ML20133B728
| ML20133B728 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 12/31/1996 |
| From: | NEBRASKA PUBLIC POWER DISTRICT |
| To: | |
| Shared Package | |
| ML20133B722 | List: |
| References | |
| NUDOCS 9701060115 | |
| Download: ML20133B728 (61) | |
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Attachment 2
. to NLS960234 60 Pages Total l
THIRD TEN-YEAR INTERVAL INSERVICE INSPECTION PROGRAM FOR COOPER NUCLEAR STATION l REVISION 1.1 l
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NEBRASKA PUBLIC POWER DISTRICT i
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i 9701060115 961231 PDR ADOCK 05000298 0 PDR ,,
l Cooper Station 3rd Interval Inservice Inspection Program 2.0 REVISION
SUMMARY
SHEET '
Section Effective Page(s) Revision Date 1 Revised 1.1 12/04/96 2 Revised 1.1 12/04/96 3 Revised page 3-2 to delete Code Case N-435-1 1.1 12/04/96 4 Initial Issue 0 10/18/95 5 Added new relief requests 1.1 12/04/96 6 Revised CT-1 & 4 in response to NRC comments 1 3/01/96 7 Revised RI-02, RI-14, and RI-23, corrected typos in RI- 1.1 12/04/96 19 thru 22, and added RI-24.
8 Initial Issue 0 10/18/95 9 Revised PT-03. 1.1 12/04/96 10 Revised PR-02and PR-05 1.1 12/04/96 11 Revised Section 11.1 to delete references 5 & 6. 1.1 12/04/96 Revised Section 11.2 to add BWRVIP-18. Revised Section 11.4 to remove non-safety related RWCU welds. Revised Section 11.8 to add BWRVIP-18.
Revised 11.13 to delete Jet Pump Adjusting Screw.
Revised Section 11.15 regarding Core Shroud reinspection. Revised 11.16 for clarification. Revised 11.18 for reinspection of 90 degree aligner pin assembly. Removed 11.20. Added 11.21 for Jet Pump Adjusting Screw.
12 Initial Issue 0 10/18/95 13 Revised to add component drawings 1 3/01/96 -
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'14 I Initial Issue 0 10/18/95 -
l 15 Initial Issue 0 10/18/95 16 Updated Tables to reflect the above listed changes 1.1 12/04/96 17 Initial Issue 0 10/18/95 t
(2-1) Revision 1.1
l Cooper Station 3rd Interval '
Inservice Inspection Program 3.2.3.3 Inservice pressure testing for Class 1, 2 and 3 components will be performed in accordance with ASME Section XI Code Case N-498-1. .
This Code Case has not been generically approved for use in USNRC Regulatory Guide 1.147 but is included in Section 10 of this ISI Program as Relief Request No. PR-07.
3.2.3.4 The Scram Discharge Volume is considered as Class 2 piping for examination purposes, but is pressure tested with the reactor coolant pressure boundary piping each refueling outage in accordance with
. GL 86-01.
3.2.3.5 An ISI Program per Subsections IWE and IWL is not included in this j submittal. These subsections of Section XI are currently not invoked l by 10CFR50.55a.
3.2.3.6 The Program _ for inservice testing of pumps and valves per l- Subsections IWP and IWV is not part of this ISI Program and will be -
issued as a separate submittal.
3.2.3.7 As allowed by 10CFR50.55a(c)(3) and USNRC Regulatory Guide ,
1.147, Revision 11, certain ASME Section XI Code Cases have been i determined acceptable . for application to ISI Programs. The ,
following Code Cases are being adopted by CNS and incorporated in j the 3rd interval ISI Program. The use of Code Cases not currently i identified in Regulatory Guide 1 147 is addressed as relief requests in Sections 7 and 10.
Case N-307 Revised Ultrasonic Examination Volume for Class 1 Bolting, Table IWB-2500-1,' Examination Category B-G-1, When Examinations Are Conducted From the Center Drilled Hole.
Case N-408 Alternative Rules for Examination of Class 2 Piping.
CaseN-416 - Alternative Rules for Hydrostatic Testing of Repair or
. .Replaccinent of Class 2 Piping.
1 Case N-457 - Qualification Specification Notch Location for -
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Ultrasonic Examination of Bolts and Studs.
Case N-458 - Magnetic Particle Examination of Coated Materials.
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Case N-460 - Alternative Examination Coverage for Class 1 and 2
- Welds.
(3-2) Revision 1.1
i Cooper Station 3rd Interval Inservice Inspection Program !
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5.0 INSERVICE INSPECTION
SUMMARY
TABLE -
Examination Item Description Number of Exam Technical Position or Category Number Components Requirements Relief Request I Bl.11 Circumferential Shell Welds 4 Volumetric dT-01, RI-06, RI-09, RI-II Bl.12 Iongitudinal Shell Welds 12 Volumetric- CT-01, RI-06, RI-09. RI-II Bl.21 Circumferdntial llead Welds 3 Volumetric CT-01, RI-06, RI-09, RI-l1 '
B-A Bl.22 Meridional Head Welds 22 Volumetric' CT-01, RI-06, RI-09, RI-l1 Bl.30 Shell-to-Flange Weld 1 Volumetric RI-09, RI-l1 Bl.40 Head-to-Flange Weld 1 Volumetric & RI-09, RI-I1 Surface B3.90 Nozzle-to-Vessel Welds in Reactor Vessel 28 Volumetric RI-09, RI-I1, RI-19. RI-21 B-D B3.100 Nozzle Inside Radius Section 28 Volumetric RI-03, RI-09. RI-I1, RI-21 in Reactor Vessel B4.11 Partial Penetration 1 Visual, VT-2 Vessel Nozzle Welds B-E B4.12 Partial Penetration 137 Visual, VT-2 Control Rod Drive Nozzle Welds B4.13 Partial Penetration 49 Visual, VT-2 Instrumentation Nozzle Welds :
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(5-1) -
Revision 1.1
Cooper Station 3rd Intefval Inservice Inspection Program 5,0 INSERVICE INSPECTION
SUMMARY
TABLE Examination item Description Number of Exam Technical Po ition or Category Number Components Requirements Relief Request B5.10 Dissimilar Metal Nozzle-to-Safe End Butt Welds 17 Volumetric & RI-02, RI-08, RI-09, RI-12 B-F NPS 4 or larger Surface B5.20 Dissimilar Metal Nozzle-to-Safe End Butt Welds O Surface Less than NPS 4 B5.130 Dissimilai Metal Butt Welds in Piping 5 Volumetric & RI-02, RI-08 RI-09, RI-12, RI-20 NPS 4 or Larger Surface B5.140 Dissimilar Metal Butt Welds in Piping 1 Surface Less than NPS 4
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B5.150 Dissimilar Metal Socket Welds in Piping 0 Surface B6.10 Reactor Vessel Closure Head Nuts 52 Surface RI-16, RI-24 B5.20 Reactor Vessel Closure Studs, in Place 48 Volumetric RI-09, RI-24 B6.30 Reactor Vessel Closure Studs, when Removed 4 Volumetric & RI-09 Surface B-G-l' B6.40 Threads in Reactor Vessel Flange 52 Volumetric RI-02, RI-09, RI-24 B6.50 Reactor Vessel Closure Washers, Bushings 104 Visual, VT-1 RI-24 i
B6.180 Bolts & Studs in Pumps 2 Sets Volumetric RI-09 B6.190 Flange Surface, When Connection Disassembled, in Pumps 2 sets Visual,' VT-1 B6.200 Nuts, Bushings, & Washers in Pumps 2 Sets Visual, VT-1 Note:
- 1. For B-G-1 and B-G-2 botting examination is limited to components selected for examination under Categories B.J. B-1 2 and B-M-2. .
i i (5-2) Revision 1.1 '
I Cooper Station 3rd Interval i Inservice Inspection Program ;
5.0 INSERVICE INSPECTION
SUMMARY
TABLE Examination Item Description Number of Exam Technical Position or Category Number Components Requirements Relief Request B7.10 Bolts, Studs, & Nuts in Vessels 3 Sets Visual, VT-1 B-G-2' B7.50 Bolts, Studs, & Nuts in Piping 13 Sets Visual, VT-1 B7.70 Bolts, Studs, & Nuts in Valves 48 Sets Visual, VT-1 B7.80 Bolts, Studs, & Nuts in CRD Housings 137 Sets Visual, VT-1 B-H B8.10 Integrally Welded Attachments to Reactor Vessel 5 Volumetric or RI-07 RI-09 Surface ,
B9.11 Circumferential Welds in Piping 369 Volumetric & RI-02, RI-08. RI-09. RI-12 NPS 4 or Larger Surface B9.12 Iengitudinal Welds in Piping N/A Volumetric & RI-02, RI-09 RI-12 :
NPS 4 or Larger Code Case 524 Surface B-J B9.21 Circumferential Welds in Piping 52 , Surface Less than NPS 4 B9.31 Branch Pipe Connection Welds 16 Volumetric & RI-02, RI-08 RI-09 RI-22 .
NPS 4 or Larger Surface ,
B9.32 Branch Pipe Connection Welds 2 Surface.,
12ss than NPS 4 i
B9.40 Socket Welds 109 Surface Note: I
- 1. For B-G-1 and B-G-2 bolting examination is limited to comporents selected for examination under Categories B-J, B-1-2 and B-M-2.
i (5-3) Revision 1,1 !
Cooper Station 3rd Interval Inservice Inspection Program -
5.0 INSERVICE INSPECTION
SUMMARY
TABLE Examination Item Description Number of Exam Technical Position or i Category Number Components Requirements Relief Request i
B10.10 Ia", rally Welded Attaclunents to Pressure Vessels 0 Volumet-ic or RI-09,RI-14, RI-17 !
Surlace B-K-1 B10.20 Integrally Welded Attachments to Piping 66 Volumetric or RI-09,RI-14, RI-17 ,
Surface ;
(Code Case 509)
B10.30 Integrally Welded Attachments to Pumps 6 Volumetric or RI-09,RI-14. RI-17 l Surface l B10.40 Integrally Welded Attachments to Valves 0 Voluinetric or RI-09. RI-14 Surface i B-1 2 B12.20 Pump Casings 2 Visual, VT-3 B-M-2 B12.50 Valve Bodies, Exceeding NPS 4 50 Visual, VT-3 B-N-1 B13.10 Vessel Interior i Visual, VT-3 ,
B13.20 Interior Attachments within Beltline Region in Reactor Vessel All Visual, VT-1 B-N-2 B13.30 Interior Attachments beyond Beltline Region in Reactor Vessel All Visual,' VT-3 i B13.40 Core Support Structure in Reactor Vessel 1 Visual, VT-3 l
B-O B14.10 Welds in CRD Housing, Peripheral CRDs 36 Volumetric or RI-09,RI-15 I Peripheral Welds Surface l C1.10 Circumferential Shell Welds 8 Volumetric RI02, RI-05, RI-09, RI-lI C-A C1.20 Circumferential Head Welds 2 Vo'lumetric RI-02, RI-09, RI-lI C1.30 Tubesheet-to-Shell Welds 0 Volumetric RI-02, RI-09. RI-11 ;
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i (5-4) ,
Revision 1.1
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Cooper Station 3rd Interval Inservice Inspection Program 5.0 INSERVICE INSPECTION
SUMMARY
TABLE Examination Item Description Number of , Exam Technical Position or Category Number Components Requirements Relief Request C2.21 Nozzle-to-Shell (or Head) Weld without Reinforcing Plates in 2 Volumetric & RI-02 RI-09,RI-I1 Vessels > 1/2" NominalThickness - Surfaw ,
C2.22 Nozzle Inner Radius 2 Volumetric RI-09. RI-I1 C-B C2.31 Reinforcing Plate Welds to Nozzle & Vessel for Nozzles with 4 Surface RI-II Reinforcing Plates in Vessels > 1/2" Nominal Thickness C2.33 Nozzle-to-Shell (or Head) Welds when Inside of Vessel is 2 Visual, VT-2 RI-I1 Inaccessible, for Vessels > 1/2* Nominal Thickness with Reinforcing Plates [
C3.10 Integrally Welded Attachments to Pressure Vessels 2 Surface RI-14 C-C C3.20 Integrally Welded Attaclunents to Piping 139 S'urface RI-14, RI-17 (Code Case 509) C3.30 Integrally Welded Attachments to Pumps 6 Surface RI-14. RI-17. RI-18 C3.40 Integrally Welded Attachments to Valves 0 Surface RI-14. RI-17 C5.11 Circumferential Welds in Austenitic Stainless Steel or High Alloy Volumetric & RI 02, RI-09 Piping a 3/8" Nominal Wall Thickness for Piping > NPS 4 0 Surface C-F-l i C5.12 Longitudinal Welds in Piping a 3/8" Nominal Wall'Ihickness for Volumetric & RI-02, RI-09, RI-12 Piping > NPS 4 0 Surface C5.41 Circumferential Welds in Austenitic Stainless Steel or High Alloy 0 Surface Pipe Branch Connections of Branch Piping > NPS 4 (Reference Table IWC-2500-1, Note 1)
Note: 1. 'Ihe number of components identified includes those welds in piping < 3/8" nominal wall thickness in accordance with Note 2 of Table IWC-2500-1, Categories C-F-1 and C-F-2.
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i (5-5) Revision 1.1
Cooper Station 3rd Interval Inservice Inspection Program 5.0 INSERVICE INSPECTION
SUMMARY
TABLE Examination Item Description Number of , Exam Technical Position or Category Number Components Requirement = Relief Request C5.51 Circumferential Welds in Carbon or low Alloy Steel Piping 967 Volumetric & RI-02, RI-09, RI-12, RI-23 2 3/8" Nominal Wall Thickness for Piping > NPS 4 Surface C5.52 lengitudinal Welds in Carbon or low Alloy Steel Piping 0 Volumetric & - RI-02, RI-09, RI-12 C-F-2' a 3/8" Nominal Wall Thickness for Piping > NPS 4 Surface C5.81 Circumferential Welds in Carbon or Low Alloy Steel Pipe Branch 4 Surface Connections of Branch Piping > NPS 4 (Reference Table IWC-2500-1, Note 1)
C-G 2 C6.10 Pressure Retaining Welds in Pump Casings 0 Stirface C6.20 Pressure Retauung Welds in Valve Bodies 16 Surface DI.10 Integrally Welded Attachments to Pressure Vessels 24 Visual, VT-3 RI-14 D-A DI.20 Integrally Welded Attachments to Piping If4 Visual, VT-3 RI-14, RI-17 (Code Case 509)
DI.30 Integrally Welded Attachments to Pumps Visual, VT-3 RI-14 DI.40 Integrally Welded Attachments to Valves 0 Visual, VT-3 RI-14 F1.10 Class I Component Supports 170 Visual, VT-3 RI-13 F-A F1.20 Class II Component Supports 382 Visual, VT-3 RI-13 (Code Case 491) F1.30 Class III Component Supports 413 Visual, VT 3 RI-13 F1.40' Supports Other Than Piping Supports (Class I,2 and 3) 57 Visttal VT-3 RI-13 Note: 1. The number of components identified includes those welds in piping < 3/8" nominal wall thickness in accordance with Note 2 of Table IWC-2500-1, Categories C-F-1 and C-F-2,
- 2. In case of multiple pumps and valves of similar design, size, function, and service in a system, the exammation of only one pump and one valve among each group of multiple pumps and valves is required.
- 3. For multiple components other than piping, within a system of similar design, function, and service, the supports of.only one of the multiple components are required to be exanuned, n
(5-6) Revision 1.1
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Cooper Station 3rd Interval Inservice Inspection Program INSERVICE INSPECTION RELIEF REQUESTS 7.0 INSERVICE INSPECTION RELIEF REQUESTS Per the requirements of 10CFR50.55a(g)(5)(iii), if a licensee determines that conformance to certain Code requirements is impracticable for the facility the licensee shall notify the Commission and submit, as specified in 10CFR50.4, information to support the determination.
The 1989 Edition of Section XI Code contains provisions permitting alternative or substitute examinations, with evaluation and technicaljustification, to satisfy applicable Code requirements. These evaluations are to be prepared in accordance with Nonmandatory Appendix F. The intent of Appendix F, Article 3000 is to provide guidance for preparation of requests for relief from Code requirements where it has been determined that certain Code requirements cannot be met or are deemed impracticable.
At CNS, Relief Requests will be prepared in accordance with Appendix F and submitted to the NRC per 10CFR50.55a.
The following pages contain relief requests written in accordance with 10CFR50.55a(a)(3) and (g)(5) '
! when specific ASME Section XI requirements for inservice inspection are considered impracticable or pose an undo burden on the licensee. The relief requests contained are subject to change during the course of the ten year inspection interval as a result of changes in technology, plant design or as a result of installed modifications. If examinations or tests are determined to be impracticable, or result in
! hardship or unusual difficulty without a commensurate increase in the level of quality or safety, during ,
l the course of the interval, additional or modified relief requests will be submitted in accordance with '
i 10CFR50.55(a)(3) and (g)(5).
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The following Table summarizes each relief request and provides for sequential numbering to maintain continuity for the remainder of the inspection interval.
Relief Rev. Summary l Request i
RI-01 0 24" HPCI Turbine Exhaust 10" Branch Connection - Withdrawn RI-02 1 Use of Existing Calibration Blocks for Ultrasonic Examination of Class 1 and l
2 Components.
RI-03 0 Reactor Vessel Top Head Nozzle.Inher Railius Examinations -
RI-04 0 Intentionally Left Blank-RI-05 .0 Inspection of Residual Heat Removal (RHR) Heat Exchanger Tubesheet-to-Shell Welds.
RI-06 1 Circumferential a'nd Longitudinal Welds in the Reactor Pressure Vessel RI-07 0 Inspection of the RPV Support Skirt to Reactor Vessel Bottom Head Weld.
j RI-08 0 Expansion Criteria for Welds Governed by Generic Letter 88-01 and NUREG 0313, Rev. 2.
(7-1) Revision 1.1 L _ - __ . _ . _ __ -
Cooper Station 3rd Intervel Inservice Inspection Program INSERVICE INSPECTION RELIEF REQUESTS Relief Rev. Summary Request '
RI-09 0 Exemption from Appendix VII Ultrasonic Examination Personnel Qualification Requirements.
RI-10 0 Use of the 1989 Addenda of Section XI to Govern Repair Procedures (IWX-4000) Replacements (IWX-7000).
l RI-11 0 Successive Examination Requirements for Class 1 and 2 vessels.
RI-12 0 Alternative Examination of Class 1 and 2 Piping Longitudinal Seam Welds.
RI-13 0 Examination and Testing of Class 1,2, and 3 Snubbers RI-14 1 Alternative Rules for the Selection and Examination of Class 1,2, and 3 Integrally Welded Attaciunents RI-15 0 Examination of Peripheral Control Rod Drive Housing Welds RI-16 0 Use of the Examination Requirements, Examination Method, and Acceptance Standard of the 1989 Addenda of ASME Section XI for Reactor Vessel Closure Head Nuts.
RI-17 0 Integrally Welded Shear Lugs RI-18 0 Integrally Welded Attachment to the RHR Pump Casings RI-19 1 Feedwater Nozzle-to-Vessel Welds RI-20 1 Dissimilar Metal Butt Welds in Piping RI-21 1 Reactor Vessel Nozzle-to-Vessel Welds RI-22 1 Branch Pipe Connection Welds RI-23 1 Withdrawn RI-24 0 Category B-G-1 Inspection. Schedule - -
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l (7-2) Revision 1.1
Cooper Station 3rd Interval Inservice Inspection Program INSERVICE INSPECTION RELIEF REQUESTS RELIEF REQUEST NUMBER: RI-02, REVISION 1 COMPONENT IDENTIFICATIOl{
Code Classes: 1 and 2
References:
IWA-2232 Appendix I,1-2200 Appendix III, III-3411 Examination Categories: B-F, B-G-1, B-J, C-A, C-B, C-F-1, C-F-2 Item Numbers: B5.10, B5.130, B6.40, B9.11, B9.12, B9.31, C1.10, C1.20, C1.30, C2.21, C5.11, C5.12, C5.51, C5.52
Description:
Use of Existing Calibration Blocks for Ultrasonic Examination of Class 1 and 2 Components.
Component Numbers: Various
{ CODE REOUIREMENT IWA-2232 states that ultrasonic examination shall be conducted in accordance with
! Appendix I.
. Appendix I, I-2200 states that ultrasonic examination of vessel welds less than 2 inches thick and all piping welds shall be conducted in accordance with Appendix III, as supplemented by Appendix I.
Appendix III, III-3411 outlines the material specification requirements for calibration blocks. It
- basically requires calibration blocks to be fabricated from the same material specification as the piping being joined by the weld. It also states that if material of the same specification is not available, material of similar chemical analysis, tensile properties, and metallurgical stnicture may be used.
BASIS FOR RELIEF Several of the calibration blocks currently being used at CNS lack the documentation necessary to s
demonstrate compliance with the material specification requirements of Appendix III. This is be::ause
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the documentation requirements existing at the time of their fabrication did not require traceability to the material?s chemical or physical certifications. Consequently, the only documentation available for ~
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these existing calibration blocks is verification of the appropriate P-number grouping.
It would be impracticable to fabricate a new set of calibration blocks in order to satisfy the documentation requirements of the current Code. Existing records, which indicate the appropriate P-number grouping, provide adequate assurance that the blocks will establish the proper ultrasonic calibration and sensitivity.
4 (7-4) Revision 1.1
1 Cooper Station 3rd Interval Inservice Inspection Program INSERVICE INSPECTION RELIEF REQUESTS RELIEF REQUEST NUMBER: RI-02, REVISION 1 BASIS FOR RELIEF (Continued)
Based on the above, CNS requests relief from the ASME Section XI, Appendix III requirements for calibration block material specifications, in order to allow the continued use of the existing calibration blocks.
PROPOSED ALTERNATE PROVISIONS All future calibration blocks will meet the material specification requirements of ASME Section XI, l Appendix III and will be provided with the documentation necessary to demonstrate compliance with these requirements. Additionally, when using existing calibration blocks that lack the appropriate documentation, comparisons will be made between the attenuation and the material velocity of the calibration blocks, and the materials being examined.
l APPLICABLE TIME PERIOD l
Relief is requested for the third ten-year interval of the Inservice Inspection Program for CNS.
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l (7-5) Revision 1.1
I Cooper Station 3rd Interval Inservice Inspection Program l
j INSERVICE INSPECTION RELIEF REQUESTS l l
RELIEF REQUEST NUMBER: RI-14, REVISION 1 '
COMPONENT IDENTIFICATION Code Class: 1, 2, and 3
References:
Tables IWB, IWC and IWD-2500-1 Examination Category: B-K-1, C-C, D-A and D-B Item Numbers: B10.10, B10.20, B10.30, B10.40, C3.10, C3.20, C3.30, C3.40, DI.10, D1.20, D1.30, and D1.40 i
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Description:
Alternative Rules For the Selection and Examination of Class 1,2, and 3 l
Integrally Welded
Attachment:
Component Numbers: Integrally Welded Attachments in Examination Categories B-K-1, C-C, D-A, and D-B.
l l CODE REQUIREMENT Table IWB-2500-1, Category B-K-1 requires a volumetric or surface examination as applicable of integrally welded attachments exceeding 5/8" e sign thickness.
Table IWC 2500-1, Category C-C requires a surface examination of all integrally welded attachments I exceeding 3/4" design thickness.
l Table IWD 2500-1, Category D-A and D-B a surface examination of all integrally welded attachments corresponding to those component supports selected by IWF-2510(b).
I BASIS FOR RELTEF l Specific relief is requested on the basis that the proposed alternative would provide an acceptable level of quality and safety. Code Case N-509, " Alternative Rules for the Selection and Examination of l Integrally Welded Attachments,Section XI, Division 1", provides an alternative to the Tables of i IWB/C/D-2500-1 for integrally welded attachments. The alternative requires a surface examination of !
10% of the integrally welded attachments associated with the component supports selected for i examination under IWF-2510. In addition, an examination is required whenever component support member deformati.on is identified. This Code Case recognizes tiie results of over 20 years of - .
inservice inspections and the considerable attention that c'omponent supports have received threagh NRC bulletins.
PROPOSED ALTERNATE POSITIONS l
l CNS proposes to examine 10% of the the integrally welded attachments in each Examination Category l in each Code class in accordance with Code Case N-509 requirements.
APPLICAHLE TIME PERIOD h
Relief is requested for the third ten-year interval of th: Inservice inspection Program for CNS. '
(7-31) Revision 1.1 l _ _
Cooper Station 3rd Interval Inservice Inspection Program INSERVICE INSPECTION RELIEF REQUESTS RELIEF REQUEST NUMBER: RI-19, RFXISION 1 l
l COMPONENT IDENTIFICATION Code Class: 1
References:
IWB-2420(b), Table IWB-2500-1 Examination Category: B-D Item Numbers: B3.90
Description:
Nozzle-to-Vessel Welds Component Numbers: Feedwater Nozzles N4A, N4C, and N4D
. CODE REOUIREMENT IWB-2420(b) states that flaw indications or relevant conditions are evahated in accordance with IWB-3142.4 and the component qualifies as acceptable for continued service, the areas containing such flaw indications or relevant conditions shall be reexamined during the next three inspection periods.
1 Table IWB-2500-1 requires a volumetric examination be performed on nozzle-to-vessel welds def'med i by the volume shown Figure IWB-2500-7. )
BASIS FOR RELIEF Specific relief is requested on the basis that the proposed alternative would provide an acceptable level of quality and safety. 4 Flaw indications in Feedwater nozzle-to-vessel welds, N4A, N4C, and N4D, were identified during ,
the 1991 refueling outage and were reexamined during the 1995 refueling outage. The flaws are attributed to construction defects and are not considered to be service induced. The fracture mechanics evaluation in 1991 found the flaws to be acceptable per IWB-3600. The reexamination in 1995 indicated that the flaws have remained essentially unchanged from the 1991 examination. The 1995 fracture mechanics evaluation shows that the flaws are acceptable for the remaining life of the plant. Radiation doses of approximately 4 Person-Rem were received during the examinations in 1,995. .
Since the flaws have remained essentially' unchanged from the 1991 examination, the indications are -
acceptable per Subarticle IWB-3600 of ASME Section XI, and the fracture mechanics analysis shows the indications to be acceptable for the remaining life of the plant, additional successive examinations as required by Paragraph IWB-2420(b) of the Code are not warranted. Furthermore, additional exposures of approximately 8 Person-Rem would be experienced during the performance of these examinations over the next two inspection periods.
(7-39) Revision 1.1
Cooper Station 3rd Interval Inservice Inspection Program INSERVICE INSPECTION RELIEF REQUESTS RELIEF REQUEST NUMBER: RI-19, REVISION 1 PROPOSED ALTERNATE EXAnilNATION CNS will perform the volumetric examination of Feedwater nozzle-to-vessel welds N4A, N4C, and N4D, once during the third ten-year interval in accordance with Table IWB-2500-1.
APPLICABLE TIME PERIOD Relief is requested for the third ten-year interval of the Inservice Inspection Program for CNS.
Approved, NRC letter dated June 7,1996 (TAC No. M94260)
.s (7-40) Revision 1.1
Cooper Station 3rd Interval Inservice Inspection Program INSERVICE INSPECTION RELIEF REQUESTS RELIEF REQUEST NUMBER: RI-20, REVISION 1 COMPONENT IDENTIFICATION Code Class: 1
References:
IWB-2420(b), Table IWB-2500-1 Examination Category: B-F Item Numbers: B5.130
Description:
Dissimilar Metal Butt Welds in Piping Component Numbers: Weld RVD-BF-14.
CODE REOUIREMENT Table IWB-2500-1 requires a surface examination to be performed on dissimilar metal butt welds in piping s 4 inches defined by the areas in Figure IWB-2500 8.
BASIS FOR RELIEF:
A rigid support is located adjacent to this 2 inch NPS stainless steel to carbon steel butt weld in the reactor drain line. The design of the support does not permit disassembly without cutting the support members. The support limits access to one side of the weld crown such that only % inch of the adjacent base metal can be examined. The total surface accessible for examination, based on the examinations performed in the second interval, is approximately 83%.
PROPOSED ALTERNATIVE:
In lieu of performing the Code required examinations, CNS proposes to examine the accessible portions of weld RVD-BF-14.
(7-41) Revision 1.1
Cooper Station 3rd Interval Inservice Inspection Program INSERVICE INSPECTION RELIEF REQUESTS RELIEF REQUEST NUMBER: RI-21, REVISION 1 COMPONENT IDENTIFICATION Code Class: 1
References:
IWB-2500 Table IWB-2500-1 Examination Category: B-D Item Numbers: B3.90, B3.100
Description:
Reactor Vessel Nonle-to-Vessel Welds Component Numbers: N1A, NIB, N2A, N2B, N2C, N2D, N2E, N2F, N2G, N2H, N2J, N2K, N3A, N3B, N3C, N3D, N4A, N4B, N4C, N4D, N5A, N5B, N6A, N6B, N7, N8A, N8B, and N9.
CODE REOUIREMENT Table IWB-2500-1 requires a volumetric examination of the reactor vessel nonL-to-vessel welds.
BASIS FOR RELIEF The Cooper Nuclear Station constmetion permit was issued before the effective date of implementation for ASME Section XI and thus the plant was not designed to meet the requirements of inservice inspection; therefore,100% compliance is not feasible or practical. The configuration of the nozzles, the design of the vessel insulation suppon rings and the nozzle access hatches, and interferences from thermocouple pads, instrument lines, etc. prevents 100% examination of the required weld volumes.
Alternate angles were used to the extent practical to increase the volume examined. The extent of the nozzle restrictions and the total volume accessible for examination, based on the examinations performed in the second interval, is summarized on table RI-21-1.
PROPOSED ALTERNATE EXAMINATION In lieu of performing the Code required examinations, CNS proposes to examine the accessible ponions of reactor vessel nozzle-to-vessel welds.
APPLICABLE TIME PERIOD ~
Relief is requested for the third ten-year interval of the Inservice Inspection Program for CNS.
V (7-42) Revision 1.1 i
I Cooper Station 3rd Interval Inservice Inspection Program INSERVICE INSPECTION RELIEF REQUESTS RELIEF REQUEST TABLE RI-21-1, REVISION 1 Nozzle Nozzle Access Restrictions %
Number Description Examined N1A,B Recirculation Inlet Nozzle configuration, and insulation suppon 32 %
frame N2A-H, Recirculation Outlet Nozzle configuration, and insulation support 40 % !
J&K frame N3A-D 1% tin Steam Nozzle configuration 35 %
N4A&C Feedwater Nozzle configuration, insulation support 27 %
frame, thermocouple pads, and Instmment Nozzles NilA&B N4B&D Feedwater Nozzle configuration, insulation support 31 %
frame, and thermocouple pads N5A,B Core Spray Nozzle configuration, insulation support 31 %
frame, tnd thermocouple pads l
N6A,B Top Head Spray Nozzle configuration 58%
N7 Top Head Vent Nozzle configuration 30 %
l N8A,B Jet Pump Nozzle configuration, and insulation support 76 %
Instmmentation frame N9 CRD Return Nozzle Nozzle configuration, and insulation suppon 70 %
and Inner Radius frame (7-43) llevision 1.1
Cooper Station 3rd Interval Inservice Inspection Pmgram INSERVICE INSPECTION RELIEF REQUESTS RELIEF REQUEST NUMBER: RI-24, REVISION 0 l
COMPONENT IDENTIFICATION i
Code Class: 1
References:
IWB-2412(a), IWB-2420(a), IWB-2500 Table IWB-2412-1, Table IWB-2500-1 '
Examination Category: B-G-1 Item Number.i: B6.10, B6.20, B6.40, and B6.50
Description:
Pressure Retsining Bolting, Greater Than 2 in. In Diameter Component Numbers: Closure Head Nuts, Studs in Place, Threads in Flange, Closure Washers ;
and Bushings l CODE REOUIREMENT IWB-2412(a) states that the required examinations in each examination category shall be completed during each successive inspection interval in accordance with Table IWB-2412-1.
IWB-2420(a) states that the sequence of component examinations established during the first inspection interval shall be repeated during each successive. inspection interval, to the extent practical.
BASIS FOR RELIEE The reactor vessel closure head nuts and closure washers are removed each outage for disassembly of the vessel. The studs and bushings are normally left in place. During the two previous inspection intervals, the studs, nuts, bushings, washers, and the threads in flange were each divided into three groups. One group of each item was scheduled for examination during each period of the interval. Every period, an I entry would be made into the reactor cavity to examine the scheduled threads in the flange. Every period, equipment would be brought up to the refueling floor to clean the nuts and washers scheduled for examination. The same philosophy was applied to the closure studs and bushings, except that during the second period of the second interval the studs were replaced. The new studs and the old bushings were inspected while the studs were removed. The old examination schedule appears to have been based on
~
an incorrect interpretation of the Code. Code Interpretation XI-1-86-74, clarifies that scl.edule -
. requirements are to be applied by examination category; not by item number. -
In order to more effectively use plant resources, and reduce personnel exposure, CNS would like to reschedule some of the Category B-G-1 examinations. Rescheduling, however, would conflict with the requirements of IWB-2412(a) since approximately 40% of the B-G-1 examinations would be performed during the first period,20% during the second period, and the balance during the third period.
l Rescheduling would also conflict with the requirements of IWB-2420(a) because one third of the closure i nuts and washers would be reexamined after more than ten years of service since the previous l examination, and a third of the threads in the flange and the bushings would be reexamined after less than ten years of service since the previous examination. The studs would be re-examined at the Code t required frequency.
I (7-47) Revision 1.1
Cooper Station 3rd Interval Inservice Inspection Program i INSERVICE INSPECTION RELIEF REQUESTS
) RELIEF REQUEST NUMBER: RI-24, REVISION 0 PROPOSED ALTERNATE EXAMINATION In lieu of maintaining the Code required successive e:: amination schedule, CNS proposes to re-examine ;
the threads in the reactor vessel flange and the bushings during the first period; the closure head studs ;
during the second period, and the closure washers and nuts during the third period.
)
APPLICABLE TIME PERIOD Relief is requested for the third ten-year interval of the Inservice Inspection Program for CNS. l i
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(7-48) Revision 1.1
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Cooper Station 3rd Interval Inservice Inspection Program 9.0 SYSTEM PRESSURE TESTING TECHNICAL APPROACH AND POSITION INDEX/ SUMMARIES Position Rev. Summary PT-01 0 Adoption of Code Case N-498-1 for Class 1 and 2 hydrostatic pressure testing.
PT-02 0 Hydrostatic and operational pressure testing of open ended piping.
PT 03 1 Test temperature for hydrostatic testing of systems containing ferritic steel components.
PT-04 0 Valve seats as pressurization boundaries. l PT-05 0 leakage through mechanical connections.
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(9-1) Revision 1.1
Cooper Station 3rd Interval Inservice Inspection Program a
TECIINICAL APPROACH AND POSITION NUMBER: PT-03, REVISION 1 COMPONENT IDENTIFICATION i
i Code Classes: 2 and 3 i
References:
IWC-5230(b)
IWD-5230(a)
Examination Categories: C-II and D-A
Description:
Test Temperature for Ilydrostatic Testing of Systems Containing Ferritic Steel Components.
CODE REOUIREMENT The referenced sections of ASME Section XI require that the system test temperature, during a system hydrostatic test in systems constructed of ferritic steel components for which fracture toughness requirements were not specified nor required in the construction of the components, shall be determined by the owner.
POSITION Fracture toughness requirements were not specified (or required) for Class 2 or 3 components when CNS was constmeted. Since fracture toughness requirements were not specified, hydrostatic tests of systems containing ferritic steel components will be performed at or above the minimum operating temperature of the system.
The purpose of using a minimum test temperature is to ensure that the system is not highly stressed when the temperature is at or below the nil-ductility transition temperature (NDTT) of the metal. At this temperature, fracture will initiate with essentially no prior plastic deformation, causing a sudden catastrophic failure.
The NDTT of a metal is sensitive to a variety of parameters including carbon content, presence of other alloys, grain size, grain orientation, and heat treatment. These factors combine to make the choice of an " average nil-ductility transition temperature" difficult. In general, the NDTT point for ferritic materials is well below 32 "F. .
, The, minimum temperature requirement that. will be used is justified by .the following:
- The minimum olierating temperature of the Service Water system is 40 *F and no catastrophic failure has ever occurred. Other low temperature systems are operated above this temperature.
- Piping systems are designed to withst'and stresses due to internal pressure, dead weight, and thermal growth during system operations as well as various dynamic loads, including earthquake and hydrodynamic loads. During a hydrostatic test the only stresses that the system experiences are due to dead weight and a pressure of 1.10 to 1.25 times design. The stresses developed in a piping system during a hydrostatic test do not approach the allowable stresses for the piping.
(9-6) Revision 1.1
Cooper Station 3rd Interval Inservice Inspection Program i
l TECHNICAL APPROACH AND POSITION NUMBER: PT-03, REVISION 0 POSITION (Continued) l
- The measures required to heat the piping system or the pressurizing medium are prohibitive when one considers the length of some piping runs and the corresponding volume of pressurization meditun required. Setting a minimum temperature at or above the minimum operating temperature of the system with no basis represents a hardship in terms of testing.
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(9-7) Revision 1.1
Cooper Station 3rd Interval Inservice Inspection Program 10.0 SYSTEM PRESSURE TESTING RELIEF REQUESTS Relief Rev. Summary Request PR-01 0 Alternate Testing for ISI Class 1,2, and 3 repaired / replaced components.
PR-02 2 Defm' ition of pressure retaining boundary for system leakage test PR-03 0 Alternate corrective measures for bolted connections.
PR-04 0 Exemption from pressure testing Reactor Vessel Head Flange Seal Izak Detection System.
PR-05 1 Alternate test for containment penetration piping.
PR-06 0 Alternate pressure testing for buried components.
PR-07 0 Pressure retaining components within each system boundary subject to hydrostatic pressure testing.
PR-08 0 Alternate Testing for MSRV Discharge Piping.
PR-09 0 Alternate Testing for HPCI and RCIC Discharge Piping 3
4 d
(10-1) Revision 1.1
Cooper Station 3rd Interval Inservice Inspection Program RELIEF REQUEST NUMBER PR-02, REVISION 2 COMPONENT IDENTIFICATION Code Class: 1
Reference:
Table IWB-2500-1, Note 1 Examination Category: B-P Item Number: B15.10
Description:
Definition of Pressure Retaining Boundary for System Leakage Test.
l Component Numbers: All components subject to pressurization during a system leakage ;
- test. j
, CODE REOUIREMENT l
l Table IWB-2500-1, Note 1 states that the pressure retaining boundary during the system leakage I test shall correspond to the reactor coolant system boundary, with all valves in their normal position required for normal reactor operation startup. The VT-2 visual examination shall, however, extend to and include the second closed valve at the boundary extremity.
BASIS FOR RELIEF l
It is impracticable to perform a system leakage test during actual reactor startup. The high dose rates associated with reactor operation, the temperature levels in the drywell, and the large amount of piping and components to be examined makes this examination a hardship. In lieu of a system leabge test during reactor startup a hydrostatic test is performed at the pressure associated with 100% rated reactor power.
Section XI states that the boundary for the system leakage test shall be the reactor coolant pressure boundary with all valves in the position required during reactor startup. It is impracticable to
- extend the boundary this far during pressure testing.
a) Three of the four Feedwater Check valves and will be closed for the system pressure test following a refueling outage. The inboard check on one. Feedwater line is kept open by
. Reactor Water Cleanup (RWCU) flo'w. .The RWCU system is kept in service during the pressure t'ests. .The outboard check valves are the class 1 boundary valves.
b) The four outboard Mein Steam Isolation Valves (MSIV) will be closed for the system pressure test and the ten-year hydrostatic pressure test. The inboard MSIV's are opened to pressurize the system to the outboard valves. The outboard MSIV's are the class I boundary valves.
c) Both High Pressure Coolant injection (HPCI) and both Reactor Core Isolation Cooling (RCIC) steam supply valves will be closed for the system pressure test following a refueling outage. These valves close automatically on low steam supply pressure. During the ten-year hydrostatic pressure test, the system will be pressurized to the outboard valves. The outboard valves are the class I bouridary valves (10-4) Revision 1.1
. _ ~ - - - . - - ... - - - - .
Cooper Station 3rd Interval Inservice Inspection Program I
RELIEF REQUEST NUMBER: PR-02, REVISION 2 BASIS FOR RELIEF (Continued) l In addition to the extensive line-ups required to perform a system leakage test of this magrdtude, special measures would be required to temporarily support steam lines due to the excess weight of the water. ,
The position of the valves for the system leakage test as described above is consistent with the intent offootnote I to Table IWB-2500-1, Category B-P. Abnormal lineups and installation ofjumpers is not required for the system leakage test. The valves described above are normally open during a i
reactor startup. In order to pressurize the reactor coolant pressure boundary for testing, these valves must be closed. Except as described above, the Class I boundary is pressurized as required by the Code. The VT-2 inspection includes the entire reactor coolant pressure boundary.
Since the portions of the piping between the valves described above are operated at or above reactor pressure during normal operation, any through wall leakage would be detected by the drywell leakage collection system, or by operations personnel on normal rounds.
i
- In summary, it is unsafe to perform a VT-2 visual examination during actual reactor startup during l i reactor operation and it is impracticable to perform a system leakage test of the reactor coolant pressure boundary with all valves in the position required for normal reactor startup. !
l Based on the above, CNS requests relief from the ASME Section XI requirements for performing a system leakage test using the boundaries stated in Note 1 of Table IWB-2500-1.
PROPOSED ALTERNATE PROVISIONS The Feedwater Check valves, the outboard MSIV's, the Main Steam Line Drain valves, and the I HPCI and RCIC Steam Supply Valves will be closed during the system leakage test, but will be i included in the VT-2 examination. A VT-2 visual examination will be performed during the system leakage test at a pressure not less than that associated with 100% rated reactor power. I In addition, a system hydrostatic test will be performed once per interval at a pressure not less than that associated with 100% rated reactor. power. The pressurization boundary and the VT-2 visual examination fo'r this test will extend to the Class 1 boundary.
APPLICABLE TIME PERIOD Relief is requested for the third t'en-year interval of the Inservice Inspection Program for CNS.
(10-5) Revision 1.1
Cooper Station 3rd Interval Inservice Inspection Program RELIEF REQUEST NUMBER: PR-05, REVISION 1 COMPONENT IDENTIFICATIOR Code Classes: 2
References:
IWA-5000, IWC-5000 IWA-5110, IWC-5210 Examination Categories: C-H Item Numbers: C7.30 through C7.80
Description:
Alternate testing for containment penetration piping.
Component Numbers: Class 2 pressure retaining components penetrating containment connected to nonsafety-related piping.
CODE REOUIREMENT l IWA-5210 requires the pressure retaining components within each system boundary to be subjected to a system pressure test. l l
IWC-5210(a) requires pressure retaining components to be tested at the frequency stated in, and visually examined by the methods specified in Table IWC-2500-1.
BASIS FOR RELIEF The portion of piping that penetrates containment and the associated inboard and outboard containment isolation valves are required to be constructed in accordance with Class 1 or Class 2 design requirements. In instances where the piping penetration is for a nonsafety-related system, the sole function of the penetration piping and associated valves is to provide containment isolation and maintain containment integrity in the event of a failure of the attached nonsafety-related piping. In all cases during normal plant operation, the isolation valves associated with these penetrations are maintained in the locked closed position, are administratively closed (controlled procedurally), or they close automatically upon receipt of a containment isolation signal or on loss of flow. The integrity of these penetrations is verified by 10CFR50, Appendix J, leakage testing.
Additionally, Code Case N-522, " Pressure Testing of Containment Piping Section XI, Division 1," has determined that pressure testing of these containment. penetrations per 10CFR50, . App,endix
~
'J, is an acceptable alternative to the requireme,nts of Table IWC-2500-1, Category C-H.
Performing system pressure tests each inspection period and a hydrostatic test each inspection interval per Section XI, Table IWC-2500-1, Category C-H, is r'edundant to Appendix J testing.
l Code pressure testing provides no commensurate increase in quality or safety with cost benefit.
l Pressure testing of piping in nonsafety-related systems penetrating containment pursuant to the l requirements of 10CFR50, Appendix J, in lieu of Section XI pressure testing requirements provides an acceptable level of quality and safety.
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(10-11) Revision 1.1 l
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. Cooper Station 3rd Interval Inservice Inspection Program RELIEF REQUEST NUMBER: PR-05, REVISION 1 PROPOSED ALTERNATE PROVISIONS As an alternative to Section XI pressure testing requirements for piping penetrating containment attached to a nonsafety-related system, CNS will adopt the provisions of ASME Section XI Code Case N-522.
Pressure testing of the below listed penetrations shall be performed in accordance with the requiremeio and frequency specified in 10CFR50, Appendix J, in lieu of the additional requirements specified in Table IWC-2500-1, Category C-H. The test will be conducted at the peak calculated containment pressure. If the leak rate exceeds the Appendix J acceptance criteria, additional measures will be applied to verify that the test failure is not due to a through-wall leak.
class 2 PORTIONS OF SYSTEMS AT CONTAIm4ENT PENETRATIONS SYSTEM DRAWING PENETRATION # CIASS FUNCTION INST AIR 2010-2 22, 30E, 30F, 335, 33F 2 NNS PCC, NI 2022 2, 25, 26, 45C, 515, 51F, 203A, 2038, 2 N'IS
& SBNI 2084 205, 220
( RPV INST 2026 40A, 408, 40C, 40D, 47 (A11) 2 NNS REACTOR 2027 29E, 209A, 2098, 209C, 209D, 213A, 113B, 2 NNS 92 CIRC. 215, 22 9A, 2298, 229C, 229D, 229E, 229F, 2290, 229n, 2293, 229E, 229M, DRAINS 2028 18, 19, 43, 44 2 NHS DEMIN. 2029 20 2 NNS NATER H202 2022 36, 203A, 203B 2 NNS REC 2031-1 23, 24 2 NNS l 2031-2 SERVICE 2010-3 21 2 NNS j AIR i TIP 2083 35A, 355, 35C, 35D, 35E 2 NNS
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AITLICABLE TIME PERIOD j Relief is requested for the third ten-year interval of the Inservice Inspection Program for CNS.
t (10-12) Revision 1.1
Cooper Station 3rd Interval Inservice Inspection Program 11.0 AUGMENTED INSERVICE INSPECTION l
Augmented Inservice Inspections (AISI) are not ASME Section XI Code requirements, but are 1) additional examination areas or 2) increased inspection frequencies, or combinations of both which are requested by the Nuclear Regulatory Commission, recommended in General Electric Company Service Information letters, or added by management direction.
When examination components fall into the scheduled testing requirements of ISI and are also AISI requirements, then credit for both requirements may be taken by one examination (no double testing). The following types of Augmented Inservice Inspections are required at Cooper Nuclear Station. The TAB number corresponds to the tabbed pages that follow which contain information on the specific examination to be performed.
TAB DESCRIPTION REVISION DATE l 11.1 Ultrasonic examination of the feedwater nozzle safe ends, bores, and Dec. 96 inside blend radii, and visual inspection of the feedwater spargers per Table 2 and Section 4.3.2.4 of NJREG 0619. In lieu of the dye penetrant examination of feedwater nozzles per NUREG 0619, automated UT of the nozzles is performed.
! 11.2 Visual inspection of the Core Spray spargers and the Core Spray Dec. 96 l piping inside the RPV shall be conducted each refueling outage.
(
Reference:
IE Bulletin No. 80-13 and BWRVIP-18.)
11.3 Ultrasonic examinations of the jet pump hold down beams. These July 95 i examinations shall be performed once during the third ten year interval and may be deferred to the end of the interval. (Reference i
NUREG CR3052) l 11.4 Ultrasonic examinations per Generic Ixtter (GL) 88-01 of BWR Dec. 96 l piping made of austenitic stainless steel. Accessible welds will be examined in accordance with CNS GL 88-01 commitments. Added requirements for weld crown conditidning for UT (future welds) per Generic Electric SIL No.117R3'., Deleted non-safety related RWCU.
welds.
i 11.5 Visual inspection of steam dryer channel welds during each July 95 l inspection period (Reference General Electric SII. No. 474.) .
11.6 Visual inspection of Jet Pump nozzles and mixer inlets each ' July 95
, inspection period in conjunction with Jet Pump inspection.
(
Reference:
General Electric SIL No. 465 S1.)
(11-1) Revision 1.1
Cooper Station 3rd Interval i Inservice Inspection Program 1
TAB DESCRIPTION REVISION
{
DATE 11.7 Based on the results of previous examinations, an ultrasonic July 95 examination of the shroud support access hole cover.; will be performed once every five years, and a visual examination will be performed once each refueling outage. (
Reference:
General Electric SIL No. 462, Supplement 3) 11.8 Visual inspection of the Core Spray T-junction box welds inside the Dec. 96 reactor vessel. (
Reference:
General Electric SIL No. 289, R1, SI) l 11.9 Visual examination of the Reactor Recirculation (RR) pumps' shafts, July 95 l pump covers, impeller / shaft attachment region (including bolts), and hydrostatic bearings (including baffle plate). (
Reference:
General Electric SIL No. 459 and RICSIL No. 038) 11.10 Visual examination of all accessible areas of the Intermediate Range July 95 Monitor (IRM) and Source Range Monitor (SRM) dry tubes the sixth refueling outage after replacement, and every third refueling l outage thereafter. (
Reference:
General Electric SIL No. 409 RI) 11.11 Ultrasonic (UT) examination of all remaining old design creviced March 96 Inconel 600 Shroud Head Bolts (SHBs) each refueling ourage.
(
Reference:
General Electric SIL No. 433 S1) 11.12 Augmented Inservice Inspection (UT) requirements for the REC March 96 system required by CNS CR94-0485.
11.13 Visual (VT) examination of the Jet Pump Sensing Lines and Sensing Dec. 96 Line Support Brackets each inspection period in conjunction with scheduled ISI examinations. (
Reference:
General Electric SIL No.
420) 11.14
. Visual examination (VT) of the Steam Separator, once per Inspection March 96 Interval as described by the CNS Invessel Visual Examination Procedure.
11.15 Ultrasonic Inspection (UT) of the Core Shroud per BWRVIP and GL . Dec. 96 94-03. (Supersedes GE SIL No. 572 and RICSIL No. 68) 11.16 Inspection ofInstrument Nozzle Safe Ends in conjunction with Dec. 96 scheduled ISI examinations. (
Reference:
GE SIL No. 571) 11.17 Visual Inspection (VT) of the Top Guide. (
Reference:
GE SIL No. July 95 554) 11.18 Visual Inspection (VT) of the Top Guide and Core Plate. Dec. 96
(
Reference:
GE SIL No. 588 RI)
(11-2) Revision 1.1
4 Cooper Station 3rd Interval Inservice Inspection Program I i
- i l TAB DESCRIPTION REVISION DATE 11.19 Visual Inspection of Jet Pump Riser Brace (VT) each inspection July 95
- period. (
Reference:
GE SIL No 551) 11.20 Deleted. Visual inspection of the Refueling Platfc ta will be Dec. 96 controlled by other means.
, 11.21 Visual Inspection (VT) of Jet Pump Adjusting Screw each inspection Dec. 96
- period. (
Reference:
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l (11-3) Revision 1.1
Cooper Station 3rd Interval Inservice Inspection Program
-11.1 FEEDWATER NOZZLE EXAMINATIONS ;
IN ACCORDANCE WITH U.S. NRC NUREG 0619 1
- Revision 1 "
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REFERENCES:
- 1. U.S. NRC NUREG 0619, BWR Feedwater Nozzle and Control Rod Drive
)
^
Return Line Nozzle Cracking, published November,1980. ,
i
- 2. I2tter, G. R. Hom (NPPD) to U.S. NRC, dated January 22,1991, subject:
BWR Feedwater Nozzle Inspections, Cooper Nuclear Station.
- 3. Ietter, G. R. Hom (NPPD) to U.S. NRC, dated August 14,1991, subject:
BWR Feedwater Nozzle Inspections, Cooper Nuclear Station.
- 4. Letter, P. W. O'Connor (U.S. NRC) to G. R. Horn (NPPD), dated October 2,1991, subject: Review of NPPD Request Regarding Feedwater Nozzle Examination Methods.
In 1980, as a msult of previous commitment to Reference 1, CNS removed the existing stainless -
steel cladding from the reactor pressure vessel (RPV) feedwater nozzles and installed new triple sleeve / double piston ring seal feedwater spargers. Also at that time, CNS implemented the non- -
destmetive examination requirements of NUREG 0619.
NUREG 0619, Table 2, requires a dye penetrant (PT) exam of the inner surfaces on one feedwater nozzle every nine refueling cycles. This would have required, as a minimum, removal of one feedwater sparger and a penetrant examination of that nozzle, as well as examinations of accessible portions of the remaining nozzles. Due to ALARA concerns and operational considerations, CNS proposed in Reference 2, to perform an automated ultrasonic examination of the feedwater nozzles -
in lieu of the specified dye penetrant examination. CNS also conunitted to implement automated feedwater sparger seal leakage and fatigue usage / crack growth monitoring. Furthermore, CNS committed in Reference 3 to qualify the automated UT examination techniques to be employed on a full-size BWR nozzle mockup with several narrow notches and at least one actual fatigue crack. The table below summarizes the NUREG 0619 required examinations proposed for CNS.
The actual examination sghedule may be adjusted depending on the number of startup/ shutdown !
cycles since the last examination. .
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_ . _ . _ . .- _ _ . . _ _ _ _ . _ _ _ . . __ ._~ _
l Cooper Station 3rd Interval Inservice Inspection Program FEEDWATER NOZZLE EXAMINATIONS IN ACCORDANCE WITH U.S. NRC NUREG 0619 Revision 1 REFUELING OUTAGE EXAMINATION SCHEDULE FOR FW NOZZLES YEAR PT UT VT l
1997 NO NO NO ;
1998 NO YES NO 2000 NO NO YES-SPARGERS ONLY i 2002 NO YES NO 2004 NO NO NO 2005 NO YES NO l
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The NRC in Reference 4, approved the CNS proposal to perform automated UT examination in i lieu of PT examination of feedwater nozzles. CNS conducted an automated UT exam of the feedwater nozzles during the 1991 Refueling Outage using the General Electric Reactor Inspection System (GERIS) and the applicable General Electric procedures. The feedwater nozzle UT l examinations will be reperformed as shown above during the Third Inservice Inspection Interval.
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(11.1-2) Revision 1.1
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i Cooper Station 3rd Interval Inservice Inspection Program 11.2 CORE SPRAY SPARGER AND PIPING Revision 1
REFERENCES:
- 1. U.S. NRC IE Bulletin 80-13, Visual Inspection of Core Spray Spargers l
l 2. Letter, J. H. Mueller to U.S. NRC, dated November 22,1995,
! subject: Visual Inspection cf Cwe Spray Spargers. i
Subject:
Inspection of Core Spray Spargers and Piping.
l Visual examination (VT-1) of the Core Spray spargers and associated piping has been performed '
at refueling outages in accordance with Reference 1. As reported in Reference 2, three crack-like indications, and two suspect indications were identified in the Fall 1995 refueling outage. These indications will be reinspected during the Spring 1997 Refueling outage. In Reference 3, CNS notified the NRC that future examinations of the Core Spray Spargers and associated piping would be performed in accordance with the guidance in BWRVIP-18. The BWRVIP-18 examinations will commence in 1997.
3 .
1 (11.2-1) Revision 1.1
l Cooper Station 3rd Interval Inservice Inspection Program 11.4 INTERGRANULAR STRESS CORROSION CRACKING IN ACCORDANCE WITH U.S. NRC GENERIC LETTER 88-01 l Revision 1
References:
- 1. NRC position on IGSCC in BWR austenitic stainless steel piping (Generic Letter 88-01).
l 2. Letter, G. A. Trevors (NPPD) to U.S. NRC, dated October 9,1990.
l
Subject:
Generic Letter 88-01, Cooper Nuclear Station. '
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- 3. Leta P. W. O'Connor to G. R. Horn (NPPD), dated May 24, 1991.
Subject:
Reactor Water Cleanup (RWCU) Pipe Weld Inspection.
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- 4. NRC position on IGSCC in BWR austenitic stainless steel piping (Generic I Letter 88-01, Supplement 1).
l 5. Ixtter, G. R. Horn (NPPD) to USNRC, dated February 27,1996,
Subject:
Generic letter 89-10, Safety Related Motor-Operated Valve Testing and l Surveillance. .
J j As a result of previous commitments to Reference 1, CNS replaced the majority of the Category l D Intergranular Stress Corrosion Cracking (IGSCC) susceptible piping and welds with Category l A IGSCC resistant piping and welds during the 1990 Refueling Outage. The Category D piping and welds that were not replaced consisted of the RWCU return piping from the regenerative heat I exchanger outlet to the RWCU/RCIC attachment to the~ feedwater inlet line. In Reference 2, l CNS proposed to revise its previous commitment to replace this piping and instead conduct I continued inspection of this piping in accordance with the requirements of GL 88-01. The NRC i approved this change, and future inspection requirements for RWCU piping weld inspections were l documented in Reference 3. In Reference 5, CNS notified the NRC that t had successfully i
l completed the GL 89-10 requirements, therefore CNS has removed the non-safer related RWCU welds from the program. l l
The following pages document the CNS Augmented ISI requirements for all of the applicable RWCU piping welds in accordance with Reference,3 and 5. Also,. weld RCA-BF-1 (CRP nozzle cap weld) has been reclassified as Category D and included in the attached program.
Tliere are additional IGSCC Category A welds in Class 1 portions of the Reactor Recirculation, l Core Spray, and RWCU systems. These welds are included in the CNS ASME Section XI ISI Program. These welds are also documented in the following pages in order to provide a complete list of welds subject to GL 88-01.
CNS will conform to the NRC staff position on reporting requirements as stated in GL 88-01.
The NRC will be notified of any flaws identified that do not meet IWB-3500 criteria from Section XI of the Code for continued operation without evaluation, or a change found in the condition of welds previously known to be cracked. The NRC will be notified of any flaw evaluation required 11.4-1 Revision 1.1
Cooper Station 3rd Interval i Inservice Inspection Program 4
INTERGRANULAR STRESS CORROSION CRACKING IN ACCORDANCE WITH U.S. NRC GENERIC LETTER 88-01 Revision 1 for continued operation and/or flaw repair plans.
l Category A welds in austenitic stainless steel piping at CNS have had the outside surface weld crowns conditioned (machined) to provide optimum surface condition for ultrasonic (UT) examination. This was done in accordance with General Electric Company reconunendations l which are now documented in GE Service Information Ietter (SIL) No.117, Revision 3. Future I welds in austenitic stainless steel piping systems subject to Generic Letter 88-01 will be ;
conditioned / machined for ultrasonic inspection in accordance with the recommendations of SIL i No.117, Revision 3. -
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11.4-2 Revision 1.1
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s QUGMENTED INSERVICE INSPECTION TAB: 5 COOPER NUCLEAR STATION .
GENERIC LETTER 88-01 ,
INSERVICE INSPECTION PROGRAM REV: 1.1 ,
THIRD INTERVAL P I PE . . . . . . . . . . . . . . . . . STST EM. . CNT. I GSCC CF IG. . . SI ZE. . TKNS. . . . . MAT . . . VB1. CAL'. . 150. . . . . . . . . . . . . . . . . PER RELREQ REMARits. . . . . . . . . . . . . . . . . .
CSA-BJ-2* CS-A 1 A P-SE 10 .594 P20 49 2502-1 3 RI-08
- FORMER PIPE WHIP EXAM CSA BJ-3* CS-A 1 A P-P 10" .594" P20 49 2502-1 RI-08
- FORMER PIPE WHIP EXAM CSA-BJ-4 CS-A 1 A P-P 10 .594 P20 49 2502-1 RI-08 CSA-BF-1* CS-A 1 A SE-N 13.44 1.06 P20/RP 51/61/121 CNS-CS-4 3
- FORMER PIPE WHIP EXAM *
( NSA N0Z 90 DAZ ) GL 88-01 (PSI,UTO,F84) ALSO REF: JELCO DWG 2502-1...
CSA-BF-4A CS-A 1 A P-E 10 0.631 P20/P2 4/49 CNS-CS-4 2 ALSO REF: JELCO DWG 2502-1...
CSB-BJ-2* CS-B 1 A P-SE 10 .594 P20 49 2502-1 1 RI-08
- FORMER PIPE WHIP EXAM CSQ-BJ-3* CS-B . 1 A PP 10 .594 P20 49 2502-1 1 RI-08
- FORMER PIPE WHIP EXAM CSB-BJ-4 CS-B 1 A P-P .10 .594 P20 49 2502-1 2 RI-08 CSB-BF-1* CS-B 1 A SE-N 13.44 1.06 P20/RP 61/51 CNS-CS-3 1
- FORMER PIPE WHIP EXAM, NSB (ALSO REF JELCO DWG 2502-1) (PSI,F84)
CSB BF-4A CS-S 1 A P-E 10 0.631 P20/P2 4/49 CNS-CS-3 1 ALSO REF JELCO DWG 2502-1 JPA BF-1 JPI-A 1 A SE-N 6 0.828 P20/RP 107/109 CE.232-241 2 ( JPI-A ) GL 88-01 (PSI,UTO,F84,EDS # N-433) ,
ALSO REF CB&I DWG 20. !
REFER TO SIL 455 REY. 1 FOR ADDITIONAL COVERAGE REcopetENDATIONS; DUE To INCONEL 182 FILLER MATERIAL AND BUTTERING JPB-BF-1 JPI-B 1 A SE-N' 6 0.828 P20/RP 107/109 CE.232-241 3 ( h8B N0Z ) GL 88-01 (PSI,UTO,F84,EDS # N-433)
ALSO REF CB&I DWG 20.
REFER TO SIL 455 REV. 1 FOR ADDITIONAL COVERAGE REC 0l#EENDATIONS; DUE TO INCONEL 182 FILLER MATERIAL AND BUTTERING CWA-BJ-1* RR-A 1 A WOL-P 6 .432 P20 48 2503-1 2 RI-08
- FORMER PIPE WHIP EXAM
- ALSO REFERENCE JELCO DWG
- 2511-1 AND NPPD DWG t
- Ces-RR-37...
CWA-BJ-2 RR-A 1 A P-P - 6" .432" P20 48 2503-1 3 RI-08 '
CWA-BJ-3 RR-A 1 A P-P 6" .432" P20 48 2503-1 RI-08 CWA BJ-4 RR-A 1 A P-YA 6 .432 P20 48 2503-1 3 RI-08 RAD-BF-7 RR-A 1 A P-P 24 1.218 P20/P3 55/106 CNS-RR-37 3 FROM RHR "A"... INCLUDE'S '
INTERSECTION OF ADJ. LS RAD-BJ-40A (C.S. PIPE !
SIDE) .
RAD-BJ-1 RR-A 1 A PU-P 28 1.250 P20 56 CNS-RR-37 3 RI-08 f RAD-BJ-2 RR-A 1 A P-VA 28 1.250 P20 56 CNS-RR-37 3 RI-08 i RAD-BJ-3 RR-A 1 A VA-P 28 1.250 P20 56 CNS-RR-37 3 RI-08 I
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AUG"ENTED INSERVICE INSPECT 104 TAB: 5 COOPER NUCLEAR STATION GENERIC LETTER 88-01 . INSERVICE INSPECTION PROGRAM REY: 1.1 THIRD INTERVAL P I PE . . . . . . . . . . . . . . . . . . SYSTEM. . CNT. I GSCC CF I G. . . SIZE. . T KNS. . . . . MAT. . . W81. CAL. . . I S0. . . . . . . . . . . . . . . . . PER RELREQ REMARKS. . .. . . . . . . . . . . . . . .
RAD-BJ-4 RR-A 1 A P-T 28" 1.250" P20 56 CNS-RR-37 2 RI-D8 CAD-8J-5 RR-A 1 A T-4W 30" 2.250" P20 58 CNS-RR-37 RI-08
- 2512-1...
QQM BJ-1 RR-A 1 A 4W-P. 22" 1.125" P20 54 CNS-RR-37 RI-08 RAM-BJ-2 RR-A 1 A 4W-P 22" 1.125" P20 54 CNS-RR-37 RI-08 RAS-BF-1 RR-A 1 A N-SE ' 29 1.973 P20/RP 59/57 CNS-RR-37 1 N1A RAS BF-12 RR-A 1 A P-P 20 1.031 P20/P3 53/103 CNS-RR-37 1 (TO RRR) INCLUDE'S INTERSECTION OF ADJ. LS RNA-BJ-3A (C.S. PIPE
, . SIDE)... -
RAS-BJ-10 RR-A 1 A E-WOL 20-6 1.4/1.6 P20 53/108 CNS-RR-37 2 RI-08 ALSO REFERENCE JELCO DWG
- 2511-1 AND DWG 'I
- 2503-1...
AAS-BJ-11 RR-A 1 A E-E 20 1.031 P20 53 CNS-RR-37 1 RI-08 ALSO REFERENCE JELCO DWG
- 2511-1... :
RAS-BJ-2 RR-A 1 A SE-P 28 1.250 P20 56 CNS-RR*37 1 RI-08 '
RAS-BJ-3 RR-A 1 A P-T 28" 1.250" P20 56 CNS-RR-37 RI-08 RAS-BJ-4 RR-A 1 A T-P 28" 1.250" P20 56 CNS-RR-37 RI-08 RAS-BJ-5 RR-A 1 A P-VA 28" 1.250" P20 56 CNS-RR-37 RI-OS RAS-BJ-6 RR-A 1 A VA-P 28" 1.250" P20 56 CNS-RR-37 RI-08 RAS-BJ-6A RR-A 1 A P-WOL 28-4 P20 CNS-RR-37 RI-08 ,
RAS BJ-6B RR-A 1 A WOL-F 4" P20 CNS-RR-37 RI-08 RAS-BJ-7 RR-A 1 A P-E 28" 1.250" P20 56 CNS-RR-37 RI-08 RAS-BJ-8 RR A 1 A E5PU 28" 1.250" P20 56 CNS-RR-37 RI-08 RAS-BJ-9 RR-A 1 A T-E 20 1.031 P20 53 CNS-RR-37 1 RI-08 ALSO REFERENCE JELCO DWG !
- 2511-1...
RRF-BF-1 RR-A 1 A SE-N 14 1.187 P20/RP 52/60/121 CNS-RR-37 3 ( N2F N0Z 210 DAZ ) i RRF-BJ-2 RR-A 1 A P-SE. 12 .688 P20 50 CNS-RR-37 RI-08 RRF-BJ-3 RR-A 1 A P-P 12" .688" P20 50 CNS-RR-37 RI-08 RRF-BJ-4 RR-A 1 A .P-P 12" .688" P20 50 CNS-RR-37 RI-08 :
RRF-BJ-5 RR-A 1 A R-P 12" .688" P20 50 CNS-RR-37 RI-08 l 2RG-BF-1 RR-A 1 A SE-N- 14 1.187 P20/RP 52/60/121 CNS-RR-37 3 ( N2G N0Z 240 DAZ )
RRG-BJ-2 RR-A 1 A P-SE 12 .688 P20 50 CNS-RR-37 RI-08 RRG-BJ-3 RR-A 1 A T'P 12" .688" P20 50 CNS-RR-37 RI-08 RRH BF-1 RR-A 1 A SE-N 14 1.187 P20/RP 60/52 CNS-RR-37 1 N2M RRM-BJ-2 RR-A 1 A P-SE 12 .688 P20 50 CNS-RR*37 1 RI-08 RRM-BJ-3 RR-A 1 A R-P 12" .688" P20 50 CNS-RR-37 2 RI-08 RRJ-BF-1 RR-A 1 A SE-N 14 1.187 P20/RP 60/52 CNS-RR-37 2 N2J RRJ-BJ-2 RR-A 1 A P-SE 12 .688 P20 50 CNS-RR-37 RI-08 RRJ-BJ-3 RR-A 1 A T-P 12" .6S8" P20 50 CNS-RR-37 RI-08 [
RSK-BF-1 RR-A 1 A SE-N 14 1.187 P20/RP 60/52 CNS-RR-37 2 N2K RSK-BJ-2 RR-A 1 A P-SE 12 .688 - P20 50 CNS-RR-37 RI-08 RRK-BJ-3 RR-A 1 A P-P 12" .688" P20 50 CNS-RR-37 RI-08 RRK-BJ-4 RR-A 1 A PyP 12" .688" P20 50 CNS-RR-37 RI-08 RRK-BJ-5 RR-A 1 A R-P - 12" .688" P20 50 CNS-RR-37 RI-08 PAGE'2
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t AUGMENTED INSERVICE INSPECTION TAB: 5 . COOPER NUCLEAR STATION GENERIC LETTER 88-01
- INSERVICE INSPECTION PROGRAM REY: 1.1
. THIRD INTERVAL P!PE.................. SYSTEM.. CNT. ICSCC CFId.. 512E.. TKNS..... MAT... W81. CAL.. 150................. PER RELREQ REMARKS..................
RBD-BF-7 RR-8 1 A P-P 24 1.218 P20/P3 55/106 CNS-RR-38 2 FROM RMR "B"... INCLUDE'S
+
INTERSECT!DN OF ADJ. LS RBD-BJ-40A (C.S. PIPE SIDE)
RBD-BJ-1 RR-B 1 A PU-P .28" 1.250" P20 -56 CNS-RR-38 RI-08 i 1 A 28" 1.250"
^
QBD-BJ-2 RR-B P-VA P20 56 CNS-RR-38 RI-08 RBD-BJ-3 RR-B 1 A VA.-P 28" 1.250" P20 56 CNS-RR-38 RI-08 RBD-BJ-4 RR-B 1 A P-T 28 1.250 P20 56 CNS-RR-38 RI-D8 -
RBD-BJ-5 RR-B 1 A T-4W 30" 2.250" P20 58 CNS-RR-38 RI-08 ;
RBD-BJ-6 RR-B 1 A P-T 24 1.218 P20 55 CNS-RR-38 2 RI-08 ALSO REFERENCE JELCO OWG 5
_ #2512-1...
RBM-BJ-1 RR-B 1 A ~4W-P' 22" 1.125" P20 54 CNS-RR-38 RI-08 RBM-BJ 2 RR-B 1 A 4W-P 22" 1.125" P20 54 CNS-RR-38 RI-08 RBS BF-1 RR-B 1 A N-SE - 29 1.973 P20/RP 57/59 CNS-RR-38 3 N1B RBS-BJ-2 RR-B 1 A SE-P 28" 1.250" P20 56 CNS-RR-38 RI-08 RBS-BJ-3 RR-B 1 A P-P. 28" 1.250" P20 56 CNS-RR-38 RI-08 L RBS-BJ-4 RR-B 1 A P-P 28" 1.250" P20 56 CNS-RR-38 RI-08 !
RBS-BJ-5 RR-B 1 A P-VA 28" 1.250" P20 56 CNS-RR-38 RI-08 ROS-BJ-6 RR-B 1 A VA-P 28" 1.250" P20 56 CNS-RR-38 RI-08 l R BS- B J- 6A RR-B 1 A P-DOL 28-4 1.25 P20 56 CNS-RR-38 3 RI-08 RBS-BJ-6B RR-B 1 A WOL-F 4" P20 CNS-RR-38 RI 08 RBS-BJ-7 RR B 1 A P-E - 28" 1.250" P20 56 CNS-RR-38 RI-08 i RBS-BJ-8 RR-B 1 A E-PU 28" 1.250" P20 56 CNS-RR-38 RI-08 i RRA-BF-1 RR-B 1 A SE-N 14 1.187 P20/RP 60/52/121 CNS-RR-38 3 N2A RRA-BJ-2 RR-B 1 A 'P-SE 12 .688 P20 50 CNS-RR-38 3 RI-08 I RRA-BJ-3 RR-B 1 A P-P 12" .688" P20 - 50 CNS-RR-38 RI-08 RRA-BJ-4 RR-B 1 A P-P 12" .688" P20 50 CNS-RR-38 RI-08 RRA-BJ 5 RR-B 1 A R-P 12" .688" P20 50 CNS-RR-38 RI-08 RRB BF-1 RR-B 1 A SE-N 14 1.187 P20/RP 60/52/121 CNS-RR-38 3 N2B RRB BJ-2 RR-B 1 A P-SE 12 .688 . P20 50 CNS-RR-38 3 RI-08 ,
RRB-BJ-3 RR-B 1 A T-P 12" .688" P20 50 CNS-RR-38 RI-08 '
RRC-BF-1 RR-B 1 A SE-N' 14 1.187 P20/RP 60/52 CNS-RR-IS 1 N2C RRC BJ-2 RR-B 1 A P6SE 12 .688 P20 50 CNS-RR-38 RI-08 ,
RRC-BJ-3 RR-B 1 A R-P 12" .688" P20 50 CNS-RR-38 RI-08 RRD-BF-1 RR-B 1 A SE-N 14 1.187 P20/RP 60/52/121 CNS-RR-38 3 N20 RRD BJ-2 RR-B 1 A P-SE 12 .688 P20 50 CNS-RR-38 3 RI-08 RRD-BJ-3 RR-B 1 A T-P 12" .688" P20 50 CNS-RR-38 RI-08 RRE-BF-1 RR-B 1 A SE-N 14 1.187 P20/RP 60/52 CNS-RR-38 1 N2E RRE-BJ-2 RR-B 1 A P-SE- 12 .688 P20 50 CNS-RR-38 1 RI-08 RRE BJ-3 RR-B 1 A P-P' 12 .688 P20 50 CNS-RR-38 2 RI-08 !
RRE-BJ-4 RR-B 1 A P-P 12 .688 P20 50 CNS-RR-38 2 RI-08 RRE-BJ-5 RR-B 1 A R-P 12 .688 P20 50 CNS-RR-38 2 RI-08 CWA-BJ-10 RWCU 1 A E-P 6 .432 P20 48 2503-1 1 RI-08 CWA-BJ-11 RWCU 1 A P-FM 6" .432" P20 48 2503-1 RI-01 INACCESSIBLE, INSIDE CONTAINMENT PENETRATION X-14... ALSO REFERENCE PAGE 3
AUGMENTED INSERVICE INSPECTION TAB: 5 COOPER NUCLEAR STATION GENERIC LETTER 88-01 INSERVICE INSPECTION PROGRAM REY: 1.1 THIRD INTERVAL P I PE. . . . . . . . . . . . . . . . . . SYSTEM. . CNT. I GSCC CF I G. . . SI ZE . . TKN S. . . . . MAT. . . W81. CAL . . 150. . . . . . . . . . . . . . . . . PER RELREQ REMARKS. . . . . . . . . . . . . . . . . .
NPPD DWG CNS-RWCU-3...
CWA BJ-14 RWCU 1 A P-P 6" .432" P20 48 2503-1 RI-08 CWA BJ-15 RWCU 1 A FM-P 6 .432 P20 48 2503-1 2 RI-08 (PSI F91) REPLACED RWCU-MO-18 VLV, THIS
' REPLACED WELD NO.
CWA-BJ-12 CWA-8J-16 RWCU 1 t. P-V 6" 432" P20 48 2503-1 RI-08 (PSI F91) REPLACED RWCU-MO-13 VLV, THIS IS A NEW WELD CWA BJ-17 RWCU 1 A PV 6" 432" P20 48 2503-1 RI-08 (PSI F91) REPLACED RWCU-Mo-15 VLV, THIS REPLACED WELD NO.
CWA-BJ-7 CWA BJ-18 RWCU 1 A 'V-P. 6" .432" P20 48 2503-1 RI-08 (PSI F91) REPLACED RWCU-Mo-15 VLV, THIS REPLACED WELD NO.
CWA-BJ-8 CWA BJ-5 RWCU 1 A VA ,P 6 432 P20 48 2503-1 3 RI-08 CWA-BJ 6 RWCU 1 A P-P 6" .432" P20 48 2503-1 RI-08 CWA-BJ 9 RWCU 1 A P-E 6" 432" P20 48 2503-1 RI-08 106 =
RCA-BF-1 NB 1 D N-C 5.25 160 P18/RP 20 CE.232-242 3 ( M9 NOZ ) GL 88-01, CAP MAT. IS N!.GR.FE AND INCONEL 182 WITM INCONEL 82 WELD FILLER METAL...
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Cooper Station 3rd Interval Inservice Inspection Program 11.8 CORE SPRAY T-BOX INSPECTION Revision 1 GE SIL 289 Revision 1 Supplement I reported crack like indications in the T-box welds during the Core Spray sparger inspections required by IEB 80-13. CNS will include the accessible T-box welds in the visual (VT-1) examinations required by IEB S0-13 in accordance with the guidance of BWRVIP-18.
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(11.8-1) Revision 1.1 J
Cooper Sta: ion 3rd Interval Inservice Inspection Program 11.13 INSPECTION OF JET PUMP SENSING LINES l Revision 1 J l
General Electric Company Service Information Letter (SIL) No. 420, dated March 28,1985, documents the discovery of fatigue failures (cracking) of the Jet Pump sensing lines and sensing line support brackets in the reactor vessel of two domestic BWRs. SIL 420 recommends that the Jet Pump sensing lines and brackets receive a visual (VT) examination when convenient due to the effect of failures on Jet Pump flow surveillance and Technical Specification requirements.
CNS performs visual examinations of the Jet Pump sensing lines (VT-3) and sensing line brackets (VT-1) during each inspection period in conjunction with scheduled ISI jet pump examinations, i
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(11.13-1) Revision 1.1
Cooper Station 3rd Interval ~
Inservice Inspection Program 11.15 REACTOR CORE SHROUD Revision 1
REFERENCES:
- 1. USNRC Generic letter 94-03, dated July 25,1994: Intergranular Stress Corrosion Cracking of Core Shrouds In Boiling Water Reactors.
- 2. Ietter dated August 26,1994, G. R. Horn to USNRC: Response to Generic letter 94 Core Shroud Cracking.
- 3. Letter dated July 14,1995, G. R. Horn to USNRC: Core Shroud Inspection Plan.
- 4. Ietter dated December 8,1995, J. M. Mueller to USNRC: Core Shroud Inspection Results.
- 5. GENE-523-113-0894 dated March 1995, "BWR Core Shroud Inspection and Flaw Evaluation Guidelines".
- 6. Ixtter U.S. NRC to G. R Horn (NPPD). Dated June 27,1996, .
Core Shroud Inspection and Flaw Evaluation (TAC NO.
M94401).
- 7. Ixtter dated October 22,1996,P.D. Graham to USNRC: Core Shroud Re-Inspection.
~
Reference 1, notified utilities of the potential for intergranular stress corrosion cracking of core shrouds in boiling water reactors. In Reference 2, CNS conunitted to perform an inspection of the Core Shroud during the 1995 refueling outage. CNS provided the core shroud inspection plan, flaw evaluation criteria, and repair plan in Reference 3. The examination was completed and the results provided in Reference 4. Indications found during the inspection were evaluated and accepted by CNS in accordance with Reference 5. In Reference 6, the NRC concluded that the core shroud inspection and flaw evaluations are acceptable, and that .CNS can be safely operated for at least one 18-month fuel cycle without implementing a repair of the core shroud. ,,
In Reference 7,;CNS requested deferral of the the Core Shroud re-inspection for one sdditional fuel cycle while the NRC reviews EPRI TR-105747, "BWR Vessel and Internals Project Guidelines for Reinspection of BWR Core Shroud (BWRVIP-07)". The frequa cv and extent of future examinations of the Core Shroud have not been determined at this tim 11.15-1 Revision 1.1
Cooper Station 3rd Interval Inservice Inspection Program 11.16 INSTRUMENT NOZZLE SAFE ENDS Revision 1 i
\
Augmented supplemental volumetric examinations of the entire instmment nozzle safe end for nozzles N10, N11A/B, and N16A/B will be performed when flaws are detected during the l scheduled surface examination in accordance with the ISI program. The surface examination
{
will be extended to cover the entire nozzle safe end. These examinations are recommended in j GE SIL No. 571. <
Nozzles N12A/B are exempt from examination by the rules of ASME Section XI. If relevant 1 indications are found in the above listed nozzles, CNS will also perform supplemental j examinations of nozzles N12A/B.
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Cooper Station 3rd Interval Inservice Inspection Program 11.18 TOP GUIDE & CORE PLATE Revision 1 A visual examination of the members which provide the load path between the alignment pins, the Top Guide, and the Core Shroud will be performed during the invessel visual examinations required by the Code as recommended by GE SIL No. 588 RI. In addition, the 90 degree aligner pin assembly inspected during the 1995 refueling outage will be reinspected during the 1997 refueling outage.
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t 11.18-1 Revision 1.1
Cooper Station 3rd Interval Inservice Inspection Program 1
11.20 REFUELING PLATFORM Revision 1 i i
Visual examinations of the refueling platform structural mtegrity is r" controlled by this !
program. j i
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Cooper Station 3rd Interval Inservice Inspection Program 11.21 INSPECTION OF JET PUMP ADJUSTING SCREWS Revision 0 General Electric Company Service Information Letter (SIL) No. 574, identified a concern with the jet pump adjusting screw and recommended that they be visually examined.
CNS performs visual examination of the Jet Pump adjusting screws and tack welds during each inspection period in conjunction with scheduled ISI jet pump examinations.
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1 11.21-1 Revision 1.1
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Cooper Station 3rd Interval Inservice Inspection Program 16.0 COMPONENT EXAMINATION
SUMMARY
LISTING All components and component supports potentially subject to inservice NDE examination under the 1989 Edition of Section XI are contained in the following Tables.
The tables identify those components and component supports selected for examination during the third inspection interval and provides a schedule by period, for the applicable required examination to be performed. The components and component supports selected are those scheduled to be examined during the third interval. The total number of components and component supports for each Code Category and item number by system are provided in the tables.
Where regulatory requirements or specific CNS commitments impose additional examinations or use NDE techniques exceeding Code requirements, these augmented requirements are shown in the tables. The examination data will be used to saafy both Code and augmented requirements, e.g., GL 88-01, NUREG 0619 GL 94-03, etc.
There are three tables divided by Code Class and sorted by; Code Category / Item No., System, Unique Mark No., Configuration, Scheduled Period, and required NDl' examination method.
The fourth table identifies the component supports required to be exam'ned.
(16-1) Revision 1.1
IWB-2500-1 CAT: B-D COOPER NUCLEAR STATION INSERVICE INSPECTION PROGRAM REV: 1.1 THIRD INTERVAL P!PE........... ...... SYSTEM.. CNT. ITEM.NO. CFIG... SIZE.. TKNS..... KAT... W81. CAL.. 150................. PER RELREQ REMARKS..................
NVIR-BD-N1A NB 1 B3.160 NIR 28 ---
RPV 1 22,24 CE.232-231 1 CA - COMPOUND ANGLE NVIR-BD-N1B NB 1 83.100 NIR 28 ---
RPV 1 16 CE.232-231 3 CA - COMPOUND ANGLE NVIR-BD-N2A NB 1 83.100 NIR 12 ---
RPV 1 16 CE.232-231 3 CA - COMPOUND ANGLE NVIR-BD-N2B NB 1 B3.100 NIR 12 ---
RPV 1 16 CE.232-231 3 CA - COMPOUND ANGLE NVIR-BD-N2C NB 1 B3.100 NIR 12 ---
RPV 1 22,25 CE.232-231 1 CA - COMPOUND ANGLE NVIR-BD-N2D NB 1 B3.100 NIR 12 . ---
RPV 1 16 CE.232-231 3 CA - COMPOUND ANGLE NVIR-BD-N2E NB 1 B3.100 NIR - 12 ---
RPV 1 22,25 CE.232-231 2 CA - COMPOUND ANGLE NVIS-BD-N2F NB 1 B3.100 NIR 12 ---
RPV 1 22,25 CE.232-231 1 CA - COMPOUND ANGLE NVIR-BD-N2G NB 1 B3.100 NIR 12 ---
RPV 1 22,25 CE.232-231 1 CA - COMPOUND ANGLE NVIR-BD-N2H NB 1 83.100 NIR 12 ---
RPV 1 22,25 CE.232-231 1 CA - COMPOUND ANGLE NVIR-BD-N2J NB 1 B3.100 NIR 12 ---
RPV 1 22,25 CE.232-231 2 CA - COMPOUND ANGLE NVIR-BD-N2K NB 1 B3.100 NIR 12 ---
RPV 1 22,25 CE.232-231 2 CA - COMPOUND ANGLE NVIR-BD-N3A NB 1 83.100 NIR 24 ---
RPV 1 22,26 GE.731E611 1 CA - COMPOUND ANGLE NVIR-BD*N38 NB 1 B3.100 NIR 24 ---
RPV 1 22,26 GE.731E611 2 CA - COMPOUND ANGLE NVIR-BD-N3C NB 1 B3.100 NIR 24 ---
RPV 1 16 GE.731E611 3 CA - COMPOUND ANGLE NVIR-BD N30 NB 1 B3.100 'NIR 24 ---
RPV 1 22,26 GE.731E611 2 CA - COMPOUND ANGLE NVIR-BD-N4A NB 1 B3.100 NIR 12 ---
RPV 1 16 CE.232-231 2 NUREG 0619... UT IN LIEU OF PT F91... CA-COMPOUND ANGLE...
NVIR-BD-NtB NB 1 B3.100 NIR 12 ---
RPV 1 16 CE.232-231 1 NUREG 0619... UT IN LIEU OF PT F91... CA-COMPOUND ANGLE...
NVIR-BD-N4C NB 1 83.100 N!R 12 ---
RPV 1 16 CE.232-231 3 NUREG 0619... UT IN LIEU OF PT F91... CA-COMPOUND ANGLE...
NVIR-BD-N4D NB 1 B3.100 NIR 12 ---
RPV 1 16 CE.232-231 1 RUREG D619... UT IN LIEU OF PT F91... CA-COMPOUND ANGLE..
NVIR-BD-NSA NB 1 B3.100 NIR 10 ---
RPV 1 22,28 CE.232-231 2 CA - COMPOUND ANGLE NVIR-BD-NSB NB 1 B3.100 N!R 10 ---
RPV 1 16 CE.232-231 3 CA - COMPOUND ANGLE NVIR-BD-N$A NB 1 B3.100 N!R 6 ---
RPV 1 N/A CE.232-244 3 RI-03 (RI-03 RELIEF REQUEST)
N6A NO2, RPV TP.HD 0 DAZ, ALSO REF: GE DWG BA-3 AND BA-4 NVIR-BD-N6B NB 1 33.100 NIR 6 ---
RPV 1 N/A CE.232-244 2 RI-03 (RI-03 RELIEF REQUEST)
N6B NO2, RPV TP.RD 180 DA2 NVIR-BD-N7 NB 1 B3.100 NIR 6 ---
RPV 1 N/A CE.232-244 1 RI-03 (RI-03 RELIEF REQUEST) N7 NO2, RPV TP. HD, CENTER OF TP.HD NVIR-BD-NBA NB 1 B3.100 NIR S ---
RPV 1 22,29 CE.232-241 2 CA - COMPOUND ANGLE (LOC.
DW. 928' *05 DAZ)
NVIR-BD-N8B NB 1 B3.100 NIR 5 ---
RPV 1 16 CE.232-241 3 CA - COMPOUND ANGLE ( N8B NO2 ) LOC. DW 928' 285 DA2, ALSO REF: GE DWG
( BA-2 AND BN-3 PAGE 1
_ _ _ ~ _ . _ _ _ _ _ _ m two-2500 1 CAT: B-D COOPER NUCLEAR STATION INSERVICE INSPECTION PROGRAM REY: 1.1 -
, THIRD IkTERVAL PIPE....... .... ..... SYSTEM.. CNT. ITEM.NO.'CFIG... SIZE.. TKNS..... KAT... WB1. CAL.. 150................. PER RELREQ REMARKS.................. ,
f NVIR-BD-N9 NB 1 83.100 WIR S ---
RPV 1 16 CE.232-242 3 ( N9 N0Z ) ALSO REF: GE DWG BA-2 AND BN-3, LOC DW 962' 146 DAZ, EXAM LIMITED DUE TO PROXIMITY RPV INSULATION SUPPORT !
RING E
, 28 ***
NVE-BD N1A NB 1 B3.90 N-VE '- 28 7.2 RPV 1 16 CE.232-231 1 RI-21 NVE-BD N1B NB 1 B3.90 N-VE 28 7.2 RPV 1 16 CE.232-231 3 RI-21 t NVE-BD-N2A NB 1 83.90 N-VE 12 7.2 RPV 1 16 CE.232-231 3 RI-21 NVE-BD-N2B NB 1 B3.90 N-VE 12 7.2 RPV 1 16 CE.232-231 3 RI-21 NVE-BD-N2C NB 1 83.90 N-VE 12 7.2 RPV 1 16 CE.232-231 1 RI-21 i NVE-BD-N2D NB 1 83.90 . N-VE 12 7.2 RPV 1 16 CE.232-231 3 RI-21 N VE -BD- N 2E NB 1 83.90 N-VE 12 7.2 RPV 1 16 CE.232-231 2 RI-21 N VE -BD- N 2 F NB 1 B3.90 N-VE 12 7.2 RPV 1 16 CE.232-231 1 RI-21 NVE-BD-N2G NB 1 B3.90 N-VE 12 7.2 RPV 1 16 CE.232-231 1 RI-21 NVE-BD-N2M NB 1 83.90 N-VE 12 7.2 RPV 1 16 CE.232-231 1 RI-21 l NVE-BD-N2J NB 1 B3.90 N-VE, 12 7.2 RPV 1 16 CE.232-231 2 RI-21 '
NVE-BD-N2K NB 1 B3.90 N-VE 12 7.2 RPV 1 16 CE.232-231 2 Rt-21
- NVE-BD-N3A NB 1 83.90 N-VE 24 6.2 RPV 1 16 GE.731E611 1 RI-21 -I NVE-BD-N38 NB 1 83.90 N-VE 12 6.2 RPV 1 16 GE.731E611 2- RI 21 i NVE-BD-N3C NB 1 B3.90 N-VE 24 6.2 RPV 1 16 GE.731E611 3 RI-21 NVE-BD-N30 NB 1 83.90 ,.N-VE 24 6.2 RPV 1 16 GE.731E611 2 RI-21 !
NVE-BD-N4A NB 1 B3.90 N-VE 12 6.2 RPV 1 16 CE.232-231 2 RI-21 l NVE-BD-N48 NB 1 B3.90 N-VE 12 6.2 RPV 1 16 CE.232-231 1 RI-21 NVE-BD-N4C NB 1 83.90 .N-VE 12 6.2 RPV 1 16 CE.232-231 3 RI-21 ,
NVE-BD-N4D NB 1 B3.90 N-VE 12 6.2 RPV 1 16 CE.232-231 1 RI-21 NVE BD-N5*. NB 1 B3.90 N-VE 10 6.2 RPV 1 16 CE.232-231 2 RI-21 ( NSA NCZ ) LOC. DW. 962' '
90 DAZ NVE-BD-NSB NB 1' 83.90 u-VE 10 6.2 RPV 1 16 CE.232-231 3 RI-21 ( NSB N0Z ) LOC. DW. 962' 270 DAZ NVE-BD-N6A NB 1 83.90 N-VE 6 3.2 RPV 1 15 CE.232-244 3 RI-21 ( N6A NOZ ) RPV TP.HD 0 I DAZ. ALSO REF: GE DWG t BA-3 AND BA-4 NVE-BD-N6B NB 1 83.90 - N-VE 6 3.2 RPV 1 15 CE.232-244 2 RI-21 ( N68 N0Z ) RPV TP.HD 180 DAZ NVE-BD-NT NB 1 83.90 N-VE 6 3.2 RPV 1 15 CE.232-244 1 RI-21 ( NT N0Z ) RPV TP.ND, CENTER OF TP.ND NVE-BD-NBA Na 1 B3.90 N-VE 5 7.2 RPV 1 16 CE.232-241 2 RI-21 ( NBA NOZ ) LOC. DW. 928' 105 DAZ ,
NVE-BD N88 NB 1 B3.90 N-VE 5 7.2 RPV 1 16 CE.232-241 3 Rt-21 ( NB8 NOZ ) LOC. DW. 928' ;
3 285 DAZ, ALS3 REF: GE DWG BA-2 AND BN-3 NVE-BD N9 NB 1 83.90 N-VE 5 6.2 RPV 1 16 CE.232-242 3 RI-21 ( M9 N0Z ) ALSO REF: GE
- PAGE 2 r
- ____.__ __ _ _ _ _ _ _ _ _ _ ___m _ _ _ _ _ _ . _ _ __ _ _ _ . _ _ _ _ _ . . _ _ _ _ _ _ _ -_ ___m____._-_ -==-7'e-
1WB-2500-1 CAT: B-D COOPER NUCLEAR STATION INSERVICE INSPECTION PROGRAM REV: 1.1 THIRD INTERVAL P!PE.................. SYSTEM.. CNT. ITEM.NO. CFIG... SIZE.. TKNS..... MAT... V81. CAL... IS0................. PER RELREQ REMARKS..................
DWG BA-2 AND BN-3, LOC DW 962' 146 DAZ, EXAM LIMITED DUE TO PROXIMITY
~
OF RPV INSULATION SUPPORT RING AND THE N4A N0ZZLE 28 ***
- 56 PAGE 3
Cooper Station 3rd Interval Inservice Inspection Program Category B-N-1 and B-N-2 RPV INTERNALS EXAMINATION REQUIREMENTS COMPONENT CATEGORY METHOE FREQUENCY REMARKS Jet Pumps B-N-1 VT-3 Each Period Jet Pump Nozzle & Mixer AUG VT-3 Each Period SIL 465 S1 Jet Pump Sensing Lines and Suppoit Brackets AUG VT-1/3 Each Period SIL 420 Jet Pump Adjusting Screw AUG VT-3 Each Period SIL 574 Jet Pump Riser Attachments,1-10 B-N-2 VT-1 Each Interval SIL 551 Jet Pump Riser Attachments,11-20 B-N-2 VT-1 Each Interval SIL 551 Jet Pump Beams AUG UT Each Interval NUREG CR/3052 Surveillance Specimen Holders B-N-1 VT-3 Each Period Surveillance Specimen Holder #1 Bracket B-N-2 VT-1 Each Interval Surveillance Specimen Holder #2 Bracket B-N-2 VT-1 Each Interval Surveillance Specimen Holder #3 Bracket B-N-2 VT-1 Each Interval Vessel Interior Wall B-N-1 VT-3 Each Period Acces3ible Areas Vessel Head Interior B-N-1 VT-3 Each Period Steam Dryer Support Lugs B-N-2 VT-3 Each Interval Steam Dryer Hold Down Lugs B-N-2 VT-3 Each Interval 1 Revision 1.1 l_ ____ _ _ _ _ ______
Cooper Station 3rd Interval Inservice Inspection Program RPV INTERNALS EXAMINATION REQUIREMENTS COMPONENT CATEGORY METHOD FREOUENCY REMARKS Steam Drver & Drain Channel AUG VT-3 Each Period SIL 474 Steam Separator AUG VT-3 Each Interval CS Sparger and Piping B-N-1 UT/VT-1 Each Outage IEB 80-13, BWRVIP-18 CS Piping Brackets B-N-2 VT-3 Each Interval BWRVIP-18 CS Tee Junction AUG VT-1 Each Outage SIL 289 R1, S1, BWRVIP-18 FW Sparger B-N-1 VT-3 Each Period VT-1 per NUREG-0619 FW Sparger Brackets B-N-2 VT-3 Each Interval Guide Rods -
B-N-1 VT-3 Each Period Guide Rod Brackets B-N-2 VT-3 Each Interval .,
Core Shroud B-N-2 UT/VT-1 Each Interval GL 94-03 Old Style Shroud IIead Bolts AUG UT Each Outage SIL 433 Lower Shroud B-N-2 VT-3 Each Interval As Accessible Support Plates,0-180 B-N-2 VT-3 Each Interval 11 Plates Support Plate Attachments,0-180 B-N-2 VT-1 Each Interval 11 Attachments Support Plates, 180-360 B-N-2 VT-3 Each Interval 11 Plates Support Plate Attachments, 180-360 B-N-2 VT-1 Each Interval i 11 Attachments 2 Revision 1.1
--___._--_--_-__._-w.__.__- _---_----.._. - -__.-- - -___ _ _ _ _
t Cooper Station 3rd Interval inservice Inspection Program RPV INTERNALS EXAMINATION REQUIREMENTS COMPONENT CATEGORY METHOD FREQUENCY REMARKS ;
Access Hole Covers AUG VT-1 Each Outage SIL 462 R1, S1, S3 Access Hole Covers AUG UT Every 5 Years SIL 462 R1, S1, S3 SRMs, IRMs, LPRMs AUG VT-3 Each Interval SIL 409 R1 ICM Housing & Stub Tubes B-N-2 VT-3 Each Interval As Accessible SLC Pipe Penetration B-N-2 VT-3 Each Interval As Accessible '
RPV Bottom Head Drain Nozzle B-N-2 VT-3 Each Interval As Accessible Top Guide & Hardware B-N-2 VT-3 Each Interval SIL 588 R1 Core Plate & Hardware -
B-N-2 VT-3 Each Interval As Accessible, SIL 588 R1 Fuel Support Castings B-N-2 VT-3 Each Interval As Accessible CRD Housing & Stub Tubes B-N-2 VT-3 Each Interval As Accessible CRD Guide Tubes & Housing B-N-2 VT-3 Each Interval As Accessible i
~
3 Revision 1.1 I
. _ _ _ . _ . _ . ._. . _ . . _ _ . _ . . . _ . . . .. .....m . .. .m - . , _ _ _ _ _ _... _.. _.. - -.,_
l r
4 CODE CASE N-408-2 COOPER NUCLEAR STATION i IWC-2500-1 CAT: C-F-2 INSERVICE INSPECTION PROGRAM REV: 1.1 RLIC SYSTEM THIRD INTERVAL P ! PE . . . . . . . . . . . . . . . . . . SYSTEM. . CNT. I TEM.io. CF I G. . . S I ZE. , TKNS. . . . . MAT. . . W81. CAL. . . I S0. . . . . . . . . . . . . . . . . PER RELREQ REMARKS. . . . . . . . . . . . . . . . . .
RWA-CF-15 RCIC 1 P-E 6" .280" P1 2621-1 EXEMPT FROM NDE BASED ON
. WALL THICKNESS (N-408-2), ,
MUST BE INCLUDED IN TOTAL WELD POPULATION RWA-CF-16 RCIC i E-P 6" .280" P1 2621-1' EXEMPT FROM NDE BASED ON WALL THICKNESS (N-408-2),
MUST BE INCLUDED IN TOTAL !
WELD POPULATION RWA-Cr.17 RCIC 1 PE 6" .280" P1 2621-1 EXEMPT FROM NDE BASED ON
. WALL THICKNESS (N-408-2),
MUST BE INCLLCED IN TOTAL WELD POPULAT10N RWA-CF-18 RCIC 1 E-P 6" .280" P1 2621-1 EXEMPT FROM NDE BASED ON WALL THICKNESS (N-408-2), ,
MUST BE INCLUDED IN TOTAL WELD POPULATION !
RWA-CF-19 RCIC 1 P-E 6" .280" Pt 2621-1 EXEMPT FROM NDE BASED ON WALL THICKNESS (N-408-2),
MUST BE INCLUDED IN TOTAL WELD POPULATION-RWA-CF-20 RCIC 1 E-P 6" .280" P1 2621-1 EXEMPT FROM NDE BASED ON WALL TMICKNESS (N-408-2), !
MUST BE INCLUDED IN TOTAL
=
WELD POPULATION RWA-CF-21 RCIC 1 P-E 6" .280" P1 2621-1 EXEMPT FROM NDE BASED ON i WALL THICKNESS (N-408-2),
MUST BE INCLUDED IN TOTAL
. WELD POPULATION RWA-CF-22 RCIC 1 ,
E-P 6" .280" P1 2621-1 EXEMPT FROM NDE BASED ON l WALL THICKNESS (N-408-2), ;
e"JST BE INCLUDED IN TOTAL ,
t WELD POPULATION RWA-CF-23 RCIC 1 P-E 6" .280" P1 2621-1 EXEMPT FROM NDE BASED ON WALL THICKNESS (N-408-2), ,
MUST BE INCLUDED IN TOTAL WELD POPULATION RWA-CF-24 RCIC 1 E-P 6" .280" P1 2621-1 EXEMPT FROM NDE BASED ON WALL THICKNESS (N-408-2), ;
MUST BE INCLtBED IN TOTAL r WELD POPULATION !
RWA-CF-25 RCIC 1 P-E 6" .280" P1 2621-1 EXEMPT FROM NDE BASED ON WALL THICKNESS (N-408-2),
MUST BE INCLUDED IN TOTAL WELD POPULATION RWA CF-26 RCIC 1 E-P 6" .280" P1 2621-1 EXEMPT FROM NDE BASED ON WALL THICKNESS (N-408-2),
PAGE 1
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^
CODE CASE N-408-2
- COOPER NUCLEAR STATION IWC-2500 1 CAT: C-F-2 INSERVICE INSPECTION PROGRAM REV: 1.1 RCIC 57 STEM THIRD INTERVAL PIPE. ................ SYSTEM.. CNT. ITEM.NO. CFIC... SIZE.. TKNS..... MAT... W81. CAL., 150................. PER RELREQ REMARKS..................
MUST BE INCLUDED IN TOTAL WELD POPULATION RWA-CF-27 RCIC 1' P-E 6" .280" P1 2621-1 EXEMPT FROM NDE BASED ON WALL THICKNESS (N-408-2),
MUST BE INCLUDED IN TOTAL WELD POPULATION RWA CF-28 RCIC 1 E-V 6" .280" F1 2621-1 RCIC-LV-23, EXEMPT FROM NDE BASED ON WALL THICKNESS (N-408-2), MUST BE INCLUDED IN TOTAL WELD POPULATION RWA-CF-29 RCIC 1 V-P 6" .280" P1 2621-1 RCIC-LV-23 EXEMPT FROM NDE BASED ON WALL THICKNESS (N-408-2), MUST BE INCLUDED IN TOTAL WELD POPULATION RWA-CF-30 RCIC 1 P-E 6" .280" P1 2621-1 EXEMPT FROM NDE BASED ON WALL THICKNESS (N-408-2),
MUST BE INCLUDED IN TOTAL s WELD POPULATION RWA-CF-31 RCIC 1 E-P 6" .280" P1 2621-1 EXEMPT FROM NDE BASED ON WALL THICKNESS (N-408-2),
MUST BE INCLUDED IN TOTAL
. - WELD POPULATION RWA-CF-32 RCIC 1 P-E 6" .280" P1 2621-1 EXEMPT FROM NDE BASED ON WALL THICKNESS (N-408-2),
MUST BE INCLUDED IN TOTAL WELD POPULATION RWA-CF-33 RCIC 1 E-P 6a .280" P1 2621-1 EXEMPT FROM NDE BASED ON WALL THICKNESS (N-408-2),
MUST BE INCLUDED IN TOTAL WELD POPULATION RWA-CF-34 RCIC 1 P-V 6" .280" P1 2621 1 RCIC-MO-41, EXEMPT FROM NDE BASED ON WALL THICKNESS (N-408-2), MUST BE INCLUDED IN TOTAL WELD POPULATION RWA-CF-35 RCIC 1 V-P 6" .280" P1 2621-1 RCIC-MO-41, EXEMPT FROM NDE BASED ON WALL THICKNESS (N-408-2), MUST BE INCLUDED IN TOTAL WELD POPULATION RWA-CF-37 RCIC 1 P-V 6" .280" P1 2621-1 RCIC-CV-11. EXEMPT FROM NDE BASED ON WALL THICKNESS (N-408-2), MUST BE INCLUDED IN TOTAL WELD PAGE 2
- - - - - - . ,------------w------------_-a--------_:__----___- - - - -
CCDE CASE N-403-2 COOPER NUCLEAR STATICN IWC-2$CO-1 CAT: C-F-2 INSERV!CE INSPECTION PROGRAM REY: 1.1
, RCIC $7 STEM THIRD INTERVAL PIPE.................. SYSTEM.. CNT. ITEM.NO. CFIG... SIZE. TKNS..... MAT... W81. CAL... ISO................. PER RELREQ REMARKS..................
POPULATION CWA-CF-38 RCIC 1 V-T 6" .280" F1 2621-1 RCIC-CV-11, EXEMPT FROM NDE BASED ON WALL TMICKNESS (N-408-2), MUST BE INCLUDED IN TOTAL WELD POPULATION RWA-CF-39 RCIC 1 T-T 6" .280" F1 2621-1 EXEMPT FROM NDE BASED ON WALL TNICKNESS (N-408-2),
MUST BE INCLUDED IN TOTAL WELD POPULATION ,
RWA-CF-40 RCIC 1 T-V 6" .280" F1 2621-1 RCIC-CV-10, EXEMPT FROM NDE BASED ON WALL
, THICKNESS (N-408-2), MUST i 8E INCLUDED IN TOTAL WELD i POPULATION .
RWA-CF-41 RCIC 1 V-V 6" .280" F1 2621-1 RCIC-CV-10.TO.RCIC-MO-18, l EXEMPT FROM NDE 8ASED ON !
WALL THICKNESS (N-408-2),
MUST BE INCLUDED IN TOTAL ?
WELD POPULATION RWA-CF-42 RCIC 1 T-P 6" .280" P1 2621-1 EXEMPT FROM NDE BASED ON WALL THICKNESS (N-408-2),
MUST BE INCLUDED IN TOTAL .
I WELD POPULATION '
RWA-CF-42A RCIC 1 P-V 6" .280" P1 2621-1 RCIC-LV-10, EXEMPT FROM NDE BASED ON WALL THICKNESS (N-408-2), MUST !
BE INCLUDED IN TOTAL WELD POPULATION RWA-CF-43 RCIC 1 P-V 6" .280" P1 2621-1 RCIC-LV-10, EXEMPT FROM NDE BASED ON WALL TMICKNESS (N-408-2), MUST BE INCLUDED IN TOTAL WELD POPULATION RWA-CF-44 RCIC 1 E-P 6" .280" P1 2621-1 EXEMPT FROM NDE BASED ON .
WALL THICKNESS (N-408-2), l MUST BE INCLUDED IN TOTAL t WELD POPULATION RWA-CF-45 RCIC 1 P-F 6" .280" P1 2621-1 EXEMPT FROM NDE BASED ON WALL THICKNESS (N-408-2),
MUST BE INCLUDED IN TCTAL
. WELD POPULATION RWA-CF-46 RCIC 1 F-P 6" .280" P1 2621-1 EXEMPT FRCM NDE BASED ON WALL THICKNESS (N-408-2),
MUST 8E INCLUDED IN TOTAL WELD POPULATION PAGE 3
CODE CASE N-408-2 COOPER NUCLEAR STATION IWC-2500-1 CAT: C-F-2 INSERVICE INSPECTION PROGRAM REV: 1.1 RCIC SYSTEM TMIRD INTERVAL P ! PE . . . . . . . . . . . . . . . . . . SYST EM. . CNT. ITEM.NO. CF I G. . . SI ZE . . TKNS. . . . . MAT. . . W81. CAL. . . I S0. . . . . . . . .. . . . . . . . PE R RELREQ REMARKS. . . . . . . . . . . . . . . . . .
~
RWA-CF-47 RCIC 1 P-F 6" .280" P1 2621-1 EXEMPT FROM NDE BASED ON WALL THICKNESS (N-408-2),
MUST BE INCLUDED IN TOTAL WELD POPULATION RWA-CF-48 RCIC 1 F-P 6" .280" P1 2621-1 EXEMPT FROM NDE BASED ON WALL THICKNESS (N-408-2),.
MUST BE INCLUDED IN TOTAL WELD POPULATION RWA-CF-49 RCIC 1 P-PU 6" .280" Pt 2621-1 RCIC PUMP, EXEMPT FROM NDE BASED ON WALL THICKNESS (N-408-2), MUST BE INCLUDED IN TOTAL WELD POPULATION RWA-CF-50 RCIC 1 T-E 6" .280" F1 2621-1 EXEMPT FROM NDE BASED ON WALL TMICKNESS (N-408-2),
MUST BE INCLUDED IN TOTAL WELD POPULATION RWA-CF-51 RCIC 1 E-P 6" .280" P1 2621-1 EXEMPT FROM NDE 8ASED ON WALL THICKNESS (N-408-2),
MUST BE INCLUDED IN TOTAL WELD POPULATION RWA-CF-52 RCIC 1 P-E 6" .280" P1 2621-1 EXEMPT FROM NDE BASED ON WALL THICKNESS (N-408-2),
MUST BE INCLUDED IN TOTAL WELD POPULATION RWA-CF-53 RCIC 1 E-P 6" .280" P1 2621-1 EXEMPT FROM NDE 8ASED 04 WALL THICKNESS (N-408-2),
MUST BE INCLUDED IN TOTAL WELD POPULATION RWA-CF-54 RCIC 1 P-E 6" .280" P1 2621-1 EXEMPT FROM NDE BASED ON WALL THICKNESS (N-408-2),
MUST BE INCLUDED IN TOTAL WELD POPULATION RWA-CF-55 RCIC 1 E-P 6" .280" P1 2621-1 EXEMPT FROM NDE BASED ON WALL THICKNESS (N-408-2),
MUST BE INCLUDED IN TOTAL WELD POPULATION RWA-CF-56 RCIC 1 P-E 6" .280" P1-F1 2621-1 EXEMPT FROM NDE BASED ON WALL THICKNESS (N-408-2),
MUST BE INCLUDED IN TOTAL
. . WELD POPULATION RWA-CF-57 RCIC 1 E-E 6" .280" F1 2621-1 EXEMPT FROM NDE BASED ON WALL THICKNESS (N-408-2),
MUST BE INCLUDED IN TOTAL WELD POPULATION RWA-CF-58 RCIC 1 E-P 6" .280" P1 2621-1 EXEMPT FROM NDE BASED ON PAGE 4
CODE CASE '.1-408-2 COOPER NUCLEAR STATION IWC-2500-1 CAT: C-F-2 ,
INSERVICE INSPECTION PROGRAM REY: 1.1 RCIC SYSTEM ' THIRD INTERVAL P I PE . . . . . . . . . . . . . . . . . SY ST EM. . CNT . I TEM.NO. C F I G. . . S I ZE . . TKNS. . . . . MAT. . . W8 t . CAL . . 1 S0. . . . . . . . . . . . . . . . . PE R RELREQ REMARKS. . . . . . . . . . . . . . . . . .
WALL THICKNESS (N-408-2),
MUST BE INCLUDED IN TOTAL WELD POPULATION RWA-CF-59 RCIC 1 P-E 6" .280" P1 2621-2 EXEMPT FROM NDE BASED ON WALL THICKNESS (N-408-2),
- MUST BE INCLUDED IN TOTAL WELD POPULATION RWA-CF-60 RCIC 1 E-P 6" .280" P1 2621-2 EXEMPT FROM NDE BASED ON WALL THICKNESS (N-408-2),
MUST BE INCLUDED IN TOTAL WELD POPULATION RWA-CF-61 RCIC 1 P-E 6" .280" P1 2621-2 EXEMPT FROM NDE BASED ON WALL THICKNESS (N-408-2),
MUST BE INCLUDED IN TOTAL WELD POPLU TION RWA-CF-62 RCIC 1 E-P 6" .280" P1 2621-2 EXEMPT FROM NDE BASED ON WALL THICKNESS (N-408-2),
MUST BE INCLUDED IN TOTAL WELD POPULATION RWA-CF-63 RCIC 1 P-E 6" .280" P1 2621-2 EXEMPT FROM NDE BASED ON WALL THICKNESS (N-408-2),
+ MUST BE INCLUDED IN TOTAL WELD POPULATION RWA-CF-64 RCIC 1 . E-P 6" .280" P1 2621-2 EXEMPT FROM NDE BASED ON WALL THICKNESS (N-408-2),
MUST BE INCLUDED IN TOTAL WELD POPULATION RWA-CF-65 RCIC 1 P-E 6" .280" P1 2621-2 EXEMPT FROM NDE BASED ON WALL THICKNESS (N-408-2),
MUST BE INCLUDED IN TOTAL WELD POPULATION RWA-CF-66 RCIC 1 E-P 6" .280" P1 2621-2 EXEMPT FROM NDE BASED ON WALL THICKNESS (N-408-2),
MUST BE INCLUDED IN TOTAL
_ WELD POPULATION RWA-CF-67 RCIC 1 9-T 6" .280" P1 2621-2 EXEMPT FROM NDE BASED ON WALL THICKNESS (N-408-2),
MUST BE INCLUDED IN TOTAL WELL POPULATION RWA-CF-68 RCIC 1 T-R 6" .280" F1 2621-2 EXEMPT FROM NDE BASED ON WALL THICKNESS (N-408-2),
MUST BE INCLUDED IN TOTAL WELD POPULATION 54 ***
PAGE 5
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CODE CASE N-408-2 COOPER NUCLEAR STATION IWC-2500-1 CAT: C-F-2 INSERVICE INSPECTION PROGRAM REV: 1.1
- RCIC SYSTEM THIRD INTERVAL PIPE.......... ...... SYSTEM.. CNT. ITEM.No. CFIG... SIZE.. TKNS..... MAT... W81. CAL.. 150................. PER RELREQ REMARKS..................
- 54 PAGE 6 m
A