 Inservice examination limited by configuration, 1996 Fig. IWB-2500-8 10 examination is complete from Elbow side and Elbow (8"-120) 20% From Valve Side limited from Valve side due to taper.
100% From Elbow Side Exam Category B-J
,,4 Item No. B9.11 Inservice examination limited by configuration, Pipe To Tee 8"-RHR-1402-4 1996 Fig. IWB-2500-8 11 examination is complete from Pipe side and 8"-120) 100% From Pipe Side limited from Tee side due to taper.
30% From Tee Side Exam Category B-J Item No. B9.11 8"-RHR-1402-7 Fig. IWB-2500-8 Inservice examination limited by configuration, Tee To Tee (8"-120) 1996 60% From Upstream Tee 12 examination is limited from both sides of the tee Side due to radius.
20% From Downstream Tee Side
Turkey Point Nuclear Plant Relief Request 15A L-2006-050 Page 9 Exam Category B-J 10"-SI-1401-14 Item No. B9.11 Inservice examination limited by configuration, Valve To Pipe 1994 Fig. IWB-2500-8 13 examination is complete from Pipe side and (10"-1 40) 26% From Valve Side limited from Valve side due to taper.
100% From Pipe Side Exam Category B-J EItem No. B9.11 Inservice examination limited by configuration, Branch 101 IV -S,4- 10 1994 tHg. iVVB-2500-8 14 examination is complete from Elbow side and Connection (10"-140) 100% From Elbow Side limited from Branch Connection side due to 18% From Branch taper.
Connection Side Exam Category B-J Valv To 10"-S1402-1 Item No. B9.11 Inservice examination limited by configuration, ve To 10"--1402 1999 Fig. IWB-2500-8 15 examination is complete from Elbow side and Elbow (10"-140) 100% From Elbow Side limited from Valve side due to taper.
26% From Valve Side Exam Category B-J
,Item No. B9.11 Inservice examination limited by configuration, Pipe To Valve 10"-SI-1402-13 1997 Fig. IWB-2500-8 17 examination is complete from Pipe side and (1 "-140) 100% From Pipe Side limited from Valve side due to taper.
23% From Valve Side Exam Category B-J Elbow TO Item No. B9.11 Inservice examination limited by configuration, Branch 10"-SI-1402-17 1997 Fig. IWB-2500-8 18 examination is complete from Elbow side and Conct (10"-140) 100% From Elbow Side limited from Branch Connection side due to 23% From Branch Conn. taper.
_Side_
Turkey Point Nuclear Plant Relief Request 15A L-2006-050 Page 10
.xatm Category b-J 10"-SI-1402-4 Item No. B9.11 Inservice examination limited by configuration, Elbow To Tee 1999 Fig. IWB-2500-8 16 examination is complete from Elbow side and (10"-140) 100% From Elbow Side limited from Tee side due to radius.
11 % From Tee Side 1ra[hExam Category B-J Branch To 1 No.
FIgem WB9.11 IInservire examination limited by configuration, Connection To (12"' 0") 1997 36 1g. vvn-c ouu-n 19 examination is limited from Branch Connection Pipe Side and Elbow side due to taper.
86% From Pipe Side Exam Category B-J Branch Item No. B9.11 Inservice examination limited by configuration, Connection To 14"-RHR-1401-1 1994 Fig. IWB-2500-8 20 examination is limited from Branch Connection Elbow~ (14"-140) 70% From Branch Conn. adEbwsd u otpr Elbow ~~~~~~~Side adEbwsd u otpr 35% From Elbow Side Exam Category B-J 14"-RHR-1401-5 Item No. B9.11 Inservice examination limited by configuration, Pipe To Valve (14";40 1994 Fig. IWB-2500-8 21 examination is complete from Pipe side and (1-1) 100% From Pipe Side limited from Valve side due to taper.
0% From Valve Side Exam Category B-J 14"-RHR-1401-6 Item No. B9.11 Inservice examination limited by configuration, Valve To Pipe 14" 140) 1994 Fig. IWB-2500-8 22 examination is complete from Pipe side and 0% From Valve Side limited from Valve side due to taper.
100% From Pipe Side
Turkey Point Nuclear Plant Relief Request 15A L-2006-050 Page 11 Exam Category B-J 14"-RHR-1401-9 Item No. B9.11 Inservice examination limited by configuration, Elbow To Pipe 1994 Fig. IWB-2500-8 23 examination is limited from Pipe side and Elbow (14"-140) 54% From Elbow Side side due to weld crown.
53% From Pipe Side Exam Category B-J Item No. B9.11 Inservice examination limited by configuration, Pump 2To5 s 1997 FnI" i'veB Sidg 25 examination is complete from Pipe side and 0% From Pump Side limited from Pump side due to taper.
100% From Pipe Side Exam Category B-J Item No. B9.31 Inservice examination limited by configuration, 10" Branch 27.5"-RCS-1406- Fig. IWB-2500-10 examination is complete from Branch Connection Connection 18 1994 100% From Branch Conn. 24 side and limited from Main Loop Piping side due Sidetotpr 0% From Main Loop Piping to taper.
Side Exam Category B-J 27.5"-RCS-1407- Item No. B9.11 Inservice examination limited by configuration, Pump To Pipe 2 1 1994 Fig. IWB-2500-8 26 examination is limited from Pump due to taper 118% From Pump Side and Pipe side due to instrumentation line.
41% From Pipe Side
Turkey Point Nuclear Plant Relief Request 15A L-2006-050 Page 12 Exam Category B-J Item No. 89.31 Inservice examination limited by configuration, Fig. IWB-2500-10 10" Branch 27.5"-RCS-1407- examination is complete from Branch Connection 1994 100% From Branch Conn. 24 Connection 20 side and limited from Main Loop Piping side due Side 0% From Main Loop Piping to taper.
Side 1 xam Category B-J Item No. B9.31 Inservice examination limited by configuration, 4" Branch 27.5"-RCS-1409- Fig. IWB-2500-10 examination is complete from Branch Connection Connection 16 1994 100% From Branch Conn. 27 side and limited from Main Loop Piping side due Sidetotpr 0% From Main Loop Piping to taper.
Side Exam Category B-J Item No. B9.31 Inservice examination limited by configuration, 10" Branch 27.5"-RCS-1409- Fig. IWB-2500-10 24 examination is complete from Branch Connection Connection 17 1994 100% From Branch Conn. side and limited from Main Loop Piping side due Side to taper.
0% From Main Loop Piping Exam Category B-J Item No. B9.31 Inservice examination limited by configuration, 14" Branch 29"-RCS-1404- 1994 Fig. IWB 28 examination is complete from Branch Connection Connection 18 1 rom rac . side and limited from Main Loop Piping side due 0% From Main Loop Piping to taper.
Side
Turkey Point Nuclear Plant Relief Request 15A L-2006-050 Page 13 Exam Gategory B-J Item No. B9.31 12" Branch 29"-RCS-1405- Fig. IWB-2500-10 Inservice examination limited by configuration, Connection 21 1994 75% From Branch Conn. 29 examination is limited from Branch and Main Side Loop Piping side due to taper.
0% From Main Loop Piping Side l Exam Category B-J Elb T 31"-RCS-1401 Item No. 9.11 Inservice examination limited by configuration, Pmow o0 1994 Fig. IWB-2500-8 31 examination is limited from the Elbow due to weld Pump 10 57% From Elbow Side crown and taper and Pump side due to taper.
0% From Pump Side Exam Category B-J Item No. B9.11 Inservice examination limited by configuration, Elbow To Pipe 31"-RCS-1401-8 1994 Fig. IWB-2500-8 30 examination is limited from Elbow due to taper 64% From Elbow Side and Pipe side due to weld crown.
88% From Pipe Side Exam Category C-A Inservice examination limited by configuration, Item No. C1 .20 examination is limited from the Head and Shell Head To Shell 4-RHE-Al 1996 Fig. IWC-2500-1 32 side due to support integral attachment, welded 79% From Head Side attachments and nozzle reinforcement plate.
______________ From Shell Side_____________________
~~~~~52%
Exam Category C-A Inservice examination limited by configuration, Shell To 4REA196Item No. C1.10 33 examination is limited from the Shell and Flange Flange 4-RHE-A2 1996 Fig. IWC25001 33 side due to support integral attachment, welded 70%From Flange Side attachments and nozzle reinforcement plate.
Turkey Point Nuclear Plant Relief Request 15A L-2006-050 Page 14 Exam Category C-A Nozzle To Item No. C2.21 Inservice examination limited by configuration, 4-RHE-All 1996 Fig. IWC-2500-4(a) 34 examination is limited from Nozzle side due to Shell 99% From Nozzle Side taper and Shell side due to weld crown.
41% From Shell Side Exam Category C-F-IInservice examination limited by configuration, rid'llv A A Item No. C5.21 examination Derformed with ADDendix Vill ElbTow (W-8240, 1 2002 '%From Flange Side 35 demonstrated procedure, examination is Elbow (3"-80) 0% From Flange Side complete from Elbow side and limited from 100% From Elbow Side Flange side due to taper.
Examined 2002 Exam Category C-F-1 Inservice examination limited by configuration, "Item No. C5.11 examination performed with Appendix VIII Pipe To Valve 8-S124037 2002 Fig. IWC-2500-7(a) 36 demonstrated procedure, examination complete 8 -12) 100% From Pipe Side from Pipe side and limited from Valve side due to 0% From Valve Side taper.
Exam Category C-F-1 Inservice examination limited by configuration, Item No. C5.11 examination performed with Appendix VilI Pipe To Valve 8"-SI-2404-2 1999 Fig. IWC-2500-7(a) 37 demonstrated procedure, examination is (8"-120) 100% From Pipe Side complete from Pipe side and limited from Valve 45% From Valve Side side due to taper.
Exam Category C-F-1 Inservice examination limited by configuration, 8"-SI-2407-8 Item No. C5.11 examination performed with Appendix VilI Tee To Pipe 8"-120) 1999 Fig. IWC-2500-7(a) 38 demonstrated procedure, examination is (8"-120) 75% From Tee Side complete from Pipe side and limited from Tee 100% From Pipe Side side due to radius.
Turkey Point Nuclear Plant Relief Request 15A L-2006-050 Page 15 L CAII I /L~ JI ) N.- I - I 10"-SI-2407-4 Item No. C5.11 Inservice examination limited by configuration, Pipe To Valve 1999 Fig. IWC-2500-7(a) 39 examination is complete from Pipe side and (10"-140) 100% From Pipe Side limited from Valve side due to taper.
15% From Valve Side Exam Category C-F-1 l Item No. C5.11 Inservice examination limited by configuration, Valve To 1 O"-S-2407-5 19U9 iig. iVVC-2500-7(a) 4u examination is complete from Eibow side and Elbow (10 -140) 35% From Valve Side limited from Valve side due to taper.
100% From Elbow Side Exam Category C-F-1 12"-RHR-2402- Item No. C5.11 Inservice examination limited by configuration, Pipe To Flange 15 1996 Fig. IWC-2500-7(a) 41 examination is limited from Pipe side due to weld (12"-40) 27% From Pipe Side crown and Flange side due to taper.
70% From Flange Side Exam Category C-F-1 Item No. C5.11 Fig. IWC-2500-7(a) Inservice examination limited by configuration, Tee To Tee 14"-RHR24031 1996 78% From Upstream Tee 42 examination is limited from the both sides of the (14"-40) Side Tee due to the radius.
56% From Downstream Tee Side Exam Category C-F-1 143-RHR-2403-2 Item No. C5.11 Inservice examination limited by configuration, Tee To Pipe 14"-40) 1996 Fig. IWC-2500-7(a) 43 examination is complete from Pipe side and (14"-40) 78% From Tee Side limited from Tee side due to the radius.
100% From Pipe Side
Turkey Point Nuclear Plant Relief Request 15A L-2006-050 Page 16 Exam Category C-F-1 Item No. C5.11 Inservice examination limited by configuration, Elbow To 14"-RHR-2403-4 1996 Fig. IWC-2500-7(a) 44 examination is limited from Elbow side due to Valve (14"-40) 36% From Elbow Side weld crown and Valve side due to taper.
73% From Valve Side
Turkey Point Nuclear Plant Relief Request 15A L-2006-050 Page 17 STEAM GENERATOR TO NOZZLE .......... -...
TRANSITIN AREA .........- -2X2) W INISMLATI.ON
. .. ..... . .. .. . . RACKETS LOCATED AT e0.
.. .... ^'i---
- E 'i1 3. 2216i 27Q Ar3D ns1 f .......
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. s.:'DkES DEGREES
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- 1
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- 4-SGAI-IRS (TYPICAL) 18" OF SCANAREA IS . . ..- S --
LIMITED DUE TO CLOSE :-4-, G -IRS
- PROXIMIlTY OF STEAM - i -i:--
GENERATOR SUPPORT .......
LOCATED AT 90 :
DEGREES Figure 1
................. - (2 X A 2- INSULATION BRACKETS.
LOCATED AT45.,90,412,150 AN0202
-. DEGREES 18SOFSCANAREA . .... .. '. .
I LIMITED DUE TO ' /.N CLOSEPRoXiMiT 4 ,f ,- '
OFSTEAM \ - (y -
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LOCGATWDAT1O8l DEGREES ..... 44SA3GA-0 IRS (TYPICAL)
- .. . ..-- 4-$G-.0-.IRS 4-SGG-Q_-lIRS
' ~~~~~~~~ . . . E..g:. . . : E i E : : .............................
-_ NOZ=LE TO STEAM
- :GENERATOR TRANSITION AREA Figure 2
Turkey Point Nuclear Plant Relief Request 15A L-2006-050 Page 18 Figure 3
Turkey Point Nuclear Plant Relief Request 15A L-2006-050 Page 19 Figure 4
-W .
PRESSURIZER SURGE NJOZZLE.
4-isEGN-.01-1R:
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Turkey Point Nuclear Plant Relief Request 15A L-2006-050 Page 20 29"-RCS4 4044 (TYPICAL)
Figure 6 29"- RCS-1 405-4 (TYPICAL)
-- X-. -. re. . ..... ..iEE NO-ZZLE X -ELBOW -
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Turkey Point Nuclear Plant Relief Request 15A L-2006-050 Page 21 31`-RC$-1401-55 (TYPICAL)
NOZZLE ELBOW Figure 8 31 0-RGS-1402-5 (TYPICAL)
NOZZLE --/
/ : ELBOW
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Figure 9
Turkey Point Nuclear Plant Relief Request 15A L-2006-050 ,Page 22 8"1-RHR-44G1-6 (TYPICAL)
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Turkey Point Nuclear Plant Relief Request 15A L-2006-050 Page 23 8Vt-RHR-4 402i 7 (TYPICAL)
AREA 2.
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Figure 12
Turkey Point Nuclear Plant Relief Request 15A L-2006-050 1Page 24 jur-%-14011-14 :(TYIPICAfL)
~~~~~~......- ';.'.- ::-':. l
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Turkey Point Nuclear Plant Relief Request 15A L-2006-050 Page 25 I 0Y'-SI-142-4 (TYfPICAL)
- -:-.-. -.-E-:-.:.
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Turkey Point Nuclear Plant Relief Request 15A L-2006-050 Page 26 12^RC 1401-1 (TYPIQA.L)
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Turkey Point Nuclear Plant Relief Request 15A L-2006-050 Page 27 14-F-RHR-1401-6 (TYPICAL)...........
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27.5"'-RCS-1 408-18 (TYPICAL) 2T5T-ROS-1 407-20 27f5'-RCS-1, 409-17 MAIN LOOP PIPING Figure 24 BRANCH CONNSECOTION
Turkey Point Nuclear Plant Relief Request 15A L-2006-050 Attachment S Page 28
....-.. .. ..-.. .:.-.. . -.. ...EE 27.5'-RCS-1406-1 1 (TYPICAL)
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Turkey Point Nuclear Plant Relief Request 15A L-2006-050 Page 29 291-RCS-1404-18 (TYPICAL)
.. ... r-....-..i. . ,m
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- CONNECTION Figure 28
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. ' 'l'"'-X0' i BRANCH Figure 29 0 ~ ~ ........~ ~ .. .. . ...- ..... . .X/ , , , NNECTION
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Turkey Point Nuclear Plant Relief Request 15A L-2006-050 Page 30 31 !-RCS1.401 -10 PU P -.-.,'.-,' --. ELBOW '
Figure 31 / - -: i 4-RHEA1-
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